ML101970339
| ML101970339 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/28/2010 |
| From: | Progress Energy Carolinas |
| To: | NRC/RGN-II |
| References | |
| 50-261/08-301 | |
| Download: ML101970339 (421) | |
Text
{{#Wiki_filter:HLC-08 NRC Written Exam
- 1. Given the following:
- The plant is operating at 100% RTP.
-
- The PRT is at 74% and 110 of.
- °F.
- A load rejection results in a Reactor Trip.
-
- Following the trip, a Pressurizer Safety valve opens, and will NOT close.
-
- The PRT rupture disks function as designed.
-
- Containment pressure peaks at 35 PSIG.
- PSG.
Which ONE (1) of the following is the approximate MAXIMUM MAXf MUM temperature indicated by the Safety Valve tailpiece RTD during the entire event? A. 281 of.
°F.
338°F. B. 338 of. C. 547 of.
°F. 1 do {\o+ -
5('.G P\D..l<~;b',\;1y
~V' VO,.\LA- £, gt'l... \-~'
D. 651 of.
°F.
CcAAd . 1 1
Name: ________________~------------- HLC-08 NRC Written Exam Form: 0 Version: 0
- 1. 000008 AK1.01 OOlIPZR 001/PZR VAPOR SPACE ACCI/1/1/3.2/3.7IRO/HIGH/N/NNEW ACCTJ1/1/3.2/3.7IROIHIGH!N/A/NEW - 200S/THERMO
- 2008/THERMO CHAP 3-00S 3-008 Given the following:
- The plant is operating at 100% RTP.
-
--The The PRT is at 74% and 110 of. F.
0
- A load rejection results in a Reactor Trip.
-
~- Following the trip, a Pressurizer Safety valve opens, and will NOT close.
- The PRT rupture disks function as designed.
-
- Containment pressure peaks at 35 PSIG.
-
Which ONE (1) of the following is the approximate MAXIMUM temperature indicated by the Safety Valve tailpiece RTO RTD during the entire event? A. 281 of. °F. B:' B 338 of. °F. C. 547547°F.of. D. 651 of. °F. The correct answer is B. A: Incorrect - Saturation temperature for Containment pressure is 35 PSIG.
-
B: Correct - - PRT saturation temperature for 100 PSIG. C: Incorrect - Saturation temperature for No-load T
- AVG.
TAVG. D: Incorrect - Saturation temperature for 2235 PSIG. 0: - Exam Question Number: 1 1
Reference:
Steam Tables; SO-059 SD-059 PZRlPRT, PZRIPRT, Page 12. KA Statement: Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident: Thermodynamics and flow characteristics of open or leaking valves. History: New - Written for HLC-08 NRC Exam.
-
17,2008 1:20:59 PM Tuesday, June 17,20081:20:59 1
SD-059 SD-059 PRESSURIZER PRESSURIZER SYSTEM SYSTEM provides Temperature Over Low Temperature provides Low pressure Protection Over pressure Protection (LTOPP) (LTOPP) forfor the the RCS when itit isis RCS when water-solid, that water-solid, that is, is, at temperatures that at temperatures steam bubble that aa steam bubble cannot cannot be be maintained maintained in in the the PZR. The PORVs PZR. The PORVs are pneumatic valves, are pneumatic valves, with with nitrogen nitrogen being being supplied by the Plant supplied by the Plant System. To Nitrogen System. assure proper To assure proper operation operation of of the the LTOPP LTOPP System, System, the the Instrument Instrument Air Air System is valved System is valved into into service service as as aa backup for for the the Plant Plant Nitrogen System System whenever LTOPP is LTOPP is in in service. service. For Appendix R Safe ShutdownShutdown purposes, PCV PCV-455C
-455C and PCV -456 are classified as Hi I/
PCV-456 Lo Pressure Interface Valves. During normal operation these valves are are closed except as described above. During a postulated Appendix R fire in Fire Area A5, these valves are required to be closed initially in order to maintain the RCS operating parameters (Pressurizer level, pressure and temperature) within the expected ranges. Key operated switches are located on the Containment Fire Protection Panel in the Control Room. These are two position switches for each PORV (Normal or Isolate). The basic function of the Pressurizer PORV Normal I Isolate switches is to de-energize the electrical circuit during a postulated fire in Fire Area A5 to preclude (to the extent possible) the possibility of spurious operation of these valves. The addition of the isolation switches in conjunction with the actions taken in FP-001 FP-00 1 ensure that the circuit is de-energized and protected against the possibility of conductor to conductor hot shorts within a cable. This will result in the Pressurizer PORVs failing closed. 3.6 PZR Relief Tank (PRT) Design Pressure 100 psig Design Temperature 340°F Normal Operating Pressure 33 psig
. Normal Operating Temperature 120°F Normal Water Volume 900 ft 3 fe Rupture Disc Release Pressure 100 psig Rupture Disc Relief Capacity 900,000 #Ihr#/hr saturated steam Internal Volume 1300 ftfe 3
The PRT is a horizontally mounted 1300 ft fe tank inside the Containment Vessel (CV). It 3 has a design temperature and pressure of 340°F and 100 100 psig respectively. It It is piped to the PZR safety and PORVs by a 12 12" line. It It is protected from over pressurization by by.nYQ. two
~ scs rupture disc~ that will relieve pressure to the Containment Vessel at approximately lQ.Q. 100 psig. The rupture discs are designed to pass pass 900,000 900,000 lbs/hr. saturated steam.
The discharge from the High Point Vent System can also be be directed to the PRT. The The PRT PRT also also collects collects leakage leakage and and liquid liquid from various various system system relief relief valves valves located located inside inside PZR PZR Page Page 12 12 of of 27 27 Revision 99 Revision INFORMAT INFORMATION ION USE ONLY
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 2. During
- 2. During implementation implementation of of EPP-9, EPP-9, TRANSFER TRANSFER TO TO COLD COLD LEGLEG RECIRCULATION, RECIRCULATION, how how isis the the Charging Header Charging Header isolated isolated and and why?
why? A. IVSW isis automatically A. IVSW automatically aligned. aligned. To To prevent leakage by prevent leakage seating the by seating the RCP RCP Seal Injection line Seal Injection line check check valves. valves. B. A B. A manual valve alignment manual valve alignment of IVSW is of IVSW performed. is performed. To prevent To leakage by prevent leakage by seating the RCP seating the RCP Seal Injection line Seal Injection line check check valves. valves. IVSW is C. IVSW automatically aligned. is automatically ~ I "f\" <\"(!.'
~ Y'\oT SL~ CL.,;t;z?
prevent leakage To prevent leakage from Containment. Containment. ~1\f1. ""e",\'- ,){- I:V ~'vI.! ~.$ C/Li.Jl CAc9b 'b\e. t\;\A~ UJV QI~"d D. A manual valve alignment of IVSW IVSW isis performed. ~~-\-i,">'\.$ I.L><llM..\,I.. X.\I5W Gt.!-tk:- prevent leakage To prevent leakage from Containment. Containment. cJ-.I;s"", ~e,/ ~ '1'.,,1-- d"s-n~d w~1 ~ Ov~ ftiCr 1'N?,,.:t- IS ex.
",\CUAS;\'\<l ~$\i'~ .
22
HLC-08 NRC HLC-08 Written Exam NRC Written Exam 2.
- 2. 000011 000011 EA1.12 001/LBLOCA/1/1/4.1/4.4IROILOW/N/A NEW - 200S/EPP-9-005 EA1.12 001ILBLOCAllI1I4.1I4.4/ROILOW/N/A/NEW - 2008/EPP-9-005 During implementation During implementation of of EPP-9, EPP-9, TRANSFER TRANSFER TO TO COLD COLD LEGLEG RECIRCULATION, RECIRCULATION, howhow isis the the Charging Header Charging isolated and Header isolated and why?
why? A. IVSW isis automatically A. IVSW automatically aligned. aligned. To prevent leakage by prevent leakage seating the RCP by seating RCP Seal Injection line Seal Injection line check check valves. B. A manual valve alignment B. alignment of IVSW IVSW isis performed. performed. To prevent To prevent leakage leakage by seating the by seating the RCP RCP SealSeal Injection Injection line line check check valves. valves. C. IVSW is automatically aligned. To prevent leakage from Containment. D A manual valve alignment of IVSW Dr IVSW is performed. To prevent leakage from Containment. The correct answer is D. A: Incorrect - During EPP-9 IVSW is manually aligned to the Charging header. IVSW is
-
applied to the Charging Pump discharge side of the check valves. This would open the check valve, NOT seat them. B: Incorrect - During EPP-9 IVSW is manually aligned to the Charging header. IVSW is
-
applied to the Charging Pump discharge side of the check valves. This would open the check valve, NOT seat them. C: Incorrect - During EPP-9 IVSW is manually aligned to the Charging header. IVSW is
-
applied to the Charging Pump lines to preveent leakage if Continament is pressurized above Charging Pump header pressure and the Charging Pumps are stopped. D: Correct - 0: - During EPP-9 IVSW is manually aligned to the Charging header. IVSW is applied to the Charging Pump lines to preveent leakage if Continament is pressurized above Charging Pump header pressure and the Charging Pumps are stopped. Exam Question Number: 2
Reference:
EPP-9, Pages 32, 33; EPP-9 EPP-9 BD Page 37; SD-021 CVCS, Figure 10. 10. KA Statement: Ability to operate and monitor the following as they apply to a Large Break LOCA: Long-term containment of radioactivity. History: History: New New - Written
- Written for HLC-08 HLC-08 NRCNRC Exam.
Exam. 22
Rev. 31 EPP-9 TRANSFER TO COLD LEG RECIRCULATION Page 32 of 40 CONTINUOUS USE ATTACHMENT 2 2 Attachment 2 2 (Page 22 of 3)
************************************************************************** ********************************************************** ****************
CAUTION The Control Room will be initiating CV Sump Recirculation. This may result in high radiation in the Auxiliary Building.
************************************************************************** ********************************************************** ******* * ********
NOTE
- CVC-297A.
CVC-297A, B.B, and C C are located in the Northwest corner above Seal Inj Filter shield wall.
- CVC-293A.
CVC-293A, 293C. 293C, 292A. 292A, and 295 are located in Northwest corner outside Seal Inj Filter shield wall.
- CVC-295A is located in Northwest corner above Seal Inj Filters.
- CVC-309A and 202A 2O2A are located on West wall adjacent to HCV-121.
- 5. Verify CLOSED the following valves in the Charging Pump Room:
~ a. CVC-297A. A SEAL WATER FLOW CONTROL VALVE. CVC-297A, RCP "A"
?
- b. b. CVC- 297B. RCP "B" CVC-297B, B SEAL WATER FLOW CONTROL VALVE.
~c. C SEAL WATER FLOW CONTROL VALVE. CVC-297C, RCP "c"
- c. CVC-297C.
~d. d. CVC-293A.
CVC-293A, SEAL INJECTION FILTER "A" A OUTLET.
--7
- e. e. CVC-293C, SEAL INJECTION FILTER "B" CVC-293C. B OUTLET.
- >*
?f. CVC-292A. SEAL INJECTION FILTER PIC-157 ISOLATION.
- g. CVC-295.
CVC-295, SEAL INJECTION FILTER "A"A AND "B" B BYPASS.
- h. CVC-295A.
CVC-295A, SEAL INJECTION FILTERS OUTLET VENT. CVC-3O9A, HCV-121
- i. CVC-309A. HCV-l21 BYPASS.
CVC-2O2A. HCV-l21 OUTLET.
- j. CVC-202A.
Rev. 31 EPP-9 TRANSFER TO COLD LEG RECIRCULATION Page 33 of 40 CONTINUOUS USE ATTACHMENT 2 2 Attachment 2 2 (Page 33 of 3) ~~~~ 6. Open the following valves at the IVSW Tank Area Manual Header:
-
- a. IVSW-16, IVSW-l6, IVSW TO PEN 24, CHARGING LINE ISOLATION.
IVSW-l6A, IVSW TO PEN 25, 26, &
- b. IVSW-16A, & 27, RCPS SEAL INJECTION.
- 7. Notify Control Room that Attachment 22 is complete.
- END -
- -
RNP RNP WOG WOG BASIS/DIFFERENCES BASIS/DIFFERENCES STEP STEP STEP STEP 33 RNP BASIS RNP BASIS Closing isolates the CVC-282 isolates Closing CVC-282 charging line the charging outside CV line outside CV penetration penetration P-24. P-24. This This isis because the necessary because necessary the Charging Pumps will Charging Pumps be stopped will be stopped when when thethe RWST RWST is is emptying emptying (<27%) which
<<27%) depressurizes the which depressurizes header below the header below design design CV pressure.
CV pressure. The isolation The isolation of the Charging of the Charging andand Seal Injection lines Seal Injection lines and and initiation initiation of of IVSW IVSW is is aa corrective action corrective for SCR action for SCR 90-084 and is 90-084 and documented under is documented under correspondence correspondence RNPD/91- RNPD/91 - 0275. The 0275. The reason reason thethe penetrations penetrations areare isolated isolated is is that, that, although although IVSWIVSW is is not not credited credited in in the accident analysis, the Appendix J leakage leakage testing program program requires requires all valves to be be RFO intervals. IfIf the valves are sealed by tested at RFO by a qualified seal system (such (such as IVSW), the testing may be performed with water and the leakage excluded from the IVSW), overall leakage overall leakage raterate of of the the CV. The RNP CV. The program is RNP testing program set up is set up to to take take advantage advantage of of portion of this portion of the testing requirements. the Appendix J testing requirements. Since Since the the valves areare tested tested under under requirements, the valves must these requirements, must be closed and IVSW be closed IVSW mustmust bebe initiated initiated when the system is depressurized. An alternative would be to leave at least one Charging Pump in service during the duration of the accident. This however would create water inventory problems in the CV. 4 RNP BASIS The operator must notify the Control Room when the critical steps of the attachment are complete in order to expedite the restoration of core cooling. 1N5, RNP BASIS 2N5 Location of valves is shown to assist in performing the actions. They are included as a 3N5, note to reduce clutter in the action steps. 4N5 5 RNP BASIS Charging flow isolation to the RV was accomplished by cloSing closing CVC-282 in a previous step. This step completes the isolation of charging by closing manual isolation valves for RCP seal water and seal injection filters. In addition, the HCV-121 HCV-1 21 outlet isolation is closed and its bypass is verified closed. 6 RNP BASIS The IVSW System is activated to enhance CV isolation at penetrations 24, 25, 26 and 27. 7 RNP BASIS This step directs the operator to notify the control room that this attachment is complete. This is a standard step at the end of attachments. Attachment 33 The following steps are contained in in Attachment 3. 3. There are are no no equivalent ERG ERG steps, steps, accordingly, there are are no step differences. no step differences. These steps are are necessary to increase increase CV CV Sump Sump PH long term corrosion control per Westinghouse NSAL PH for long NSAL 93-016. 93-016. This letter letter describes thethe long long term term corrosion control concerns ifif aa SBLOCA occurs which does not not result in a Spray Actuation. This attachment aligns RHR and SI in in a manner to to establish a suction path for the CV Spray suction path Spray Pumps (Piggy-Back (Piggy-Back Mode).Mode). This alignment alignment is is performed in in the same manner the same manner as that done as that done in in the the main main body body ofof the the procedure procedure ifif CVCV Spray Spray is is required. required. IEPP-9-BD EPP-9-BD Rev. Rev. 31 31 Page Page 37 37 of of 52 521
SEAL SEAL INJECTIONINJECTION cvcs-CVC S-FIGURE-FIGURE-l100 CVC-307 RCPC SEAL I SEAL I RETURN RETURN SEAL I BYPASS fROM RCPB&C fSEAl3-1 L ____ J fSW21 '-- _ _ _ .J HVC-137 SEAL WATER HEAT EX. r----, FROM LOOP * ~ I ~TO I SEALI ___ J I I~ L LEG LOOP 2 TO VCT RCDT EXCESSlETDOVVN 389 HEAT EXCHANGER ~ I ~- --
- -
---'I~vt.~
,:>-3 7 S tt elI--r bf1
'1 - {
SEAL WATER INJECTION filTERS (rof"" xvSvJ TORCPB&C FROM CHARGING PUMP DISCH. IcvcsPfOJ CVCSFIO INFORMATION USE ONLY INFORMATION ONLY
HLC-08 NRC HLC-08 NRC Written Exam Exam Given the following:
- 3. Given 3.
plant is
- The plant
- is operating operating at at 8% RTP making 8% RTP making preparations preparations for synchronizingsynchronizing to the the grid.
0800, Annunciator APP-001-D2,
- At 0800,
- APP-001 -D2, Rep RCP #1 SEAL LEAKOFF LEAKOFF HI H FLOW, FLOW, alarms.
alarms.
- At 0802, the RO
- RD reports #1 sealleakoff seal leakoff is 5.2 GPM for Rep RCP 'A'. A.
- At 0805, the RO
- RD reports #1 sealleakoff seal leakoff is now at 5.7 GPM and increasing for Rep RCP 'A',
A, seal leakoff for Rep and #1 sealleakoff RCP '8' B and Rep RCP 'e' C have decreased from 2.4 GPM to 1.1 1 .1 GPM. APP-001-C5, Rep
- APp-001-e5,
- RCP STANDPIPE HIILO HI/LO LVL alarm is illuminated.
- Status light indicates A LOW.
-
Which ONE (1) of the following describes the Rep RCP seal failure and the action required? A. #1 seal has failed; trip the reactor, trip Rep RCP "A"; A; enter PATH-1.PATH-i. B. #2 seal has failed; trip the reactor, trip Rep RCP "A"; A; enter PATH-1.PATH-i. C. #1 seal has failed; place plant in MODE 3 lAW GP-006, and trip Rep RCP "A". A. D. #2 seal has failed; place plant in MODE 3 lAW GP-006, and trip Rep RCP "A". A. ND NCS
) 44 A T~ ,\s\ ~9p;\i? ~cP ,. ;tl'l\~ CcAo
\ <, r,.t ~\,uJ,e6 '\-<0 '\V'QV--e CuIISCv<{!'
cos c,\r--oices """':q~e, . A, 4-!), I ccJ 4, W F4 ~~ Qi\, --r;..iv 1 \("",,1T,. BB, -IF L
*2 ,--r;:'1> (2 (2e&.~h cb r...
C, LI -LI ,5ID:LAWG-P-&. t>. 11=- , ." 'D ::r;m.J r;.f-t,. 33
HLC-08 NRC Written Exam 3.000015
- 3. AK2.10 000015 AK2. OOlIRCP MALFUNCT 10 OO1IRCP IONS/1/1/2.8/2.8/RO/HIGHJN/AJROBINSON - 2002/AOP-0 MALFUNCTIONSI1I1I2.8/2.8IROIHIGHINIA/ROBINSON - 1 8-004 2002/AOP-018-004 Given the following:
- The plant is operating at 8% RTP making preparations for synchronizin
-
synchronizing g to the grid.
- At 0800, Annunciator APP-001
- APP-001-D2,-D2, RCP #1 SEAL LEAKOFF HI FLOW, alarms.
- At 0802, the RO reports #1 seal
-
leakoff is 5.2 GPM for RCP A. sealleakoff 'A'.
- At 0805, the RO reports #1 seal
-
leakoff is now at 5.7 GPM and increasing for RCP A, sealleakoff 'A', and #1 seal leakoff for RCP B 'B' and RCP C 'c' have decreased from 2.4 GPMG PM to 1.1 GPM. G PM. APP-001-C5,, RCP STANDPIPE HI/LO
- APP-001-C5
-
HIILO LVL alarm is illuminated.
-- Status light indicates A LOW.
Which ONE (1) of the following describes the RCP seal failure and the action required? A'I A #1 seal has failed; trip the reactor, trip RCP "A"; A; enter PATH-1. PATH-i. B. #2 seal has failed; trip the reactor, trip RCP "A"; PATH-i. A; enter PATH-1. C. #1 seal has failed; place plant in MODE 3 lAW GP-006, and trip RCP "A". A. D. #2 seal has failed; place plant in MODE 3 lAW GP-006, and trip RCP "A". A. The correct answer is A. A: Correct - - Indications for #1 seal failure and plant is in MODE 1. B: Incorrect - All indications support #1 Seal failure, not #2.
-
C: Incorrect - With plant in MODE 1, required actions is to trip the Reactor instead of entering
-
G P-006. GP-006. D: Incorrect - All indications support #1 Seal failure, not #2. With a #2 seal failure and the
-
plant in MODE 1, correct actions are to enter GP-006. Exam Question Number: 3
Reference:
APP-001-C5 and D2; AOP-018, Pages 5, 10; SD-001, SD-OOi, RCS, Figures 22, 23 and 25. KA Statement: Knowledge of the interrelations between the Reactor Coolant Coolant Pump Malfunctions (Loss of RC Flow) and the following: RCP indicators and controls. History:
- Tuesday, Tuesday, June June 17, 17, 2008 2008 11:21
- 21 :00
- 00 PM PM 3
APP-001 -D2 APP-001-02 ALARM
*** WILL REFLASH ***
***
Rep RCP #1 SEAL LEAKOFF HI FLOW AUTOMATIC ACTIONS
- 1. None Applicable CAUSE
- 1. Failure of RCP Number 1 1 Seal OBSERVATIONS
- 1. Labyrinth Seal ilP P1-i 31A) zP (PI-125A, PI-128A, PI-131A)
- 2. Temperatures AND flows (FR-154, RCP Temperature Recorder, and RCP Seal Leakoff Temperatures Computer)
- 3. (P1-i 54A, PI-155A, RCP Number 11 Seal ilP (PI-154A, P1-i 56A)
Fl-i 55A, PI-156A) ACTIONS
- 1. IF failure of a RCP Number 11 Seal has occurred, THEN refer to AOP-018.
DEVICEISETPOINTS DEVICE/SETPOINTS
- 1. FC-156A/5g FC-154A, FC-155A, FC-156A pm
/ 5 gpm POSSIBLE PLANT EFFECTS
- 1. Loss of RCS inventory REFERENCES REFERENCES
- 1. ITS LCO 3.4.4, LCO 3.4.5, LCO 3.4.6 and LCO 3.4.13
- 2. AOP-Oi 8, Reactor Coolant Pump Abnormal Condition AOP-018,
- 3. CWO CWD B-190628, B-i 90628, Sheet 477, Cables K, L, and M M IAPP-001 APP-OO1 I Rev. 41 I Page 29 of 54541I
APP-001-C5 APP-O01 -05 ALARM ALARM RCP STANDPIPE Rep STAN DPIPE HI/LO LVL HI/LO LVL ***
*** WILL REFLASH WILL REFLASH ***
AUTOMATIC ACTIONS AUTOMATIC ACTIONS 1.
- 1. None Applicable None Applicable CAUSE CAUSE High High 1.
- 1. Failure of Failure of Reactor Reactor Coolant Coolant Pump Pump Number Number 11 Seal (after isolation)
Seal (after isolation) 2.
- 2. Failure of Failure of Reactor Reactor Coolant Coolant Pump Pump Number Number 22 Seal Seal Low Low 1.
- 1. Failure of Failure of Reactor Reactor Coolant Coolant Pump Pump Number Number 33 Seal Seal OBSERVATIONS
- 1. Status Light Panel to determine affected Pump 2 x 2 Status
- 2. Labyrinth Seal ilPzP (PI-125A, PI-128A, P1-i 28A, PI-131A)
Pl-131A)
- 3. RCP Seal Leakoff Temperatures AND flows (FR-154, (FR-i 54, RCP Temperature Recorder, and Computer)
- 4. RCP Number 11 Seal ilP AP (PI-154A, (P1-i 54A, PI-155A, P1-i 55A, PI-156A)
P1-i 56A) ACTIONS
- 1. IF level is Low, THEN fill the Standpipe using OP-1 OP-i 01.
- 2. IF level is High, THEN check for rising level in Reactor Coolant Drain Tank.
- 3. IF seal failure is indicated, THEN refer to AOP-01 AOP-018. 8.
DEVICE/SETPOINTS DEVICE/SETPOINTS 1.
- 1. LC-406A, LC-407A, LC-407 A, LC-408A 11ft.
/ 1 ft. above normal
- 2. LC-406B, LC-407B, LC-408B lift, 11ft. below below normal normal POSSIBLE PLANT PLANT EFFECTS EFFECTS 1.
- 1. Loss Loss of of RCS RCS inventory inventory REFERENCES REFERENCES 1.
- 1. ITS LCO 3.4.4, ITS LCO 3.4.4, LCO LCO 3.4.5, 3.4.5, LCO LCO 3.4.6 3.4.6 and and LCO LCO 3.4.i3 3.4.13 2.
- 2. AOP-018, Reactor AOP-018, Coolant Pump Reactor Coolant Pump Abnormal Abnormal Conditions Conditions 3.
- 3. CWD CWD B-190628, B-190628, Sh Sh 104, 104, CabIeJ Cable J 4.
- 4. OP-i OP-1 01, 01, Reactor Reactor Coolant Coolant System System and and Reactor Reactor Coolant Coolant Pump Pump Startup Startup and and Operation Operation IAPP-OO1 APP-001 Rev. 41 Rev. 41 Page 24 Page of 54 24 of 541
Rev. 17 Rev. 17 AOP-018 AOP-018 REACTOR COOLANT REACTOR COOLANT PUMP ABNORMAL CONDITIONS PUMP ABNORMAL CONDITIONS Page of 41 Page 55 of 41 __STEP H INSTRUCTIONS INSTRUCTIONS I I SECTION AA SECTION RESPONSE NOT RESPONSE NOT OBTAINED OBTAINED I REACTOR COOLANT REACTOR COOLANT PUMP PUMP SEAL SEAL FAILURE FAILURE (Page 11 of (Pag of 11) 11)
- 1.
- 1. Check Any Check Any RCP RCP #1#1 Seal Seal Leakoff Leakoff IF seal seal leakoff exceeds 5.7 leakoff exceeds 5.7 gpm, gpm.
Flow - GREATER Flow - GREATER THAN THAN 5.7 5.7 GPM GPM THEN Go THEN Go To To Step Step 2. 2. Go To Go To Step Step 8. 8. 2.
- 2. Check Either Check Either OfOf The The Following Following Perform the following:
Perform the following: Conditions Conditions Exist: Exist:
- a. Perform
- a. cross-check of Perform cross-check of all all
** RCP #1 RCP #1 Seal Seal Leakoff Leakoff FlowFlow On On RCP parameters to RCP parameters to determine determine Unaffected RCP(s)
Unaffected RCP(s) - DECREASED
- DECREASED cause of cause of indicated indicated high high leakoff flow.
leakoff OR
- b. Observe The NOTE Prior To
** RCP Thermal Barrier RCP Barrier iP ~P On Step 11 and Go To The Main Affected RCP(s)
Affected RCP(s) - DECREASED
-
Body. Step 11 Of This Procedure Body,
**************************************************************************
***************************** *********************** **********************
CAUTION To prevent damage to the RCP Seal Stack. Stack, the affected RCP Seal Leakoff Isolation valve must be closed between 33 minutes and 55 minutes of stopping the the RCP. RCP.
**************************************************************************
**************************** ********************** ** ****** ****************
3.
- 3. Check Check Plant Plant Status - MODE 11
- Stop the affected RCP(s)
Observe the CAUTION prior to Step Step 55 and and Go Go To To Step Step 5. 5. 4.
- 4. Perform Perform The The Following:
Following: a.
- a. Trip Trip the the reactor reactor b.
- b. Trip Trip the affected RCP(s) the affected RCP(s) c.
- c. Go Go ToTo Path-1 Path-i while while continuing continuing with with this this procedure.
procedure.
Rev. Rev. 17 17 AOP-018 AOP-018 REACTOR COOLANT REACTOR COOLANT PUMPPUMP ABNORMALABNORMAL CONDITION S CONDITIONS Page Page 10 10 of of 41 41 -LJ-E INSTRUCTIONS INSTRUCTI ONS I I RESPONSE NOT RESPONSE NOT OBTAINED OBTAINED SECTION AA SECTION REACTOR COOLANT REACTOR COOLANT PUMP PUMP SEALSEAL FAILURE FAILURE
... ,,' ..... ....."
~
(Page 66 of (Page of 11) 11)
/ .,,,",
- 16.
*16. Check Calculated Check Calculated #2 #2 Seal Seal Leakoff Leakoff *rform the
//.perform the following:
following: \ Flow - LESS Flow - THAN l:*I{jppr--'*- LESS THAN l.1PE .7
/
// a. a. Place Place the the Plant Plant in in Mode Mode 33 f within 88 hours within hours using using GP-006, GP-006.
iic-I 7) /
,/ Normal Normal Plant Plant Shutdown Shutdown From From )
-
- .::::( Power Power Operation Operation To To Hot Hot ,J
/I Shutdown.
Shutdown. (/ /
/
i b. WHEN the plant plant has been /
" placed in Mode 3,3. THEN stop/
\. RCP (s) .
the affected RCP(s). //
//
/
...~.//
Go 5 2 pSp
*** ~ ___ o<-
- 17. Check Calculated #2 Seal Leakoff Go To Step 19.
Flow - GREATER THAN 0.5 GPM
-
- 18. Perform The Following For The Affected RCP:
- a. Closely monitor RCP Seal parameters
- b. Notify Engineering of RCP Seal condition N2 AND instruct them to contact Westinghouse Westinghouse for further instructions.
- c. Maintain Seal Injection flow between 88 gpm and 13 13 gpm
- d. Go To To Step 35
#1 RCP
#1 Rep SEAL SEALFAILURE FAILURE Res-FIGURE-22 RCS-FIGURE-22
#1#1 SEAL SEAL FAILURE FAILURE As Asthe the#1 #1 seal seal opens opens up up flowwill f10wwill increase increase past past the the seal seal and and out out the the#1 #1 leak leak STAND PIPE off offline.
line. RCS RCS flowflowand and seal seal injection injection flow flowwill will turn turn and and flowup flow up the the stack stack giving giving aa SEAL LEAK
#2 SEAL
#2 LEAK OFF OFF thermal barrier thermal barrier low Delta-P (neg.)
lowDelta-P (neg.) TO RCDT TO RCOT On aa large On failure the large failure the high high flowof flow ofhot hot RCSRCS past past the the thermal thermal barrier barrier will will cause cause SEAL LEAK SEAL LEAK OFF OFF the CCW flash the CCW to flash into to into steam. steam. TOVCT TO VCT #3 SEAL This This willwill give high flow give high flowspikes spikes LEAK OFF on on the the CCWCCW return return fromfrom the the RCP RCP which which in in turn turn will cause FCV-626 will cause FCV-626 SEAL LEAK
#1 SEAL
#1 LEAK OFF OFF FROM OTHER FROM OTHER RCPS RCP'S to to shut.
shut. Incrased Incrased Ilowinflow in thethe failed failed pump pump leak leak off line will off line will pressurize the pressurize the common common return header to return header to the the VCT VCT and and cause cause thethe seal seal leak leak off off flowfrom f1owfrom the the other other pumps pumps to to decrease. decrease. SEAL INJECTION ~
~!~liI8888 FROM CHARGING FROM 1:
;;;;i.J 15 ..~, CCW RETURN CCWRETURN IMPELLER FCV-626 FCV-626 FROM FROM THERMAL THERMAL BARRIER BARRIER RCSF22 RCSF22 INFORMATION USE ONLY
CVC-303 CLOSED CVC-303 CLOSED RCS-FIGURE-23 RCS-FIGURE-23 CVC*303 VALVE CVC-303 VALVE SHUT SHUT When the When the 303 303 Valve Valve is is shut shut the major leak the major leak path path is is isolated. isolated. This will This will relieve relieve the the excess excess pressure pressure on on the return header the return header
,
STAND PIPE and leak and offflowfrom leak off flow from the the other other RCP's should RCPs return to should return to normal. normal. Additional Additional pressurepressure is placed on is placed on the #2 the seal causing
#2 seal causing itit to to tilt tilt slightly slightly
'12 SEAL SEAL LEAK OFF TO RCDT TO RCDT and become and become aa film riding seal film riding seal similar similar to the to the #1#1 seal.
seal. This returns the This returns the RCP RCP to near to near normal normal valuesvalues with with 55 GPM GPM flowing up flowing up past past thethe #2#2 seal,seal, and and aa SEAL SEAL LEAK LEAK OFF OFF small amount small amount going going to to the the #3 #3 seal. seal. TO TOVCT VCT SEAL
#3 SEAL
#3 At this At this point point CCW flow through the CCW flowthrough the LEAK OFF ,
I ...
#1
#1 SEAL
- FROM SEAL LEAK FROM OThER LEAK OFF OFF OTHER RCPS RCP'S
+
TO SUMP
' ther!1lal barrier thermal past the past barrier may opening FCV-626.
opening the #2 FCV*626. The
#2 seal may be seal will restored by be restored increased flow The increased give aa high will give by high stand flow stand pipe level.
pipe level. The net The net difference difference will will be be seal leak off seal leak off flowgoing flow going to to the RCDT through the RCDT through the the stand pipe. stand pipe. (This (This is treated as is treated as RCS RCS CVC-307 leakage). leakage). Note: Note: FCV-626 FCV*626 may may required required several cycles several cycles to flush the to flush the steam from steam from the lines before the lines before SEAL INJECTION SEAL INJECTION itit will remain open. will remain open. FROM CHARGING FROM CHARGING l~ ~- ......
'lIIo....-
CCW Return Return IMPELLER FCV-626 FCV*626 From Thermal From Thermal Barrier Barrier RCSF23 RCSF23 INFORMATION INFORMAT ION USE ONLY ONLY
MAJOR DIFFERENCES RCS-FIGURE-25 RCS-FIGURE-25 THERMAL SMALL SMALL #1 LARGE #1 BARRIER SEAL SEAL SEAL SEAL FAILURE FAILURE FAILURE* FAILURE
- ifi FLOW ALARM SEAL LEAKOFF ill X X SEAL LEAKOFF HI TEMP ALARM X X THERMAL BARRIER DELTAP LO ALARM X X X x X
- 1 SEAL DELTA P LO ALARM X SEAL LEAKOFF LO FLOW ALARM X X (UNAFFECTED RCPs)
THERMAL BARIER BAfflER COOLING WATER ill ifi X x X TEMP ALARM TEMPALARM RCP BEARING TEMP ill ifi ALARM X X CCW SURGE TANK HI LEVEL ALARM X R-17 INCREASE OR ALARM X
*PRIOR TO SHUTTING CVC-303 INFORMATION USE ONLY
QUESTIONS REPORT (Joo2) for AUDIT (2ü2) 1. 1 015 AA2.01 001/I/Il/Il
. 0011//1//1/
Given the following conditions:
- The plant is operating at 8% RTP making preparations for synchronizing to the grid.
- APP-001-D2, RCP #1 SEAL LEAKOFF HI FLOW, alarms.
At 0800, Annunciator APP-00i-D2,
- At 0802, the RO reports #1 seal leakoff is 5.2 GPM for RCP A.
sealleakoff 'A'.
- At 0805, the RO reports #1 seal leakoff is now at 5.7 GPM and increasing for RCP sealleakoff
'A', and #1 seal A, leakoff for RCP B sealleakoff 'B' and RCP C 'C' have decreased from 2.4 GPM to 1.1 GPM.
Which ONE (1) of the following describes the RCP failure and the action required? A"I #1 seal has failed; Trip the reactor, trip RCP A; A! 'A'; enter PATH-1. PATH-i. B. #2 seal has failed; Trip the reactor, trip RCP A; 'A'; enter PATH-1. PATH-i. C. #1 seal has failed; Trip RCP 'A' A and commence plant shutdown lAW JAW GP-006. D. #2 seal has failed; Trip RCP 'A' A and commence plant shutdown lAW JAW GP-006. A. Correct. Indications for #1 seal failure and we are in MODE 1. SRO Question 76 Tier 11 Group 11 K/A Importance Rating - SRO 3.5 KIA - Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Cause of RCP failure. AOP-01 8, Section A Reference(s) - AOP-018,
-
Proposed References to be provided to applicants during examination - None - Learning Objective - - Question Source - Modified Bank
-
Question History - 2002 NRC Exam
-
Question Cognitive Level - Comprehension
-
10 CFR Part 55 Content - 43 - Comments - - Category 1: Category 2: Category 3: Category 4: Category 5: Category 6: Category 7: Category 8: Monday, June 09, 2008 11 :03:59 AM 1 1:03:59 1
HLC-08 HLC-08 NRC NRC Written Written Exam Exam
- 4. Given
- 4. Given the the following:
following: The plant
- The
- plant isis operating operating at at 100%
100% RTP. RTP. RCS boron
- RCS
- boron concentration concentration isis 600 600 ppm.
ppm. Earlier in
- Earlier
- in the shift, VCT level level transmitter LLT-115 LOW.
T -115 failed LOW.
- All actions of AOP-003,
- AOP-003, MALFUNCTION MALFUNCTION OF REACTOR REACTOR MAKEUP MAKEUP CONTROL, CONTROL, have have been been completed.
completed.
- VCT level is
- is currently 30 inches as indicated on level transmitter LLT-112. T -112.
I&C reports they have deenergized LLT-1
- I&C
- T -11212 inadvertently.
Which ONE (1) of the following describes how the actual VCT level and T AVG would respond? TAvG (Assume no operator action) A. VCT level increases; T AVG increases. TAVG I'A-V{'- )V\c-~'S~\'\.3 \> B. VCT level decreases; T
'(\(7\- '?\~\~ Ie, £vx.1f-. ~.\
AVG increases. TAVG
.~e.. \J L.
_T'T ~
\-c ~ Ov-C!o 1"",,\4>..-v.~ ) Ii\--i 6- W\:)t~JJ \I) cit-C. VCT level increases; T AVG decreases.
TAVG
~ VI c.. 'l'tcx.5f.
D. VCT level decreases; T AVG decreases. TAVG VDT ltwl ote.U'.Q56
\.50 vw ,?\w.<.s'l'v:M. Nt nO+- \cws\e No f'{\~:SCtr-nc'4>+1 OV\. ~<.Y>v" .~),.~
s~ ~\c9 \;"c0 C\..v.... o.~\,\~ CC\;.A-\- -\-0 .~',,,,-\. "VC*T
~v-J ~s 90\"'::' (~<tu.n-, 1 tIL v(h",6 '30 c10uAV\.
44
HLC-08 NRC Written Exam
- 4. 000022 AA1.01 MAKE/1/1/3.4/3.3IROIHIGH/N/AJFARLEY - 2001lCVCS-004 001/LOSS OF RX COOL MAKE/1I1I3.4/3.3IROIHIGHJNIAIFARLEY AAl.Ol OOllLOSS - 2001/CVCS-004 Given the following:
- The plant is operating at 100% RTP.
-
- RCS boron concentration is 600 ppm.
-
- Earlier in the shift, VCT level transmitter L
- LT-1 15 failed LOW.
T -115
- All actions of AOP-003, MALFUNCTION OF REACTOR MAKEUP CONTROL, have been
-
completed.
- VCT level is currently 30 inches as indicated on level transmitter L
- LT-1 12.
T -112.
- I&C reports they have deenergized LT-112 inadvertently.
-
Which ONE (1) of the following describes how the actual VCT level and T AVG would respond? TAVG (Assume no operator action) A. VCT level increases; T AVG increases. TAvG B. VCT level decreases; T AVG increases. TAvG C VCT level increases; T C:-" AVG decreases. TAVG D. VCT level decreases; T AVG decreases. TAvG The correct answer is C. A: Incorrect - RWST will be supplying the charging pump suction with water of 2000+ ppm
-
boron, this will cause T AVG to decrease. TAVG B: Incorrect - T - AVG will NOT increase due to boration from the RWST. TAVG C: Correct - - Letdown will still be going to the VCT causing level to increase; boration from the RWST will be causing T AVG to decrease. Having both level transmitters low will TAVG LCV-1 1 5C. This swaps charging pump suction from LCV-1 1 5B and shut LCV-115C. open LCV-115B the VCT to the RWST. 0: D: Incorrect - VCT level will NOT decrease, there is no outlet flow from the VCT due to
-
LCV-1 1 5C going shut and letdown still going to the VCT. LCV-115C Tuesday, June 17, 2008 1 1:21
- 21 :00 PM 4 4
HLC-08 NRC HLC-08 Written Exam NRC Written Exam Exam Question Exam Number: 44 Question Number:
Reference:
SD-021, eves,
Reference:
SO-021, CVCS, Pages Pages 41, 41, 56, Figures 1, 56, Figures 1, 17a, 1 7a, 6; 6; OWP-005, OWP-005, CVCS, CVCS, Page Page 53. 53. KA Statement: KA AbNity to operate and /I or monitor Statement: Ability monitor the following as they apply apply to the Loss Loss of of Reactor Coolant Reactor Makeup: eves Coolant Makeup: CVCS letdown letdown and charging. charging. History: Modified History: Modified from Farley Farley 2001 NRC NRC exam, Changed Changed distractors/answer to TTAVG vs Rx AVG VS Rx power. power.
- Tuesday, Tuesday, June June 17,2008 17,2008 1:21 1:21 :00
- 00 PM PM 55
SD-021 CHEMICAL AND VOLUME CONTROL SYSTEM be accommodated in the VCT. LCV-115A is a three-way valve which is controlled by a AUTO/MANUAL proporti proportionalicontroller controller which uses VCT level (normally LT-112) LT-1 12) as an input when selected to AUTO. If level in the VCT reaches 51.6" 51.6the the valve will be removed from its controller and fully diverted to the CVCS holdup tanks. The valve can also be overridden with the switch on RTGB. Upon a loss of air, LCV-lISA LCV-11SA will fail to the VCT position. LCV-1 iSA is aligned to divert letdown from the VCT, flow is directed to one of If LCV-115A three CVCS Holdup Tanks. Alarms with the CVCS Holdup Tanks annunciate at the Waste Disposal Boron Recycle Panel. The CVCS Holdup Tanks and their instrumentation are discussed in more detail in the Waste Disposal System Description. 5.2.3 Emergency Makeup to Charging Suction (LCV-115B) (LCV-i 15B) LCV--115B LCV
-
11 5B is an air-operated valve which is controlled by a three-position (CLOSE-AUTO-OPEN) switch on the RTGB. In AUTO, this valve will automatically open to provide emergency makeup from the RWST to the VCT if level drops below 12.4". 12.4. LCV- 11 LCV -115B 5B has a backup air supply from the compressed air bottles in the charging pump room. There is also a three-position switch located on the Charging Pump Panel in the Charging Pump Room. The three positions are CLOSED-AUTO-OPEN. This key operated switch will always be maintained in the AUTO position. While in AUTO this control scheme (totally independent of the normal interlock with LCV LCV-1 -115C/auto 15C/auto swap over) will open LCV-115 LCV-l 15 if both LCV-115C LCV-i 15C and LCV-115B LCV-i 15B are closed at the same time for 60 seconds. An AC powered solenoid was added to LCV LCV-1 15B and it is
-115B powered by the DS Bus. This new control scheme was added to ensure the running charging pump will have a suction source during a smart fire event.
5.2.4 VCT Outlet ValveValve(LCV-115C) (LCV-115C)
.;;11'
LCV- 11 5C is a motor operated valve, controlled from the RTGB by a three position LCV-115C (CLOSE, AUTO, OPEN) switch. In AUTO, its position is controlled by LT-112 LT-1 12 and LT-1 15 for the emergency swapover to the RWST via LCV-115B. LT-115 LCV-1 15B. The power supply to LCV-115C is MCC-6. 5.2.5 Makeup System Components Boric Acid Flow Control Valve, FCV-1I3A, FCV-113A, BA TO BLENDER, is controlled by a three position (OPEN, AUTO, CLOSE) RTGB switch. In AUTO, the position is controlled by AUTO/MANUAL RTGB controller FCV-113A, FCV-1 13A, BORIC ACID FLOW. Operation with the potentiometer set for greater than 9.0 should be avoided since this could result in boric acid flowrates of greater than 10.0 gpm which are beyond the indicating range of FR-113 FR-i 13 and YIC-113. YIC-i 13. This valve is used for boration and normal makeup. It regulates the boric acid flow to the blender and fails open. eves CVCS of7l Page 41 of71 RevisionlO Revision 10 INFORMATION USE ONLY
SD-021 CHEMICAL AND VOLUME CONTROL SYSTEM LT-115 LT-115 L T -115 Fails LT-112 L T -112 Fails LT-112-Fails L T -112-Fails Fails LOW IDGH HIGH LOW HIGH IDGH LT-1 12 ERFIS LT-1I2 Increasin~ Increasing Decreasing BAD; <0 > 100 BAD; >100 LT-1 15 ERFIS LT-1I5 BAD; <0 BAD; >60 No effect Decreasing Decreasin~ RTGB VCT LvI Lvi <0 >60 No effect Decreasin~ Decreasing LCV-1 15A LCV-1I5A Closed Open Closed Open LC-1 15A LC-115A No Demand No Demand No Demand Full Demand Auto Makeup Start; Not Available Still available Still Available; Continuous cycling Auto Emergency Still possible Not possible Still possible Not possible . Switchover APP-003-E3 Received Received No No Overall Effect Continuous VCT level Hardest to VCT level will auto makeup decreases due recognize decrease due as long as LCV-1 iSA to LCV-115A since no real LCV-1 15A to LCV-1I5A system in open off of change to diverting. An AUTO. LT-i 15 Hi LT-1I5 system other auto makeup VCT fills level backup. than LCV- will occur and and LCV- Since no auto 1 iSA will not 1I5A restore VCT 1 15A diverts 115A emergency divert until level. The of LT-off ofLT- switchover is LT-i 15 the LT-115 makeup will control, 112 control. possible, if Hi level take longer operator backup is than normal. action is not reached. Will Once makeup taken will only see if stops, VCT lose charging monitor level will pump suction. ERFIS. decrease and cause a repeated cycling of the auto makeup. 6.5 Emergency Operation The CVCS is used in the Dedicated Shutdown procedures and the Emergency Operating procedures to control RCS inventory and maintain seal injection. Its use can be from inside the control room or outside the control room in either set of procedures. For example, a fire in the charging pump room would render normal charging useless, but the Dedicated Shutdown procedures provide a means to shutdown and cooldown the eves CVCS of 71 Page 56 of7! RevisionlO Revision 10 INFORMATION USE ONLY
eves CVCS FLOW FLOW DIAGRAM DIAGRAM CVCS-FIGURE-l CVCS-FIGURE- 1 2O9j_ø.T0 VCT TOTOPRT 4 PRT4_qi.........---. Non-Regen. TE- TE PT 1204A 2048 HX 144 LOOPt 1EV- LCV* 460A 4608 r NOV 142 I
- T]
92 50 250 cvc-244 245 245 212 223
...MixedMixed LOOP 1 cOLDLEG~
COLD TE Gas Compressor s 11 A 255 F 249 uU Bed Bed Demins. Demins LOOPt LOOP HOT HOT LEG 1 LEG 310A Gas Analyzer PCV-199 T 256 2590 117 260 260A FCV-1 148 To CVCS HUT 112 115 115 226
- orating 2168 lJeborating Demins. .
mins. I216B~) 225 225 216 216 A! REGEN AUX AUX SPRA SPRAY LOOP 2 Y4V1' .14 I HX rn Seal Water VCT ØØQ - 237A J228 Cation J Bed Cation I Bed LOOP2 JE237A Demin. Demin. COLD COLD LEG LEG EXCESS I Hx TE LJTDNHX 389 LCV 116 From Loop 2 FCV 1150 FCV-113B FromLoop2JL,LIL I 114A 247D ColdLegLeg 387 Cold IICV- I (PT\I 266 Primary 37 I 114 Water Pumps To RCDTt _ç 359A From From RCP RCP Seals Seals 380 F 320 271 272 272 Chemical Charging Charging Mixing Pumps Suction Tank
- Pulsation pulsation Pumps Dampener Stabilizer Dampen 272A 286 '\
1~ 11 3A From 352 353 To To RCPRep Seals Seals i RWST I FromFromBA BA Transfer Transfer Pumps Pumps
%i I, r 351 350 INFORMATIONUSE INFORMATION USEONLY ONLY
VCT LEVEL VCT LEVEL CONTROL CONTROL CVC S-FIGURE-i 7A CVCS-FIGURE-17A FROM ROM eve DEMINS CVC DEMINS AUTO VC~LDP 0HLDP VCT TK K
\2/ "/
/
OVERRIDES LCll2AAT OVERRIDES LCII2A AT 51.6 51.6 AND
,----------------------,,
AND RETURNS
RETURNS CONTROL NORMAL NORMAL CONTROL AT
*
- AT 45.6" 45.6 J
~--.,-----1 LT11mT115
/ LTII 0 LTII5 CVC HUT eVeHUT4---~~~
* -
1 LCV-115A 1 I FROM FROM : SWITCH LOCATED SWITCH LOCATED IN IN : t--II.....~DILUTE I RACK 19 RACK 19 I MAKEUP ip I 60 H0 2 . FC -114B ) LC115A
.., COMPAR*
r..ICOMPAR I ATOR I IJ I I
-8
;
I CONTROLLER I _ _ '_. DUAL I t r I LC115C DUAL COMPAR.L COMPAR'f- _ LCII5B f---~ ____ _ HIALARM48.6 HALARM48.6
~ ALARM 17.2" ARM 17.2 I LCl15B ---4 AUTO MAKEUP AT AUTOMAKEUPAT 1.... DUAL 20.2" AND STOP 2O.2 AND 0 'r C 1COMPAR~_.,
OMPA..._ AT 24.4" 24,4 I I U AUTO CLO~EN B-------." COMPARATOR"
-j
,,)
I LCV-115C
, ~
, "
! - - -. . .I-FROM AUTO MAKEUP MAKEUP
"~ LO-LO (12.4") V~
CLOSES LO-LO (12.4) CLOSES LCV-115C AND LCV-115C AND OPENS INTERLOCKED SO LCV-115B IN LCV-115B IN AUTO AUTO BOTH CANT BOTH CAN'T CLOSED CLOSED IN IN AUTOMATIC AUTOMATIC FROM FROM RWSTRWST LCV-115B
*
*IFIF SWITCH SWITCH IN IN LT-112; LT-112; LT-112 LT-112 AUTO CONTROLS CONTROLS ALL ALL COMPARATORS COMPARATORS CLOSPEN &&CONTROLLERS.
CONTROLLERS. IF IF SWITCH SWITCH IN IN LT-115: LT-115: LT-115 LT-115 CONTROLS CONTROLS ALL ALL COMPARATORS COMPARATORS
&& CONTROLLERS CONTROLLERS CHARGING PUMP CHARGING PUMP SUCTION SUCTION
/cvcsf11a /
ICvcstl7aI INFORMATION INFORMATION USE USE ONLY ONLY
AUTOMATIC (NORMAL) MAKEUP FLOWPATH cvcs- FIGURE-6 CVCS-FIGURE-6 lCV-115A FROM LCV-1 15A CVCS MAKEUP
...--.,
---.,
CONTROL I I I I I FROM PRIMARY WATER PUMPS CHARGING PUMPS 356 l--..:......ji.....Y-LCV-115B
~
FCV-113A 1~~
~
Jl268 FROM RWST FROM B 269 r BORIC 358 .....~... ACID ACID TRANSFER PUMPS HEAT TRACING INFORMATION USE ONLY
REFERENCE USE REFERENCE USE OWP Title: CVC-18 OWP Title: CVC-18 Page Page _1_ 1 ofof _2_ 2 Volume Control LT-115, Volume LT-115, Control Tank Tank Level{ Level{ TC LT-1l5, Volume TC "LT-llS f Volume Control Control TankTank Level" Level
\f
\f CC \1 1 })
\l "1" 1.
- 1. This revision This revision has has been verified to been verified to be the latest be the latest revision revision available.
available. Name (Print) Name (Print) Initial Initial Signature Signature Date Date 2.
- 2. System: CVC System: CVC W/O W/O No:, _ _ _ ____________
No:________ _ _ _ _ ____ _ 3.
- 3. Component: LLT-1 Component: Volume Control 15, Volume T -115, Control TankTank Level Level
- 4. Scope of Scope Calibrate/repair LLT-1 of Work: Calibrate/repair 15.
T -115. 5.
- 5. required on redundant Testing required redundant equipment prior prior to rendering rendering component inoperable:
inoperable: N/A
- 6. Precaution:
Precaution: _--- 1)
- 1) When placing LLT-112 T -112 in operation, the selector switch should be operated swiftly to prevent prolonged loss of level signal from both loops. Loss of both
?
signalsl_u1cuse LQ-115to could cause LCV-115B to open r--=--
- 2) When selected to the LLT-112 position, the RTGB and ERFIS indications will be T -112 pOSition, LT-1 12.
driven by LT-112.
- 3) If mechanical work will not be performed, only the electrical lineup is required.
- 4) If mechanical work will be performed, both the electrical and the mechanical lineups are required.
- 5) Complete the electrical lineup for maintenance prior to performing the mechanical lineup.
- 6) This activity has been screened in accordance with PLP-037 criteria and determined to be outside the bounds of an Infrequently Performed Test or Evolution.
- 7. Valve/Break er/Switch lineup has been Valve/Breaker/Switch /
completed. Signature Date
- 8. Clearance Issued Issued (If applicable) No: _ _ ____________
Clearance No:_______ _____ __ _______
- 9. Testing required on redundant equipment while component is inoperable. inoperable.
N/A 10.
- 10. I&C Maintenance l&C Maintenance lineuplineup completed. N/A / N/A N/A Signature Signature Date Date 11.
- 11. Clearance Clearance removed removed and and Valve/Break er/Switch Valve/Breaker/Switch /
lineup lineup restored restored toto normal. normal. Signature Signature Date Date 12.
- 12. Post Post Maintenance Maintenance Testing.
Testing. 1)
- 1) Verify Verify calibration calibration of of component component repaired repaired or or replaced replaced in in accordance accordance with with PIC-002.
PIC-002. I/ Signature Signature Date Date OWP-005 (cvc.s 1OWP-005 (c vcs) Rev. 57 Rev. 57 Page Page 53 53 of 961 of 96
A - Correct, need a ctmt pressure of 27 psig to start CS pumps with an LOSP. If all
-
systems function normally, an SI signal is recieved at 4 psig. B - Incorrect, Requires 27 psig on 2/4 detectors.
-
C - Incorrect, Must also have an SI signal present.
-
D - Incorrect, An SI signal alone will cause the Containment Fans Coolers to operate in
-
slow speed but will not start a spray pump. Source: New Answer: A --...-...---- 3 . . 1 FI1;eu=2. /{/,-(( c 01 c/ Given the following conditions on Unit 2:
- Reactor is at 100 % steady-state power.
-
- RCS boron concentration is 600 ppm.
-
- VCT level is currently 40% as indicated on level transmitter LT
- LT-1 12.
-112.
- Earlier in the shift VCT level transmitter LT-115
- LT- 115 failed low and has been released to I&C for repair.
- Make up Mode Control Switch is in STOP
-
- The I&C person has just left the control room to electric
- electrically LT-1 all y isolate LT 15.
-115.
I&C reports they have deenergized LT-112 LT-1 12 inadvertently. Which ONE of the following describes how the VCT level and reactor power would respond? (Assume no operator action) A. VCT level increases; reactor power remains the same. B. VCT level decreases; reactor power increases. C. VCT level increases; reactor power decreases. D. VCT level decreases; reactor power decreases. A - Incorrect, RWST will be supplying the charging pump suction with water with 2000+
-
ppm boron, this will cause reactor power to decrease. B - Incorrect, Reactor power will not increase due to boration from the RWST.
-
C - Correct, Letdown will still be going to the VCT causing level to increase; boration
-
from the RWST will be causing power to decrease. Having both level transmitters low LCV-1 15B & D and shut LCV-1I5C will open LCV-1I5B LCV-1 15C & E this swaps charging pump suction \
- ,
from the VCT to the RWST. D - Incorrect, VCT level will not decrease, there is not out let flow from the VCT due to
-
LCV-1 15C and LCV-115E LCV-115C LCV-1 15E going shut and letdown still going to the VCT. i Source: Modified from Vogtle NRC Exam 2001
\ \ ~.
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Given the
- 5. Given
- 5. the following:
following: Following aa LOCA,
- Following
- LOCA, the the plant plant isis in in Cold Cold Leg Leg Recirculation Recirculation lAW lAW EPP-9, EPP-9, TRANSFER TRANSFER TO TO COLD LEG COLD LEG RECIRCULATION.
RECIRCULATION. RHR Pump
- RHR
- Pump "A"A isis in in service providing core service providing core cooling.
cooling. RHR Pump
- RHR
- discharge pressure Pump discharge pressure is is fluctuating fluctuating by by 40 40 PSIG PSIG and and flow flow is is approximately approximately 3350 3350 GPM and GPM and oscillating.
oscillating.
- APP-001-A7, RHR
- RHR HX HX LO FLOW, has alarmed and cleared several times.
- APP-003-D3, PRT HIILO
- HI/LO LVL alarm has just illuminated.
Which single malfunction could be causing the event? ECCS Sump screens are clogging. A. ECCS B. RHR-752A, RHR PUMP A SUCTION VALVE has drifted partially shut. C. RHR-706, RHR RELIEF VALVE is cycling. Sl-887, RHR RECIRCULATION TO RWST VALVE disc has separated from its valve stem. D. SI-887, l"'-~ ?~T IL
\'{-.'!Le e
~<-~
\,,'\~ 'c." ~e. o\'\Jtl!1Q5
()vv\ :;'clAA-"-, r ct.) nor 2)ee... Mw..~1 'i\- eVAy <. xe&}!} ~~i-y c QMf)
~ '" ~'t o~ .~-e... Cj-(CL4(). d(.'.>'\-fCL(,/..-O.
55
HLC-08 NRC Written Exam
- 5. 001/LOSS OF RHRJ1/1/3.2/3.4/RO/ETIGHIN/AINEW 000025 AA2.06 OOllLOSS 2008/AOP-020-004 RHR/l/l/3.2/3.4IRO/HIGH/N/A/NEW - 200S/AOP-020-004
-
Given the following:
- Following a LOCA, the plant is in Cold Leg Recirculation lAW EPP-9, TRANSFER TO
-
COLD LEG RECIRCULATION.
- RHR Pump "A"
- A is in service providing core cooling.
- RHR Pump discharge pressure is fluctuating by 40 PSIG and flow is approximately 3350
-
GPM and oscillating.
- APP-001-A7, RHR HX LO FLOW, has alarmed and cleared several times.
-
- APP-003-D3, PRT HIILO HI/LO LVL alarm has just illuminated.
Which single malfunction could be causing the event? A. ECCS Sump screens are clogging. B. RHR-752A, RHR PUMP A SUCTION VALVE has drifted partially shut. C~ RHR-706, RHR RELIEF VALVE is cycling. C D. SI-887, RHR RECIRCULATION TO RWST VALVE disc has separated from its valve stem. The correct answer is C. A: Incorrect - Sump screen clogging would cause RHR flow to decrease NOT fluctuate. PRT
-
level indicators make this condition NOT the cause. B: Incorrect - RHR-752A is closed in Cold Leg Recirculation.
-
C: Correct - - Normal flow rate (NOT a suction problem), with pressure oscillations and PRT level indications. D: Incorrect - SI-887 is isolated from RHR during Cold Leg Recirc. (SI-863A
- (Sl-863A and 863B are closed)
Exam Question Number: 5
Reference:
APP-001-A7; APP-003-D3; SD-003, RHR, Figure 3. KA Statement: Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System: Existence of proper RHR overpressure protection. History: New - Written for HLC-08 NRC exam.
-
Tuesday, June 17, 20081:21:01 2008 1:21 :01 PM 6
APP-001-A7 APP-001 -A7 ALARM ALARM RHRHXLO RHR HX LO FLOW FLOW ACTIONS AUTOMATIC ACTIONS AUTOMATIC 1.
- 1. Applicable None Applicable None CAUSE CAUSE 1.
- 1. Lossof Loss RHR Pump of RHR Pump 2.
- 2. Loss of Loss of suction head head (Le., Loss of water from RCS)
(i.e., Loss RCS)
- 3. Closure of Closure of system flowpath valves
- 4. Intentional operator action Intentional OBSERVATIONS
- 1. (Fl-605)
RHR Flow (FI-605)
- 2. RHR Pump status
- 2. Position of HCV-758
- 4. Position of FCV-605
- 5. Position of system flowpath valves
- 6. Pressurizer Level (LI-459A, (Ll-459A, LI-460, LI-461 LI-461,, and LI-462)
- 7. RCS Loop Standpipe Levels (LI-403, LI-404)
ACTIONS 1.
- 1. IF alarm due to intentional operator action, THEN no further action is required.
- 2. IF alarm due to flow control valve operation, THEN verify flow set between 2800 gpm and 3750 gpm.
- 3. IF flow can NOT be restored to greater than 2800 gpm via flow control valve change, THEN refer to AOP-020.
DEVICE/SETPOINTS OEVICE/SETPOINTS 1.
- 1. FC-605A FC-605A /I 3000 gpm gpm POSSIBLE POSSIBLE PLANT PLANT EFFECTS EFFECTS 1.
- 1. Loss Loss of of decay decay heat heat removal REFERENCES 1.
- 1. ITS ITS LCO LCO 3.4.6, 3.4.6, LCO LCO 3.4.7, 3.4.7, LCO LCO 3.4.8, 3.4.8, LCO LCO 3.9.4 3.9.4 and and LCO LCO 3.9.5 3.9.5 2.
- 2. AOP-020, AOP-020, Loss of Residual Loss of Residual Heat Heat Removal Removal System System (Shutdown (Shutdown Cooling)
Cooling) 3.
- 3. CWD CWO B-190628, B-190628, Sheet Sheet 487, 487, Cable Cable SS JIAPP-OO1 APP-001 Rev. 41 Rev. 41 Page 11 Page 11 of 541 of 54
APP-003-D3 ALARM
***
PRT HI/LO LVL *** WILL REFLASH *** AUTOMATIC ACTIONS
- 1. Not Applicable CAUSE High
- 1. Excessive makeup water added
- 2. In leakage from Makeup Water, Pressurizer Relief Valves, Pressurizer Safety Valves, RHR Loop Relief Valves, Letdown Relief Valves, Seal Water Return Relief Valve, SI Test Line Relief Valve, or SI Cold Leg Injection Header Relief Valve
- 3. Opening of Pressurizer Safety or PORV Low
- 1. Leakage from PRT to the Reactor Coolant Drain Tank or other area.
- 2. Excessive draining.
OBSERVATIONS
- 1. (LI-470), Pressure (PI-472),
PRT Level (L1-470), (P1-472), and Temperature (TI-471)
- 2. Tl-467, TI-469)
Pressurizer Safety Valve Line Temperatures (TI-465, TI-467,
- 3. PORV Discharge Line Temperature (TI-463)
ACTIONS
- 1. IF a PZR PORV or Safety fails open while greater than 350°F, THEN Refer To Path-1.
Path-i.
- 2. OP-i 03.
IF level is high, THEN drain the PRT using OP-103.
- 3. IF level is low, THEN add Primary Water to the PRT using OP-103.
OP-i 03. DEVICE/SETPOINTS
- 1. LC-470 I/ 83%
- 2. LC-470 /I 68%
POSSIBLE PLANT EFFECTS 1.
- 1. None Applicable REFERENCES 1..
1 Path-i, Path-1, EOP Network
- 2. OP-i OP-103,03, Pressurizer Relief Tank Control System
- 3. CWD B-i 90628, Sheet 461, Cable M, N B-190628, N IAPP-003 Rev. 37 Page 33 of 53 531
COLD LEG RECIRC - RHR FLOW> - FLOW >1200 1200 GPM, RCS<125 PSIG RHR-FIGURE-3
,------,-------------------------11/1-1----..,
SI*887 TOSI PUMP B&C * ~411 ISI*891 C SUCTIONS
......-
SI*891 D RHR*752B TO SIAND CONTAINMENT RHR*764 RHR*754B SPRAY PUMP SUCTIONS
~
;;-
<;:
.... RHR PUMP B o .'4 .'4 . FROM RWST
~
;;-
!i!n RHR*757A RHR PUMP A evcs I' r- ___ .J l+
RHR*
~
FCV*605
~
-~
- --'~ -
MINI FLOW RECIRC FROM CONTAINMENT SUMP TO PRESSURIZER RHR HEAT-UP LINE RELIEF TANK RHR*743 TO RC lOOP 1
~
~
SI.:a7sA COLD lEG
....
~
TO RC LOOP 3 ~ COLD lEG ~ Ul o TO RC lOOP 2 COLD lEG FROM RC FROM LOOP RC LOOP RHR*744B RHR-744B SI*876B SI-876B SI*875B SI-875B HOT lEG 22 HOT LEG INFORMATION INFORMATION USE USE ONLY ONLY
HLC-08 NRC HLC-08 NRC Written ExamExam
- 6. Given
- 6. Given the the following:
following: The Crew
- The
- Crew is responding to is responding to aa LBLOCA LBLOCA lAWlAW PATH-1 PATH-i and and are are unable unable to to start any any CCW COW pumps.
pumps. AOP-0i4, CCW SYSTEM MALFUNCTION, Section "C",
- AOP-014,
-
C, CCW COW PUMP DISCHARGE PRESSURE LOW is being performed.
- An AO was dispatched to perform Attachment 1, EMERGENCY COOLING TO
-
CHARGING PUMPS.
- Charging Pump "B"
- B is running with speed controller in MANUAL set at 75%.
- All RCP Thermal Barrier DP indications are at approximately 3.5 inches.
-
- AOP-0i4, Section "c"
- Step 9 of AOP-014, C directs raising Charging Pump speed to obtain RCP Thermal Barrier DP of of>> 5 inches.
Which ONE (1) (i) of the following is the reason for raising the RCP Thermal Barrier DP to to>
>5 inches?
A. The increased charging rate ensures RCP POP seal leakage will be minimized. B. ONLY seal injection is available for cooling, since there is no CCW COW to the Thermal Barriers. C. The increased charging rate ensures the Charging Pump temperatures remain low until Attachment 11 is completed. D. Increasing the Thermal Barrier DP is in preparation for restarting the RCP(s) after CCW COW is restored.
\"D\\ bs ~ ~~\<--e CvJ'.'(
~ sc:... L'_il'+~ C'~ G:vc-r
\o-vcc\,\L Lot.
cc U:1l- fJ-, 66
HLC-08 NRC Written Exam
- 6. 000026 AAl.02 AA1.02 OOllLOSS CCW/1/1/3.2/3.3/RO/LOW/N/AJNBW - 2008/AOP-014-003 001/LOSS OF CCW/l/l/3.2/3.3IROILOW/N/A/NEW -
Given the following:
- The Crew is responding to a LBLOCA
-
PATH-i and are unable to start any CCW LBLOCA lAW PATH-1 pumps.
- AOP-014, CCW SYSTEM MALFUNCTION, Section "C",
- C, CCW PUMP DISCHARGE PRESSURE LOW is being performed.
- An AO was dispatched to perform Attachment 1, EMERGENCY COOLING TO
-
CHARGING PUMPS.
- Charging Pump "B"
- B is running with speed controller in MANUAL set at 75%.
- All RCP Thermal Barrier DP indications are at approximately 3.5 inches.
-
- Step 9 of AOP-O1
- AOP-014, 4, Section "C" C directs raising Charging Pump speed to obtain RCP Thermal Barrier DP of of>> 5 inches.
Which ONE (1) of the following is the reason for raising the RCP Thermal Barrier DP to to>> 5 inches? A. The increased charging rate ensures RCP seal leakage will be minimized. B:' BY ONLY seal injection is available for cooling, since there is no CCW to the Thermal Barriers. C. The increased charging rate ensures the Charging Pump temperatures remain low until Attachment 11 is completed. D. Increasing the Thermal Barrier DP is in preparation for restarting the RCP(s) after CCW is restored. The correct answer is B. A: Incorrect - RCP Seal leakage is NOT a concern for LBLOCA, but is a step for increased
-
seal leakage. B: Correct -- Thermal Barrier Delta P is the only means of ensuring pump seals are receiving adequate cooling. C: Incorrect - Step 9 RNO has direction to wait until Attachment 11 is complete before reducing
-
Charging Pump speed to minimum, but NOT for Charging Pump temperature. D: Incorrect - Raising Thermal Barrier Delta P
- P to minimum is a step to start RCPs, but no restart of RCP will occur in this situation.
Tuesday,Junel7,20081:21:O1 Tuesday, June 17,20081 :21 :01 PM 7
HLC-08 NRC HLC-08 Written Exam NRC Written Exam Question Number: Exam Question Exam Number: 66
Reference:
AOP-014,
Reference:
C, Page Section C, AOP-014, Section 40; AOP-014 BD, Page 40; Page 24. SD, Page 24. KA Statement: Ability to KA Statement: to operate operate and monitor the or monitor and I/ or the following as as they apply to to the Loss of the Loss of Component Cooling Water: Loads on the CCWS in the control room. History: History: New - HLC-08 NRC exam. New - Written for HLC-08
- Tuesday, Tuesday, June June 17, 17, 20081 :21 :01 2008 1:21 :01 PM PM 8
24 Rev. 24 AOP-014 AOP-0l4 WATER SYSTEM COMPONENT COOLING WATER SYSTEM MALFUNCTION 40 of Page 40 of 104 104 __STEP H INSTRUCTIONS I I SECTION C SECTION C OBTAINED RESPONSE NOT OBTAINED CCW PUMP DISCHARGE PRESSURE LOW (Page 5S of 7)
~ Check RCP Thermal Barrier P - ~P - Increase Charging Pump speed to GREATER THAN 5S INCHES maintain RCP Thermal Barrier P ~P greater than 5S inches.
- PI-13lA PI-131A WHEN Attachment 11 has been been
** PI-128A completed.
completed, THEN perform the following:
- PI-l25A PI-l2SA
- a. Reduce the running Charging Pump to minimum speed.
- b. Locally throttle RCP SEAL WATER FLOW CONTROL VALVE(s) to assure at least 66 gpm flow to each RCP.
- CVC-297A CVC- 297 A
- CVC-297B
- CVC-297C
- 10. Notify Chemistry Personnel To Stop Any Sampling In Progress
*11. Determine If Emergency Cooling To Spent Fuel Pit Heat Exchanger Is Required As Follows:
- a. Check APP-036-B4.
APP-036-B4, SPENT FUEL a. IF at any time APP-036-B4 PIT HI TEMP - ILLUMINATED
-
illuminates. illuminates, THEN perform Step 11. b. 11.b. Go To Step 12.
- b. Align emergency cooling to the Spent Fuel Pit Heat Exchanger using Attachment 2. 2, Emergency Cooling To Spent Fuel Pit Heat Exchanger.
Exchanger, while continuing with this procedure
BASIS DOCUMENT, COMPONENT BASIS DOCUMENT, COMPONENT COOLING COOLING WATER WATER SYSTEM SYSTEM MALFUNCTION MALFUNCTION Step Description Description While starting While starting and and stopping Charging Pumps, stopping Charging Pumps, thethe operator operator should should observe observe Seal Injection flow Seal Injection flow by checking Thermal by checking Thermal Barrier Barrier indications. indications. During During this this period no CCW cooling to the Thermal period no CCW cooling to the Thermal Barrier exists, Barrier exists, therefore therefore the the only only seal seal cooling is cooling provided by is provided intermittent seal by intermittent seal injection. injection. (CR (CR 95-1752, 95-1752, see see Section Section A, step 34 A, step additional information) for additional 34 for information) 10 10 Chemistry is Chemistry is notified notified to stop sampling due to the lack to stop lack of of COOling cooling to the the heat heat exchangers. exchangers. 11 11 determines if cooling must This steps determines must be supplied to the SFP Heat Heat Exchanger. The step checks temperature above the high temperature alarm alarm commences efforts setpoint, then commences efforts to establish establish cooling. cooling, ItIt is is not expected that the SFP SEP will reach elevated temperatures for an extended period of time. This procedure assumes that refueling efforts are NOT in progress. Should those efforts be underway, plant procedures are in place to more rapidly establish emergency cooling in the event that normal cooling is lost. 12 This step acts as a hold point until a CCW Pump is started. At this point all actions to restart a pump have been directed and emergency cooling is established where possible. 13 If Charging Pumps are being supplied by emergency cooling they may now be restored to normal cooling. Engineering is consulted at this point to determine what restoration should be used based on the type of cooling used. The pump coolers will have been contaminated with high chloride water and may require extensive flushing. 14 14 This step determines if Charging and letdown should be reestablished reestablished.. If the RCS is above 150°F 150°F charging will be required. If RHR is not in the Core Cooling Mode Mode letdown will be required. If these are required required subsequent subsequent steps will establish. IfIf not, the operator is is transitioned around the steps. 15 15 IfIf charging is is required, pumps pumps are started (see above).above). 16 16 IfIf letdown letdown is is required itit is is placed placed in in service using using the appropriate procedure. procedure. This step is entered step is entered ifif previous previous steps steps determined that that charging charging and and letdown letdown must must be be placed placed in in service. service. IAOP-014-BD AOP-014-BD Rev. Rev. 24 24 Page Page 2424 of of 34 341
HLC-08 NRC Written Exam
- 7. Given the following:
Reactor failed to automatically trip when the Reactor Coolant Pumps
- The Reactor
- Pumps tripped.
- APP-005-F6, AMSAC TRI
- TRIP P alarm is illuminated.
Which ONE (1) of the following will result? A. Turbine trip and and ALL AFW Pumps start. B. Reactor trip and and ALL AFW Pumps start. C. Reactor trip and and ONLY MDAFW Pumps start. D. Turbine trip and and ONLY MDAFW Pumps start. 4'N.~ ().~ ~ çc- \~ LtfY)cVtl W\5
~t- ctu $.. eM C CVU L<;:I!l?lA..\t\ C -
Cj-, \y
~ e.., frSAR) tv\S) AFw 'CL$ \>tt-w.{> 5> 'b D
s~~? 7
HLC-08 NRC HLC-08 Written Exam NRCWritten Exam
/1/4.1/4.1IROJHIGHJN/AINEW -2008IAMSA C-006 7.7.00002902.1.28 001/ATWS/1/1I4.1I4.1IRO/HI0H/NINNEW 000029 G2.1.28 001/ATWS/1 -
2008/AMSAC-006 Given the Given thefollowing: following:
-
- The The Reactor Reactorfailedfailed to automaticallytrip to automatically when the trip when the Reactor Pumpstripped.
Coolant Pumps Reactor Coolant tripped.
-
- APP-005-F6 APP-005-F6, AM8AC TRIP
, AMSAC alarm isis illuminated.
TRIP alarm illuminated. Which ONE Which ONE (1) (1) of of the the following will result? following will result? A'I Turbine A Turbine trip trip and and and and ALL ALL AFW Pumps start. AFW Pumps start. B. Reactor B. Reactor trip trip and and andand ALL ALL AFW Pumps start. AFW Pumps start. C. Reactor C. Reactor trip trip and and andand ONLY MOAFW Pumps ONLY MDAFW Pumps start. start. D. Turbine D. Turbine trip trip and and and and ONLY MOAFW Pumps ONLY MDAFW Pumps start. start. The correct The correct answer is is A. A: Correct - AMSAC trips the Turbine and starts BOTH MDAFW and the SDAFW A: Correct - Pump. Pump. B: Incorrect - AMSAC does NOT trip the Reactor at RNP. B: Incorrect - C: Incorrect - AMSAC starts ALL AFW Pumps, NOT just the MDAFW Pumps. C: - D: D: Incorrect - AMSAC does NOT trip the Reactor at RNP and the circuit starts ALL
-
AFW Pumps Pumps.... Exam Exam Question Question Number: 7
Reference:
APP-005-F6; 80-062,
Reference:
APP-005-F6; SD-062, AM8AC, AMSAC, Figure 1. 1. KA KA Statement: Statement: Knowledge Knowledge of of the purpose and the purpose function of and function major system of major system components and components and controls. controls. History: History: New New - Written
- Written forfor HLC-08 HLC-08 NRC exam.
NRC exam. Wednesday, Wednesday,JuneJune18, 18,200810:14:50 2008 10:14:50AM AM 99
APP-005-F6 APP-005-F6 ALARM ALARM AMSACTRIP AMSAC TRIP AUTOMATIC AUTOMATI ACTIONS C ACTIONS 1.1. Motor and Motor and Steam Driven AFW Steam Driven Pumps Start. AFW Pumps Start. 2.
- 2. Turbine Trips.
Turbine Trips. CAUSE CAUSE 1.
- 1. Low-Low Level Low-Low Level in in two two out out of three Steam of three when above Generators when Steam Generators above 40% turbine load.
40% turbine load. OBSERVATIONS OBSERVAT IONS 1.
- 1. S/G A S/G "A" Level Level (LI-474)
(LI-474) 2.
- 2. "B" Level S/G B Level (Ll-485)
(LI-485) 3.
- 3. "C" Level S/G C Level (Ll-496)
(LI-496) 4.
- 4. Turbine (PI-446 & P1-447)
Turbine First Stage Press (P1-446 PI-447) ACTIONS 1.
- 1. IF a reactor trip has occurred, THEN refer to EOP Network.
IF DEVICE/SETPOINTS DEVICE/SE TPOINTS 1.
- 1. AMSAC PROCESSOR AMSAC PROCESSOR -
S/G Level Narrow Range LLT-474, LT-485, T -47 4, LT -485, LLT-496 / 11% T -496/11 %
-
Turbine First Stage Press PT-446, PT-447 1 /191 191 psig (35%) POSSIBLE PLANT EFFECTS
- 1. Plant Shutdown REFERENCES REFERENCES
- 1. EOP Network
- 2. CWD B-190628, B-i 90628, Sheet 1731 IAPP-005 APP-005 I Rev. 29 Rev. 29 I Page 40 Page of 40 40 of 40 II
AMSAC LOGICDRAWING AMSACLOGIC DRAWING AMSAC-FIGURE-AMSAC-FIGURE-l 1 LT-474 LT-485 LT-496 PT-446 PT-447 2/3 2/2
<11% 360 Second 360 Second 35%
T.D. T.O. Relay Relay JJ~. ARM li J<J IX RTGB BYPASS 25 Second ~ T.O. T.D. Relay \...t3t...
~
URBINE RIP/AFW amsacfCl amsacf01 START INFORMATION INFORMATION USE USE ONLY ONLY
HLC-08 NRC HLC-08 NRC Written Exam Exam Given the
- 8. Given
- 8. the following:
The crew
- The
- crew is is responding responding to to aa SGTR SGTR inin S/G A with aa loss SIG "A" loss of of offsite offsite power.
power. Supplement G
- Supplement
- is in G is in progress.
progress.
- ALL S/G pressures are 1025
- 1025 PSIG.
P51G.
- ALL S/G PORVs are partially OPEN.
-
- The step in Supplement G which requires Steam Flow to be isolated from the ruptured
-
S/G has just been reached. Which ONE (1) of the following describes the action that is required regarding the ruptured S/G PORV lAW Supplement G? A. Raise the RUPTURED S/G PORV controller's controllers setpoint to MAXIMUM. B. Verify the RUPTURED S/G PORV controller's controllers setpoint at 1035 PSIG. C. Reduce the RUPTURED S/G PORV controller's controllers setpoint to 1000 PSIG. D. Verify the RUPTURED S/G PORV controllers' controllers setpoint is 15 PSIG less than the INTACT S/G PORV controllers.
' A1 II ~\GW~~ \,'1 \\<f-y ? Luheovt Q ? wolA\b iv ~ U'fU/(d~f:S tccs
-tcde \'CL/'s.e dQs ~\-~+ ~ 1'f\c,)<.I\<v\.u,Vv -: bo y\ t.y eve" do c i-~ s ?
jD Ck_ )v 88
HLC-08 NRC HLC-08 NRC Written Exam
- 8. 000038 G2.1.20 001/SGTRI1/1/4.6/4.6IROILOW/N/A!RNP
- 8. 001lSGTR/1I114.6/4.6IROILOWINIAIRNP BANKIPATH-2-003 Given the following:
- The crew is responding to a SGTR in S/G A
- "A" with a loss of offsite power.
- Supplement
- Supplement G in progress.
G is in S/G pressures are 1025
- ALL SIG
- 1025 PSIG.
- ALL S/G PORVs are partially OPEN.
-
-- The step in Supplement G G which requires Steam Flow to be isolated from the ruptured S/G has just been reached.
Which ONE (1) of the following describes the action that is required regarding the ruptured S/G PORV lAW Supplement G? A. Raise the RUPTURED S/G PORV controllers controller's setpoint to MAXIMUM. 8:1 Verify the RUPTURED S/G PORV controllers B controller's setpoint at 1035 1035 PSIG. C. Reduce the RUPTURED S/G controller's setpoint to 1000 PSIG. SIG PORV controllers D. Verify the RUPTURED S/G controller& setpoint is 15 PSIG less than the INTACT SIG PORV controllers' SIG PORV controllers. S/G The correct answer is B. A: Incorrect - Placing the ruptured S/G
- SIG PORV to MAXIMUM is undesirable as the PORV will NOT OPEN and pressure may reach S/G SIG safety valve setpoint.
B: Correct - - The setpoint on the ruptured S/G PORV is increased to 1035 PSIG from 1025 PSIG. This minimizes the potential for radiological release and ensures the PORV is maintained available to prevent challenging the S/G SIG safety valves. C: Incorrect - Reducing the RUPTURED S/G PORV's
- PORVs setpoint would result in MORE, NOT less release of radioactive fluid to the atmosphere.
D: Incorrect - Reducing the RUPTURED S/G's
- S/Gs PORV setpoint to less than the intact S/Gs would result in more steam flow from the contaminated S/G, SIG, rather than from the SIGs.
intact S/Gs. Exam Question Number: 8
Reference:
Supplement G, 3, Page 37; Supplement G BD, Pages 4 and 7. KA Statement: Ability to interpret and execute procedure steps. History: Direct from Bank. Wednesday, June 18, 10:14:50 AM 18, 2008 10:14:50 10
Rev. 35 EPP-Supplements SUPPLEMENTS Page 37 of 89 -j__STEP H INSTRUCTIONS I I CONTINUOUS USE RESPONSE NOT OBTAINED I Supplement GC Steam Generator Isolation (Page 11 of 12) vt.
- 1. Go To Appropriate Step From Following Table:
S/G TO BE ISOLATED STEP S/G S/GA A 22 S/G S/GBB 18 S/G S/CcC 34
~~ 2. Check S/G A A - FAULTED
-
~~ WHEN Tavg less than 547°F, THEN perform Steps 3 3 AND 4.
WHEN S/G S/C A A level is greater than 8% [18%J, [18%] THEN observe the NOTE
,
prior to Step 5 5 and perform Steps 55 though 9. _.--\ 7 Verify ruptured STEAM LINE PORV",,", PORV setpoint at 1035 psig using )) atus Board . " '...------ sBoard. Go To Step 11.
- 3. Verify VI-3A, V1-3A, MSIV - CLOSED
-
- 4. Verify MS-353A, MSIV VI-3A V1-3A BYP --
CLOSED CLO S ED NOTE Local operation of the FRV and B/P valves below is via reverse acting handwheels.
- 5. Verify FRV A A - CLOSED
-
- 6. Verify FRV A A BYP - CLOSED
-
Supplement Supplement G G - This
- This supplement provides the supplement provides Operator with the Operator listing of with aa listing of valves valves to to be be closed closed toto isolate isolate aa Steam Steam Generator.
Generator. The The Supplement differentiates between Supplement differentiates between the two types the two types of of SIG problems to S/G problems to ensure ensure that that the the proper proper actions are actions are taken taken to safely isolate to safely isolate the the S/G. Therefore the S/G. Therefore the Supplement Supplement ensuresensures that that the the MSIV MSIV on on aa ruptured ruptured SIG not closed S/G isis not closed prior to RCS prior to temperature being RCS temperature less than being less than 54?DF 547°F thereby thereby preventing preventing an an inadvertent inadvertent lifting lifting of of the Steam the Steam Line Line PORV while the PORV while the MSIV MSIV on faulted SIG on aa faulted S/G isis immediately immediately closed closed to to minimize minimize the the uncontrolled uncontrolled cooldown. The cooldown. The UFSAR credits SIG UFSAR credits isolation within 30 S/G isolation minutes for the 30 minutes the consequences consequences of of the the Off-Site Off-Site Dose Dose release. From the original release. From original licensing basis this is licensing basis considered to occur is considered occur when the MISV affected SIG MISV on the affected S/G isis closed (Original closed (Original FSAR chapter 14 FSAR chapter description). 14 description). 8.
- 8. Supplement Supplement H H - This supplement provides
- provides the Operator Operator with aa listing listing of of valves valves that that require require local local checks checks for Phase A Verification during Phase loss of during aa loss of DC. intent is DC. The intent is that the Operator Operator will perform perform normal normal verification for those valves that have indication in the Control Room. Then also dispatch an Operator to locally verify the valves listed in the Supplement. The Supplement only checks those valves that do not have redundant isolation with indication in the Control Room.
- 9. Supplement I - This supplement provides the Operator with an abbreviated lineup for placing the RHR System
-
in the Core Cooling Mode. This Supplement is referenced in numerous procedures throughout the EOP Network during evolutions involving an RCS cooldown. This supplement provides the minimum items necessary to place the RHR System in the Core Cooling Mode in an expeditious manner, reflecting the priorities of the EOP Network.
- 10. Supplement J - This supplement provides a methodology for determining RHR flow in the event that FT-605
-
becomes inoperable. FT FT-605
-605 does not have redundant indication.
- 11. Supplement K - This supplement provides valve alignments that may be used to enhance Auxiliary Spray flow
-
when required in the EOP Network. Various procedures within the EOPs require the use of Auxiliary Spray. Should the flow rate available from charging be insufficient to reduce pressure, this supplement may be used to increase flow by forcing all charging flow through the Auxiliary Spray valve instead of both Auxiliary Spray and the normal Charging Line. To provide for a finer control of the spray flow into the Pressurizer and the subsequent RCS pressure changes, the Charging Pump Speed can be varied or the normal Pressurizer spray valves from the RCPs can be modulated to provide a recirc path back to the RCS cold leg. This supplement is not required to be used. It is only included should the operator need to reference the steps.
- 12. Supplement L - This supplement provides the guidance for verifying automatic equipment start following an SI.
-
Its use is directed from within procedures which may require an SI, but from which exiting to Path is not desired. An Operator would use the Supplement to verify equipment starts while the Control Room Team remains in the primary procedure. This occurs primarily in FRPs, such as FRP-S.1 and FRP-H.1. 13.
- 13. Supplement M M - This supplement provides a list of components in the secondary that must be secured
-
following isolation of SW to the Turbine Building. The Supplement ensures that the MSIV on aa ruptured S/G SIG is not closed prior to RCS temperature being less than 547°F thereby preventing an inadvertent lifting of the Steam Line PORV. This list is too lengthy to be provided in the Path. 14.
- 14. Supplement N N - This supplement provides the steps necessary to isolate aa ruptured S/G
- SIG from the intact S/Gs SIGs on failure of the ruptured S/G SIG MSIV MSIV to close when demanded. The steps are derived from WOG ERG, E-3.
These steps had formerly been in Path-2, however, due to difficulties experienced by some crews in performing the steps, they were moved to this supplement in order to provide more detailed information in the steps than can be be provided provided in in the path path decision and action decision and action blocks. These steps steps are are necessary necessary ifif anan MSIV MSIV fails to close since since the WOG strategystrategy requires thatthat the ruptured ruptured S/GSIG pressure pressure remain elevated in in order to limit limit the the amount amount of of depressurizatiori depressurization required to stop the primary to secondary leakage. By By isolating isolating the the ruptured S/G SIG from thethe intact S/Gs, SIGs, the RCS may may be be cooled by by steaming steaming the the intact S/Gs SIGs to atmosphere atmosphere without effecting the pressure pressure in in the ruptured S/G. IEPP-SUPP-BD EPP-SUPP-BD I Rev. Rev. 35 35 I Page Page 44 of of 10 10 II
RNP RNP Basis Basis STEP STEP Supplement G Supplement G This supplement This supplement is transitioned to from various points is transitioned in the pOints in EOP Network. the EOP instructions to contains instructions Network. ItIt contains isolate the S/Gs. Placing these instructions isolate the SIGs. Placing these instructions in a in a supplement prevents prevents repeating this information information aa number of of times times in in the EOP EOP Network. Network. The supplement is is structured such that Operator may that the Operator may move quickly to the the appropriate step step to isolate the isolate the faulted or or ruptured ruptured SIG. S/G. An An RNO RNO is provided early is provided early in section to each section in each to provide steps that provide for steps that dependent when aa SIG are time or condition dependent S/G Tube Rupture has occurred. Generally, the Operator Operator will stay in the left (AER) column for aa Faulted S/G and enter the RNO at step aa for aa Ruptured S/G. The step for verifying the S/G PORV closed is only reached if the S/G is faulted since since for aa rupture the action is to verify the correct setpoint. During aa fault or aa ruptured-faulted, the pressure will always be be below the setpoint and therefore should be closed. Once dry out occurs for the affected S/G, actions are directed to dump steam from intact generators to control RCS RCS repressurization and temperature increase. The MSIV Above and Below Seat drains are listed as aa check step with an RNO to direct the Operator" to close the appropriate valve. The intent of these steps is to ensure that the "Dedicated Operator Dedicated valves are closed by the most expeditious means. It is expected that the CRSS will know if any have been opened since these valves are normally locked closed and are controlled under the Containment Integrity Program of OP-923. There is Q NO intent to dispatch an operator to locally check these valves. If they are open, an operator will be pre-designated for closure in the event of an accident. Directions have been provided in the RNO for isolating instrument air to a failed open S/G PORV. A note has been included reminding the operator that at least one PORV is needed for decay heat removal if the condenser is not available. Thus for a ruptured S/G one would not wish to use the common isolation valve which isolates motive air to all three S/Gs if the condenser is unavailable since there would then be no way to cool down the RCS. The final section of the procedure deals with minimization of the spread of secondary contamination. These actions are consistent with those performed in Path-2 and AOP-035. The actions are credited in the response to INPO SOER 93-01 GS-36 is closed to assure that the Auxiliary Boilers will be capable of supplying Gland Seal Steam. (OPEX AR 18118, Indian Point 2 SGTR Event) Supplement H Supplement H is intended to be used during a Loss Loss of DC DC Bus A or B to verify Containment Isolation. Loss of DC will remove power to numerous lights for the Status Panels (Pink & Blue Lights). The Supplements are constructed to check only those valves that do not not have redundant indications on the panels or the RTGB. Thus, the Operator would check all indications that are available via normal mechanisms, and in addition, those valves listed in the appropriate section of Supplement H. On On aa loss loss of of DC DC Bus Bus A (step (step 1), 1), only only one one valve does not have does not have redundant indication (SI-855). redundant indication (SI-855). On a loss of of DC Bus Bus B there are multiple valves without redundant indication. indication. ItIt is expected that checking these valves locally locally will take some time. This is considered acceptable for several several reasons. The accident in in question is is beyond beyond the design basis for the plant, and is is therefore notnot considered to be be aa credible credible accident. accident. The The valves valves all all fail fail on loss of on aa loss power to of power to the the close position. Finally, close position. the Finally, the procedure procedure assumes assumes NO NO other other accident accident in in progress progress forfor aa loss loss of of DC. DC. IEPP-SUPP-BD EPP-SUPP-BD Rev. Rev. 35 35 Page 77 of Page 10 of 10 I
HLC-08 NRC HLC-08 NRC Written Exam Exam Given the
- 9. Given
- 9. the following:
The plant
- The
- plant was operating operating at at 100%
100% RTP RTP when S/G S/G "A" A Steam Steamline line severs inside inside Containment. Containment. Which ONE (1) of the following describes the FW valves that should have CLOSED? A. FRVs for ALL THREE S/Gs (FCV-478, 488, 498) FRV BYPs for ALL THREE S/Gs (FCV-479, 489, 499) FW HDR SECTION Valves for ALL THREE S/Gs (V2-6A1B/C) (V2-6AJBIC) B. FRVs for ALL THREE S/Gs (FCV-478, 488, 498) FRV BYPs for ALL THREE S/Gs (FCV-479, 489, 499) FW HDR SECTION Valve for S/G "A" A ONLY (V2-6A) ji N,d C. FRV for S/G "A"A ONLY (FCV-478) FRV BYP for S/G "A" A ONLY (FCV-479) FW HDR SECTION Valve for S/G "A" A ONLY (V2-6A) D. FRV for S/G "A"A ONLY (FCV-478) \11) I p~s ~'b ~ kl-y?' FRV BYP for S/G "A" A ONLY (FCV-479) FW HDR SECTION Valves for ALL THREE S/Gs (V2-6A1B/C) (V2-6A!B/C) W wocJc\t+ ~j(e Hew S.\&v1se b PR-F9y d:tt r-{<v 1S/p+o dose- 1y fe/l- iJvce:. "¥i" ~J~ OV]
':1 e-+ r=\iYf'o~e..- iSo\c<,.:\-.-J t<J 0\-\ \ 3 <;/6r5?
"3 /?
99
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 9. 000040 000040AA1.02 AAl.02001/STM OOllSTMLINE LINERUPTUREI1 /114.5/4.5JROJHIGHJN/AJNEW -2008IESF-00 RUPTURE/1I1I4.5/4.5IROIHIGHININNEW 2008/ESF-0055 9.
-
Given the Given the following: following:
-
- The The plant plant was was operating operating at at 100%
100% RTP when SIG RTP when S/G °A severs inside Steam line severs "A" Steamline inside Containment. Containment . Which ONE Which ONE (1) (1) of of the the following describes the following describes the FW valves that FW valves should have that should have CLOSED? CLOSED? A:I FRVs A FRVs forfor ALL ALL THREE THREE S/Gs (FCV-478, 488, S/Gs (FCV-478, 488, 498) 498) FRV BYPs for ALL THREE S/Gs (FCV-479, 489, 499) FRV BYPs for ALL THREE S/Gs (FCV-479, 489, 499) FW HDR FW HDR SECTION SECTION Valves Valves for ALL THREE for ALL S/Gs (V2-6A/B/C)) THREE S/Gs (V2-6AJBIC B .. FRVs B. FRVs forfor ALL ALL THREE THREE SIGs (FCV-478, 488, S/Gs (FCV-478, 488, 498) 498) FRV BYPs for ALL FRV BYPs for ALL THREE S/Gs THREE S/Gs (FCV-479, (FCV-479, 489, 499) 489, 499) FW HDR FW HDR SECTION SECTION Valve S/G A Valve for S/G "A" ONLY (V2-6A) ONLY (V2-6A) C. FRV C FRV for S/GS/G A"A" ONLY ONLY (FCV-478) FRV BYP FRV BYP for SIG S/G A "A" ONLY ONLY (FCV-479) (FCV-479) FW HDR FW HDR SECTION Valve for S/G A "A" ONLY (V2-6A) D. FRV for SIG D S/G A"A" ONLY (FCV-478) FRV BYP for S/G A "A" ONLY (FCV-479) HDR SECTION Valves for ALL THREE S/Gs (V2-6AJB/C FW HDR FW (V2-6A/B/C)) The The correct answer is A. A: Correct A: Correct - - A S/G SIG steam line severing inside Containment would cause CV pressure to steamline increase to above the CV SI setpoint. When Safety Injection actuates, feedwater will be isolated to ALL S/Gs. B: B: Incorrect - Safety Injection isolates ALL FW HDR Section valves.
-
C: Incorrect - Correct answer for FRV and FRV Bypass valves if there were a high S/G C: Incorrect - SIG level. FW FW HDR HDR Section valves do NOT NOT go CLOSED on a S/G level. SIG high level. D: D: Incorrect Incorrect - Correct
- Correct answer answer for for FRV FRV andand FRV valves ifif there Bypass valves FRV Bypass there were were aa high high S/G level.
SIG level. FW FW HDRHDR Section Section valves valves do NOT go do NOT on a SIG high CLOSED on a S/G high level. go CLOSED level. Exam Exam Question Question Number: Number: 99
Reference:
Reference:
SD-006, SD-006, ESF, ESF, Figure Figure 12.SD-027, 12.SD-027, FW, Page 20. FW, Page 20. KA KA Statement: Statement: Ability Ability to to operate operate andand // or monitor the or monitor apply to they apply as they following as the following the Steam to the Line Steam Line Rupture: Rupture: Feedwater Feedwater isolation. isolation. History: History: NewNew - Written
- Written for for HLC-08 HLC-08 NRC Exam.
NRC Exam.
- Tuesday, Tuesday,June June 17,20081:21:02 17, 2008 1:21:02 PM PM 11 11
FEEDWATER FEEDWATE ISOLATION LOGIC R ISOLATION LOGIC ESF-FIGURE-12 ESF-FIGUR E- 12 STMGEN.A STMGEN.A GEN. BB STMGEN.C STMGEN.C STMGEN. STM HIGH LEVEL HIGH LEVEL HIGH LEVEL 1-UGH LEVEL HIGH LEVEL HIGH LEVEL I n II m I n II m I NotRedun~t Not Redundant - - . j Nat Redundan'r- __ I I .... R I
-----~ ----~
I L-CLOSE CLOSE CLOSE CLOSE CLOSE CLOSE CLOSE CLOSE CLOSE
, (5 SEC)
~ _____--,.1 (5 SEC) BYPASS FEEDWATER CONTROL VAlVE (5 SEq (5 SEC) .I BYPASS FEEDWATER , (5 SEC) * (5 SEC)/ ~~~~~~~~¢~R MAIN FEEDWATER CONTROL VALVE MAIN FEEDWATER FCV-499 MAIN FEEDWATER FCv-479 CONTROL VALVE FCV-488 FCV-489 CONTROL FCV-498 VALVE FCV-498 CONTROL VAlVE
~_ _ _ _ _-,=C::::O:!.:NT:.::R~O~Lc.:V~Al::::V:.!;tFCV-478 ,
v vr-------------------J/ STMGEN.C STM. GEN. A STMGEN B STMGEN.C FEEDWATER MAIN FEEDWATER MAIN TURBINE PUMP TRIP PUMP TRIP TRIP TRIP INFORMATION INFORMATION USE USE ONLY ONLY
SD-027 SD-02 7 Feedw ater System Feedwater System program progra m level.
- 2. Depres
- 2. Depresss the AUTO pushbu tton on the FRV contro pushbutton ller AND slowly close the controller tive bypass valve.
respective respec
- 3. Verify each FRV in AUTO is mainta
- 3. ining progra maintaining mmed level.
programmed
- 4. If necess ary a FRV can be placed in Manua necessary controll level.
Manuall to contro The feedwa The feedwater lating valve closes as flow is increas recirculating ter pump recircu ed above its set point of increased 3100 gpm. condensate The second conden 45-50 % power and the second main feedwa sate pump is started at 45-50% ter feedwater pump is started at 55-60% power. As the unit is shutdo wn, the above proced shutdown, procedure ure is follow ed in reverse order. followed 6.2 mal Operat Abnormal Abnor Operation ion AOP-010, AOP-0 10, Main Feedw Feedwater/Condensate Malfunction ater/Condensate Malfunction AOP-025, AOP-0 Instrument Failure 25, RTGB Instrument 6.2.1 Feedw Feedwater ater flow will be affecte d by receipt of the follow affected following mannerr ing signals in the manne ed: described: describ
- 1) Low TAVG °F) plus a reactor trip will close the steam generator TAVG (554 OF) feedwater generator feedwater regulating regulat valves, FCV-478, ing valves, FCV-488, and FCV-498.
FCV-478, FCV-488, FCV-498. generator level (75% narrow range) in any steam generator
- 2) A high steam generator generator will close the associated feedwater regulating associated feedwater regulat ing valve, FCV FCV-4 78, FCV
-478, FCV-4 88, or
-488, FCV-498, the associated FCV-498, regulating bypass valve, FCV-479, feedwater regUlating associated feedwater FCV-479, FCV-FCV 489, or FCV FCV-4 99, trip the main feedwater
-499, ter feedwa pumps and trip the turbine. turbine .
mismatch (0.64 X 10 steam/feedwater flow mismatch
- 3) A steam/feedwater 1066 lbs/hr) in conjunction conjunction with a low steam generator (30%
generator level (30 % narrow range) will initiate a reactor trip. low-low water level (16% narrow range) will initiate a generator low-low
- 4) A steam generator auxiliary feedwater reactor trip and start the auxiliary feedwater pumps.
pumps.
- c:. ---------- --
-".~- ..- . - - . - - ----------
feedwater header section valves, Thjection signal will close the feedwater
- 5) A Safety Injection FWN\
valves, FW-V2-6A, FW-V2-6C, open the feedwater FW-V2-6B, and FW-V2-6C, V2-6A, FW-V2-6B, feedwater pump breakers, breakers, Close the steam generator feed;~ter regulating valvesj'CV-478JCV-488,
~-and FCV498-and the steam generator generator feedwater feedwate regu~JP~_~_yaIY.es rjgypassva1y FCV-479, FCV-489, and FCV-A99.-_
- 6) An AMSAC bypassed, will cause a turbine trip;the--atmliary AMSAC signal, if not bypassed, theauxjliary feedwater pumps to start, and the steam generator feedwater blowdown valves to close.
generator blowdown FW Page 20 of 35 Revision 8 INFORMATION INFORMATION USE ONLY ONLY
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 10. Given
- 10. Given the the following:
following: The Reactor
- The
- Reactor isis atat 4%
4% RTP RTP inin preparation preparation for for Turbine Turbine startup. startup. Main Feedwater
- Main
- Feedwater Pump Pump "A" under clearance A isis under clearance for for maintenance.
maintenance. Main Feedwater
- Main
- Feedwater Pump Pump "8"B isis operating.
operating. AFW Pumps
- AFW
- Pumps are are shutdown shutdown and and aligned aligned for for automatic automatic operation.operation.
AMSAC isis aligned
-- AMSAC aligned in NORMAL.
in NORMAL. Narrow range
-- Narrow range Steam Steam Generator Generator levels levels are are at at 44%.
44%. Steam Dumps
-- Steam Dumps indicate indicate throttled throttled OPEN. OPEN.
Which ONEONE (1)(1) of the following statements describes the AFW Pump Pump status immediately immediately after Main Feedwater Feedwater Pump "8" B trips? The MDAFW A. The MDAFW and SDAFW SDAFW PumpsPumps must be manually started. B. The MDAFW Pumps have auto started but the SDAFW Pump must must be manually started. C. The SDAFW Pump has auto started but the MDAFW Pumps must be manually started. D. The MDAFW and SDAFW Pumps have auto started.
\1l v ' L.
'-- \.>
\ , \(\tr\- iP 0 ..1..6;\)\'.:: . A-s s-k\. d ~ '<\ ~
R- ,\--\l
---0A~ O ..l~ t~\!"c\\( 'rio c_- <;;,+<.M.\: ,. t1-\-=l<.,.) Y' u~.5
,4 -<_) 5 1p_
0*\-\,,<1,1- x:'\C'W\:~ CeMd.'B OW CAvL tM-.S tNLS W~ ~~)Y)-e& ~fl C&z t1 CtAA:\n
'\Jv'Ci-~. w& i u>.d 'v\~
Q....\r-Q..\ (\ft
-vc o~.J.A CLtl tNt * 'I ] :-\- 5 O/CM(M obv;"v.s
\ 5 ov; S\Jf-t-PW SYA-RJ VV"t\A.p
)v5 Sl-o.,....\- ;kz( ,~\.,f"~ c",'r kct :,'\- . G-f-(N--r) c\ ~"'-\)f\.H.v '?(}Vv<.f.5 I\Cit- <l--~<!.. ~,,~~ \..'/1 \\ S~ OV\
?~t-, jlc5 0" 105.5 o ok'- r~II,1
,t 1
V-e? Nk Pb,M.G,h!-. 10 10
FILC-Q8 NRC Written Exam HLC-OB
- 10. 000054 AA1.02 10.000054 001/LOSS OF MFW/1I1I4.4/4.4IROIHIGH/N/A/COOK AAl.02 OOlfLOSS MFW/1/1/4.4/4.4/RO/HIGHJN/A/COOK - 2002/AFW-008
-
Given the following:
- The Reactor is at 4% RTP in preparation for Turbine startup.
-
- Main Feedwater Pump "A"
- A is under clearance for maintenance.
- Main Feedwater Pump "B"
- B is operating.
- AFW Pumps are shutdown and aligned for automatic operation.
-
- AMSAC is aligned in NORMAL.
-
- Narrow range Steam Generator levels are at 44%.
-
- Steam Dumps indicate throttled OPEN.
-
Which ONE (1) of the following statements describes the AFW Pump status immediately after Main Feedwater Pump "B" B trips? A. The MDAFW and SDAFW Pumps must be manually started. B The MDAFW Pumps have auto started but the SDAFW Pump must be manually started. B:t C. The SDAFW Pump has auto started but the MDAFW Pumps must be manually started. D. The MDAFW and SDAFW Pumps have auto started. The correct answer is B. A: Incorrect - Both MDAFW Pumps start on loss of Main FW, both MFP breakers being
-
OPEN is a Loss of Feedwater. B: Correct - The MDAFW Pumps will auto start on the loss of both Main FW Pumps but the
-
SDAFW Pump will NOT. C: Incorrect - The SDAFW will only start on Lo-Lo S/G level, AMSAC, and MFP Bus UV.
-
MDAFW Pumps will start on Lo-Lo Level, AMSAC, loss of Main Main FW, Blackout, & SI. D: Incorrect - SDAFW will NOT auto start. AMSAC will NOT ARM until power has been raised
-
to> 35%. Exam Question Number: 10
Reference:
SD-042; AFW; Pump Start Logics, Figure 11. KA Statement: Ability to operate and / or monitor the following as they apply to the Loss of Main (MEW): Manual startup of electric and steam-driven AFW pumps. Feedwater (MFW): History: Changed correct answer to B from D. Tuesday, June 17, 2008 1 17,2008 :21 :02 PM 1:21 12
AFWPUMP AFW PUMP AUTO-START AUTO-START LOGIC LOGIC AFW-FIGURE- 11 AFW-FIGURE-ll SG A 2/3 SG "A" 2/3 SGSG"B" B 2/3 SG"e" 2/3 SG C 2/3 2/3 LOWlOW LOW LOW lOW LOWLOW LOW LOWLOWlOW LOW LEVEL lEVEL LEVEL lEVEl lEVEL LEVEL I I lOSS LOSS OF OF POWER POWER44 kV kV BUS BUS SG lO-lO 1/3 SG LO-LO lEVEL LEVEL BUS BUS 11 BUS BUS 44 1/3 AUTO-START BLOCK AUTO-START BLOCK UV UV UV UV UV LJV UV UV IN IN MAIN FEED FEED PUMP NORMAL MAIN PUMP BRKRS BRKRS NORMAL OPEN OPEN ....... A B 2/3 2/3 SG SG lO-lO LO-LO LEVEL AUTO-START lEVEL AUTO-START BLOCK IN BLOCK IN _15SEC,_ NORMAL NORMAL T/D MFW BKRS MFW BKRS OPEN OPEN AUTO-START BLOCK AUTO-START BLOCK IN IN NORMAL NORMAL LOSS OF LOSS OF POWER POWER E1/E2 El/E2 OR OR EDG BRKRS EDG BRKRS CLOSED CLOSED SAFEGUARDS SAFEGUARDS AND AND BLACKOUT BLACKOUT SEQUENCE SEQUENCES S MANUAL MANUAL MANUAL START MDAFW MDAFW OPEN OPEN MDAFW MDAFW PUMP PUMP CLOSECLOSE SGBD SGBD OPEN TURBINE OPEN TURBINE START TURBINE START TURBINE AA&B
&B DISCHARG DISCHARGE VALVES ISOLATION E VALVES ISOLATION VALVES VALVES PUMP DISCHARGE PUMP DISCHARGE DRIVEN DRIVEN PUMP PUMP (V2-1 6A, B, (V2-16A, B, C)
C) VALVES VALVES (OPENS Vi (OPENS Vl-8A, B, C)
-BA, B, C)
(V2-14A, B, (V2-14A, B, C) C) INFOR INFORMATIONMATION USE USE ONLY ONLY
Cook Nuclear Cook Nuclear Plant: Plant: Reactor Reactor Operator Operator License License Exam Exam December December 2002 2002
- 28. 0361
- 28. 036 1 Unit 11 Reactor Unit Reactor isis at at 4%
4% power power inin preparation preparation forfor Turbine Turbine startup startup with with the the following conditions: following conditions: West Main
- West - Main Feedwater Feedwater pumppump is tripped.
is tripped. East Main
- East - Main Feedwater Feedwater pumppump is operating.
is operating.
- AFW pumps are AFW pumps are shutdown shutdown andand aligned aligned for for automatic automatic operation.
operation. AMSAC is
- AMSAC - is aligned aligned in NORMAL.
in NORMAL. Narrow range
- Narrow - range steam steam generator generator levels levels are now 44%.
are now 44%. Steam Dumps
- Steam - Dumps indicate indicate 8%8% open.
open. Which ONE ONE of of the following statements statements correctly correctly describes describes the AFW AFW pump pump status status immediately after immediately after the East Main the East Main Feedwater Feedwater PumpPump trips? trips?
- a. The Motor Driven and Turbine Driven AFW pumps must be manually started. started.
- b. The Motor Driven AFW Pumps have auto started but the Turbine Driven AFW pump must be manually started.
- c. The Turbine Driven AFW Pump has auto started but the Motor Driven AFW pumps must be manually started.
- d. The Motor Driven and Turbine Driven AFW pumps have auto started.
Lesson Plan/Obj: RO-C-05600 / #15
Reference:
01-OHP-402 2-055-001, Loss of Main FW Pump; 01-OHP-402 01-0HP-4022-055-001, 01-0HP-4021-001-006, 1-001-006, Power Escalation; SOD SOD -05600-001, Auxiliary Feed System Loss Loss of of Main Main Feedwater Feedwater (MFW) (MFW) - Ability to operate and/or - and/or monitor monitor the following as as they apply apply to the Loss of of Main Main Feedwater (MEW): Feedwater (MFW): Manual Manual startup startup of of electric electric and and steam-driven AFWAFW pumps pumps Answer: Answer: B8
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 11. During
- 11. During aa Loss Loss of of All All AC Power Power event, event, EPP-1, EPP-1, LOSS LOSS OFOF ALL AC POWER POWER directs directs the isolation isolation of seal of seal cooling cooling for events events of 15 15 minutes minutes or more more without RCP RCP seal seal cooling.
cooling. ONE (1) Which ONE (1) of the following is is the reason reason for isolating isolating seal seal cooling? A. RCP seals and shafts may be damaged by thermal shock when power is restored to the DS Bus. OS B. RCP thermal barriers are susceptible to rupture from thermal shock when power is restored DS Bus. to the OS C. Steam binding of the Charging Pumps from RCP seal leakoff flashing when a Charging Pump is restarted. D. RCP Thermal Barriers are susceptible to rupture from water hammer when power is restored to the OS DS Bus. 11 11
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 11. 000056
- 11. 000056 AA2.67 AA2.67 OO1ILOSS OOl/LOSS OF OF OFFSITE POWRIll1l2.9/3.1fRO/LOWfN/NNEW - 2008IBPP-1-004 OFFSITE POWRI1/1/2.9/3.1IROILOWIN/AJNEW -
200S/EPP-I-004 During aa Loss During Loss of of All All AC AC Power Power event, LOSS OF EPP-1, LOSS event, EPP-1, POWER directs OF ALL AC POWER the isolation directs the isolation of seal cooling of seal cooling for for events events of of 15 15 minutes minutes or or more more without without RCP RCP seal seal cooling. cooling. Which ONE Which ONE (1) (1) ofof the the following following is is the reason for the reason for isolating seal cooling? isolating seal cooling? A'I RCP A RCP seals seals and shafts may be damaged shock when power is damaged by thermal shock is restored to the OS Bus. DS Bus. B. RCP thermal barriers are B. are susceptible to rupture from thermal shock when power is is restored to the DSOS Bus. C. Steam binding of the Charging Pumps from RCP seal C. leakoff flashing when a Charging sealleakoff Pump is restarted. Pump RCP Thermal Barriers are susceptible to rupture from water hammer when power is D. RCP D. restored to the DS OS Bus. The correct answer is A. A: Correct - - Injection loss lasting> 15 minutes may allow seals and shaft to heatup to RCS temperature. Engineering and manufacturer will be consulted prior to restoration. B: Incorrect - It is the seal themselves (NOT the Thermal Barrier) which are susceptible to
-
failure from thermal shock. C: Incorrect - Steam binding is a possibility due to no CCW, but NOT a reason for isolation
-
after a loss ofof>> 15 minutes. 0: D: Incorrect - Water hammer may occur if voids or steam formation in seal injection lines
-
occurs, but it is NOT a reason for isolation after a loss of of>
> 15 minutes.
Exam Question Number: 11
Reference:
EPP-1 Page 5; EPP-1 BO, 4-6, 64. BD, Pages 4-6,64. KA Statement: Ability to determine and interpret the following as they apply to the Loss of Offsite Power: Seal injection flow (for the RCPs). History: History: New - Written for HLC-08 NRC Exam.
-
- Tuesday, Tuesday, June June 17, 2008 11:21:03 17, 2008 PM
- 21 :03 PM 13 13
Rev. 3838 EPP-l EPP-1 LOSS OF ALL AC POWER LOSS Page 55 of 61 61 __STEP H INSTRUCTIONS I I RESPONSE NOT RESPONSE NOT OBTAINED OBTAINED I
* * * * * * * * * *~~* * * * * * * *.. ~",!!~;k.~*",,*,"If* *"f'Y"k ."""':':-t. *-;-;"* * * * * * * * *~7r1t-*"'~~"'.:t:...:t.~ * *
. CAUTION ------.-
IF more than 15 j 15 minutes elapses without RCP Seal Cooling, THEN Seal Cooling (CCW AND Seal Injection) MUST be isolated before starting CCW OR Charging or Seal Damage could occur.
*************************************************************************
* ** ** *** ******* ***
** 4. Check Seal Cooling From CCW As Follows:
- a. Check CCW Pump A "A" ~- RUNNING a. j.IF RCP Seal Cooling is NOT OR can NOT be restored in less than 15 minutes, THEN perform Step 5.
Go To Step 6.
- b. Go To Step 6 6 Perform The Following To Isolate RCP Seal Cooling:
- a. In Pipe Alley close FCV-626, a. Close CC-736,CC FROM RCP "A", A.
THERM BARRIER OUTLET B, "c" "B", C THERMAL BARRIER.
- b. In the Charging Pump Room. Room, close the RCP SEAL WATER FLOW CONTROL VALVEs
- CVC-297A
- CVC-297B
- CVC-297C
- 2. DESCRIPTION A total loss of ac power at aa nuclear power station can result only through a coincident loss of grid power from the A
high voltage distribution lines serving the station and some combination of events preventing the station emergency diesel generators from energizing the emergency ac busses. The immediate consequences of the loss of ac power, ifif not accompanied by some other complicating event such as aa loss of reactor coolant, loss of secondary coolant or steam generator tube rupture, are not severe. However, should ac power either from the grid or the emergency diesels not be restored quickly, the consequences to plant and public safety can potentially be extreme. The degree of severity of a loss of all ac power depends primarily on the duration of the ac power outage and the response of the reactor coolant pump (RCP) shaft seals to the loss of seal cooling, i.e., the simultaneous loss of high pressure injection flow to the RCP seals and of component cooling water (CCW) flow to the RCP thermal barrier. Loss of high pressure seal injection flow from the motor driven charging/SI pumps results in out leakage from the RCS along the RCP shafts. Without power this leakage cannot be replaced and a continuous loss of reactor coolant occurs with time. Loss of RCP seal cooling potentially can also cause degradation of the sealing capability of the RCP seals as aa result of overheating. Degradation of the sealing capability may result in an increase in leakage out of the RCS from several gpm per RCP to several hundred gpm per RCP. To mitigate the severity of a loss of all ac power, it is necessary to minimize RCS inventory loss with time and to restore ac power so that RCS inventory can be restored. Various aspects of the loss of all ac power event are discussed as appropriate in succeeding subsections. Due to the key role of the RCP following the loss of all ac power, a more detailed RCP description is given in the following WCAP-1 0541, Revision 2, Westinghouse Owners Group Report, subsection. Additional information is contained in WCAP-10541, Reactor Coolant Pump Seal Performance Following a Loss of All AC Power" "Reactor Power (Reference 4). 2.1 RCP Description RCP Seal System Leakage The RCP is designed such that leakage along the RCP shaft is controlled by three shaft seals arranged in series. Under normal operating conditions, the RCP shaft seal system functions to control and direct RCP seal leakage such that leakage to the containment is essentially zero. The following briefly describes the three shaft seals. o Number 1I Seal The number 1 I seal is the main seal. It is a controlled leakage film riding seal primarily consisting of a runner which rotates with the shaft and a non-rotating seal ring attached to the seal housing. The flow path is between the faceplate interface of the seal ring and seal runner, with leakage rate depending on faceplate taper angle and separation. The number 1 I seal is designed to accommodate full RCS pressure of 2235 psig and limit RCS nominal leakage to approximately 3 gpm, with a maximum acceptable leakage of approximately 4.5 gpm. The major portion of the number 1 seal leakoff line with the smaller portion directed through I seal leakage is directed to the number 1I sealleakoff the number 2 seal. The number 1 seal leakoff line normally returns leakoff through containment to the charging/SI 1 sealleakoff pump suction. This seal return line includes a relief valve inside containment which directs leakoff flow to the pressurizer relief tank when containment is isolated. The relief valve has a nominal 150 psig set pressure. I EPP-1-BD Rev. 38 106 Page 4 of 1061
o Number 2 Seal The number 2 seal is a rubbing face seal consisting of a seal ring with shrink fit insert which rubs on a runner rotating with the shaft. With the number 1 I seal operative, the number 2 seal is designed to accommodate a nominal differential pressure of 30 psig and limit RCS leakage to approximately 3 gallons per hour. If the number 1 I seal becomes inoperative, the number 2 seal is designed to accommodate full RCS pressure of 2235 psig and limit RCS leakage to approximately 8 gpm, with a maximum acceptable leakage of approximately 12 gpm. The number 2 seal functions to create a backpressure on the number 1 I seal, thus directing the major portion of number 1I seal flow to the number 1 seal leakoff line. The major portion of leakage through the number 2 seal is directed to the number 2 I sealleakoff seal leakoff line with a small portion directed through the number 3 seal, depending on number 3 seal design. sealleakoff o Number 3 Seal The number 3 seal is a rubbing-face seal that functions to limit leakage to the containment environment under normal pump operating conditions. It is designed to accommodate low differential pressures with number 3 seal leakoff being directed to the reactor coolant drain tank or containment sump, depending on number 3 seal design. The number 3 seal is not a pressure boundary seal and does not play an important role in limiting RCP seal leakage following the loss of all ac power. Under normal operating conditions, the controlled leakage shaft seal system is cooled by independent and redundant cooling systems. Adequate seal cooling for continued RCP operation can be provided by either high pressure seal injection flow from the charging/SI pumps or low pressure CCW flow circulated through the RCP thermal barrier. Seal injection flow acts as a buffer to prevent reactor coolant from entering the pump seal and bearing section of the pump. A portion of seal injection flows down the shaft and into the RCS while the remainder flows up through the seal system. If seal injection to the RCP is lost, the hot reactor coolant can flow up the pump shaft. Under this condition, the RCP thermal barrier functions as a heat exchanger to cool the hot reactor coolant before it enters the RCP bearing and seal area. The RCP is designed to accommodate the temporary loss of seal injection flow and CCW flow that accompanies a loss of offsite power, including the normal time delays associated with reestablishing these RCP support systems on emergency ac power. This is accomplished by the volume of cool water in the seal area and the time that it takes to leak this water through the RCP seals prior to hot water entering the seals. The RCP is designed to accommodate the loss of support systems for one minute following loss of offsite power. Under best estimate conditions, the RCP design should preclude hot water from entering the seal area for several minutes. Under the loss of all ac power event, RCP support systems may not be restored prior to the introduction of hot reactor coolant into the seal system. Under this condition, the RCP seal leak rate becomes dependent on RCS temperature as well as the RCS pressure. At temperatures in excess of 300°F, RCP seal system sealing capability and sealing life may start to degrade with consequential increase in seal leakage flow. The potential for degradation in sealing capability and sealing life increases with increasing temperature above 300°F. Seal performance under high temperature conditions is difficult to analyze due to several interacting considerations, including:
- 1) 0-ring material softens with increasing temperature, affecting the a-ring The seal a-ring 0-ring sealing ability and life.
- 2) The thermal gradients affect the faceplate tapers of the number 1 I seal ring and runner and the shrink fit of the number 2 seal ring insert, affecting sealing surfaces. Nonuniform thermal gradients and extrusion of a-rings 0-rings may result in nonuniform sealing surfaces.
- 3) The leakage of reactor coolant through the seals could result in crud blockage of the seals.
I EPP-1-BD Rev. 38 Page 5 of 1061 106
Due to the several interacting considerations, it is difficult to analytically or experimentally predict the RCP leakage flow following aa loss of all ac power. Further, it is possible that different RCPs may be affected in different ways with resulting variations in leakage flow. Since it is difficult to accurately predict RCP seal leakage flow following a loss of all ac power, field experience has been reviewed for relevant information and an analysis has been performed to estimate a maximum leakage rate. Although some field experience exists wherein both seal injection flow and thermal barrier CCW flow have been lost, it is of such a limited nature that RCP seal behavior cannot be accurately predicted. General conclusions drawn from this experience indicate that seal leakoff flow can be expected to increase above the normal range during the loss of all ac power event, likely going above the seal leakoff flow instrument typical upper range of 66 gpm. However, based on this limited experience, abnormally excessive leakage rates were not experienced prior to restoration of RCP support systems. To evaluate the most severe consequences of a loss of all ac power to the RCP seal system, a conservative maximum RCP leakage rate is estimated to be 300 gpm. This rate is estimated by assuming that total RCS pressure of 2235 psig exists across the Rep RCP thermal barrier labyrinth seals with the controlled leakage seals totally ineffective in controlling leakage flow. This estimate does not include credit for floating ring seals which are in a limited number of RCPs. Maximum leakage rates for RCPs with floating ring seals will be less than 300 gpm. Based on the above discussion, RCP seal integrity is a major concern during a loss of all ac power event. The high RCS temperatures and pressures characteristic of a plant no-load condition can lead to eventual RCP seal degradation and increased RCS inventory loss. This seal degradation can be mitigated by reducing the RCS pressure and temperature consistent with other plant constraints. Reducing RCS pressure reduces leakage flow through the RCP seals, thereby reducing RCS inventory loss for a given seal condition. Reducing RCS temperature reduces the thermal degradation of materials and thermal expansion effects that tend to degrade the seal system sealing capability and sealing life. Consequently, any actions to reduce RCS pressure and temperature during a loss of all ac power event are consistent with minimizing RCS inventory loss and maximizing time to core uncovery. Benefits and Consequences of Restoring Seal Cooling Following the restoration of ac power, the operator will have the capability to restore seal cooling by reestablishing seal injection flow or reestablishing thermal barrier cooling using the component cooling water system. Restoring seal cooling may have several benefits such as reducing seal leakage and preventing further damage to the seal components. However, Westinghouse has not performed an analysis of how the RCP seal package will react as the seals cool, fits contract, the shaft moves, etc., possibly with partially extruded O-rings. 0-rings. There may be a potential to make seal leakage worse by restoring seal cooling, depending on how it is done. The RCP Vendor Manual identifie~.Jirnits identifies for...reestablishingsealcoolg al ~ toaa hot seal seal cooling to aclcae to prevent further JI damage due to thermal shock and to prevent warpingwar in of the RCP shaft due to uneven cooling. These limits are only s o enough duration that the seal package heatup is limited. Although the intended for a loss of seal cooling of short limits have been extrapolated for an extended loss of seal cooling event in the past, they have not been validated for such an event that is beyond the design basis of the RCP. Therefore, no specific conclusions may be taken from the RCP vendor manual guidance for reestablishing seal cooling following an extended loss of seal cooling event. The following provides a qualitative assessment that determines the most appropriate method of restoring seal cooling following an extended loss of all ac power event: IEPP-1-BD EPP-1-BD Rev. 38 106 Page 6 of 1061
RNP WOG WOG BASIS/DIFFERENCES BASIS/DIFFERENCES STEP STEP STEP 5 88 WOG BASIS WOG BASIS PURPOSE: To PURPOSE: To isolate the RCP isolate the RCP seals seals BASIS: (Updated for Rev BASIS: Rev 22 ERG) ERG) groups three actions, with different step groups This step aimed at purposes, aimed different purposes, at isolating RCP seals. isolating the RCP seals. The actions are grouped actions are grouped since since all all require an an auxiliary auxiliary operator, dispatched dispatched from the control room, to locally close locally close containment valves (the reference plant utilizes motor operated valves isolation valves containment isolation for the RCP seal return, RCP thermal barrier CCW CCW return lines and RCP seal injectioninjection lines). lines). This grouping assumes that the subject subject valves areare located same penetration room area in the same located in area and that they are and accessible. Concurrent with dispatching the auxiliary operator, the control are accessible. operator should place the valve switches for the motor operated valves in room operator in the closed position so50 that the valves remain closed when ac power is is restored. leakage from filling the volume control tank (VCT) the seal return line prevents seal leakage Isolating the (via seal return relief valve outside containment) and subsequent transfer to other auxiliary building holdup tanks (via VCT relief valve) with the potential for radioactive release within the auxiliary building. Such a release, without auxiliary building ventilation available, could limit personnel access for local operations. operations .
- Isolating the RCP senjcti seal injection linesspre n lin ares the plant for recovery IIibila.protecting t~CEs preeares from seal and shaft damageJha1..ala.Y.QQQ!,Ir when a charging pjjmp PUInR is started as part of the recovery. With the RCP seal injection lines isolated, a charging pump can be started in the normal charging mode without concern for cold seal injection flow thermally shocking the RCPs. Seal injection can subsequently by established to the RCP consistent with appropriate plant specific procedures.
Isolating the RCP thermal barrier CCW return outside containment isolation valve prepares the plant for recovery while protecting the CCW system from steam formation due to RCP thermal barrier heating. Following the loss of all ac power, hot reactor coolant will gradually replace the normally cool seal injection water in the RCP seal area. As the hot reactor coolant leaks up the shaft, the water in the thermal barrier will heat up and potentially form steam in the thermal barrier and in the CCW lines adjacent to the thermal barrier. Subsequent automatic start of the CCW pump would deliver CCW flow to the thermal barrier, flushing the steam into the CCW system. If abnormal RCP seal leakage had developed in a pump, the abnormally high leakage rate could exceed the cooling capacity of the CCW flow to that pump thermal barrier and tend to generate more steam in the RCP thermal barrier CCW return lines. Isolating these lines prevents the potential introduction of this steam into the main portion of the CCW system upon CCW pump start. This keeps the main portion of the CCW system available for cooling equipment necessary for recovering the plant when ac power is restored. KNOWLEDGE: RCP seal integrity concerns following loss of ac power (See Subsection 2.1 2.1)) RNP DIFFERENCES/REASONS There are essentially no differences other than it is the expectation of the ERG that thi~ this step will always be implemented while the RNP step is only expected to be needed for beyond license basis events. SSD DETERMINATION not an SSD. This is not I EPP-1-BD EPP-1-BD Rev. 38 Rev. 38 Page 64 Page 64 of of 106/ 106
HLC-08 NRC HLC-08 NRC Written Exam Exam
- 12. Given
- 12. Given the following:
The plant
- The
- plant is is in in MODE MODE 66 with refueling refueling in in progress.
progress. Source Range
- Source
- Range Channel Channel N-31 N-31 is is INOPERABLE.
INOPERABLE.
- BOTH PAM Source Range monitors (N-51A and N-52A) are OPERABLE.
-
- Instrument Bus 2 trips due to a fault on the bus.
- Instrument . -\ (.. '1 1: , , '
L.-,. II..:*\:'
. \-.,. /l; 5"'\ ~ ..... ) '1<t \......:.,tl. ~
'1 If ,/, p.,..J Y
.I\\I\lr)
(}I' Which ONE (1) of the following LCO REQUIRED ACTIONS is applicable? A. Verify one PAM Source Range monitor provides indication in the CR within 15 minutes AND Log indicated SR count rate every 30 minutes. B. Verify one PAM Source Range monitor provides indication in the CR within 15 minutes, suspend core alterations AND suspend positive reactivity additions. C. IMMEDIATELY initiate action to restore one SR monitor to OPERABLE AND suspend core alterations AND suspend positive reactivity additions. D. IMMEDIATELY initiate action to restore one SR monitor to OPERABLE AND log indicated SR count rate every 30 minutes. 12 12
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 12. 000057G2.2.22 12.000057 G2.2.22OOllLOSS 001/LOSS OF OFVITAL VITALAC ACINSI1I1I4.0/4.7IROIHIGH/N/NNEW INS/1/1/4.0/4.7/RO/HIGH/N/A/NEW- 200S/GP-01O-002
- 200810P-010-002 Given the Given the following:
following: The plant
- The
- plant isis inin MODE MODE 66 with with refueling refueling inin progress.
progress. Source Range
- Source
- Range Channel Channel N-31 N-31 isis INOPERABLE.
INOPERABLE. BOTH PAM
- BOTH
- PAM Source Source RangeRange monitors monitors (N-51A (N-51A and and N-52A)
N-52A) are are OPERABLE. OPERABLE. Instrument Bus
- Instrument
- Bus 22 trips trips due due to to aa fault fault on on the the bus.
bus. Which ONE Which ONE (1) (1) of the following of the following LCOLCO REQUIRED REQUIRED ACTIONS ACTIONS isis applicable? applicable? A. Verify one A. Verify one PAM PAM Source Source Range Range monitor monitor provides provides indication indication in in the the CRCR within within 1515 minutes minutes AND Log AND Log indicated indicated SR SR count count rate rate every every 30 minutes. 30 minutes. B. Verify one B. Verify one PAM PAM Source Source Range Range monitor monitor provides provides indication indication in in the the CR CR within 1515 minutes, minutes, suspend core suspend core alterations alterations AND AND suspend suspend positive positive reactivity reactivity additions. additions. C~ IMMEDIATELY initiate CY IMMEDIATELY initiate action to restore restore one one SRSR monitor monitor to to OPERABLE OPERABLE AND suspend suspend core core alterations AND suspend positive positive reactivity reactivity additions. IMMEDIATELY initiate action to restore one SR monitor to OPERABLE AND log indicated D. IMMEDIATELY SR count rate every 30 minutes. correct answer is C. The correct The A: Incorrect - LCO for ONE SR inoperable (Condition A).
-
B: Incorrect - LCO for ONE SR inoperable AND completion times of Condition A not met.
-
C: C: Correct Correct - Loss of the instrument bus results in BOTH SR monitors inoperable. This
-
requires LCO 3.9.2, Condition C C to be implemented implemented.. D: 0: Incorrect Incorrect - Correct statement for 2 SR INOPERAB
-
INOPERABLE, LE, but logging logging SR count rate assumes assumes that that NI-51NNI-52 NI-51 AlNI-52A A Gammametri Gammametrics cs can can bebe substituted substituted forfor SR SR monitors. Exam Exam Question Question Number: Number: 12 12
Reference:
Reference:
ITS ITS 3.9.2; 3.9.2; GP-010, GP-01 0, Pages Pages 11 11 and and 56. 56. KA Statement: KA Statement: Knowledge Knowledge of of limiting limiting conditions conditions forfor operations operations and and safety safety limits. limits. History: History: NewNew - Written
-
Written for for HLC-08 HLC-08 NRC NRC Exam.Exam.
- Tuesday, Tuesday, June June 17,2008 17, 2008 1:21 1:21:03
- 03 PM PM 14 14
--,--;.,----- Nuclear Instrumentation 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Nuclear Instrumentation LCO 3.9.2 Two source range neutron flux monitors shall be OPERABLE. APPLICABILITY: MODE 6. ACTIONS AP.TTflNc CONDITION REQUIRED ACTION COMPLETION TIME A. One required source A.I A.1 Verify one Post 15 minutes range neutron flux Accident Monitor monitor inoperable (PAM) (PAN) source range neutron flux monitor provides indication in the Control Room. AND. ANfl A.2 Log indicated PAN PAM 30 minutes source range neutron monitor count rate. AMD. Once per 30 minutes ml nutes thereafter (continued) HBRSEP Unit No. 22 3.9*2 392 Amendment No. tT6,tBfr,190
.+/-8,19O I
.J b Nuclear Nuci ear Instrumentation Instrumentation 3.9.2 3.9.2 ACTIONS ACTIONS (continued) (rnnt I I IUij I CONDITION REQUIRED ACTION REQUIRED ACTION TIME COMPLETION TIME B. B. Required Actions and B.1 8.1 Suspend CORE Suspend Immediately Imediately Completion Times Completion Times of ALTERATIONS. Condition AA not met. Condition 00 NQ B.2 Suspend operations Suspend operations Immediately Imediately that would cause introduction into the RCS. coolant with boron concentration less than required to meet boron concentration of LCO 3.9.1. C. Two required source C. required source C.1 Initiate action to action Immediately range neutron fl range neutron ux flux restore* one source restoreone source monitors inoperable. monitors inoperable, range neutron flux range neutron monitor to OPERABLE monitor to status. status. 00 ANfl C.2 Suspend CORE Immediately ALTERATIONS. 00 ANfl C.3 Suspend positive positive Immediately reactivity additions. 00 ANfl C.4 Perform SR 3.9.1.1. 4 hours Nfl AND. Once per 12 hours thereafter thereafter HBRSEP Unit No. 2 HBRSEP 3.9-3 3.93 Amendment No. tT6.t86.190 tY,8U,19O
5.18 The 5.18 The principles principles of ofALARA ALARAshall shall be be used used inin planning planning and and performing performing work workand and operations inin the operations the Radiation Radiation Control Control Area. Area. 5.19 Materials 5.19 Materials used used to construct the to construct the RC-FMEA RC-FMEA and and Transfer Transfer CanalCanal Cover Cover may may be be considered transient considered transient combustibles combustibles and and shall shall bebe handled handled lAW lAW FP-003. FP-003. 5.20 AA case 5.20 case evaluation evaluation has has been been performed performed for for each each section section of of this this procedure procedure lAW PLP-037. lAW PLP-037. The The case case determination determination isis defined defined at at the the beginning beginning of of each each appropriate section appropriate section or or evolution. evolution. 5.21 5.21 Proper lighting Proper lighting shall shall be be provided provided inin the the area area ofof fuel fuel handling handling operation. operation. IfIf anyone anyone involved in involved in the the fuel fuel handling handling operation operation isis not not satisfied satisfied with the lighting, with the lighting, then then additional temporary additional temporary lights lights should should be installed. be installed. 5.22 5.22 ITS LCO ITS LCO 3.9.63.9.6 requires requires thatthat Refueling Refueling Cavity Cavity water water level level be be greater greater thanthan or or equal equal to 23 to 23 feet above the above the top top ofof the the Reactor Reactor Vessel Vessel flange. flange. Refueling Refueling Cavity Cavity Water Water level is level measured from is measured from the the operating operating deck deck down. down. 8ased Based on on UFSAR UFSAR Figure Figure 5.3.0-1 and and drawing drawing G-190188, G-1 90188, 23 23 feet above above the the Reactor Reactor Vessel flange corresponds to 35 inches below the operating corresponds operating deck. Maintaining level higher
. than 29 inches below operating deck ensures the operating ensures water level is at least 66 inches inches above the required above required ITS level.
5.23 5.23 ITS LCO 3.7.12 requires requires that SFP level be verified greater than or equal to 21 feet above the top of irradiated fuel assemblies 21 assemblies seated in the storage racks. racks. SEP SFP level is measu measured red from the SFP floor up. According to the UFSAR the top top of of the the fuel fuel is located 14 14 feet, 1/4 inch above the SEP SFP floor. Maintaining level above above 35 feet, 1/4 inch satisfie satisfiess the required ITS level. 5.24 5.24 When When the SFP GATE VALVE is open, open, it takes 1500 1500 gallon gallons s of makeu makeup to raise p to raise level 1 level 1 inch inch in in the Spent Spent Fuel Pool and and Refueling Cavity. 5.25 5.25 TheThe Fuel Fuel Transf Transfer er Cart Cart shall shall bebe on on the the CV CV side side at at the the endend stop stop position position before before the the SEP SFP GATE GATE VALVE VALVE is is closed closed.. [CAPR [CAPR NCR NCR 00239 00239329/NCR 329/NCR 00231 00231270]270] 5.2 ITS ITS 3.9.2 3.9.2 require requires s two two Source Source Range Range Neutron Neutron Flux Flux Monitors Monitors to to be be operab operable le in in MODE MODE 6. 6. IfIf one one ofof the the BF3 8F3 Source Source Range Range Detect Detectors becomes ors becom inoperable, es inoper able, a a PAM PAM Source Source Range Range Detect Detector or may may bebe used used ifif the the require requirements ments of of ITS ITS LCOLCO 3.9.2A 3.9.2A are are met. met. 5.27 5.27 RCPRCP B "8" andand RCP RCP C"c" should should NOTNOT be be uncoup uncoupled led atat the the same same timetime ifif the the RHR RHR System System isis require required d toto be be operab operable le AND AND RCSRCS level level isis at at or or below below 50 inches inches. . Uncoupled Uncoupled RCPs RCPs result result inin inaccu rate standp inaccurate ipe level standpipe level indication indication when when RCS RCS levellevel isis at at or or below below-50 -50 inches inches. . (ESR (ESR 95-00649) 95-00649) (NCR (NCR 30599) 30599) IGP-01 GP-0100 Rev. Rev. 6666 Page 11 Page 11 ofof79791
_______ ______ _______ ______ ATTACHMENT 10.2 ATTACHMENT 10.2 Page 33 of Page of 44 MODE 66 CHECKLIST MODE CHECKLIST INIT 5.
- 5. AC Instrument Bus AC Instrument source isis operable Bus source operable toto support support the the onsite onsite AC AC Instrument Bus Instrument electrical power Bus electrical power distribution distribution subsystem(s) subsystem(s) required by required by ITS ITS LCO LCO 3.8.10.
3.8.10. 6.
- 6. The necessary The necessary portion portion ofof AC, AC, DC, and AC DC, and AC Instrument Instrument BusBus electrical electrical power distribution power distribution subsystems subsystems are are operable operable to to support equipment support equipment required to required to be operable. (ITS be operable. 3.8.10)
(ITS 3.8.10)
- 7. Boron concentration of the RCS, Boron RCS, Refueling Refueling Canal Canal and the Refueling Refueling Cavity is Cavity is greater than or equal to the limits identified identified in in COLR (FMP-001) for MODE 6 (ITS LCO 3.9.1) AND SFP SEP boron greater than the limit RCS.
specified for the RCS. RCS Boron ppm Refueling Canal ppm Refueling Cavity ppm FMP-001 ppm SFP ppm NOTE: ITS LCO 3.0.4 allows entry into MODE 6 with only one Source Range Neutron Flux Monitor operable provided the actions of ITS LCO 3.9.2 are met. met. A PAM A PAM Source Source Range Detector Detector may may bebe used in place used in place of of aa BF3 BF3 detector detector ifif the the requirements of of ITS ITS LCO LCO 3.9.2 areare met. met. V (8. Two Two Source Source Range Range Neutron Neutron FluxFlux Monitors Monitors are are operable. operable. (ITS (ITS LCO 3.9.2) LeO 3.9.2) __ IGP-010 GP-010 Rev. Rev. 66 66 Page 56 Page 56 of of 79 791
HLC-08 NRC Written Exam
- 13. Given the following:
- The plant is operating at 100% RTP.
-
- Two electricians are performing MST-902, "A"
- A and "B" B STATION BATTERY TEST, obtaining battery pilot cell temperatures, electrolyte levels and battery ground checks.
- During the battery checks, Battery Charger "B"
- B is tripped.
Which ONE (1) of the following describes the effect on Battery Bus "B" B and any ITS LCOs that are applicable? Battery Bus "B" B is ... is... A. de-energized. An LCO is in effect to restore power to the bus. B. de-energized. LCO 3.0.3 is in effect. C. at 12OVDC.
-120VDC. An LCO is in effect to restore a battery charger to service.
12OVDC. NO LCO is in effect due to Battery Bus "B" D. at -120VDC. B energized within normal parameters. 13
HLC-08 NRC Written Exam 13.
- 13. 000058 G2.2.36 001/LOSS POWERlll1l3.1I4.2IRO/HIGH/NINNEW - 2008/DC-010 OOllLOSS OF DC POWERJ1/1/3.1/4.2/RO/HIGHJN/A/NEW -
2008/DC-01O Given the following:
- The plant is operating at 100%
- 100% RTP.
- Two electricians are performing MST-902, A
- "A" and B "B" STATION BATTERY TEST, obtaining battery pilot cell temperatures, electrolyte levels and battery ground checks.
- During the battery checks, Battery Charger B
- "B" is tripped.
Which ONE (1) of the following describes the effect on Battery Bus B "B" and any ITS LCOs that are applicable? Battery Bus B "B" isis...
...
A. de-energized. An LCO is in effect to restore power to the bus. B. de-energized. LCO 3.0.3 is in effect. C~ at -120VDC. C 1 2OVDC. An LCO is in effect to restore a battery charger to service. D. at -120VDC. O. ..-12OVDC. NO LCO is in effect due to Battery Bus "B" B energized within normal parameters. The correct answer is C. A: Incorrect - Bus B is still OPERABLE at 120 VDC, only the charger is tripped. Battery "B"
- B is supplying the bus.
B: Incorrect - Bus B is still energized from the battery. LCO 3.8.4 would be applicable, NOT
-
3.0.3 C: Correct - - 12OVDC, only the charger has tripped. 2 hour LCO in effect. Voltage is still at 120VDC, (3.8.4, Condition A) D: Incorrect - Voltage is still at 120VDC,
- 12OVDC, only the charger has tripped. LCO 3.8.4 should be entered. This is the correct answer for MODE 5. MODE 5 does NOT require an LCO entry for loss of a battery charger if the Bus is energized.
Exam Question Number: 13 SD-038, DC Distribution; ITS 3.8.4; ITS 3.8.4 BD, Page B3.8-41.
Reference:
SO-038, KA Statement: Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations. History: New - Written for HLC-08 NRC Exam.
-
2008 1:21:03 PM Tuesday, June 17, 20081:21:03 15 15
SD-038 DC ELECTRICAL SYSTEM grounds; if the reading exceeds 10 volts either positive or negative the ground should be located and fixed as soon as possible. B-i, the charger output voltmeter also serves as the DC A-i and "B-1", On Battery Chargers "A-I" ground meter. Ground indication is read by turning the selector switch to POS GND GNI) and then to NEG GND. C has a separate ground voltmeter to indicate DC ground in conjuction Battery Charger "C" with the Ground VM switch. When not checking for ground, this voltmeter indicates the charger output. Ground indication is read by turning the selector switch to POS GROUND and then to NEG GROUND. During testing for grounds on Battery Chargers ChargersA-l,B-i, orC, "A-1 ", "B-1 ", or "C", the voltmeter will wilL
- dro fabout 1/2 of buss voltage (approximatel 65 volts with no ound resent to about 112 resent. A
.
significantly lower rea ing mg on either direction would indicate a ground. If the reading drops to less than 50 volts, the ground should be located and fixed as soon as possible. If a trouble alarm is being received on Battery Chargers "A-1 A-i ", B-i ",
, "B-1 , or "C",
C, I&C verif, the ground is on the positive or negative buss by checking an LED personnel can verify indicator located inside the charger cabinet. Battery chargers "AA-i B-i do not have a remote ground alarm test relay. Battery
-1" and "B-1" C has a test selector switch mounted below the ground indicator selector switch charger "C" with POS GROUND and NEG GROUND positions to test the ground alarm.
4.1.1 DC Busses Each battery bus has indications for the bus voltage and also the amperes on the bus. The ammeters monitor current flow into or out of the battery attached to that MCC. 4.2 Alarms APP-036-Dl BATT CHARGER A/A-i AlA-l TROUBLE, For battery Charger A this alarm is caused by, DC output fuse blown; DC overvoltage; AC input Failure; DC Ground; Ground test. A-i the alarm is caused by, DC overvoltage; AC input failure; For Charger A-I DC output breaker open; charger failure; DC under voltage; DC ground. APP-036-D2 BATT CHARGER B/B-i B/B-1 TROUBLE, For battery Charger B this alarm is caused by, DC output fuse blown; DC overvoltage; AC input Failure; DC Ground; Ground test. DC Page 12 of 18 Revision 6 INFORMATION USE ONLY
ONE-LINE DIAGRAM OF "B" B 125 VDC SYSTEM DC-FIGURE-2 (Rev. (Rev 0) BATTERY B M M C C
" BATTERY _ , , _ MCC-6 MCC-6
- - CHARGER II "B"B B I INVERTER B
B _,,_ rr I-BATTERY
~
""
- -
BATTERY CHARGER " ..MCC-6 MCC-6 B-I B*1 DISTRIBUTION PANEL B I
)
PANEL I PANEL B*A B-A B*1 B-i INFORMATION USE ONLY
DC Sources - Operati ng Operating 3.8.4 - 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources - Operat i ng SourcesOperating LCO 3.8.4 The Train A A and Train BB DC electrical power subsystems shall be OPERABLE. APPLICABILITY: MODES 1. 1, 2.2, 3. 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One DC electrical A.1 Restore DC electrical 22 hours power subsystem power subsystem to inoperable. OPERABLE status. B. Required Action and B.1 Be in MODE 3. 66 hours Associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is 77 days
~ 125.7 VV on float charge.
(continued) HBRSEP Unit No. 22 3.8*19 3.819 Amendment No. 176
DC Sources - Operating
B B 3.8.4 BASES APPLI CAB I LITY APPLICABILITY maintained in the event of aa postulated DBA. maintained The DC (continued) electrical power pOWE!r requi rements requirements for MODES 5 5 and 66 are addressed in the Bases for LCO 3.8.5. "DC Sources-DC Sources Shutdown and During Movement of Irradiated Fuel Assemblies." Assemblies. ACTIONS A.I Condition A A represents one train with aa loss of ability to completely respond to an event. event, and aa potential loss of ability to remain energized during normal operation. It is. is, therefore, imperative that the operator's operators attention focus on stabilizing the unit. unit, minimizing the potential for complete loss of DC power to the affected train. The 22 hour limit is consistent with the allowed time for an inoperable DC distribution system train. If one of the required DC electrical power subsystems is inoperable (e.g., inoperable battery, inoperable inpperbie battery charger(~. char er(s or inopE~rable
, inoperable battery charger and associated--
associated 1noperable battery). the remaining DC electrical power inopera e battery), subsystem has the cilpacity capacity to support aa safe shutdown and to mitigate an accident condition. Since aa subsequent worst case single active failure would.would, however, result in the complete loss of thE!the remaining 125 VDC electrical power subsystems with attendant loss of ESF functions. functions, continued power operation should not exceed 2 2 hours. The 2 2 hour Completion Time reflects aa reasonable time to assess unit status as aa function of the inoperable DC electrical power subsystem and, if the DC electrical power subsystem is not restored to OPERABLE status, to prepare to effect an orderly and safe unit shutdown. B.1 8.1 and 8.2 B.2 If the inoperable DC electrical power subsystem cannot be restored to OPERABLE OPERABLE: status within the required Completion Time. Time, the unit must be brought to a a MODE in which the LCO does not apply. To achieve this status, the unit must be brought to at least MODE 3 3 within 6 6 hours and to MODE 5 5 within 36 hours. The allowed Completion Times are reasonable, based on on operating experience, to reach the (continued) (conti nued) HBRSEP Unit No. 22 B 3.8*41 B 3.84]. Revision No. 00
HLC-08 NRC Written Exam
- 14. Given the following:
100% RTP,
- The Unit was operating at 100%
- RTP, when a Pressurizer PORV failure caused a Reactor Trip.
Reactor
- APP-008-F7, SOUTH SW HDR LO PRESS, is received.
-
- South SW header pressure is 29 PSIG and slowly decreasing.
-
- North SW header pressure is 42 PSIG and stable.
-
Which ONE (1) of the following contains the correct response of the Service Water system valves based on the above plant conditions? V6-16A, SW NORTH HEADER SUPPLY TO TURBINE BUILDING. V6-16B, SW SOUTH HEADER SUPPLY TO TURBINE BUILDING. V6-16C, SW ISOLATION TO TURBINE BUILDING. than... After ONE (1) minute with South SW header pressure less than ... A. 40 PSIG, ONLY valves V6-16B, and V6-16C will close. B. 40 PSIG, valves V6-16A, V6-16B and V6-16C will close. C. 31 PSIG, ONLY valves V6-16B and V6-16C will close. D. 31 PSIG, valves V6-16A, V6-16B and V6-16C will close. 14 14
HLC-08 NRC Written Exam
- 14. 000062 AK3.02 001/LOSS OOl/LOSS OF SERV WATER/l/l/3.6/3.9/ROIHIGH/N/AIRNP WATERI1/1/3.6/39/RO/HIGHIN/A/RNP 2007/SW-008 Given the following:
- The Unit was operating at 100% RTP, when a Pressurizer PORV failure caused a
-
Reactor Trip.
- APP-008-F7, SOUTH SW HDR LO PRESS, is received.
-
- South SW header pressure is 29 PSIG and slowly decreasing.
-
- North SW header pressure is 42 PSIG and stable.
-
Which ONE (1) of the following contains the correct response of the Service Water system valves based on the above plant conditions? V6-16A, SW NORTH HEADER SUPPLY TO TURBINE BUILDING. V6-16B, SW SOUTH HEADER SUPPLY TO TURBINE BUILDING. V6-16C, SW ISOLATION TO TURBINE BUILDING. After ONE (1) minute with South SW header pressure less than than...
...
A. 40 PSIG, ONLY valves V6-16B, and V6-16C will close. B. 40 PSIG, valves V6-16A, V6-16B and V6-16C will close. C~ 31 PSIG, ONLY valves V6-16B and V6-16C will close. C D. 31 PSIG, valves V6-16A, V6-16B and V6-16C will close. The correct answer is C. V6-1 6B and C will close. 40 PSIG setpoint is alarm setpoint for APP-008-F7 A: Incorrect - V6-16B
-
and incorrect for SW isolation. B: Incorrect - V6-16B and C will close, V6-16A will NOT because there is NO isolation signal
-
for the North header. 40 PSIG setpoint is alarm setpoint for APP-008-F7 and incorrect for SW isolation. C: Correct - - V6-1 V6-16B < 31 PSIG SW Header pressure coincident with a 6B and C will close at < Turbine trip. D: Incorrect - - V6-1 6B and C will close at < V6-16B < 31 PSIG SW Header pressure coincident with a V6-1 6A will NOT close. Turbine trip. V6-16A 16
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Question Number: Number: 14 14
Reference:
SO-004,
Reference:
SD-004, SWS, Page 18, SWS, Page 18, Figures Figures 3,4; 3,4; APP-008-F7. APP-008-F7. KA Statement: KA Statement: Knowledge Knowledge ofof the the reasons reasons for for the the following following responses responses as as they they apply apply toto the the Loss Loss of Nuclear of Nuclear Service Service Water: Water: The The automatic automatic actions actions (alignments) (alignments) within within the the nuclear nuclear service water service water resulting resulting from from the the actuation actuation ofof the the ESFAS. ESFAS. History: Changed History: Changed Stem/answer Stem/answer to to question question valve valve realignment. realignment. (vs.(vs. SWB SWB Pump Pump status) status) Note: Repeat Note: Repeat question question from from last RNP exam, last RNP exam, Modified Modified as listed in as listed in History. History. 17 17
SD-004 SERVICE WATER SYSTEM differential pressure is sensed across the screens. 4.5.4 PSL-1693A, B & & C and FSL-1695A, B B& &C These switches are interlocked with the circulating water pump's pumps starting circuits. These switches will prevent their respective circulating water pump from starting upon sensing either a low pressure or low flow in the SW lines supplying gland seal and bearing cooling water to the pumps. 4.5.5 TCV-1902A This valve is interlocked with the limit switches on the SDAFW pumps pump's admission valves. The valve opens with the steam admission valves to provide cooling to the lube oil cooler. This valve is normally isolated (SW-246 locked closed). (The SDAFW self-cooling mode of operation is required due to the initial loss of SW during a station blackout event.) 4.5.6 TCV-1903A & &B These valves are interlocked with the control circuits of MDAFW Pumps A and B B to open on pump start and supply cooling water to the lube oil cooler. 4.5.7 V6-16A, B B& &C Auto closure feature to isolate Turbine Building:
- Valve V V6-16A 6-16A will close if PSL-1616A reaches 31 psig decreasing for 60 2OET Turbine Trip signal present seconds with a 20ET G PSL- 1 684A reaches 31 psig decreasing for 60 V6- 1 6B will close if PSL-1684A Valve V6-16B 2OAST Turbine Trip signal present seconds with a 20AST t;\ Valve V6-16C will close if PSL-1616B OR PSL-1684B reaches 31 psig l./ decreasing for 60 seconds with a 20ET2OET OR 20AST 2OAST Turbine Trip signal present Key lock switches (located in the Cable Spread Room) are used during maintenance, testing, or when the unit is in Cold Shutdown to inhibit the auto-close interlock.
SWPumpD 4.5.8 SW Pump D Manual circuit breakers, with Kirk key interlock, are provided to power the pump from the 480v DS Bus in case of a fire. sw SW Page 18 of 35 Revision 11 INFORMATION USE ONLY
SERVICE WATER PUMPS SW-FIGURE-3 CIRCULATING WATER PUMPS HYPOCHLOREFE - -..... HYPOCtLORITE ...AUX. ux. BUILDING SW-8 NORTH HEADER TOAux. BUILDING COMPONENTS V6*16A V6- 1 2C y, .168 AUX. BUILDING V6*12A SOUTH HEADER 1...l--......-4~ STRAINER STRAiNER ~ HYPOCHLORITE SERVICE SV1CE WATER
"'4o~~r.I AUX, BLDG* PUMPS
.-...".,., TURO.
TURII. BLDG. BlDG. SERVICE WATER ToTO TURBINE BUILDING BUIWING COMPONENTS INFORMAT INFORMATION ION USE ONLY
TURBINE BUILDING SW ISOLATION LOGIC (SIMPLIFIED) SW-FIGURE-4 TURBINE TRIP TO TO 2OET 20ET - - I 20AST 1 - - - 2OAST 31 PSIG DECREASING 31 PSIG 60 SEC 60 SEC m TD 1D
.---VJJ..VE OPeN .--ViLVE OPEN
.---..~INHI8/T INHIBIT
...--VAlVE OPEN
,--txt-INHIBIT INHIBIT
_-J---:::.:----==--- ~ CLOSE V6* 16A V6.16A CLOSE V6-16B . CLOSE V6-16 INFORMATION USE ONLY
APP-008-F7 NOTE: Alarm may be received temporarily when shifting Service Water Pump due to system pressure surges, but should clear when Service Water System pressure stabilizes. No action is necessary in these instances. ALARM SOUTH SW HDR LO PRESS AUTOMATIC ACTIONS 1.
- 1. None Applicable CAUSE
- 1. Loss of SW Pump(s)
- 2. CCW Heat exchanger Outlet Valves open too far
- 3. Rupture of Service Water Piping
- 4. Season increase in SW temperature (slow transient)
OBSERVATIONS
- 1. (P1-1684, PI-1616)
Service Water Pressure (PI-1684, P1-1616)
- 2. Service Water Pump Breaker(s) Indicating Lights ACTIONS
- 1. IF an operating SW Pump has tripped, THEN perform the following:
- 1) START a Standby Pump.
- 2) Dispatch operator to check breaker(s)
- SW Pump A - 480V Bus E1
- El (CMP 20B) - SW Pump C - 480V Bus E2 (CMP 24A)
-
SW Pump B - 480V Bus E1
- El (CMP 19C) 1 9C) SW Pump D D - 480V Bus E2 (CMP 25B)
-
- 3) Throttle CCW Heat Exchanger Return Valves, as necessary, to maintain 40 to 50 psig in the SW Headers.
- 2. IF a rupture in a SW Header has occurred, THEN refer to AOP-022.
- 3. IF an increase in SW temperature has caused SW cooling valves to throttle open, THEN locally throttle SW-739 AND SW-740 as necessary to maintain SW pressure 40 psig to 50 psig.
DEVICE/SETPOINTS
- 1. PSL-l 684 I/ 40 psig PSL-1684 POSSIBLE PLANT EFFECTS
- 1. Loss of Service Water
- 2. Overheat of CCW
- 3. Possible entry into TECH SPEC LCO REFERENCES
- 1. ITS LCO 3.7.7
- 2. AOP-022, Loss of Service Water
- 3. CWD B-190628, Sheet 840, cable M
- 4. Flow Diagram G-190199 I APP-008 Rev. 37 Rev.3? Page 50 of 51
HLC-06 NRC Replacement Exam
- 24.
Given the following:
-
- The plant is at 1 100%
00% RTP.
-
- An approved radioactive liquid waste release is in progress.
Which ONE (1) of the following correctly describes plant response if detector high voltage is lost to RMS Monitor R-18, Liquid Effluent Waste Disposal? A'I APP-036-E7 RAD A TROUBLE actuates and the release automatically RAD MONITOR TROUBLE" terminates. B. APP-036-E7 RAD TROUBLE actuates and the release continues. RAD MONITOR TROUBLE" C. Local Waste Disposal Panel alarm actuates and the release automatically terminates.
---------------------.-----
D. Local Waste Disposal Panel alarm actuates and the release continues. /,'-""r::.:
\~
25. Given the following:
-
-
-
-
A Reactor Trip has occurred. 30 seconds following the trip, Service Water pressure is 31 psig and slowly decreasing.
-
- 40 seconds following the decrease of Service Water pressure, Safety Injection actuates.
Which ONE (1) of the following describes the status of the Service Water System? isolate... Service Water to the Turbine Building will isolate ... A. 60 seconds after the Reactor Trip. B 60 seconds after Service Water pressure decreases below 31 psig. B'I C. immediately upon Service Water pressure decreasing below 31 psig. D. immediately upon the Safety Injection actuation.
'---- .... _... - ....... _..... - .~--~.--~.---
--. ---....
04, 2007 3:53:51 PM Thursday, October 04,20073:53:51 15 15
HLC-08 HLC-08 NRC NRC Written Written Exam Exam
- 15. Given
- 15. Given the the following:
following: The plant
- The
- plant isis operating operating at at 12%
12% RTP. RTP.
-A
- A line line break break in the Instrument in the Instrument Air Air header header has has occurred.
occurred. IA header pressure
- IA
- pressure is is 82 82 PSIG PSIG and and decreasing decreasing slowly.
crew has
- The crew
- has implemented implemented AOP-017, AOP-0i7, LOSS LOSS OF OF INSTRUMENT INSTRUMENT AIR.
Which ONE (1) of the following will require the crew to manuallymanually trip the reactor and enter PATH-i lAW AOP-017? PATH-1 AOP-0i7? Letdown isolates. A. Letdown B. FCV-1740, FCV-i740, IA DRYER BYPASS Valve has OPENED. flop seal injection flows increase to 15 GPM/Pump. C. RCP D. IA header pressure decreases to 58 PSIG. 15 15
HLC-08 NRC Written Exam
- 15. 000065 AA2.05 OOllLOSS 15.000065 AIRllI1I3.4/4.1/ROILOWINIAINEW - 2008/AOP-017-004 001/LOSS OF INSTR AJRJ1/1/3.4/4.1IROILOW/N/AJNEW -
Given the following:
- The plant is operating at 12% RTP.
-
- A line break in the Instrument Air header has occurred.
-
- IA header pressure is 82 PSIG and decreasing slowly.
-
- The crew has implemented AOP-017, LOSS OF INSTRUMENT AIR.
-
Which ONE (1) of the following will require the crew to manually trip the reactor and enter PATH-i lAW AOP-017? PATH-1 A. Letdown isolates. FCV-i740, IA DRYER BYPASS Valve has OPENED. B. FCV-1740, C. RCP seal injection flows increase to 15 GPM/Pump. D~ D IA header pressure decreases to 58 PSIG. The correct answer is D. A: Incorrect - AOP-017, Section A has operators check if letdown has isolated, but does not
-
Rxtrip. direct a Rx trip. B: Incorrect - FCV-1740
- FCV-1 740 OPENS automatically at 80 PSIG, AOP-017 directs the operator to check it OPEN, but the Reactor is not tripped until air header pressure reaches 60 PSIG.
C: Incorrect - AOP-017, Section A is for MODE 1/2 operation, Step directs operators to check
-
Seal Injection flow between 8-13 GPM, but allows expanded range of 6-20 GPM. D: Correct - AOP-017 directs an immediate Rx Trip if IA decreases to 60 PSIG. 0: - Exam Question Number: 15 4, 5, 11-12.
Reference:
AOP-017, Pages 4,5,11-12. KA Statement: Ability to determine and interpret the following as they apply to the Loss of Instrument Air: When to commence plant shutdown if instrument air pressure is decreasing. History: 17, 2008 1:21 :04 PM Tuesday, June 17,20081:21:04 18
Rev. 35 Rev. 35 AOP-017 AOP-017 LOSS OF LOSS OF INSTRUMENT INSTRUMENT AIR AIR Page of 61 Page 44 of 61 __STEP H INSTRUCTIONS INSTRUCTIONS f RESPONSE NOT RESPONSE NOT OBTAINED OBTAINED I 1.
- 1. Check Plant Check Plant Status Status - MODE
- MODE 11 OR Go To Go To Step Step 4.
4. MODE MODE 22 (
- 2:) Check
- 2.) Check IAIA Header Header Pressure Pressure - LESS ?
- LESS -? LIF IA IA pressure pressure decreases decreases to to less less THAN 60 THAN 60 PSIG PSIG than 60 than 60 psig, psig. THEN THEN Go Go To To Step Step 3.
3. Go To Go To Step Step 4. 4. 3.
- 3. The Following:
Perform The Perform Following:
- a. Trip
- a. Trip the the Reactor Reactor
- b. Go
- b. Go To To PATH-i, PATH-I. while while continuing with continuing with this procedure procedure 4.
- 4. Verify Instrument Verify Instrument Air Air Compressor Compressor DD - RUNNING
-
- 5. Verify The Primary Air Compressor - RUNNING
-
- 6.
- 6. Check IA Header Pressure - LESS Check - IF IA pressure decreases to less j
THAN 80 THAN 80 PSIG pSig. THEN observe NOTE than 80 psig. prior to Steps 77 and 88 and perform Steps 77 and 8. Observe the NOTE Prior To Step 99 and Go To Step 9.
Rev. 3535 Rev. AOP-017 AOP-017 LOSS OFOF INSTRUME LOSS INSTRUMENT AIR NT AIR of 6161 Page 5 5 of Page -Li-t INSTRUCTIONS INSTRUCTI ONS I I RESPONSE NOT RESPONSE NOT OBTAINED OBTAINED NOTE IA-3821 is IA-3821 is located located on on IA IA Dryer Dryer D. D. 7.
- 7. Dispatch Operator(s)
Dispatch Operator(s) To To Perform Perform The Following: The Following:
- a. Verify
- a. Verify Station Station AirAir Compressor Compressor a. Go
- a. Go ToTo Step Step 7.c.
7.c.
-
- IN IN SERVICE SERVICE WITH WITH DISCHARG DISCHARGE E VALVE VALVE OPEN OPEN
- b. Verify
- b. Verify the the following following SA SA TO TO IAIA b. Open
- b. SA-5. STATION Open SA-5, AIR TO STATION AIR TO CROSS CONNECT CROSS CONNECT BYPASS BYPASS FILTER FILTER INST AIR INST CROSS CONNECT.
AIR CROSS CONNECT. ISOLATION Valves ISOLATION Valves - OPEN:
-
OPEN:
** SA-220 SA-22O
** SA-221 SA-221 c.
- c. Verify Verify IA-18.
IA-18, AIR AIR DRYER "A" A & &
"B" BYPASS B BYPASS -
-
OPEN OPEN d.
- d. Verify Verify the the following following Compressors Compressors - RUNNING
- RUNNING
** STATION AIR COMP
** INST INST AIRAIR COMP COMP A A
** INST INST AIRAIR COMP COMP B B e.
- e. Check Check FCV-1740.
FCV-1740, AIR AIR DRYER DRYER Open IA-3665.
- e. Open
- e. AIR DRYER IA-3665, AIR A &
DRYER "A" & HIGH HIGH DP FLOW CONTROL Valve DP FLOW CONTROL Valve - - "B" B BYPASS. BYPASS. OPEN OPEN f.f. Open Open IA-3821. IA-3821, INSTRUMENT INSTRUMENT AIR AIR DRYER DRYER D "D" BYPASS BYPASS
Rev. Rev. 35 35 AOP-017 AOP-017 LOSS OF LOSS OF INSTRUMENT INSTRUMENT AIR AIR Page 11 Page 11 of of 61 61 -j__STEP H INSTRUCTIONS INSTRUCTIONS I I SECTION AA SECTION RESPONSE NOT RESPONSE NOT OBTAINED OBTAINED Modes 11 AND Modes AND 22 (Page 11 of (Page of 7) 7)
- 1.
- 1. Determine If Determine If IAIA Capacity Capacity Has Has Been Restored Been Restored As As Follows:
Follows:
- a. Check
- a. Check IAIA Header Header pressure:
pressure: IF IA
- a. .L
- a. IA capacity capacity isis restored, restored.
THEN Go THEN Go To To Step Step 1.b. 1.b.
** GREATER THAN GREATER THAN 8585 PSIG PSIG Go To Go To Step Step 2.
2. AND
** STABLE OR INCREASING STABLE INCREASING
- b. Go
- b. Go To To Attachment Attachment 4, 4.
Restoration From Loss Of Instrument Air Check Any Check Any S/G SIG Level Control - - IF any S/GSIG level control is ADVERSELY AFFECTED BY LOSS OF ADVERSELY OF IA affected. THEN Go To Step 3. affected, Observe NOTE prior to Step 44 and Go To Step 4. 3.
- 3. Perform The Following:
a.
- a. Trip the Reactor
- b. Go To PATH-I.
PATH-i, while continuing with this procedure
- c. Go To Section Section B. B, Hot Shutdown Shutdown (Without (Without RHR In Service)
Service) NOTE Use Use of of the the RWST RWST for for RCS RCS Makeup Makeup will will addadd negative negative reactivity. reactivity.
** 4.
- 4. Check Check VCT VCT Level Level - LESS
- LESS THAN THAN VCT level IF VCT
. level decreases decreases to to less less 12.5 12.5 INCHES INCHES than 12.5 inches, than 12.5 inches. THEN THEN GoGo To To Step Step 5.5.
Go Go ToTo Step Step 7.7.
Rev. 3535 Rev. AOP-017 AOP-017 LOSS OFOF INSTRUME LOSS INSTRUMENTNT AIR AIR Page 1212 ofof 6161 Page STEP H INSTRUCTIONS INSTRUCTI ONS I I RESPONSE NOT OBTAINED RESPONSE NOT OBTAINED I SECTION AA SECTION Modes 11 AND Modes AND 22 (Page 22 of (Page of 7)n 5.5. Align Charging Align Charging Pump Pump Suction Suction From The From The RWST RWST AsAs Follows: Follows:
- a. From
- a. From the the RTGB.
RTGB. verify verify a. RWST TO CVC-358. RWST Open CVC-358,
- a. Open TO LCV-115B. EMERG LCV-115B, EMERG MU MU TOTO CHG CHG CHARGING SUCTION. prior PUMP SUCTION, CHARGING PUMP prior SUCT SUCT -
- OPEN OPEN to contin to uing.
continuing.
- b. Verify
- b. Verify LCV-115C, LCV-115C. VCT VCT OUTLET OUTLET - -
CLOSED CLOSED 6.
- 6. Perform The Perform The Following:
Following:
- a. Trip
- a. Trip the the Reactor Reactor
- b. Go
- b. Go To To PATH-i, PATH-1. while while continuing with this procedure continuing with
- c. Go
- c. Go To Section To Sectio B. Hot Shutdown n B, Shutdown (Without (Without RHR RHR In In Service)
Servic e)
~'\Check
- 7. Check Any Any Of Of The The Following Following - .LE -"
(--------- lF l~tdown affected, THEN ltdown is affected.
~/. .*
ADVERSELY ADVERSELY AFFECTED: AFFECTED:
-
'-p~rm pe-r-form Step 8.
1J1S+ft ,_) ,I *
- Letdown Letdown flowflow indicated indicated on Go To Step 9.
FI-150. Fl-iSO. LOW LOW PRESS PRESS LTDN FLOW OR
** Letdown Letdown pressure pressure indicated indicated on on P1-145, LOW PI-145. LOW PRESS PRESS LTDN LTDN PRESS PRESS OR
** Letdown Letdown temperature temperature indicated indicated on on TI-140.
TI-14O, REGEN REGEN HX HX LTDN LTDN OUTLET OUTLET TEMP TEMP 8.8. Verify Verify LCV-460 LCV-46O A A& & B. B, LTDN LTDN LINE LINE STOP STOP Control Control Switch Switch - CLOSED
- CLOSED
HLC-08 NRC Written Exam following:
- 16. Given the followi ng:
- The Reactor has tripped due to a LOCA.
-
entered PA
- The crew has entered
-
PATH -i. TH-1. Which ONE (1) of the follow ng would justify entry into EPP-20, LOCA OUTSIDE followiing CONTAINM AINME ENT? NT? Auxiliaary A. Auxili ry Buildin ing. increassing. Buildingg Sump level rapidly increa Abnormal B. Abnorm al radiation in the Auxili ry building. Auxiliaary C. RWST level at 27% with the CV Sump level at 350 inches. D. Decreasing CV Pressure with a stable or increa ing RCS pressure. increassing "---" 16
HLC-08 NRC Written Exam
- 16. WE04 WEO4 EK3.1 OOllLOCA OO1ILOCA OUTSIDE CONTAIN/1/1/3.4/4.1IROILOW/NINNEW CONTAIN/1/1/3.4/4.1/ROJLOW/N/AINEW - 2008IEPP-20-002
- 2008/EPP-20-002 Given the following:
- The Reactor has tripped due to a LOCA.
-
PATH-i.
- The crew has entered PATH-1.
-
Which ONE (1) of the following would justify entry into EPP-20, LOCA OUTSIDE CONTAINMENT? A. Auxiliary Building Sump level rapidly increasing. B!o" B Abnormal radiation in the Auxiliary building. C. RWST level at 27% with the CV Sump level at 350 inches. D. Decreasing CV Pressure with a stable or increasing RCS pressure. The correct answer is B. A: Incorrect - Many different systems could cause a sump level increase. Rising sump level is
-
NOT an entry condition for EPP-20. B: Correct - - The ONLY entry condition to enter EPP-20 is abnormal radiation in the Aux building that is due to a loss of inventory from the RCS. (LOCA) , C: Incorrect - 27% is the entry condition for EPP-9, TRANSFER TO COLD LEG
-
RECIRCULATION. 350 inches is below the pOint point where Supplement 0D would be used to initiate cold leg recirculation. D: Incorrect - Increasing RCS pressure is the correct parameter used to ensure that the RCS 0: - leak outside Containment is isolated. Exam Question Number: 16
Reference:
EPP-20, Page 3; EPP-17, Page 36. KA Statement: Knowledge of the reasons for the following responses as they apply to the (LOCA Outside Containment): Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics. History: New - Written for HLC-08 NRC Exam.
-
18, 2008 10:15:38 AM Wednesday, June 18,200810:15:38 19
Rev. Rev. 88 EPP-20 EPP-20 LOCA LOCA OUTSIDE OUTSIDE CONTAINMENT CONTAINMENT Page 33 of of 99 Purpose and Entry Conditions (Page 11 of 1) 1.
- 1. PURPOSE This procedure provides actions to identify and isolate a LOCA outside Containment.
- 2. ENTRY CONDITIONS Pathi, when there is abnormal radiation in the auxiliary building Path-I, due to a loss of RCS inventory outside Containment.
- END -
- -
Rev. Rev. 18 18 SGTR SGTR WITH WITH LOSS LOSS OF OF REACTOR REACTOR COOLANT: COOLANT: SUBCOOLED SUBCOOLED EPP-l? EPP-17 RECOVERY RECOVERY Page 36 of Page 36 of 40 40 ATTACHMENT ATTACHMENT 11 CONTAINMENT CONTAINMENT SUMP SUMP LEVEL LEVEL VS. VS. RWST RWST LEVEL LEVEL Page Page 11 of of 11 INDICATED INDICATED RWST LEVEL (%) 100 ..........
.....
-
~
%
...........
...........
90 -- ...... i"""--...
.......... ç::::::::
......1'--...
EXPECTED PEC REGION I ........... TI
..........
80 I 70 I SAFE I
- 60
...... --.
--~
--------------
50 .........
%-
....
...
-
-----------
-----------
..........
40 ......
%..
i....
\
30 EZZANJ0PJ TRANSITION TO EPP-18I81EE1 I ,
- I EEEEEE
,
20 I UNSAFE II 10 10 I
, \
0o E:EHEEE , \
\
0o 48 48 96 96 144 144 192 192 240 240 288 336 336 384 384 432 432 480 528 528 INDICATED CONTAINMENT INDICATED CONTAINMENT WATER WATER LEVEL LEVEL (IN.) (IN.)
HLC-08 NRC Written Exam Given the following:
- 17. Given 17.
experienced a Reactor
- The plant has experienced
- Reactor Trip and LOCA, LOCA, followed by a Loss Loss of Emergency Emergency Recirculation.
Coolant Recirculation.
- RHR is NOT available for core cooling.
-
- The crew has implemented EPP-15, LOSS OF EMERGENCY RECIRCULATION, and is
-
initiate RCS Cooldown to Cold Shutdown". ready to perform Step 18, "Initiate Shutdown. EPP-1 5, Step 18 directs the crew to cooldown the RCS at _(a)_, using _(b)_ S/Gs. EPP-15, SIGs. A. (a) maximum rate (b) only intact
°F/hour B. (a) less than 100 of/hour (b) any intact preferred, but faulted if necessary C. (a) maximum rate (b) any intact preferred, but faulted if necessary
°F/hour D. (a) less than 100 of/hour (b) only intact 17 17
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 17. WE1 WEll EK1.2OO1ILOSS OOlILOSS OF OFEMER EMERRECIRC/1/1 /3.6/4.1IRO/LOWIN/AINEW -2008JEPP-15 RECIRC/1I1I3.6/4.1IROILOW/NINNEW - -003 2008/EPP-lS-003
- 17. 1 EK1.2 Given the Given the following:
following:
-
_The The plant plant has has experienced experienced aa Reactor Reactor Trip and LOCA, Trip and followed by LOCA, followed Loss of by aa Loss of Emergency Emergency Coolant Recirculation Coolant Recirculation..
-
- RHR RHR isis NOTNOT available available for core cooling.
for core cooling.
-
- The The crew crew has has implemented implemented EPP-15,EPP-15, LOSSLOSS OF OF EMERGENC EMERGENCY Y RECIRCULA RECIRCULATION, and isis TION, and ready to ready to perform perform Step Step 18, 18, Initiate Cooldown to RCS Cooldown "Initiate RCS Cold Shutdown.
to Cold Shutdown". EPP-15, Step EPP-15, Step 18 18 directs directs the the crew crew to cooldown the to cooldown RCS at the RCS _(a)_, using at _(a)_, (b)_ S/Gs. using _(b)_ S/Gs. A. (a) A. (a) maximum maximum rate rate (b) (b) only only intact intact B:I (a) B (a) less less than 100 °Flhour 100 OF/hour (b) any intact preferred, (b) any intact preferred, but but faulted ifif necessary C. (a) C. (a) maximum rate any intact preferred, but faulted if necessary (b) any (b) D. D. (a) (a) less than 100 °Flhour 100 °F/hour (b) (b) only intact The correct answer is B. The A: A: Incorrect Incorrect - Cooldown at the maximum rate is used to get the RCS at target temperature for
-
a SGTR per FRP-C.1, Step 21. B: B: Correct Correct - - Step 18 directs the crew to "Maintain Maintain cooldown rate in RCS cold legs less than 100 of 100 F in 0 in the last 60 minutes." minutes. and Check at and to "Check at least one SIG available for cooldown". cooldown. Step 18 18 RNO specifies that if RHR is NOT available, then a faulted SIG S/G may may be used. c: C: Incorrect Incorrect - - Rate Rate is is incorrect, but SIG incorrect, but use is S/G to use correct. is correct. D: D: Incorrect Incorrect - Rate - Rate is is correct, correct, but but may use aa faulted may use S/G ifif NO faulted SIG intact SIG NO intact S/G is available. is available.
- Tuesday, Tuesday, June June 17,17, 2008 2008 11:21:21 :04
- 04 PM PM 20 20
HLC-08 HLC-0 8 NRCNRCWritte n Exam Written Exam ExamQuesti Exam Question Number: on Numb er: 1717
Reference:
Refere EPP-15; nce: EPP-1 EPP-15-BD; 5; EPP-1 FRP-C.1, 5-BD; FRP-C Page10.
.1, Page 10.
KAStatem KA Statement: Knowledge ent: Knowl edge ofofthe theoperati onal implic operational implications thefollow ations ofofthe ing concep following concepts asthey ts as they apply apply to to the the (Loss (Loss of of Emergency Emerg ency Coolan t Coolant Recirc ulation Recirculation):): Norma l, Normal, abnorm al and abnormal and emergency operating operati ng ures procedures proced associa ted associated with with (Loss (Loss of of Emerg ency Emergency Coolan Coolantt emergency Recirculation). Recirc ulation). History: Histor New -Writte y: New - Written for HLC-0 n for HLC-08 NRC Exam. 8 NRC Exam.
- Tuesday, Tuesday,June June17,20081:21:04 17,2008 1:21 :04PM PM 2121
,"- Rev. 1717 Rev. EPP-15 EPP-15 LOSS OF LOSS OF EMERGENC EMERGENCY COOLANT RECIRCULA Y COOLANT TION RECIRCULATION of 3434 Page 9 9 of Page
-j STEP H INSTRUCTIONS INSTRUCTI ONS I I RESPONSE NOT RESPONSE NOT OBTAINED OBTAINED NOTE
** AA differe differential pressure ntial pressu re ofof 210 210 psid across the psid across the RCP number 11 seals RCP number seals is necess is necessary ary for for contin continued ued RCPRCP operati operation.
on.
** RCS cooldown RCS cooldown should should be be compl completed eted as as quickl quickly y asas possib possible since the le since the RCS may continue RCS may continue to depres to depressurize surize to to aa value value that that may may not not suppor support t differential differential pressu pressure re across across the the RCP RCP number number 11 seals.
seals. 18.
- 18. Initiate RCS Initiate RCS Cooldown Cooldown To To Cold Cold Shutdown As Shutdown As Follow Follows: s:
~Maintain cooldown rate in
&Majtamn cooldown rate in RCS RCS cold legs cold legs - LESS THAN
-
THAN 100°F 100°F IN THE IN THE LAST LAST 60 60 MINUTE MINUTE
- b. Mainta
- b. Maintain RCS temper in RCS temperature ature and pressure pressu re -
-
WITHIN WITHIN LIMITS LIMITS OF CURVE CURVE 3.4, 3.4, REACTOR REACTOR COOLANT COOLANT SYSTEM SYSTEM PRESSURE PRESSURE - TEMPERATURE
- TEMPERATURE LIMITATIONS LIMITATIONS FOR FOR COOLDOWN COOLDOWN c.
- c. Check Check RHRRHR System System - ALIGNED
- c. Go To Step 18.f. l8.f.
FOR FOR CORECORE COOLING COOLING d.
- d. Cooldown Cooldown usingusing RHR RHR System e.
- e. GoGo ToTo Step Step 24 24
~Check Check intact SIGs intact S/Gs - AT - AT LEAST LEAST ~IF RHR System RHR unavailable, System unavailable.
ONE AVAILABLE ONE AVAILABL E FOR FOR RCS RCS THEN use a faulted THEN use a faulted SIG S/G for for COOLDOWN COOLDOWN RCS cooldown. RCS cooldown. g.
- g. Check Check steam steam dumpdump to to Condenser Condenser g. Dump steam
- g. Dump from SIGs steam from using S/Gs using
- AVAILABLE
- AVAILABLE STEAM LINE STEAM PORVs.
LINE PORVs. Go Go ToTo Step Step 19. 19. h.
- h. Dump Dump steam steam to to Condenser Condenser from from SIGs S / Gs 19.
- 19. Check Check RCS RCS Hot Hot LegLeg Temperatures Temperatures - - WHEN RCS hot WHEN RCS hot leg temperatures leg temperatures LESS THAN LESS THAN 543°F 543°F less than 543°F, less than 543°F, THEN THEN GoGo To To Step Step 20.
20.
Rev. 17 RESPON RESPO SE TO INADEQ NSE UATE INADEQUAT E CORE COOLIN COOLING G FRP-C.1 Page 10 of 28 STEP H INSTRU CTION INSTRUCTIO S NS I I RESPON RESPO SE NOT OBTAIN NSE ED OBTAINED I NOTE Partia uncov ery all uncove SIG tubes is accep ry of S/G able in the follow ing steps accepttable steps
- Parti steamiing due to steam ng faste r than feedinfeeding g..
d, main block ed, Signall is blocke
- After the Low Steam line Pressure SI Signa ine isolation will occur if the high steam flow rate rate steamlline steam setpo setpoinintt is exceeexceed ded.
ed.
*21. Depre Depres ssuriz surize e All Intact S/Gs SIGs To 140 PSIG As Follows:
- a. Check Steam Dump to Condenser a. Dump steam at maxim maximuum rate m rate
- AVAILA
- AVAIL BLE ABLE using STEAM PORVs..
STEAIvI LINE PORVs Go To Step 21.c.
-
-------------~---
- b. Dump steam to Condenser at maximum rate
- c. Check RCS Hot Leg c. WHEN RCS hot leg tempe C. 2ii aturess temperrature Temp Tempe eratur ratures es - LESS THAN 543°
-
543°F F less than 543°F perfor m 543° F,, THEN perform Step 21.d. Go To Step 21. e. 2l.e. Defeatt Low Tavg Safety
- d. Defea Safety Injection Signal follow s:
Signa l as follow s: Momentarily place SAFETY
- 1) Mome SAFETY INJECT INJECTION ION T-AVG Selec Selecto torr Switc Switch h to BLOCK positi positio onn
- 2) Verif Verify SAFETY y LO TEMP SAFET Y INJECT INJECTION BLOCK ION BLOCKED ED status statu s light - ILLUN
- ILLUM INATED INATE D
- e. Check SIG S/G press pressu res - LESS ures - e. j S/G press IF SIG pressu re is ure is THAN 140 PSIG decre decrea sing,, THEN observ asing observe NOTE e NQI prior to Step 19 and Go Go To To Step 19.
IF S/G j press ure SIG pressu is re is increa increas ing, THEN sing, THEN GoGo To To Step 28. NUED NEXT PAGE (CONTIINUED (CONT PAGE))
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 18. Which ONE
- 18. Which ONE (1)
(1) of of the following isis the the following the reason reason for for placing placing the the Governor Governor valves valves on on the the Limiter Limiter while at while at 100% RTP? 100% RTP? A. Reduce the A. Reduce effects of the effects turbine overspeed of turbine overspeed in in the the event event of of aa load load rejection rejection or or Generator Generator output output breaker trip. breaker trip. Prevent Generator B. Prevent Generator overload resulting resulting from Turbine Impulse Impulse channel failures and and malfunctions. C. Prevent Generator VAR fluctuations induced induced from Impulse Impulse stage pressure fluctuations. Minimize Generator load fluctuations to prevent Reactor power from exceeding license D. Minimize limit. 18 18
HLC-08 NRC Written Exam 18.000077
- 18. 000077 AK2.06 001lGEN 001/GEN VOLT & GRID DIST/1I1I3.9/4.0/ROILOWININNEW - 2008JEHC-006 DIST/1/1/3.9/4.OIROILOW/N/AINEW - 20081EHC-006 Which ONE (1) of the following is the reason for placing the Governor valves on the Limiter while at 100% RTP?
A. Reduce the effects of turbine overspeed in the event of a load rejection or Generator output breaker trip. B. Prevent Generator overload resulting from Turbine Impulse channel failures and malfunctions. C. Prevent Generator VAR fluctuations induced from Impulse stage pressure fluctuations. D~ DY Minimize Generator load fluctuations to prevent Reactor power from exceeding license limit. The correct answer is D. A: Incorrect - Overspeed and / or Load Rejection will NOT be affected by the position of the
-
Limiter. B: Incorrect - Impulse channel effects are prevented by placing control to "IMP
- IMP OUT" OUT C: Incorrect - VAR fluctuations can occur regardless of valve position limit.
-
D: Correct - - Placing the Governor Valves on the Limiter after reaching steady state load Generators internal Speed Control from trying to maintain prevents the Turbine Generator's 60 Hz if Grid frequency drops. Exam Question Number: 18
Reference:
AOP-026 BD, Page 6. KA Statement: Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and the following: Reactor power. History: New - Written for HLC-08 NRC exam.
-
Tuesday, June 17, 2008 1 :21 :05 PM 1:21:05 22
DOCUMENT, GRID BASIS DOCUMENT, BASIS GRID INSTABILITY INSTABILITY Step Step Description Description 66 This This step checks ifif the step checks Turbine is the Turbine on-line. IfIf not is on-line. on-line the not on-line the RNO bypasses the RNO bypasses the addressing Turbine steps addressing Turbine response. steps response. 77 This This continuous continuous action step checks action step Turbine load checks ifif Turbine load has has increased increased due to the due to the decrease decrease in frequency. IfIf load system frequency. in system load has has increased, increased, thethe next next few few steps steps provide provide the operator with instructions to limit the load increase and stabilize the plant following the load change. If load has not increased the RNO bypasses these steps.
~.
(8
\
. This step checks ifif Reactor power is Reactor power less than or equal to 100%.
is less increased to greater than 100%, the RNO directs the reducing load, with the 100%. IfIf power power has has Valve Position Limiter, to maintain Reactor power less than 100%. The limiter must be used in this condition to set a fixed valve position. The governor speed.->
]goiernorspeecL g
c;ontrol s §tem will attempt to maintain RPM by opening rot s'ystem openg the ~ontrol valves, control_valves. / 9 This step directs the operator to limit the Turbine load increase based on current operating equipment ysing using the Valve Position limiter. The governor speed control system will attempt att ttoi inal RPM to maintain PM by opening the control valves. The step is dependent on the number of pumps etc operating. If feedwater flow is only sufficient to support 50%, then power must be limited to less than 50%. 10 Checking S/G levels in the normal operating range ensures the plant is stabilizing from the load change and that the automatic level control systems are operating properly. 11 This step checks Tavg trending to Tref. If not, some means of reactivity must be inserted to increase Tavg to Tref. Withdrawing Control rods in manual, or diluting the RCS will increase Tavg. 12 Checking Pressurizer pressure in its normal operating range ensures the plant is stabilizing from the load change and that the automatic pressure control system is functioning properly. 13 Checking Pressurizer level at or trending to program level ensures the plant is stabilizing from the load change and that the automatic level control system is operating properly. 14 14 This continuous action step checks if aa Turbine load reduction has occurred or is in progress. When spinning reserve starts picking up load or customers are being shed to reduce the load on the grid, the frequency may increase above 60 Hz. Being above 60 Hz means being greater than 1800 1800 RPM. The governor control system will close the control valves attempting to maintain speed. This results in aa reduction of of load, load. IfIf no load load reduction has occurred the RNO RNO bypasses the steps associated with aa load load reduction. 15 15 IfIf aa load reduction has has occurred, this this step step checks howhow much much load has been reduced to determine determine what actions need need to be be taken toto stabilize stabilize the plant. plant. IfIf the the reduction exceeds reduction exceeds 100100 MWe, MWe, thethe RNO RNO directs directs the the operator operator toto AOP-015, AOP-015, Turbine Turbine Runback Runback or or Secondary Secondary LoadLoad Rejection Rejection whilewhile continuing with with this this procedure. procedure. IAOP-026-BD Rev. Rev. 99 Page of 11 Page 66 of 11 I
HLC-08 NRC Written Exam
- 19. Given the following:
- The plant is at 45% power, with power escalation to 100% RTP in progress.
-
- Control Bank "0"
- D rods are at 185 steps on the step counters.
AUTOMATiC.
- Rod Control is in AUTOMATIC.
-
- The RO notes ALL 5 Control Bank "0"
- D rods' rods IRPI lRPl indicators are increasing.
-T
- TAVG 1 .5 of AVG is 1.5 °F higher than TTREF.
REF' indicate... The described conditions indicate ... A. a voltage or frequency problem on Instrument Bus 7A, is causing erroneous IRPI indications. B. a Control Bank "0" D Signal Conditioning Module fault is causing erroneous IRPI indications. C. a Pulse to Analog Converter fault is causing erroneous step counter indications. D. an Uncontrolled Rod Withdrawal is occurring. 19
HLC-08NRC HLC-08 NRCWritten WrittenExamExam
- 19. 000001 AK2.08 19.000001 AK2.08 OOllCONT. 001/CONT.ROD RODWITHDRAWALllI1I3.1I3.0IROIHIGHlNIAJNEW WITHDRAWALI1/1/3.1/3.OIROIHIGHIN/AINEW- 2008/AOP-00I-005 - 2008/AOP-001-005 Giventhe Given thefollowing:
following: Theplant
- The
- plantisisatat45% 45%power, power,withwithpower powerescalation escalationtoto100% 100%RTP RTPininprogress.
progress. ControlBank
- Control
- Bank"0" Drods rodsareareatat185185steps stepson onthe thestep stepcounters.
counters. RodControl
- Rod
- ControlisisininAUTOMATIC.
AUTOMATIC. TheRO
- The
- ROnotes notesALL ALL55Control Control BankBank"0" D rods' rods IRPI IRPI indicators indicatorsare areincreasing.
increasing. TAVG is 1.5 F 0 higher
- TAVG is 1.5 of higher than T REF, .
- than TREE The described The described conditions conditions indicate indicate......
A. aa voltage A. voltage or or frequency frequency problem problem on on Instrument Instrument BusBus 7A, 7A, isis causing causing erroneous erroneous IRPI IRPI indications. indications. B. Control Bank B. aa Control Bank "0" D Signal Signal Conditioning Conditioning Module Module fault fault isis causing causing erroneous erroneous IRPI IRPI indications. indications. C. aa Pulse C. Pulse to to Analog Analog Converter Converter faultfault isis causing causing erroneous erroneous step step counter counter indications. indications. DY an D'r' an Uncontrolled Uncontrolled Rod Rod Withdrawal Withdrawal is occurring. is occurring. The correct The correct answer answer is is O. D. A: Incorrect A: Incorrect - Instrument
- Instrument Bus Bus 7A 7A supplies supplies power to ALL IRPls. lRPls. Only CB "0" D IRPls lRPls are are changi changing. ng.
B: B: Incorre Incorrect ct - There
-
There is is NO NO single single SCM for a rod bank or group. Each IRPI has its own own SCM. SCM. C: C: Incorre Incorrectct - PP to
-
to A A Conve rter would affect the Converter the Rod Bottom Bypas Bypass Bistable, s Bistab but NOT le, but NOT thethe Step Step Counte Counters. rs. D: 0: Correc Correctt - RNP RNP has has NONO autom automaticatic RodRod Withd rawal, Rods Withdrawal, Rods should should NOT NOT be be movin moving.
-
g. Exam Exam Questi Questionon NumbNumber: er: 19 19 Refere nce: SD-00
Reference:
SD-009, 9, IRPI, IRPI, Figure Figure 22.22. KA KA Statem ent: Knowl Statement: Knowledge edge of of the the interre lations betwee interrelations between n the the Contin Continuous Rod Withdr uous Rod Withdrawal and awal and the follow ing: Individ the following: Individual ual rodrod display display lights lights and and indicat indications. ions. History History: : New New -Writte
-
Written n for for HLC-0 HLC-08 8 NRC NRC exam. exam. Tuesda y, June June17,200 8 1:21 :21:05
- 05PM Tuesday, 17,20081 PM 23 23
TAVG TA CONTROL BLOCK VG CONTROL BLOCK DIAGRAM DIAGRAM RDCNT-FIGURE-22 RDCNT-FIGURE-22 Nuclear Power (QN) .. Turblnll Load Repreaentlld I Powllr Mismatch L Non-Llnllar Gain K, Variable Gain r-- by Impluse Chamber Rate h--===-
- Prllssurll (Qro) Compensation J
Tref Program Trllt Compen
' - - - - - - - - -.....
-1 b:L U 100" 1----- satlon I--
A Tavg -A- Tovg Rod Splled Program
~
B Tavg Mlldlan Signal Selector ,...- Summing Unit h-iyfC Rods In Rods Out i C Tavg -C-
~
L - Control Tavg
-I Lead/l..ag I - -
Compensation Filter t-- Direction Bistabills Rod Control
~ Logic Cabinet Pressurizer Pressurizer Pressure ...-
Pressure Input (defeated) Input (defeated) I IRD9NTFi~1 RDCNTF22 I INFOR INFORMATIONMATION USE USE ONLYONLY
HLC-08 NRC HLC-08 NRC Written Exam Exam
- 20. Given Given the following:
following: The plant
- The plant has has experienced experienced aa Reactorffurbine Reactor/Turbine Trip from 100%
100% RTP*. RTP. crew is
- The crew
- is performing performing EPP-4, EPP-4, REACTOR REACTOR TRIP RESPONSE.
RESPONSE.
- Rod Bottom Light for Control Rod M6 is NOT lit.
-
- IRPI shows Control Rod M6 at 225 steps.
-
Which ONE (1) of the following actions, if any, must be performed? A. Adequate shutdown margin exists. Perform actions lAW AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM. B. Adequate shutdown margin does NOT exist. Borate for worth of most reactive rod. C. Adequate shutdown margin does NOT exist. Initiate boration to Cold Shutdown requirements. D. Adequate shutdown margin exists. No action required. 20 20
HLC-08 NRC HLC-08 Written Exam NRC Written Exam 20.
- 20. 000005 000005 AK3.01 001/INOPERABLE/STUCK ROD/l/2/4.0/4.3IROIHIGHIN/NFARLEY AK3.01 OOl/INOPERABLE/STUCK RODI1/214.014.31R0/HIGHIN/AJFARLEY - 2001IEPP-4-004
- 2001/EPP-4-004 Given the Given the following:
following: The plant
- The
- plant hashas experienced experienced aa Reactorrrurbine Reactor/Turbine Trip Trip from from 100%
100% RTP. RTP. The crew
- The
- crew isis performing performing EPP-4, REACTOR TRIP EPP-4, REACTOR TRIP RESPONSE.
RESPONSE.
- Rod
- Bottom Light Rod Bottom Light for for Control Control Rod Rod M6M6 isis NOT NOT lit.
lit. IRPI shows
- IRPI
- shows Control Control RodRod M6 M6 at 225 steps.
at 225 steps. Which ONE Which ONE (1) (1) of of the the following following actions, actions, ifif any, any, must must be be performed? performed? A. Adequate shutdown margin margin exists. Perform Perform actions lAW lAW AOP-001, MALFUNCTION MALFUNCTION OF OF REACTOR CONTROL REACTOR CONTROL SYSTEM. SYSTEM. B. Adequate shutdown margin does NOTexist. B. NOT exist. Borate Borate for worth of most reactive rod. C. Adequate shutdown margin does NOT exist. Initiate boration to Cold Shutdown requirements. D D~ Adequate shutdown margin exists. No action required. The correct answer is O. D. A: Incorrect - AOP-001 is NOT a concurrent AOP and EPP-4 would initiate ALL required
-
actions. B: Incorrect - Adequate SOM
- SDM does exist, accident analysis assumes the most reactive rod is stuck out, NO action is requred.
C: Incorrect - Adequate SDM
- SOM does exist, this is the required action for TWO or more rods stuck out.
D: Correct - - Accident Analysis supports adequate shutdown margin with one rod stuck out. Exam Question Question Number: Number: 20
Reference:
EPP-4,EPP-4, Pages 10 10 and and 11; EPP-4 BD, 11; EPP-4 BO, Pages 88 and and 9. 9. KA KA Statement: Statement: Knowledge of of the the reasons reasons for the following following responses as as they they apply apply to to the the Inoperable Stuck Inoperable // Stuck Control Control Rod:Rod: Boration Boration andand emergency emergency boration boration in in the the event event of of aa stuck stuck rod during during trip trip or or normal normal evolutions. evolutions. History: History: Modified Modified answer answer to to meet meet RNP RNP procedures, procedures, changed changed answer answer from from boration boration required required (Farley requirement) to no boration (Farley requirement) to no boration required. required.
- Tuesday, Tuesday, June June 17,2008 17, 2008 1:21 1:21:05
- 05 PM PM 24 24
Rev. Rev. 22 22 EPP-4 EPP-4 REACTOR REACTOR TRIP TRIP RESPONSE
RESPONSE
Page Page 1010 of of 2828 -j STEP H INSTRUCTIONS INSTRUCTIONS I E RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I
*******************************************************
************************************************************************** *******************
CAUTION CAUTION The boration The boration pathway pathway through through FCV-114B FCV-114B does does NOT QI have have heat heat trace. trace. Use Use ofof this pathway this pathway without without flush flush water water could could result result inin blockage blockage of of the the pathway. pathway.
* ** * * * * ** ****** ********* ** **************** *********** ****** ********** *****
**************************************************************************
@) Check All Check All Control Control Rods Rods - FULLY
- FULLY ~ IF IE only only oneone Control Control RodRod is is stuck stuck INSERTED INSERTED oU~'Go ouET!IEN Go To Step Step 14.
14. IF IF two two oror more more Control Control Rods Rods are are stuck out, ~ THEN perform the the following: following:
- a. Verify at least one Charging Pump is RUNNING.
- b. Borate to cold shutdown boron boron concentration using one of of the following:
- Blender to Charging Pump Pump suction:
- 1) Open FCV-113A, BA TO BLENDER.
- 2) FCV-113B, BLENDED Open FCV-ll3B, BLENDED MU TO CHG SUCT.
3)
- 3) Start Boric Start Boric Acid Acid Pump Pump aligned for blend.
aligned blend.
- RWST to RWST to Charging Charging Pump Pump suction:
suction:
- 1) Open
- 1) Open LCV-115B, LCV-115B, EMERG EMERG MU TO MU TO CHG CHG SUCT, SUCT, OR locally open locally open CVC-358, CVC-358, RWST TO RWST TO CHARGING CHARGING PUMP PUMP SUCTION.
SUCTION.
- 2) Close
- 2) Close LCV-ll5C, LCV-115C, VCT VCT OUTLET.
OUTLET. QR (CONTINUED NEXT (CONTINUED NEXT PAGE) PAGE)
Rev. Rev. 22 22 EPP-4 EPP-4 REACTOR REACTOR TRIP TRIP RESPONSE
RESPONSE
Page 11 of Page 11 of 28 28 1 H INSTRUCTIONS INSTRUCTIONS f I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED 13.
- 13. (CONTINUED)
(CONTINUED)
** Blender Blender to to VCT:
VCT: 1)
- 1) Open Open FCV-113A, FCV-ll3A, BA TO BLENDER.
2)
- 2) Open Open FCV-114B, FCV-ll4B, BLENDED BLENDED MU TO TO VCT.
VCT.
- 3) Start Boric Acid Pump aligned for blend.
- Emergency boration:
- 1) Open MOV-350, BA TO CHARGING PMP SUCT.
- 2) Start Boric Acid Pump aligned for blend.
- 3) Verify boric acid flow on FI-110.
Fl-lb.
- c. Open CVC-310B, LOOP 2 COLD LEG CHG.
IF CVC-310B CVC-3lOB will NOT open, THEN open CVC-310A, LOOP 1 HOT LEG CHG. charging flow
- d. Verify charging flow on on FI-122A.
14.
- 14. Check Check PZR Level Level - LESS THAN 14%
- 14% Go To Go To Step Step 16.
16.
RNP RNP WOG WOG BASIS/DIFFERENCES BASIS/DIFFERENCES STEP STEP STEP STEP 12 12 22 WOG BASIS WOG BASIS PURPOSE: PURPOSE: To ensurethe To ensure theproper properfeedwater feedwateralignment alignmentfollowing following aa reactor reactortrip trip BASIS: BASIS: Verification of Verification of main main feedwater feedwaterisolation isolation afterafter RCS RCS average average temperature temperature reachesreachesthe the setpoint isis necessary setpoint necessary to to prevent prevent an uncontrolled RCS an uncontrolled RCS cooldown cooldown from from excessive excessive feeding feeding of the of steam generators. the steam generators. Verifying Verifying feed feed flow flow toto the the steam steam generators generators ensures ensures aa secondary heat secondary heat sink sink forfor decay decay heatheat removal. removal. The The feedwater feedwater source source may may be be from from either either the AFW the AFW pumps pumps or or main main FW FW on the bypass on the bypass lines. lines. RNP DIFFERENCES/REASONS RNP DIFFERENCES/REASONS The RNP The RNP step step isis marked marked as as aa Continuous Continuous Action Action step, step, while while thethe ERG ERG does does notnot indicate indicate Continuous Continuous Action. Action. TheThe ERG ERG stepstep isis worded worded as as aa Continuous Continuous Action,Action, butbut not not indicated. indicated. This corrects This corrects an error inin the an error the ERG. ERG. Sub-step cc of Sub-step of the the RNP RNP stepstep establishes establishes flow flow toto maintain maintain levellevel inin the the normal normal control control band band rather than rather than aa minimum minimum flow flow from from MainMain or Auxiliary Feedwater. or Auxiliary Feedwater. This This will will accommodate accommodate trips from trips from low low or power level no power or no level in in which which S/G shrink would S/G shrink would be be insufficient insufficient to to drive drive level level low. IfIf feedwater low. feedwater is is established established at at the minimum flow the minimum flow specified specified by by the the ERG ERG in in these these cases, cases, S/G overfeed will result. result. Establishing Establishing aa control band band allows allows the operator operator to to vary vary thethe amount needed amount needed The The intent intent to establish required to establish required flow flow isis maintained maintained in in the the RNP RNP step. step. SSD DETERMINATION SSD DETERMINATION This is an SSD per criterion 8 and 11. C13 C13 N/A N/A WOG BASIS WOG BASIS N/A, this N/A, this step is not in the WOG ERG. DIFFERENCES/REASONS RNP DIFFERENCES/REASONS This caution is not contained in the ERG. The caution is provided as a warning to remind the operator of the fact that there is no heat tracing in the Boric Acid line to the top of the VCT and the consequence consequences s of boration through this line without the ability to flush. One of the potential pathways for boration is via the top of the VCT. This could be aa problem ifif a LOOP has occurred since the PW Pumps are powered from a non-vital bus. SSD SSD DETERMIN DETERMINATION ATION This This is is anan SSD SSD per per criterion criterion 10.10. 13 13 33 WOG WOG BASIS BASIS PURPOSE: PURPOSE: To To ensure ensure all all control control rods rods are are inserted inserted for for adequate adequate shutdown shutdown marginmargin BASIS: BASIS:
.. _----, .. _--"--:>
AA subcritical subcritical core core is is verified verified ifif all all rods rods areare at the bottom at the bottom according according to to the the rod rod bottom bottom lights lights and the and the rod rod position position indicators. indicators. IfIf these these indications indications revealreveal that that oneone rod rod isis not not inserted, inserted, no no immediate immediate action action isis [eqyjce re uired since the the core core isis designed desi ned for for adequate ade uate shutdown shutdown margiiE margm--' iTne Wit one rod rod stuck out. However, stuck out. However, ifif more more than than oneone rod rod fails fails to to insert insert fully, fullY, the the shutdown shut own reactivity reactivity margin margin mustmust be be made made up up through tiirough emergency emergency boration boration to to account account for for the the reactivity reactivity worth worth of of the the stuck stuck rods. rods. IEPP-4-BD EPP-4-BD Rev. Rev.22 22 Page Page88ofof19 19/
RNP RNP WOG WOG BASIS/DIFFERENCES BASIS/DIFFERENCES STEP STEP STEP STEP DIFFERENCES/REASONS RNP DIFFERENCES/REASONS RNP The steps accomplish The steps accomplish the same objective. the same objective. The The EPPEPP provides provides detailed detailed instructions instructions on on emergency boration emergency boration and also provides and also provides alternative alternative actions actions toto get get boron boron to to the the core. core. The ERG The directs the ERG directs operator to the operator emergency borate to emergency borate "x" x number number of of ppm ppm for for each each control control rod not fully rod not inserted. The fully inserted. The EPPEPP directs directs the the operator operator to to emergency emergency borate borate to.£Qld to.lci
~ownSQ..nditions.
ncorj!ons. This assures reactor This assures reactor shutdown shutdown regardless regardless of of the the number number of of control control rods not rods not fully inserted. This fully inserted. This guidance guidance was provided by was provided by Reactor Reactor Engineering Engineering personnel personnel to to allow for allow conservative value for aa conservative value forfor multiple multiple rods rods which which causes causes varying varying rodrod worth, worth, dependent on dependent on thethe location, location, number, number, and core life. and core life. SSD DETERMINATION SSD DETERMINATION This is This an SSD is an SSD per criterion 55 and per criterion and 10.10. 14-17 14-17 44 WOG BASIS WOG BASIS PURPOSE: PURPOSE: To ensure To ensure normalnormal post-trip post-trip pressurizer pressurizer levellevel response response BASIS: BASIS: Following the Following reactor trip, the reactor trip, pressurizer pressurizer levellevel is is expected expected to to decrease decrease to to the the no-load value due to shrinkage of the RCS from the at-power, programmed temperature to no-load temperature. The pressurizer level control system should then stabilize level at the no-load value. If level decreases below the no-load value, the operator should try to reestablish no-load level by operation of the charging system. If level drops below the letdown isolation setpoint, the operator should also verify letdown isolation and restore level prior to reestablishing reestablishing letdown. Level should then be controlled at the no-load value. DIFFERENCES/REASONS RNP DIFFERENCES/REASONS The ERG step has been split into 4 steps for the RNP procedure due to the large amount of additional information required. The decision criteria was changed from GREATER "GREATER THAN THAN" to LESS"LESS THAN THAN" to remove the NOTs from RNO column. Letdown is placed in the CLOSE position to prevent the letdown valves from automatically opening and lifting the letdown relief valve. The EPP contains supplementa supplementall information on the operation operation of PZR heaters heaters that is particular particular to plant design. When the heaters are de-energized due to letdown isolation, re-energizing the heaters heaters after level level is is regained requires the the control switch switch toto be be placed placed in in the the OFF OFF position position andand returned to to the the ONON position. position. With RCPRCP B B running and and RCPRCP C C not not running, running, andand pressurizer level level less less than 30%, 30%, PZR PZR spray spray flow flow would would be be insufficient. insufficient. The The operator operator is is directed directed to to control control level level between between 30% 30% and 40%, ifif this and 40%, this condition condition exists, and transition to exists, and to Step Step 16.
- 16. This This step step will will take take care care of of all all permutations permutations of of RCPs RCPs running.
running. ERG ERG Step Step 44 requires requires maintaining maintaining PZR PZR level level at at 22%. 22%. RNP RNP Step Step 1515 was was inserted inserted to to control control level higher level higher if RCP if RCP C not running, C not running, this step was this step was added added to to address address thethe condition condition for for C C RCP RCP running. running. SSD SSD DETERMIN DETERMINATION ATION This This isis an an SSD SSD per per criterion criterion 44 and 10. and 10. N23 N23 N/A N/A WOG WOG BASIS BASIS N/A, N/A, this this step step isis not not inin the the WOG WOG ERG. ERG. RNP DIFFERENC RNP DIFFERENCES/REASONSES/REASONS Auxiliary Spray will Auxiliary Spray will be used inin the be used the subsequent subsequent step. step. The The note note reminds reminds the the operator operatorthatthat Supplement Supplement KK isis available available for for use use ifif desired. desired. IEPP-4-BD EPP-4-BD Rev. Rev. 2222 Page 9 19/ Page 9 of of 19
Alarm DD1, "RCP Alarm DDl, RCP SEAL SEAL INJ FLOW LO," NJ FLOW annunciated aa short LO, annunciated short time after LT-459 time after LT-459 failed failed low. low. Which ONE Which ONE ofof the following describes the following describes the reason for the reason for the the above above alarm? alarm? A. The isolation of letdown caused charging flow to decrease and the seal seal injection header flow flow diminished due to the increasing pressure on the charging header. B. The loss of the the pressurizer heaters caused charging flow to to decrease andand the seal injection injection header flow diminished due to the increasing pressure on the charging header. C. As charging flow increased, the DIP across the seal injection filter rose and the seal injection header flow diminished due to the increased resistance to flow. D. As charging flow increased, the seal injection header flow diminished due to the decreasing pressure on the charging header. A - Incorrect, Increased charging header pressure would cause the seal injection flow to
-
increase. B - Incorrect, Increased charging header pressure would cause the seal injection flow to
-
increase. C - Incorrect, Increased DIP across the seal injection filter under the stated conditions
-
could only be caused by increased flow through the filter. D - Correct, Increased charging flow robs the seal injection line of flow.
-
Source: Farley Bank Question # 052101D14044 Answer:D Answer: D 10\ N<<'/-'
- 12. OO5AK1.05 005AK1.05 11 Unit 11 has experienced a reactor/turbine trip from full power. ~~.l£'
- ----
----~--.--.~---~-----
I -----."----------- While performing FNP-1-ESP-O.1, "REACTOR TRIP RESPONSE, FNP-I-ESP-O.l, REACTOR RESPONSE," it is observed that the Rod 'Rod Bottom Bottom' light is NOT lit for control rod M6 'M6' in Control Bank B. 'B'. DRPI shows control rod M6 'M6' at 228 steps. Which ONE of of the following actions must be performed performed in accordance with FNP-1-ESP-O.1, FNP-I-ESP-O.l, REACTOR "REACTOR TRIP RESPONSE, RESPONSE," in in response to this condition? A. No action is required. B. B. An emergency emergency boration of of at at least least 2500 2500 gallons isis required. required. C. C. AnAn emergency emergency boration boration of of at at least 5000 gallons least 5000 gallons is is required. required. D. D. Verify shutdown margin Verify shutdown margin within within the the limits limits provided provided inin the the COLR. COLR.
A Incorrect, Even A - Incorrect,
- Even aa single rod stuck single rod stuck inin the core, post the core, trip, requires post trip, requires anan emergency emergency
)
boration. boration. B - Correct, ESP-0.1 B - Correct, ESP-0.1 Step RNO Step Step 33 RNO requires at 3.5 requires Step 3.5 at least least 2500 2500 gal gal boration boration per per rod rod not not inserted. inserted. C - Incorrect, C - value would be for Incorrect, This value for 2 rods rods notnot fully inserted. fully inserted. D - Incorrect, This D - Incorrect, This is the TS is the TS action for one action for one or more rods or more rods untrippable. untrippable. Source: Summer NRC Exam Source: Summer 2000-301 Exam 2000-301 Answer: B
- 13. 005EG2.4.4 11 Given the following conditions on Unit 1: 1:
- Reactor power is at 73%.
-
- Turbine load is being slowly increased~
- increased.
- Control Bank D rod 'BS'
- B8 indicates 144 steps.
- Control Bank D rod 'K6'
- K6 indicates 156 156 steps.
- Remaining Control Bank D'
- D rods indicate 16S 168 steps.
-
- Control Bank D is being moved as required to maintain Delta I.
- B8 and does NOT move when Control Bank D is moved 'out'
- Rod 'BS' t or 'in'.
out in.
-
- Rod K6
'K6' does move when Control Bank D is moved 'out' out or 'in'.
in. Which ONE of the following describes the action required to be taken within one hour? A. Be in Mode 3, Hot Standby. B. Reduce turbine load and insert Control Bank D to 155 steps. C. Trip the reactor immediately and go to EEP-0, REACTOR TRIP OR SAFETY EEP-O, "REACTOR INJECTION. INJECTION." D. Determine that the shutdown margin is within the limits specified in the COLR. A - Incorrect, Must be in Mode 33 in 6 hours.
-
B - Incorrect, This will place the stuck rod within the 12 step limit but will not correct the
-
K6 rod. C - Incorrect, This is correct action for unexplained rod motion or dropped rod.
-
D - Correct, Rod B8
-
BS could be considered to be untrippable therefore, TS 3.1.4 requires verification of adequate SDM. TS 3.1.4 also requires the verification of adequate SDM SDM if more than one one rod not within alignment within alignment limit. Source: Source: New Answer: D
- 14. 005K1.13 11 14.
Given Given the following conditions on Unit 2: - The - The injection injection phase phase of of aa LOCA LOCA is in progress. is in progress. - - RHR pump flows indicate pump indicate 1350 gpm on 1350 gpm on the discharge discharge ofof each each RHR RHR pump. pump.
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 21. Given
- 21. Given thethe following:
following: The plant
- The
- plant isis operating operating at at 50%
50% RTP RTP following following aa 50% load rejection 50% load rejection from from 100% 100% RTP. RTP. APP-003-C8, PZR
- APP-003-C8,
- PROT HI PZR PROT LEVEL isis illuminated.
HI LEVEL illuminated. All Pressurizer
- All
- Pressurizer LevelLevel channels, channels, LT-459A, LT-459A, 460, 460, and and 461, 461, indicate indicate 92%.
92%. RTB AA && BB CLOSED
- RTB
- CLOSED (RED) (RED) indication indication isis illuminated.
illuminated. Which ONE Which ONE (1)(1) of of the the following following isis the the NEXT NEXT procedure procedure the the crew should implement? crew should implement? A. AOP-015, SECONDARY SECONDARY LOAD LOAD REJECTION. REJECTION. B. AOP-025, RTGB B. RTGB INSTRUMENT INSTRUMENT FAILURE.FAILURE. PATH-i. C. PATH-1. D. FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION GENERATION /I ATWS. 21 21
HLC-08NRC HLC-08 NRCWrittenWrittenExam Exam 21.000028
- 21. 000028G2.4.4 G2.4.4OOIIPZR 001/PZRLLVL MALFUNCTION/1/2/4.5/4.7/RO/HIGHJN/AINEW- 2008IPATH-I-002 VL MALFUNCTION/1I2/4.5/4.7IROIHIGHJNINNEW - 2008IPATH-1-002 Given the follow
.Given the following: ing:
Theplant
- The plantisisoperating operatingatat50% 50%RTP RTPfollowing followingaa50% 50%load loadrejection rejectionfrom from100%
100%RTP.
-
RTP. APP-003-C8,PZR
- APP-003-C8,
- PZRPROT PROTHIHILEVEL LEVELisisilluminated.
illuminated. AllPressurizer
- All
- PressurizerLevel Levelchannels, channels,LLT-45T-459A, 9A,460, 460, and and461, 461, indicate indicate92%.
92%. RTBAA&&BBCLOSED
- RTB
- CLOSED (RED) (RED)indication indicationisisilluminated.
illuminated. Which ONE Which ONE (1) (1) ofofthe the following following isis the the NEXT NEXT procedure procedure the the crew crewshould should implement? implement? A. AOP-015, A. AOP-015, SECONDARY SECONDARY LOAD LOAD REJECTION. REJECTION. B. AOP-025, B. AOP-025, RTGB RTGB INSTRUMENT INSTRUMENT FAILURE. FAILURE. C PATH-1. C~ PATH-i. D. FRP-S.1, D. FRP-S.1, RESPONSE RESPONSE TO TO NUCLEAR NUCLEAR POWER POWER GENERATION GENERATION // ATWS. ATWS. The correct.answer The correct.answer is is C. C. A: Incorrect A: Incorrect - PATH-1 PATH-i wouldwould taketake priority priority over AOP-015 AOP-0i 5 due to having high PZR PZR levels.
-
levels. B: Incorrect B: Incorrect - No- No instrument instrument failure failure is indicated. indicated. C: Correct - C: Correct Pressurizer Levels Pressurizer above 91% Levels above 91 % (2/3 while greater than P-7) should have have initiate initiatedd
-
aa reactor reactor trip. trip. Accord Accordinging to OMM-OMM-022, 022, EMER EMERGENCY OPERATING GENCY OPERATING PROC EDURES USER PROCEDURES USER'S S GUIDE GUIDE,, SectioSection n 8.2.1, Entry "Entry into the EOP Netwo Network will rk will be require d be required when when the follow followinging condit ions occur: IfIf at conditions at any any time aa reactor reactor trip trip or or safety safety injecti injectionon occurs occurs or is require or is required, d, the the Operat Operator or will will enter enter PATH PATH-1."
-i D:
D: Incorre Incorrect ct - PATH
-
PATH-1 -i isis require required,d, FRP-S FRP-S.1 .i isis NOT NOT aa direct direct entry entry proced procedure. ure. Exam Exam Questi Questionon Numbe Number: r: 2121 Refere nce: APP-0
Reference:
03-C8; OMM-APP-003-C8; OMM-022, 022, Page Page 10, 10, Step Step 8.2.1.1 8.2.1.1.. KA KA Statem ent: Ability Statement: to recogn Ability to recognizeize abnorm abnormal al indicat ions for indications for system system operati operating parameters ng parame that ters that are are entry-l evel conditi entry-level ons for conditions for emerge emergencyncy andand abnorm abnormal operating procedures. al operating procedures. History History: : New New -Writte
-
Written n for for HLC-0 HLC-08 8 NRC NRCexam. exam. Tuesda y, June June17, 2008 1:21:05 1:21 :05PM Tuesday, 17,2008 PM 25 25
APP-003-C8 APP-003-C8 ALARM ALARM PZRPROT PZR PROTHI LEVEL HILEVEL AUTOMATICACTIONS AUTOMATIC ACTIONS 1.1. Reactortrip Reactor trip (2/3 logic interlocked (2/3 logic interlockedwith withP-7) P-7) CAUSE CAUSE 1.1. Letdown-Charging mismatch Letdown-Charging mismatch 2.2. Load rejection Load rejection 3.3. Channel failure Channel failure 4.
- 4. Increasing TTavg Increasing avg OBSERVATIONS OBSERVATIONS 1.1. Pressurizer Level Pressurizer Level (LI-460, (LI-460, LI-461 LI-461 and and LI-459A)
LI-459A) 2.
- 2. Letdown and Letdown and Charging Charging flowflow (FI-150 (Fl-150 and and FI-122A)
Fl-122A) 3.
- 3. Tavg Tavg 4.
- 4. Generator load Generator load ACTIONS ACTIONS
- 1. IF Reactor Trip has occurred, THEN Refer To PATH-1, PATH-i, EOP Network.
- 2. IF a channel has failed, THEN remove from service using OWP-030.
- 3. Increase Letdown flow and/or decrease charging flow to reduce level DEVICE/SE TPOINTS DEVICE/SETPOINTS 1.
- 1. LC-459A/91 LC-459A/91% % of span 2.
- 2. LC-460A LC-460A /91%
/ 91 % ofof span span 3.
- 3. LC-461 LC-461 /91%
/91 % of of span span POSSIBLE POSSIBLE PLANT PLANT EFFECTS EFFECTS 1.1. Reactor Reactor Trip Trip REFERENC REFERENCES ES 1.1. PATH-i, PATH-1, EOPEOP Network Network 2.2. ITS ITS LCO LCO 3.3.1, 3.3.1, 3.4.9 3.4.9 3.3. AOP-0i5, AOP-015, Secondary Secondary LoadLoad Rejection Rejection 4.4. OWP-030, OWP-030, Pressurizer Pressurizer Level Level Transmitters Transmitters (PLT)
(PLT) 5.5. CWD CWD B-190628, B-190628, SheetSheet440, 440, Cable Cable BF BF IAPP-003 APP-003 Rev. Rev. 37 37 Page30 Page 30ofof53 531
8.1 .4 (Continued) 8.1 .4 (Continued) 4.
- 4. Applicability - The Applicability - The AOPs AOPs are generally applicable are generally applicable forfor all all plant plant conditions from conditions from ColdCold Shutdown Shutdown to to full full power.
power. TheThe specific specific applicability of applicability of an AOP isis listed an AOP listed on on thethe Purpose Purpose andand Entry Entry Conditions (PEC) Conditions (PEC) page page of of the the procedure. procedure. 8.1.5 8.1.5 APP General APP General LayoutLayout 1.
- 1. The APPs The APPs are are comprised comprised of procedures containing of procedures containing the the instructions for instructions for each each individual individual alarm alarm function function ofof an an Annunciator Annunciator Panel.
Panel. 2.
- 2. The specific The specific format of the APPs of the APPs is is described described in in AP-007.
AP-007.
- 3. The APPs APP5 provide provide instruction instruction specific to a single alarm. These alarms mayor may or may not be indicative of a plant transient. These alarms are generally indicative of a problem with an individual component.
- 4. Specific guidance for use of the APPs is given in OMM-001-15. OMM-O01 -15.
8.2 General Use of The EOP Network NOTE: In all cases of EOP use, the reactor is assumed to either be shutdown or attempts are in progress to shutdown the reactor. 7
,,
E tyinto1fli / civo rk (_.
- 1. Entry into the EOP Network will be required when the folIoW{n.g conditions occur:
.* If at any time aa reactor trip or safety injection occurs or is
- uiredJp
_ _ _r:..:::e~u}_~e.9! rator will the Oeerator will enter enter Path-i. Path-1 . /
-----~-------~--.--- .. - - ---- -- ----...-
.* IfIf at any time at any time aa complete complete loss loss of of power power on on the ACAC Emergency Emergency Busses takes Busses takes place, the Operator place, the Operator will will enter enter EPP-1, EPP-1, Loss Loss OfOf AllAll AC AC Power.
Power. This This includes includes any any time time during during the the performance performance of of any any other other EOPEOP procedure. procedure.
.* EPP-5 EPP-5 may may be be entered entered directly directly whenever whenever natural natural circulation circulation is is required.
required.
.* EPP-21 EPP-21 may may be be entered entered directly directly whenever whenever pressurizer pressurizer heaters heaters must be energized must be energized from from thethe Emergency Emergency Busses.Busses.
.* EPP-25 EPP-25 may may be be entered entered directly directly whenever whenever itit isis required required to to energize supplementa energize supplemental l plant plant equipment equipment using using the the DSDS Bus.Bus.
OMM-022 IOMM-022 I Rev. Rev. 2828 I Page 10 Page 10 of of 5454/
HLC-08 NRC HLC-08 NRC Written Exam Exam l&C has
- 22. I&C has just completed completed aa surveillance surveillance onon the the high high voltage power power supply supply to to the Source Source Range Range nuclear instruments.
nuclear instruments. The The surveillance surveillance determined determined the as-found as-found voltage was 1400 1400 VDC, instead of instead of the normal normal 1600 1600 VDC. Which ONE ONE (1) of the following following describes describes the effect effect and and reason reason the lower lower voltage has has on on SR SR N-31 and N-32 instrument response? will.... N-31 and N-32 indication will .... A. NOT be affected because the high voltage only supplies power to the channels' channels amplifiers and electronic circuitry. B. increase due to a reduction of pulse height discriminations that allows more ionization events to pass through the discriminator circuit. C. increase due to a reduction in gamma compensation, allowing more, lower energy events to pass through the pulse height discriminator circuit. D. decrease because reduced voltage results in fewer ion pairs reaching the detector electrodes due to lower potential applied to the detector. 22 22
HLC-08 NRC HLC-08 NRC Written Written ExamExam
- 22. 000032AK1.01
- 22. 000032 AK1.01OOllLOSS 001/LOSSOF OFSRSRNII1I2/2.S/3.1IRO/HIGH/N/AfTURKEY NJJ1/2/2.5/3.1IROIHIGHJN/AJTURKEYPOINT POINT- 2001lCOMPON
- 2001/COMPONCHAP CHAP2-020 2-020 I&C hasjust l&C has justcompleted completed aasurveillance surveillance on on the the high high voltage voltage power powersupply supplytoto the the Source Range Source Range nuclearinstruments.
nuclear instruments. The surveillance determined The surveillance determined the the as-found as-found voltage voltage waswas 1400 1400 VDC, VDC, instead ofofthe instead normal 1600 the normal VDC. 1600 VDC. Which ONE Which ONE (1) (1) ofofthe the following following describes describesthethe effect effectand and reason reason thethe lower lowervoltage voltage has has onon SR SR N-31 and N-32 instrument N-31 and N-32 instrument response? response? N-31 and N-31 and N-32 N-32 indication indication willwill....
....
A. NOT be A. NOT be affected affected because because the the high voltage only high voltage only supplies supplies power power to to the the channels' channels amplifiers amplifiers and electronic and electronic circuitry. circuitry. B. increase due B. increase due to to aa reduction reduction of of pulse pulse height height discriminations discriminations that that allows allows more more ionization ionization events to events to pass pass through through the the discriminator discriminator circuit. circuit. C. increase due C. increase due to to aa reduction reduction in in gamma gamma compensation, compensation, allowing allowing more, more, lower lower energy energy events events to pass through the pulse height discriminato to pass through the pulse height discriminatorr circuit. circuit. D D~ decrease because decrease because reduced reduced voltage voltage results results inin fewer fewer ion ion pairs pairs reaching reaching thethe detector detector electrodes due to lower potential electrodes due lower potential applied applied to the detector. The correct The correct answer answer is D. A: Incorrect A: Incorrect - Indicated
- Indicated power will decrease. The reduction of 200 VDC is significant.
B: Incorrect - Pulse B: Incorrect - Pulse height height discriminator discriminator circuit has no relation to the High Voltage applied to to the the detector. Incorrect - There is NO gamma compensatio C: Incorrect - compensation n circuit (lR (IR Only). D: D: Correct - - The high voltage set at 1600 1600 VDC in the Proportional Region of the detector curve, such that a significant reduction in in applied voltage will result in in aa reduced count count rate. Exam Question Number: 22 Exam Question 22
Reference:
Reference:
SD-010, SD-010, NI, NI, Pages Pages 16-17, 16-17, Figure Figure 7. 7. KA KA Statement: Statement: Knowledge Knowledge of of the the operational operational implications implications of of the the following following concepts concepts asas they they apply to Loss of Source Range Nuclear apply to Loss of Source Range Nuclear Instrumentat Instrumentation: ion: Effects Effects of of voltage voltage changes changes on on performance performance.. History: History: Modified Modified by by changing changing threethree distractors distractors and and updating updating to to to to RNP RNP equipment equipment voltages. voltages.
- Tuesday, Tuesday,June June17,2008 17, 20081:21:06 1:21 :06PMPM 26 26
SD-OlO SD-OlO NUCLEARINSTRUMENTATION NUCLEAR INSTRUMENTATION SYSTEM SYSTEM in the in NIS. the NIS. Region II isis the Region Recombination Region the Recombination Region which which hashas the the following following general general characteristics: characteristics:
** Not all Not ion-pairs formed all ion-pairs formed are are collected collected
** Increasing the Increasing applied voltage the applied voltage results results inin an an increase increase inin the the number number of of ion-pairs ion-pairs collected collected
** The number of The number of ion-pairs ion-pairs formed formed isis dependent dependent uponupon the the type type of of radiation radiation (i.e.
(i.e. Neutron and Neutron and Gamma Gamma caused caused ionization ionization will will bebe different) different) The IR The IR inner chamber operates inner chamber operates in in this this region, region, allowing allowing large large changes changes in in compensation compensation with small with small changes changes in in voltage voltage (0-1 (0-1 IOV) 10V) Region II Region II is is the Ionization Region the Ionization Region which which has has the following following general general characteristics: characteristics:
** All ion-pairs formed All formed are collected are collected
** Increasing the Increasing the applied voltage results in no increase in the number of ion-pairs collected collected
- The number of ion-pairs formed is dependent upon the type of radiation (i.e.
Neutron and Gamma caused ionization will be different) The IR JR outer chamber, PR, and Channels N5I/N52 N5 1/N52 detectors operate in this region. Region III Ill is the Proportional Region which has the following general characteristics: characteristics:
- Applied voltage is sufficiently sufficientlhig nigh h to cause secondary ionizations (called Gas Amplification)
Amplification)
- Output is proportional to the ionizing event
- The Gas Amplificatio Amplification n ranges from a factor of 11 to a factor of iO 104 The SR Detectors operate in this range._..
The Nuclear Nuclear Instrumentat Instrumentation ion System detectors are the gas filled type. The The SR detectors use BF3 as a fill gas, the Intermediate and PR Detectors Detectors use N2 N2 as fill gas. The fission chambers chambers are also also gas filled. When When boron boron is is used used to to detect detect neutrons neutrons by by indirect indirect ionization ionization the the following following interactions interactions occur: occur: on + sB°
- 7 + 2He 3Li 4 + 5e The 2He4 particle The 2He 4 particle isis also also called called an an alpha alpha particle.
particle. TheThe Li 3Li +3 and and He2He +2 ions ions induce induce ionization ionization of gas atoms. of gas atoms. The The neutrons neutrons detected detected by by excore excore detectors detectors areare leakage leakage neutrons neutrons NIS NIS Page 16of Page 16 of48 48 Revision 77 Revision INFORMAT INFORMATION ION USE USE ONLY ONLY
SD-OlO SD-OIO NUCLEARINSTRUMENTATION NUCLEAR INSTRUMENTATION SYSTEM SYSTEM The Nuclear The Instrumentation System Nuclear Instrumentation System employs employs eight eight radial radial detector detector locations locations containing containing total of aa total sixteen detectors of sixteen detectors (two Proportional Counters, (two Proportional Counters, two two Compensated Compensated Ionization Ionization Chambers, four Chambers, four dual-detector Uncompensated Ionization dual-detector Uncompensated Ionization Chamber Chamber assemblies, assemblies, and and two two dual-detector fission dual-detector fission chambers) chambers) installed installed around around the Reactor in the Reactor in the the Primary Primary shield shield (see (see Figure 1). Figure 1). 3.1.1 SR 3.1.1 Detectors SR Detectors BF3 Proportional Counters BF3 Proportional Counters (see (see Figure Figure 8) have aa nominal
- 8) have nominal thermal thermal neutron neutron sensitivity sensitivity of of ten counts per neutron per square centimeter-se ten counts per neutron per square centimeter-second. ~ominal ap~d cond. Nominal voltage i~
applied voltage is16. Vdc with Vdc with aa maximum maximum of of 1900Vdc. l900Vdc. ------ These counters These counters provide provide pulse signalssignals to to the the SRSR Channels. Channels. TheseThese detectors detectors areare installed installed on opposite sides on opposite sides of of the core at the core an elevation at an elevation approximating approximating the quarter core height. the quarter core height. High density polyethylene is is used as as aa moderator and and insulator inside the housing assembly. The SR detectors are designed such that gas pressure and volume minimize the magnitude of pulse signals caused by gamma radiation. The incident neutrons interact with the boron in the BF3 gas producing large pulses. The pulse amplitude created by the neutron is about 6 times larger than that created by the gamma. The gamma radiation does not interact with the boron to produce a large pulse. The output of these discriminator circuit which will not pass the smaller gamma detectors is then fed to a discriminator produced pulses, but will pass the larger pulses produced by neutron ionization. 3.1.2 JR IR Detectors Compensated Ionization Chambers (see Figure 9) serve as neutron sensors for the JR IR Channels, and are located above, in the same instrument wells and detector assemblies, as the SR SR Detectors. These detectors have a nominal nominal thermal neutron neutron sensitivity of of 44 xx 1014 10- 14 amperes per neutron per neutron per square centimeter-se centimeter-second. cond. Gamma sensitivity sensitivity is less than 33 xx 10 11 amperes roentgen per per hour 10- amperes per roentgen per hour when operated uncompensat when operated uncompensated, and is ed, and is reduced reduced to approximatel approximately 10- 13 amperes/R/h y 33 xx iO- amperes/R/hrr in in compensated operation. operation. The The detectors detectors areare positioned with their centers at an elevation positioned with their centers at an elevation corresponding correspondin to one g to one half of the half of the core core height. height. The The JR IR Detectors Detectors are are constructed constructed to to have have two two N2N2 filled filled chambers, chambers, one one inside inside thethe other. other. Both Both the the inner inner and and outer outer surfaces surfaces of the outside of the outside chamber chamber is is coated coated with with Boron-lO. Boron-lO. The The inner inner chamber chamber has has no no coating coating and and operates operates in in the the recombinatio recombination region. Both n region. Both neutron neutron and and gamma gamma reactions reactions occur occur in in the the outer outer chamber chamber while while only only gamma gamma reactions reactions occur occur in in the inner chamber. the inner chamber. The The output output of of the inner chamber the inner chamber isis subtracted subtracted from from the the output output of of the the outer outer chamber chamber which which results results in net output in aa net output caused caused byby neutron neutron radiation radiation only. only. TheThe NIS NIS Page Page 1717 of of4848 Revision 77 Revision INFORMAT INFORMATION ION USE USE ONLY ONLY
NUMBER OF TYPICAL NUMBER TYPICAL OF ION PAIRS COLLECTED ION PAIRS COLLECTED PER PER RADIATION EVENT RADIATION VERSUS VOLTAGE EVENT VERSUS VOLTAGE APPLIED APPLIED ON ON A GAS-A GAS-FILLED DETECTOR FILLED DETECTOR NI-FIGURE-7 NI-FIGURE-7 I-I Z z c C w I~a. 0 >> cc .... ww zz 12 12
+=
jl c
.2 t 0 0 I QI
.21 QI I 00 10 10 C C>
I~ E 0 ~ 81 N
'2
.2 a.
0
.... I I
~ ~ CI.. QI 10 ....... cW 10 I I] I I-U III V VI 0 u w
-' -' 10 10 8
I" I
'<< II "I-C I
~ I/) c.:: 66 I I z Q u. 10 10 I I 0 c.:: w a::I 10 44 I
- E
- >
z 2 I 10 I V1 V2 V3 V4 V5 APPLIED VOLTAGE APPLIED Curve 1: Radiation event Curve 1: event of of lower specific ionization. Curve 2: Radiation Curve 2: event of Radiation event of higher specific ionization. higher specific I nif07 nifO7 I
V (0 op 7 O32AK1.01 C TurkeyPoint Turkey Unit PointUnit 12/15/2003 3 I&Cjust I&C completedaa surveillance just completed surveillance on on the the high high voltage voltage power powersource source toto the the Source Source Range Range (SR) (SR) nuclear nuclear instruments. instruments. I&C determined the I&C determined the voltage voltage was was 1800 1800 Vdc, Vdc, (200 Vdc lower (200 Vdc lower than than the the normal normal 2000 2000 Vdc). Vdc). Which ONE Which ONE of the following ofthe following describes describes the effect (and the effect (and the the reason) reason) this this lower lower than than normal normal voltage voltage has has on on SR SR nuclear nuclear instrument performance. instrument performance. SR indication will... SR indication will... D . . decrease because D..... decrease because thethe reduced reduced voltage voltage inin the the high high voltage voltage power power supply supply results results in in fewer fewer ion ion pairs pairs reaching reaching the the electrodes due electrodes due to to lower lower potential potential applied applied toto the the detector. detector. A. ......not A. not be affected because be affected because the high voltage the high voltage only only supplies supplies power power toto the the electronic electronic circuitry circuitry of of the the amplifier. amplifier. B .. .increase because B.... .increase because thethe reduced reduced voltage voltage inin the high voltage the high voltage power power supply supply results results in in more more ion ion pairs pairs reaching reaching the the electrodes due electrodes due to lower potential to lower potential applied applied to the detector. to the detector. C..... C ...decrease because smaller decrease because smaller pulses pulses are are generated generated by the the alpha alpha decay decay ofU235 ofU235 andand gamma gamma interactions. interactions. A - Incorrect; A - Incorrect; Indicated Indicated power power would would decrease. The high voltage is set at 2000 V Vdc dc in the plateau of SD004SDOO4 Figure Figure 15 so 15 so thatthat small small variations variations inin high voltage voltage will not greatly greatly effect the count rate sensed by the detector. 200 200 Vdc Vdc decrease is decrease is not not aa small small variation. B - Incorrect; Indicated B - Incorrect; Indicated would would decrease decrease because the fewer ions would be measured due to the lower voltage. C - Incorrect; Pulses C - Incorrect; Pulses generated generated by the the alpha decay are unaffected by the voltage, measurement measurement of those pulses is affected. affected.
HLC-08 NRC HLC-08 NRC Written Written ExamExam
- 23. Given
- 23. Given the the following:
following:
- The
- The plant at 30%
plant isis at RTP, with 30% RTP, with aa power power escalation escalation in in progress. progress. Power escalation
- Power
- escalation isis limited limited to to 11%/hr due to
%/hr due to fuel fuel leakage leakage limitations.
limitations. APP-036-C7, R-24
- APP-036-C7,
- R-24 MONITOR MONITOR HI HI has has just just alarmed.
alarmed. R-24, MAIN R-24, MAIN STEAM STEAM LINE LINE N-16 N-16 DETECTOR DETECTOR Which ONE (1) of the following describes the condition and the appropriate AOP entry entry requirements, ifif any? requirements, any? A. R-24 information is is considered invalid invalid with identified identified fuel leakage. No further actions are required. B. R-24 information is useful only for trending below 40% power. Observe R-24 R-24 trends, and if R-15 OR R-19 confirm evidence of leakage, refer to AOP-035, S/G TUBE LEAKAGE. C. R-24 in alarm is an entry condition, crew must enter AOP-035, S/G TUBE LEAKAGE. D. R-24 information below 40% power is useful only for trending. Adjust R-24 leakage model firmware for power level below 40%. 23 23
HLC-08NRC HLC-08 WrittenExam NRCWritten Exam
- 23. 000037AA1.06 23.000037 AM .0600l/SGTRl1/2/3.S/3.9/RO/HIGH/N/A/NEW OO1ISGTRJ1I2/3.813.9JROIHIGHINIAJNEW- 200S/AOP-035-002- 2008/AOP-035-002 Giventhe Given following:
thefollowing:
- The
- Theplant plantisisatat30%30% RTP,RTP, with withaapower powerescalation escalation inin progress.
progress. Powerescalation
- Power
- escalation isis limited limited to to 11%/hr
%/hr dueduetotofuel fuel leakage leakage limitations.
limitations. APP-036-C7, R-24
- APP-036-C7,
- R-24 MONITOR MONITOR HI HI has hasjust just alarmed.
alarmed. R-24, MAIN R-24, MAIN STEAMSTEAM LINE LINE N-16 N-16 DETECTOR DETECTOR Which ONE Which ONE (1) (1) of the following of the following describes describes the condition and the condition and the the appropriate appropriate AOPAOP entry entry requirements, ifif any? requirements, any? A. R-24 A. R-24 information information isis considered considered invalid invalid with with identified identified fuel fuel leakage. leakage. No No further further actions actions are are required. required. B:' R-24 information BY R-24 information isis useful useful only only for for trending trending below below 40%40% power. power. Observe Observe R-24R-24 trends, trends, and and ifif R-15 OR R-19 confirm R-15 OR R-19 confirm evidence evidence of leakage, refer of leakage, refer to to AOP-035, AOP-035, S/G SIG TUBE TUBE LEAKAGE. LEAKAGE. C. R-24 in C. R-24 in alarm is an entry condition,condition, crewcrew must enter AOP-035, S/G S/G TUBE LEAKAGE. LEAKAGE. D. R-24 information D. R-24 information below 40% power is useful only for trending. Adjust R-24 leakage leakage model model firmware firmware for for power level below 40%. The The correct answer is correct answer is B. B. A: Incorrect A: Incorrect - R-24 provides useful information, but only when
-
when? 40% power. R-24 is an an N-i N-16 6 monitor, does NOT become invalid due to fuel leakage. B: B: Correct Correct - - Entry Entry into into AOP-035 is not justifiedjustified unless R-1 R-155 or R-1 R-19 9 indication confirms primary to secondary secondary leakage, leakage, due due to the limitations limitations of of R-24 R-24 when powerpower is is less less than 40%. than 40%. C: C: Incorrect Incorrect - Confirmation
-
Confirmation of of S/G S/G Tube Tube Leakage Leakage isis required required for for AOP AOP entry. entry. This This would would be be confirmed confirmed by by an an increasing increasing trend. trend. D: D: Incorrect Incorrect - Action
-
Action to to adjust adjust leakage leakage modelmodel firmware firmware isis to to make make R-24 R-24 valid valid below below 40% 40% power. power. This This may may be be performed performed during during extended extended low low power power operation. operation. Exam Exam Question Question Number:Number: 23 23
Reference:
Reference:
AOP-035, AOP-035, Page Page 3; 3; APP-036-C7 APP-036-C7. . KA KA Statement: Statement: Ability Abilityto to operate operate and and// or or monitor monitorthe the following following as as they they apply applytoto the the Steam Steam Generator GeneratorTube Tube Leak: Leak: Main Main steam steam lineline rad rad monitor monitor meters. meters. History: History: New New -Written
-
Writtenfor for HLC-08 HLC-08 NRC NRC Exam.Exam.
- Tuesday, Tuesday,June June17, 2008 1:21 :06 PM 17,20081:21:06 PM 27 27
Rev. Rev. 1919 AOP-035 AOP-035 S/G TUBE SIG TUBE LEAK LEAK I
. Page Page 33 ofof 5252 Purpose and Purpose and Entry Entry Conditions Conditions (Page 11 of (Page of 1)1) 1.
- 1. PURPOSE PURPOSE This procedure This procedure provides provides thethe direction direction necessary necessary to to respond respond toto aa Steam Genera tor tube Steam Generator tube leak when leak when thethe EOP EOP network network hashas not not been been entered.
entered. NOTE
** An alarm An alarm on on RR-1 RR-1 is is confirmed confirmed if if any any diverse diverse OR redundant redundant indicat indicationion shows shows primary primary to to secondary secondary leakage.
leakage.
** Alarms on Alarms on R-15.
R-15, 19. 19, and R-24 are confirmed confirmed in accordance accordance with with APP-0 36. Auxili ary Annunciator. APP-036. Auxiliary Annunciator. 2.
- 2. ENTRY CONDITIONS ENTRY CONDITIONS Any Any ofof the the below below condit ions:
conditions:
** Confir med R-24 Confirmed R-24 leakag leakage e greater greater thanthan 30 30 gpd.
gpd. OR
** Confir med alarm Confirmed alarm onon radiati radiationon monito monitors R-15 OR rs R-l5 OR R-l9.
R-19. OR
** Confir med warnin Confirmed warningg alarm alarm onon RR-1, RR-1. RNS RMS RECORDER RECORDER., for for radiati radiation on monito monitors rs R-15 R-15 OROR R-19.
R-19. OR
** Notific ation by Notification by Chemi stry Person Chemistry Personnel nel thatthat aa PSAL-PSAL-1. PSAL-2.
- 1. PSAL- OR 2, OR PSAL-PSAL-33 conditi on exists condition exists forfor primar primaryy to to second secondary leakage.
ary leakag e.
- - END END --
APP-036-C7 APP-036-C7 Page 11 of2 Page of 2 ALARM ALARM R-24 MONITOR R-24 MONITOR HI HI WILL REFLASH
*** WILL REFLASH ***
AUTOMATIC ACTIONS AUTOMATIC ACTIONS 1.1. None None CAUSE CAUSE
- 1. Primary
- 1. Primary to to Secondary Secondary S/G SIG Tube Tube leakage leakage while while at at power power
- 2. Failure
- 2. Failure of ERFIS power of ERFIS power input input (causes (causes monitor monitor to to default default to to 40%
40% andand increases increases sensitivity) sensitivity) OBSERVATIONS OBSERVATIONS 1.
- 1. R-24 Monitor Chart R-24 Monitor Chart Display Display 2.
- 2. Trends of Trends of radiation radiation monitors monitors R-15 R-15 and R-19.
and R-19. 3.
- 3. Power Level, Power Level, NISNIS andand ERFIS ERFIS NOTE:
NOTE: IF power IF power is is less less than than 40%, 40%, THENTHEN R-24 R-24 information information is is useful useful only only for for trending. trending. Also, Also, the the information is information not likely is not likely to to bebe accurate accurate onon the the initial initial alarm alarm atat any any power power level level prior prior to to unit unit adjustment for the leakage adjustment location. leakage location. IF the cause of the alarm is known known to be be the movement of radioactive material, material, such as aa loaded spent fuel cask, THEN no further actions are required. ACTIONS ACTIONS
- 1. OBSERVE monitor trends for leak rate AND evidence of short term spiking.
- 2. IF short term spiking is evidenced, THEN allow the indicated level to decrease prior to continuing.
IF short term spiking is present, THEN the alarm is NOT valid.
- 4. IF trends from R-15 OR R-19 confirm evidence of primary to secondary leakage, THEN REFER to to AOP-035.
- 5. IF neither R-15, nor R-19, show evidence of primary to secondary leakage, THEN PERFORM OP-504 OP-504 to monitormonitor for low low level primary primary to secondary leakage.
- 6. IF OP-504 performance confirms evidence of primary primary to secondary secondary leakage, leakage, THEN REFER to AOP-035.
7.
- 7. CONTACT CONTACT E&C E&C Personnel to to sample sample the affected SIG the affected S/G to to determine determine thethe status status ofof primary primary toto secondary secondary leakage..
leakage.. 8.
- 8. IF IF primary primary to to secondary secondary leakage leakage is confirmed, THEN is confirmed, THEN INITIATE INITIATE action action toto adjust adjust the the R-24 R-24 leakage leakage model firmware model firmware for for the the leakage leakage location.
location. 9.
- 9. WHEN WHEN the the R-24 R-24 leakage leakage model model firmware firmware hashas been been adjusted adjusted for for the the leakage leakage location, THEN location, THEN PERFORM PERFORM the the following:
following: 1)
- 1) IF IF indicated indicated leakage leakage isis greater greater thanthan 55 gpd, gpd, THEN THEN MONITOR MONITOR R-24 R-24 using using ERFIS ERFIS ANDAND REFER REFER to to OMM-001-13.
OMM-001-13. 2)
- 2) IF IF indicated indicated leakage leakage isis greater greater thanthan 30 30 gpd, gpd, THEN THEN REFER REFER to to AOP-035.
AOP-035. 10.
- 10. IF IF the the alarm alarm isis NOT NOT valid, valid, TI-lEN THEN INITIATE INITIATE action action to to determine determine the the reason reason forfor the the alarm.
alarm. Troubleshoo Troubleshoot and repair t and repair channel channel Investigate Investigate area for transient area for transient radioactive radioactive material material IAPP-036 APP-036 Rev. 62 Rev. 62 Page 23 Page 23 of 961 of96
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 24. Which
- 24. Which ONE ONE (1)
(1) of of the the following following describes describes the location and the location type of and type of indication indication available available outside outside of the of the Control Control Room Room to to monitor monitor the the availability availability of Heat Sink? of Heat Sink? A. Steam Flow A. Steam Flow and Feedwater Flow and Feedwater Flow for all 33 S/Gs for all S/Gs atat the the Secondary Secondary Control Control Panel. Panel. B. All B. SIG Levels All 33 S/G Levels and and Pressures Pressures atat the the Charging Charging PumpPump RoomRoom Panel. Panel. C. All C. All 33 S/G SIG Levels Levels and and Pressures Pressures atat the the Secondary Secondary Control Control Panel. Panel. D. Steam D. Steam Flow Flow and Feedwater Flow and Feedwater Flow for all 33 S/Gs for all S/Gs atat the the Charging Charging Pump Pump Room Room Panel. Panel. 24 24
HLC-08NRC HLC-08 NRCWritten WrittenExam Exam 24.000068
- 24. 000068AA2.0S AA2.05OOllCONTROL 001/CONTROLROOM ROOMEVAC/1/2/4.2/4.3fROILOW/N/A/NEW EVAC/1/2/4.2/4.3IRO/LOW/N/AINEW- 2008/AOP-004-00S
- 2008/AOP-004-005 Which ONE (1) of Which ONE (1) of the followingthe follow ingdescribes describesthe thelocation locationand andtype typeofofindication indicationavailable outside available outside ofofthe theControl ControlRoom Roomtotomonitor monitorthe theavailability availabilityofofHeat HeatSink?
Sink? SteamFlow A.A. Steam Flowand andFeedwater FeedwaterFlow Flowfor forall all33S/Gs S/Gsatatthe theSecondary SecondaryControl Control Panel. Panel. B. All B. All33S/G S/G Levels Levelsandand Pressures PressuresatatthetheCharging Charging PumpPump Room Room Panel. Panel. C All c~ All33 S/G SIG Levels Levels and and Pressures PressuresatatthetheSecondary Secondary Control Control Panel. Panel. D. Steam D. Steam Flow Flow and and Feedwater Feedwater Flow Flowfor for all all 33 S/Gs S/Gs atatthe the Charging Charging Pump Pump RoomRoom Panel. Panel. The correct The correct answer answer isis C. C. A: Incorrect A: Incorrect - There There areare NONO Steam Steam Flow/Feed Flow/Feed Flow Flow indications indications available available outside outside of
-
of the the Control Control Room at Room at the the Secondary Secondary Control Control Panel. Panel. B: Incorrect B: Incorrect - S/G
- SIG Pressure Pressure isis NOT NOT available available at at the the Charging Charging Pump Pump RoomRoom Panel.
Panel. C: Correct C: Correct - - WR S/G WR S/G Levels Levels and and S/G S/G PORVs PORVs and and PICs PICs are are available available atat the the Secondary Secondary Contro Panel. Controll Panel. D: Incorrect D: Incorrect - There There are are NO NO Steam Flow/Feed Flow/Feed Flow indications indications available available outside of of the the Control
-
Control Room Room at at the Chargi Chargingng Pump Room Panel. Exam Question Exam Question Number: Number: 24 24
Reference:
AOP-0
Reference:
AOP-004, 04, Pages Pages 18 and 26. KA KA Statem ent: Ability Statement: Ability to to determ ine and interpr determine interpret et the follow ing as they apply to the Contro following Controll Room Room Evacua tion: Availa Evacuation: bility of heat sink. Availability Histor History: y: New New - Writte
-
Written n for for HLC-0 HLC-08 8 NRC NRC exam. exam. Tuesda y, June June17,200 8 1:21 :21:06
- 06PM Tuesday. 17,20081 PM 28 28
AOP-004 Rev. 16 CONTRO CONTROL L ROOM INACCESSIB ESSIBIILITY LITY Page 18 of 30 INSTRU INSTRUCTIO CTION )__STEP_H S NS CONTINUOUS USE RESPON
RESPONSE
SE NOT OBTAIN ED OBTAINED I ATTACH MENT ATTACHME NT 22 TURBIN TURBINE E BUILDI NG OPERAT BUILDING OPERATOR OR (Page 33 of 6)
- 9. Trans Transfferer S/G PORV Contr Controoll To The Local Contr Contro ollers llers At The Secon Second dary ary Contr Contro oll Panel As.
As ~
, <:. l ., ....1(1 CHI Follow "d~""""V'"
o11 ows: fp F s: ~ _~l"Jr [Iers
- a. Place PIC-4PIC-47 77.
7, manual thumbwheel. wheel, to to the closed positi positio onn by rotati rotatingng the white thumbwheel in the up direc tion
- b. Place PORV RV-l Switch in the DEFEAT DEFEAT positi positio onn
- c. Place the transfer switch on PIC-477 to MAN positi on positio n
- d. Place PIC-4 81.
Place_PIC-48 7, manual thumbwheel. wheel, to the closed positi on positio n by rotati rotatingng the white thumbwheel in the up direc tion
- e. Place PORV RV-2 Switch in the DEFEAT DEFEAT positi positio onn
- f. Place the transfer switch on PIC-487 to MAN positi on positio n
- g. Place ,PIC-4C Q, manual f..LC..h-9L thumbwheel.
wheel, to the closed positi positio onn by rotati rotatingng the white thumbwheel in the up direc tion
- h. Place PORV RV-3 Switch in the DEFEAT DEFEAT positi positio onn
- i. Place the trans fer switch on PIC-497 to MAN positi on positio n
Rev. Rev. 16 16 AOP-004 AOP-004 CONTROL CONTROL ROOM ROOM INACCESSIBILITY INACCESSIBILITY Page Page 26 26 of of 30 30
STEP H INSTRUCTIONS INSTRUCTIONS 1 1 RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED CONTINUOUS CONTINUOUS USE USE ATTACHMENT ATTACHMENT 33 AUXILIARY AUXILIARY FEEDWATER FEEDWATER OPERATOR OPERATOR (Page (Page 55 of of 8) 8) 13.
- 13. Check Check MDAFW Pump MDAFW Pump Status Status - AT
- AT Verify Verify thethe SDAFW SDAFW Pump Pump isis running running LEAST LEAST ONE RUNNING ONE RUNNING as as follows:
follows: a.
- a. Verify Verify MS-Vl-8A, MS-Vl-8A, SG SC "A" A STM STM SUPPLY SUPPLY TO TO STM STM DRIVEN DRIVEN AFWAFW PUMP, isis OPEN.
OPEN. b.
- b. Verify Verify MS-Vl-8B.
MS-Vl-8B, SG SC "B" B STMSTM SUPPLY TO STM DRIVEN AFW AFW PUMP, is OPEN.
- c. Verify MS-Vl-8C, MS-V1-8C, SG SC "C" C STM STM SUPPLY TO STM DRIVEN AFW AFW PUMP, is OPEN.
- d. Verify AFW-V2-14A, AFW-V2-14A, SDAFW PUMP PUMP FW DISCH TO SG SC "A",
A, isis OPEN. OPEN.
- e. Verify AFW-V2-14 AFW-V2-14B, B, SDAFW PUMP PUMP FW DISCH TO SG "B", B, is OPEN.
is OPEN. AFW-V2-14C,. SDAFW
- f. Verify AFW-V2-l4C SDAFW PUMPPUMP FW DISCH TO SC SG "C",
C, isis OPEN. OPEN.
- g. Throttle SDAFW Pump Pump Discharge Discharge Valves To Maintain S/C SIG Levels Levels 60% And Between 60%
Between And 68% 68% WRWR Using Using The SIG WR Level Indicators
~ ~econdary Control Panel
- h. Go
- h. Go To To Step Step 17.
17.
-
14.
- 14. Contact Contact The The SSO SSO And And Request Request An An IF an j an additional additional operator operator is is NOT NOT Additional Additional Operator Operator With With AA Radio Radio available, THEN available, THEN the the Auxiliary Auxiliary Feedwater Operator Feedwater Operator should should periodically monitor periodically monitor S/CSIG level level AND perform perform Steps Steps 1515 AAND 16.
16.
HLC-08 NRC Written Exam
- 25. Given the following:
- A Large Break LOCA has occurred.
-
- Containment pressure peaked at 36 PSIG.
-
- BOTH Containment Spray pumps are operating.
-
- Containment pressure and leak rate from Containment continue to decrease.
-
At which Containment pressure will the leak rate from Containment be Y2 1/2 the leak rate of the peak pressure? A. 33PSIG. PSIG. B. 66PSIG. PSIG. C. 99PSIG. PSIG. D. 1818PSIG. PSIG. 25 25
HLC-08NRC HLC-08 NRCWritten WrittenExam Exam
- 25. 000069
- 25. 000069AK1.01 AK1.01OOllLOSS 001/LOSSOF OFCONT CONTINTEG/1/2/2.6/3.1/RO/HIGH/N/A/NEW INTEG/1/2/2.6/3.1/RO/HIGHJN/AINEW- 200S/COMPON2008/COMPONCHAP
- CHAP2-010 2-010 Giventhe Given thefollowing:
following:
- AALarge
- Large Break BreakLOCA LOCAhas hasoccurred.
occurred. Containmentpressure
- Containment
- pressurepeaked peakedatat36 PSIG.
36 PSIG. BOTH Containment
- BOTH
- Containment Spray Spray pumps pumps are are operating.
operating. Containment pressure
- Containment
- pressure andand leak leak rate rate from from Containment Containmentcontinue continue to to decrease.
decrease. At which At which Containment Containment pressurepressure will will the the leak leak rate rate from from Containment Containment be be Y2Y2 the the leak leak rate rate of of the the peak pressure? peak pressure? A. 33PSIG. A. PSIG. B. 66PSIG. B. PSIG. C 99 PSIG. c~ PSIG. D. 18 D. 18PSIG. PSIG. The correct The correct answer answer is is C. C. A: Incorrect A: Incorrect - 33 is
- is the the square square root of the correct answer.
B: Incorrect - 66 is B: Incorrect - is the the square square root of the peak pressure. c: C: Correct Correct - - Break Break flow is proportional to the square root of Delta P. D: D: Incorrect Incorrect - 18
-
18 isis half half of peak pressure. Exam Exam Question Question Number: Number: 25 25
Reference:
Reference:
GFES, GFES, Detectors Detectors section section of of Components Components,, Equation Equation 2-2. 2-2. KA KA Statement: Statement: Knowledge Knowledge of of the the operational operational implications implications of of the the following following concepts concepts as as they they apply to apply to LossLoss of of Containment Containment Integrity: Integrity: Effect Effect of of pressure pressure on on leak leak rate. rate. History: History: NewNew - Written
-
Written for for HLC-08 HLC-08 NRCNRC exam. exam.
- Tuesday, Tuesday,June June17,2008 17, 20081:21 1:21:07
- 07PMPM 29 29
Eq 2-2
*
*OIPoc{V)2 DIP (V) 2 Where:
Where: D/P DIP... Differential Pressure
= DifferentiaJPressure V
V =
= Volu metric flow rate {spfm Volumetric (scfm)
Eq 2-3
- V :::: K!b V= K,JD1P IP Whe Where: re:
*
.
VV = Volu
= metric Volumetric flow rate (scfm (scfm))
KK =Con
= stant for Constant th\e restr for the restriction iction D/P DIP ==Diffe rential press Differential pressure ure FWR PWR// Compo nents // Chapte Components Chapterr 22
Head flow Head flow meters meters operate operate on on principle principle that that placing placing restriction in restriction in fluiQ fluid stream stream causes causes pressure pressure drop drop The respltingDP The resulting DP is measured to is measured to provide provide flow flow rate rate The Qasicprimciple basic principle is is that when fluid flows flows through through restriction, its velbqity restri.ctiJlfits velocity willincreaSce will increase anciit& and its .pressLJrewill pressure will decrease decrease Although fluid's Although fluids velocity velocity increases, increases, its volumetric volumetric flow rate does not changechange The change change in press pressure ure (DIP), (D/P), however,isproportional however, is proportional to squa squarE)re of volu metric flow rate volumetric PWR PWR//Compo nents //Chapte Components r 22 Chapter
HLC-08 NRC HLC-08 NRC Written ExamExam Given the
- 26. Given the following:
Reactor trip has
- A Reactor
- has occurred.
occurred. The The crew crew is is preparing preparing to to transition from PATH-1 PATH-i after after checking SI checking SI NOT NOT actuated actuated OR OR required. required. 10-14% Narrow Range.
- All S/G levels are 10-14%
-
- AFW flow indicates 400 GPM.
-
A and "S"
- S/G "A"
- B pressures indicate 11080 080 PSIG.
C pressure indicates 1150 PSIG.
- S/G "C"
-
Which ONE (1) of the following describes the status of CSF-3, HEAT SINK and the initial crew actions to address the event? A. RED; Check total feedwater flow less than 300 GPM due to operator action, lAW FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK. B. YELLOW; Isolate feedwater to affected S/G lAW FRP-H.2, RESPONSE TO S/G OVERPRESSURE. OVERPRESSU RE. C. YELLOW; Check any S/G level greater than 75% lAW FRP-H.3, RESPONSE TO S/G HIGH LEVEL. D. YELLOW; Check level in affected S/G less than 16% lAW FRP-H.5, RESPONSE TO STEAM GENERATOR LOW LEVEL. 26 26
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 26. WEl3
- 26. WE13EK2.2 EK2.2OOllSG OVERPRESSURE/1/2/3.013.2IROIHIGHIN/AINEW- 200S/FRP-H.2-002 001/SGOVERPRESSURE/l/2/3.0/3.2IROIHIGH/N/A/NEW - 2008JFRP-H.2-002 Given the
. Given thefollowing:
following:
- Reactortrip
- AA Reactor trip has occurred. The has occurred. The crew crew isis preparing preparing toto transition transition from from PATH-1 PATH-i after after checking SI checking SI NOT NOT actuated actuated OR OR required.
required. All SIG
- All
- levels are SIG levels are 10-14%
10-14% Narrow Narrow Range. Range. AFW flow
- AFW
- flow indicates indicates 400 400 GGPM.
PM. SIG "A"
- SIG
- A and and "8"B pressures pressures indicate indicate 1080 1080 PSIG.
PSIG. S/G "c"
- SIG
- pressure indicates C pressure indicates 1150 1150 PSIG.
PSIG. Which ONE Which ONE (1) (1) of the following of the following describes describes the the status status of of CSF-3, CSF-3, HEAT HEAT SINKSINK andand the the initial initial crew crew actions to actions to address address the the event? event? A. RED; Check A. RED; Check total total feedwater feedwater flow flow less less than than 300 300 GPMGPM due due to to operator operator action, action, lAW lAW FRP-H.1, FRP-H.1, RESPONSE TO RESPONSE TO LOSS LOSS OF OF SECONDARY SECONDARY HEAT HEAT SINK.SINK. B B~ YELLOW; Isolate YELLOW; Isolate feedwater to affected SIG SIG lAWlAW FRP-H.2, FRP-H.2, RESPONSE RESPONSE TO S/G . OVERPRESSURE. OVERPRESSURE. C. YELLOW; Check any S/G C. YELLOW; SIG level greater than 75% lAW FRP-H.3, RESPONSE RESPONSE TO TO SIG S/G HIGH LEVEL. HIGH LEVEL. D. YELLOW; D. YELLOW; Check level in affected SIG less than 16% lAW FRP-H.5, RESPONSE TO STEAM GENERATOR STEAM GENERATOR LOW LEVEL. The correct answer is B. The correct A: A: Incorrect Incorrect - No RED status, but correct actions for FRP-H.1.
-
B: B: Correct Correct - - Any S/G pressure> 1140 1140 is YELLOW status, entry condition for FRP-H.2, initial action action is to ISOLATE is to ISOLATE flow to to affected affected S/G. S/G. C: Incorrect C: Incorrect - FRP-H.3
-
FRP-H.3 YELLOW YELLOW would would apply apply IFIF affected affected S/G SIG Level Level was was high. high. D: 0: Incorrect Incorrect - Incorrect
-
Incorrect entry,entry, S/G SIG levels levels are are required required to to be be less less than than 8%8% for for FRP-H.5 FRP-H.5 entry. entry. Exam Exam Question Question Number: Number: 26 26
Reference:
Reference:
FRP-H.2, FRP-H.2, Pages Pages 3-4; 3-4; H.1, H.1, Page Page 3;3; H.3, H.3, Page Page 3; 3; H.5, H.5, Page Page 3; 3; CSFST, CSFST, Page Page 5. 5. KA KA Statement: Statement: Knowledge Knowledge of of the the interrelations interrelations between between the the (Steam (Steam Generator Generator Overpressure Overpressure) ) and the following: Facilitys heat removal and the following: Facility's heat removal systems, systems, including including primary primary coolant, coolant, emergency emergency coolant,coolant, thethe decay decay heat heat removal removal systems, systems, and and relations relations between between the the proper proper operation operation of of these these systems systems to to the the operation operation of of the the facility. facility. History: History: New New - Written
-
Written for for HLC-08 HLC-08 NRC NRC Exam. Exam.
- Tuesday, Tuesday,June June17, 17,2008 20081 1:21:07
- 21 :07PM PM 30 30
Rev. 88 Rev. FRP-H.2 FRP-H.2 RESPONSE TO RESPONSE TO STEAM STEAM GENERATOR GENERATOR OVERPRESSURE OVERPRESSURE Page 33 of Page of 66 Purpose and PuriDose and Entry Entry Conditions Conditions (Page 11 of (Page of 1) 1) 1.
- 1. PURPOSE PURPOSE This procedure This procedure provides provides actions actions for an an overpressure overpressure condition condition affecting any affecting any Steam Steam Generator Generator where where pressure pressure has has increased increased above above the highest the highest Steamline Steamline Safety Safety Valve Valve setpoint.
setpoint. 2.
- 2. ENTRY CONDITIONS ENTRY CONDITIONS Sink Critical CSF-3, Heat Sink Critical Safety Safety Function Function Status Tree Tree on on a YELLOW condition.
condition.
-END-
- END -
Rev. 88 Rev. FRP-H.2 FRP-H.2 RESPONSE TO RESPONSE TO STEAM STEAM GENERATO GENERATOR OVERPRESSURE R OVERPRES SURE Page 44 of Page of 66 STEP H INSTRUCTIONS INSTRUCTI ONS I J NOT OBTAINED RESPONSE NOT RESPONSE OBTAINED NOTE Throughout this procedure, affected Throughout "affected" refers to any S/G S/G in in which pressure is greater than 1140 1140 psig.
1.
- 1. Check S/G Check S/G Pressures - ANY
- Reset SPDS bNQ return to GREATER THAN GREATER THAN 1140 PSIG step in efffect.
procedure and Step
- 2. Verify FW Isolated To Affected S/G(s) :
S/G(s)
- FW REG Valve(s) - CLOSED
-
- FW REG BYP Valve(s) - CLOSED
-
- FW HDR SECTION Valve(s) - -
CLOSED
** 3. Check Affected S/G(s) Level - - Go To FRP-H.3, Response To Steam LESS THAN 84% [82%] Generator High Level.
- 4. Check APP-002-F7, APP-002-F7, INSTR AIR HDR Align nitrogen to Steam Line LO PRESS - EXTINGUISHED
- EXTINGUISHED PORVs using AOP-017, Loss Of Instrument Air.
5.
- 5. Dump Steam From The Affected Observe CAUTION prior to Step 7 S/G(s) Using One Of The bNQ Go To Step 7.
Following Methods:
** STEAM LINE PORV(s)
** Unlock Unlock andand close close the the breaker breaker at at MCC-8 forfor the affected affected S/G(s)
S/G(s) andand use use the the MSIV BYP(s) BYP(s) QR
** STEAM STEAM SHUTOFF(s)
SHUTOFF(s) to to SDAFW SDAFW PUMP PUMP
Rev. 22 Rev. 22 FRP-H.1 FRP-H.i RESPONSE TO RESPONSE TO LOSS LOSS OF OF SECONDARY SECONDARY HEAT HEAT SINK SINK Page 33 of Page of 45 45 Purpose and Purpose and Entry Entry Conditions Conditions (Page 11 of (Page of 1) 1) 1.
- 1. PURPOSE PURPOSE This procedure This procedure provides provides actions actions toto respond respond toto aa loss loss of of secondary secondary heat sink heat sink in in all all Steam Steam Generators.
Generators. 2.
- 2. ENTRY CONDITION ENTRY CONDITIONSS
- a. PATH-i, PATH-I, when when minimum m1nlmum AFW AFW flow isis not not verified verified AND narrow narrow range range level in level in all all S/Gs S/Gs is is less less than than 8%
8% [18%] [18%].
- b. CSF-3, Heat Sink Critical
- b. Critical Safety Function Status Tree on a RED condition.
condition.
- END -
- -
Rev. 99 Rev. FRP-H.3 RESPONSE TO STEAN RESPONSE STEAM GENERATOR HIGH HIGH LEVEL Page 33 of Page of 77 Purpose and Entry Conditions PurDose (Page 11 of 1) 1) 1.
- 1. PURPOSE PURPOSE procedure provides actions to respond to a steam generator This procedure high level condition and to address the steam generator overfill concern.
- 2. ENTRY CONDITIONS
- a. CSF-3, Heat Sink Critical Safety Function Status Tree on a YELLOW condition.
- b. FRP-H.2, Response To Steam Generator Overpressure Overpressure,, if the SIG level is high.
affected S/G
- c. FRP-H.4, Response To Loss Of Normal Steam Release Capability, if the affected S/G SIG level is high.
- END -
- -
Rev. Rev. 77 FRP-H.5 FRP-H.5 RESPONSE TO RESPONSE TO STEAM STEAM GENERATO GENERATOR LOW LEVEL R LOW LEVEL Page 33 of Page of 55 Purpose and Purpose and Entry Entry Conditions Conditions (Page 11 of (Page of 1) 1) 1.
- 1. PURPOSE PURPOSE This procedure This procedure provides provides actions actions toto respond respond to to aa steam steam generator generator low level low level condition.
condition. 2.
- 2. ENTRY CONDITION ENTRY CONDITIONS S
CSF-3. Heat Sink Critical Critical Safety Safety Function Function Status Status Tree Tree on on a YELLOW condition. condition.
- END -
-END-
CSF-3, HEAT SINK ENTER
~
NO NO FW FLOW* S/Os GREATER THAN 300 GPM OR 0.2 ES YES NO NO NO PRESS IN ALL S/Os LESS THAN 1085 PSIG LEVEL IN ALL S/Os GREATER 11-lAN 8% [18%] RED GOTO GO TO FRP-H.1 FRP-H.1 YELLOW YELLOW YELLOW YELLOW GO GO TO GO GO TO GOTO GO TO GO TO FRP-H.5 FRP-H.4 FRP-H.2 FRP-H.2 GREEN FRP-H.3 CSF-SAT J 1 CSFST Rev. Rev.44 Page5of9J Page 5 of 91
HLC-08 NRC Written Exam
- 27. Which ONE (1) of the following identifies the major concern or license limitation associated post-LOCA Containment Flooding?
with post-LOCA Flooding? A. ITS Bases for containment integrity are compromised in situations above maximum flood level. B. Dilution of sump water with CCW or Fire Water may potentially cause a return to criticality. C. Water introduced into the ECCS sump beyond capacity can potentially affect the operation of vital equipment. D. Loss of inventory from interfacing cooling systems can potentially result in a loss of ability to remove heat from the reactor core. 27
HLC-08 HLC-0 NRCWritte 8 NRC Writtenn Exam Exam AUDIT -2001IFRP-J. 2-003 I1I2/3.6I4.5/ROfLOW/N/AJ AUDIT
- 27. WEIS G2.2.38 OOllCTMT FLOODING/1I2/3.6/4.5IROILOWININRNP 2001/FRP-J.2-003
- 27. WE15 G2.2.38 001/CTMT FLOODING
-
WhichONE ONE(1) (1)ofofthe thefollowing followingidentifies identifiesthe majorconcer themajor n or license limitation associated concern or license limitation associated Which withpost-LOCA with post-LOCAContai nment Flooding? Containment Flooding? A. ITS ITSBases Basesfor forcontain containment integrityare ment integrity arecompr omised ininsituatio compromised situations maximumflood abovemaximum ns above flood A. level. level. B. Dilution Dilutionof ofsump sumpwater waterwith with COW CCW or Watermay FireWater or Fire maypotentially returnto cause aa return potentiallycause to criticality. criticality. B. C C~ Water Water introduced introduced into into the the ECCS ECCS sump beyond capaci sump beyond ty can capacity affectthe potentially affect can potentially the operation operation ofof vital vital equipm equipment. ent. D. Loss D. Loss of of inventory inventory from from interfacing cooling system interfacing cooling systems can potentially s can result inin aa loss potentially result of ability loss of ability to remove heat from to remove heat from the reactor the reactor core. core. The correct The correct answer answer is is C. C. A: Incorrect A: Incorrect - ITS-ITS Bases Bases addres addresses ses Contai Containment as part Integrity as nment Integrity of OPERABiLI part of OPERABILITY, but does TY, but does NOT address NOT address Contai Containment nment Flooding. Flooding. B: Incorrect B: Incorrect - Basis
-
Basis for for FRP-J FRP-J.2, CONTAINMENT
.2, CONTAINM FLOODING does ENT FLOODING does NOT NOT addres address reactivity as s reactivity as a concern.
a concer n. Both CCW and Firewater are isolated on Phase A and and Phase Phase B B isolation. isolation. C: C: Correct Correct - - The purpos The purpose e of the sump is to collect and divert water in areas that will NOT will NOT affect equipment. Flooding may jeopard affect vital plant equipment. jeopardizeize that function. D: D: Incorrect Incorrect - A - A loss loss of ability to remove procedures. The major remove heat is dealt with in other procedures. major concern concern in FRP-J.2 FRP-J.2 is containment contain ment flooding. Exam Exam Question Question Number: Number: 27 27
Reference:
Reference:
FRP-J.2FRP-J.2 BD, BD, Page Page 3. 3. KA KA Statement: Statement: Knowledge Knowledge of of conditions conditions and in the limitations in and limitations license. facility license. the facility History: History:
- Tuesday, Tuesday,June June17,17,2008 20081:21 1:21:07
- 07PMPM 3131
DISCUSSION DISCUSSIO (Fromthe N (From theWOGWOGFR-Z.2 FR-Z.2BasisBasisDocurnnfi Document) 1.1. INTRODUC INTRODUCTION TION that Guideline FR-Z.2, RESPONSE TO CONTAINMENTFLOODING FLOODING, , isisaaFunction RestorationGuideline FunctionRestoration Guideline(FRG) (FRG) that Guideline FR-Z.2, RESPONSE TO CONTAINMENT providesprocedural proceduralguidanceguidancewhen whenthe containmentlevel thecontainment greaterthan levelisisgreater thanfloodfloodlevel. level. provides Thereisisonly onlyone oneexplicit explicittransition transitiontotoguideline guidelineFR-Z.2. FR-Z.2. ItItisisfrom fromthe CriticalSafety theCritical FunctionStatus SafetyFunction StatusTree TreeF-O.5, F-O.5, There sump level is greater than flood level. CONTAINMENT, on an ORANGE priority priority when when containment containment sump level is greater than flood level. CONTAINMENT, on an ORANGE in After all the actions in guideline FR-Z.2 are completed,the operatorisisinstructed theoperator instructedtotoreturn returntotothe guidelineand theguideline andstep step in After all the actions in guideline FR-Z.2 are completed, effect. effect. 2.2. DESCRIPTI DESCRIPTION ON Guideline FR-Z.2, Guideline FR-Z.2, RESPONSE RESPONSE TO TO CONTAINM CONTAINMENT ENT FLOODING FLOODING, provides actions
, provides actionsto respond when to respond when the thecontainment containment level is greater level is greater than than design design flood flood level.
level. This This level level is is significant significant since since the the critical critical systems systems and and components, components, which are which are necessary to ensure an orderly safe plant plant shutdown shutdown and and provide provide feedback feedback to to the the operator operator regarding regarding plant plant conditions, conditions, necessary to ensure an orderly safe are normally are normally located located above above the the design design flood flood level. Therefore, the level. Therefore, guideline FR-Z.2 the guideline entered from FR-Z.2 isis entered from the the Containment Containment Status Tree on an ORANGE priority when when this this design design flood flood level level is is exceeded. exceeded. Status Tree on an ORANGE priority The primary The primary purpose purpose of of the the containment containment sump sump area area isis to collect the to collect the water injected into water injected into the containment or the containment spilled from or spilled from the reactor coolant system following an accident. accident. The The water water collected collected in in the the containment containment sump sump is is then then available available for for the reactor coolant system following an long term long term core core and/or and/or containment containment cooling cooling via via the emergency core the emergency COOling or core cooling containment spray or containment spray recirculation recirculation systems. In systems. In addition, addition, the the containment containment sump sump collectscollects the the injected or spilled water into areas such injected or spilled water into areas such that that vital systems or vital systems or components will not be flooded components will not be flooded and thus rendered and thus rendered inoperable. inoperable. The maximum The maximum level level ofof water water in in the containment following the containment following aa major generally is accident generally major accident based upon is based upon the entire water the entire water contents of the reactor coolant system, refueling water water storage storage tank, tank, condensate condensate storage storage tank, tank, and and SI SI accumulators accumulators. . contents of the reactor coolant system, refueling plus This water volume approximates the maximum maximum water volume introduced introduced into into the the containment following following aa LOCA LOCA plus This water volume approximates aa steamline steamline or or feedline feedline break break inside containment. An indicated An indicated water level in the containment greater than the maximum expected volume (design basis water level flood level) basis flood level) is is an indication that water volumes volumes other than those represented by the above noted volumes have have been been introduced introduced into into an indication that water the the high water level provides an indication that potential flooding of critical systems systems and and the containment. containment. Also, Also, the components components needed for needed for plant recovery may occur. The this guideline attempt to identify any unexpected source of water and isolate itit ifif possible. possible. Beyond Beyond that that The actions actions in in this the plant engineering the plant engineering staff is consulted to determine if transfer of containment sump water to other tanks tanks is is appropriate. appropriate. 3.
- 3. RECOVERY/RESTORATION RECOVERY/RESTORATION TECHNIQUE TECHNIQUE The incorporated into into guideline guideline FR-Z.2 FR-Z.2 is is to to provide actions to provide actions respond to respond The objective objective of of the the recovery/restoration recovery/restoration technique technique incorporated to containment to containment flooding. flooding.
The the major major action categories of action categories of operator actions and operator actions and the the key utility key utility The following following subsections subsections provide provide aa summary summary of of the decision points for guideline decision points for guideline FRZ.2, RESPONSE FR-Z.2, RESPONSE TO TO CONTAINM CONTAINMENT ENT FLOODING FLOODING. . 3.1 3.1 HighHigh Level Level Action Action Summary Summary AA highhigh level level summary summaryof of the the actions performed inin FR-Z.2 actions performed FR-Z.2 isis givengiven below below inin the form of the form major action of major categories. These action categories. These are are discussed discussed below below inin moremore detail. detail. MAJOR MAJOR ACTION CATEGORIES IN ACTION CATEGORIES FR-Z.2 IN FR-Z.2 oo Try Tryto to Identify IdentifyUnexpected Unexpected Source Source of SumpWater of Sump Water and Possible Isolate ItItifif Possible and Isolate oo Notify NotifyPlantPlantEngineering Engineering Staff Staffof ofSump Sump LevelLevel and and Activity ActivityLevel Level oo Try Trytoto Identify IdentifyUnexpected UnexpectedSource Sourceof ofSump SumpWater Waterand IsolateItItififPossible andIsolate Possible The trytotoidentify sourceofofwater thesource waterwhich whichisiscausing containmentflooding causingcontainment floodingand isolate andisolate Thefirst firstaction actionininthis thisguideline guidelineisistototry identifythe it.it. The plant components needed for plant criticalplant components needed for plant recovery could be damaged and recovery could be damaged and Theconcern concernregarding regardingflooding floodingisisthat thatcritical rendered inoperable. rendered inoperable. oo Notify NotifyPlant PlantEngineering EngineeringStaff StaffofofSump SumpLevel Leveland andActivity ActivityLevel Level By engineeringstaff plantengineering staffcan determineififthe candetermine excesswater theexcess watercan canbe be Byknowing knowingthe thesump sumplevel leveland andactivity activitylevel, level,the theplant transferred to storage transferred to storage tanks tanks located located outside outside containment. containment. IFRP-J.2-BD FRP-J.2-BD I Rev Rev33 I Page33ofof6/ Page 6 I
2/ /fd
/1i4 TIONS REPO QUESTIONS QUES REPORT RT forAUDIT for AUDIT 1.1.E15 E15EK1.2 001ll11111!
EK1.20011/1111/I Giventhe Given thefollow following conditions: ing condit ions:
** AALOCA LOCAhas hasoccurr occu rred.
ed. ioned toto
** Due to an abnormal Due to an abnormal rise riseinincontain ment sump containment level,the sumplevel, crewhas thecrew hastransit transitioned FRP-J.2, FRP-J .2, RespoResponse nse totoContai nment Floodi Containment ng.
Flooding. Which ONE Which ONE (1) (1) ofofthe thefollow following ies the identifies ing identif majorconcer the major concernn associa ted with associated the actions with the actions inin this this proced procedure? ure? A. Dilution Dilution of of sump sump water water maymay potent potentially cause aa post-L ially cause OCA reactiv post-LOCA ity transie reactivity nt transient A. resulting resulti ng inin loss loss ofof subcrit subcriticaJity. icality. B. Contam Contaminants in water water from from other other system systems can potent s can ially block potentially flow channe block flow channels ls B. inants in during the during the long long term term coolin cooling phase of g phase the recove of the recovery.ry. C~ Water Water introdu introduced into the ced into the sump beyond the sump beyond the capaci capacity ty to to contain in approp contain itit in riate appropriate C areas can areas can potentpotentially affect the operati ially affect operation on of vital equipm of vital ent. equipment. D. Loss D. Loss of of invent inventory interfacing ory from interfa cooling cing coolin g system systems s can potent ially result in potentially loss of in aa loss of ability to remove ability to remove heat from the reactor core. Core. A. A. Incorrect. Incorrect. ProcedureProcedure does not consider consider reactivity abnormally. reactivity abnormally. B. B. Incorrect. Incorrect. Other systems systems may contain contaiminants post-LOCA not a major contaiminants but post-LOCA major threat threat to to cooling. cooling. C. C. Correct. Correct. The purpose purpose of the sump is to collect and divert water in areas that will will not not affect affect vital plant plant equipment. Flooding may jeopardize equipment. Flooding function. jeopardize that function. D. D. Incorrect. Incorrect. The The major major concern concern is flooding for is flooding procedure. Loss this procedure. for this Loss of of ability to ability to remove remove heat heat is is dealt dealt with with inin other proced other procedures. ures. Common Question Common Question 064 064 Tier Tier 11 Group Group 22 KIA K/A Importance Rating Importance Rating - RO- RO 23.7/ 23.7 / SRO SRO 2.7 2.7 Knowledge Knowledge of of thethe operational operational implications implications of the following of the concepts as following concepts apply to they apply as they to the the (Containment (Containment Flooding) Flooding) Normal, abnormal and Normal, abnormal emerge and emergency ncy operatingng proced operati procedures ures associated with associated with (Containment(Containment Flooding). Floodi ng). 10 10 CFR CFR Part Part55 55 Content Content- 55.41- 55.41 Comments Comments - - Category Category1:1: Category2:2: Category Category Category3:3: Category4:4: Category Category Category5:5: Category6:6: Category Category Category7:7: Category8:8: Category
- Thursday, Thursday,JuneJune05, 05,2008 20081:44:01 1:44:01PM PM 1
HLC-08 NRC HLC-08 NRC Written Exam Exam
- 28. During
- 28. During containment containment isolation isolation valve testing, testing, CCW-716A, CCW-716A, CCW CCW to RCP RCP ISOLATION ISOLATION VALVE, VALVE, was inadvertently CLOSED inadvertently CLOSED with with RCP RCP "B" B running.
running. ONE (1) Which ONE (1) of of the following following RCP RCP components components suffered suffered aa loss loss of of cooling cooling water flow? A. Motor Bearing Oil Coolers ONLY. B. Thermal Barrier Heat Exchangers ONLY. C. Thermal Barrier Heat Exchangers and Motor Bearing Oil Coolers. D. Motor Air Coolers, Thermal Barrier Heat Exchangers, and Motor Bearing Oil Coolers. 28 28
HLC-08 NRC Written Exam
- 28. 003 K6.04 OOllREAC PUMP/2/112.813. 1/ROILOWIN/A/NEW - 200S/CCW-009 001/REAC COOL PUMP/2/1/2.S/3.1IROILOW/N/A/NEW - 2008/CCW-009 During containment isolation valve testing, CCW-716A, CCW to RCP ISOLATION VALVE, was inadvertently CLOSED with RCP "B" B running.
Which ONE (1) of the following RCP components suffered a loss of cooling water flow? A. Motor Bearing Oil Coolers ONLY. B. Thermal Barrier Heat Exchangers ONLY. Ct C Thermal Barrier Heat Exchangers and Motor Bearing Oil Coolers. D. Motor Air Coolers, Thermal Barrier Heat Exchangers, and Motor Bearing Oil Coolers. The correct answer is C. A: Incorrect - Motor Oil Cooler is correct, but NOT a complete answer as Thermal Barrier HX
-
is also cooled by CCW. B: Incorrect - Thermal Barrier HX is correct, but NOT a complete answer as the Motor Oil
-
Cooler is also cooled by CCW. C: Correct - - CCW -716A is the CCW supply to all RCP cooling. Discharge lines have seperate isolation valves. D: Incorrect - Motor Air Coolers are CV HVH units which are cooled with Service Water. 0: - Exam Question Number: 28
Reference:
SD-013, CCW, Pages 20-21, Figure 3. KA Statement: Knowledge of the effect of a loss or malfunction on the following will have on the RCPS: Containment isolation valves affecting RCP operation. History: New - Written for HLC-08 NRC exam.
-
17, 2008 11:21:07 Tuesday, June 17,2008 :21 :07 PM 32
SD-013 COMPONENT COOLING WATER SYSTEM LCV-1030A supplies auto makeup from the CCW system to WGC "A". LCV-I030A A. Level is automatically controlled by makeup and drain valves in conjunction with a level controller on each separator. Local push buttons (seal water bypass switch [es]) [es)) allow for manual filling prior to WGC start (Push buttons bypass running interlocks). A low level (7.5") (7.5) will open the separators makeup valve from CCW. separator's 5.4 LCV- 1 032A, Waste Gas Compressor "B" LCV-1032A, B Seal Water Level Control LCV-1032A supplies auto makeup from the CCW system to the WGC "B". B. Level is automatically controlled by makeup and drain valves in conjunction with a level controller on each separator. Local push buttons (seal water bypass switch(es>> switch(es)) allow for manual filling prior to WGC start (Pushbuttons bypass running interlocks). A low level (7.5")(7.5) will open the separators makeup valve from CCW. separator's 5.5 TCV-144, Non-Regenerative Heat Exchanger Temperature Control Valve (CWD-B-190628 Sh00471) The flow of CCW through the non-regenerative heat exchanger is controlled by TCV- TCV 144, which is controlled by the Temperature Controller TC-144 located on the RTGB. The temperature signal is provided by TE-144 located in the CVCS downstream of the TC- 144 is a 0-10 turn potentiometer. The controller non-regenerative heat exchanger. TC-144 has both Automatic and Manual control capability. The 0-10 turn potentiometer is used TCV--144 to adjust the control set point for TCV 144 when operated in Automatic. Pushbuttons located on the controller are used to transfer from Automatic control to Manual control and vice-versa. When in Manual control the operator opens or closes the valve by depressing OPEN or CLOSE push buttons located on the RTGB mounted controller. Valve TCV-144 is located on the 2nd level ofthe of the Non-Regenerative Heat Exchanger Room. , 5.6 ) CC-716A1B, CCW to RCP Isolation - Motor Operated Valve(MOV)
-
\..---"" (CWD-B-190628 Sh00231, Sh00232) Valves CC-716A and CC-716B are operated by two position (OPEN/CLOSE), spring return to center, switches located on the RTGB. The valves also automatically close on a P signal (CS) providing containment isolation of this potential leak path. The valves "P" are located outside containment downstream of CV Penetration P-18 P-i 8 in the Auxiliary Building pipe alley. The valves are powered from MCC-5 and 6 respectively. Valve position indication is provided on the RTGB at the control switch and as part of the ccw CCW of 38 Page 20 of38 Revision 9 INFORMA INFORMATION TION USE ONLY ONL Y
SD-013 SD-013 COMPONENT COOLING COMPONENT WATER SYSTEM COOLING WATER SYSTEM Containment Phase Containment isolation indications. B isolation Phase B indications. 5.7 Outlet Isolation - MOV CC-730, Bearing Outlet - (CWD-B-190628 5h00233) Sh00233) Valve CC-730 is operated by a two position (OPEN/CLOSE), spring return to center, switch located on the RTGB. The valve also automatically closes on a P switch UP" signal providing containment isolation of this potential leak path. The valve is located outside containment downstream of CV Penetration P-i ofCV 9 in the Auxiliary Building pipe alley. P-19 The valve is powered from MCC-6. Valve position indication is provided on the RTGB at the control switch and as part of the Containment Phase B B isolation indications. 5.8 Control- MOV FCV-626, Thermal Barrier Outlet Isolation Flow Control - B-190628 Sh00234) (CWD- B-i90628 Valve FCV-626 is operated by a two position (OPEN/CLOSE), spring return to center, switch located on the RTGB. The valve will automatically close on a high flow (100 gpm) as monitored by FIC-626. The valve also automatically closes on a P "P" signal providing containment isolation of this potential leak path. The valve is located outside containment downstream of CV Penetration P-20 in the Auxiliary Building pipe alley. The valve is powered from MCC-6. Valve position indication is provided on the RTGB at the control switch and as part of the Containment Phase B isolation indications. 5.9 CC-735, Thermal Barrier Outlet Isolation - MOV
-
(CWD-B-190628 Sh00230) Valve CC-735 is operated from the two position (OPEN/CLOSED), spring return to the center, switch located on the RTGB. The valve is located outside containment downstream of FCV-626 in the Auxiliary Building pipe alley. The motor operator for the valve is powered from MCC-5. Upon receipt ofa of a "P" P signal, the valve will close. 5.10 CC-739, Excess Letdown HX. Outlet Isolation Valve, Air Operated Valve (CWD-B- 190628 Sh00229) (CWD-B-190628 Valve CC-739 is operated from the RTGB using a two position (OPEN/CLOSED), spring return to center, switch. This valve is located in the Auxiliary Building pipe alley and provides CV isolation downstream of CV penetration P-22. CC-739 is an Air Operated Valve that receives operating air from the instrument air system through 125V l25V DC solenoid valves. The solenoid valves receive power from the 125V l25V DC Auxiliary Panel GC CKT#29. A safeguards actuation signal, "T" T signal, will de-energize the ccw CCW of 38 Page 21 of38 Revision 9 INFORMA TION USE ONLY INFORMATION ONL Y
COMPONENT COOLING WATER SYSTEM CCW-FIGURE-3 SPENT FUEL r----l PITHX CONTROL ROD DRIVE COOLERS WASTE EVAPORATOR "A" RHR PUMPS r EXCESS LETDOWN EXCHANGER .....a-f"'...,.,..--------I HEAT EXCHANGER REACTOR COO~NT~;n~__~~--- COOLANT PUMPS L- - - - - - - - - - - - - - - - INSIDE CONTAINMENTJ
-------
OUTSIDE CONTAINMENT
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 29. Given
- 29. Given the the following:
following: GP-002, COLD
- GP-002,
- COLD SHUTDOWN SHUTDOWN TO TO HOT HOT SUBCRITICAL SUBCRITICAL AT AT NO NO LOAD LOAD TTAVG, AVG ' is is in in progress.
progress. RHR has
- RHR
- has been been removed removed from from service.
service. RCS heatup
- RCS
- heatup isis inin progress.
progress. RCS isis at
- RCS
- at 370 370 OF
°F and and 800 PSIG.
800 PSIG. The RO
- The
- RO notes notes that that RCSRCS pressure pressure isis no no longer longer increasing.
increasing. VCT Makeup
- VCT
- Makeup isis in in progress.
progress. Which ONE (1) (1) of the following plant plant conditions has caused caused the RCS RCS pressure pressure response, response, and what is (are) the parameter(s) the crew can use to verify the cause? A. S/G tube leakage; monitor increasing level in the S/G with feed flow secured. B. RHR-706, RHR SYSTEM RELIEF VALVE lifting; monitor PRT level and pressure. C. CVC-209, LOW PRESSURE RELIEF VALVE lifting; monitor letdown line flow and temperature. D. HCV-121 has closed, isolating charging line; monitor FI-122A, CHARGING LINE FLOW INDICATOR. 29 29
NRC Written Exam HLC-08 NRC 29.004
- 29. 004 A1.05 001lCVCS/2/112.9/3.2IROIHIGHlNIAlNEW - 2008/CVCS-008 A1.0S OO1ICVCSI2I1I2.9/3.2IROIHIGHIN/AJNEW -
Given the following:
-
- GP-002, COLD SHUTDOWN TO HOT SUBCRITICAL AT NO LOAD TAVG, TAVG ' is in progress.
is in
-- RHR has been removed from service.
-- RCS heatup is in progress.
- RCS is at 370 °F
- SOO PSIG.
of and 800
- The RO notes that RCS pressure is no longer increasing.
-
- VCT Makeup is in progress.
-
Which ONE (1) of the following plant conditions has caused the RCS pressure response, and what is (are) the parameter(s) the crew can use to verify the cause? S/G tube leakage; monitor increasing level in the S/G with feed flow secured. A'I SIG A B. RHR-706, RHR SYSTEM RELIEF VALVE lifting; monitor PRT level and pressure. C. CVC-209, LOW PRESSURE RELIEF VALVE lifting; monitor letdown line flow and temperature. D. HCV-121 has closed, isolating charging line; monitor FI-122A, CHARGING LINE FLOW INDICATOR. The correct answer is A. A: Correct - - °F, S/G pressure is - 160 PSIG. Any S/G tube leakage will result in RCS At 370 of, to S/G leakage. B: Incorrect - RHR system has been isolated in the question stem.
-
C: Incorrect - CVC-2091ifts
- CVC-209 lifts to the VCT. Valve lifting will divert flow from the demineralizers but will NOT stop flow.
D: Incorrect - RCP Seal Injection flow would continue via seal injection lines. 0: - Exam Question Number: 29
Reference:
GP-002, Section S.4.7, 65, 66; SD-021 CVCS, Pages 37,38, 8.4.7, Page 65,66; 37, 38, Figure 1, SD-003 RHR, Figure 6. KA Statement: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including: S/G pressure and level. History: New - Written for HLC-OS
- HLC-08 NRC exam.
17, 2008 11:21 Tuesday, June 17, :21 :08 PM 33
S.4.7 8.4.7 (Continued) ]JJ.[ VERI CAUTION If the starting limitations stated in the Precautions and Limitations Section of OP-201 are exceeded, motor damage can occur due to motor overheating. NOTE: When an RHR pump is started and its train ventilation unit is inoperable, the opposite train ventilation can be started by placing the RUN/AUTO switch on the power supply breaker to RUN.
- 3. Alternately operate RHR Pump "A" A and "8" B to
-maintain temperatures, as read on TR-604 maintain the outlet temperatures, Pens 11 and 3, within 50°F until the temperatures are 125°F.
less than 125 ° F. (CR 95-00565)
-
TR-604 Pen 11 temperature less than 125°F of
-
TR-604 Pen 3 temperature less than 125°F of
- 4. Stop the RHR Pumps AND verify both RHR pump room ventilation units are STOPPED.
-
RHR Pump "A" A
-
- RHR Pump "8" B 4
-
- HVH-SA HVH-8A
-
- HVH-8B HVH-S8
() Perform the following:
- a. Close RHR-750, LOOP 2 HOT LEG TO RHR SYSTEM.
- b. Close RHR-751, LOOP 2 HOT LEG TO RHR SYSTEM.
- c. Open the breaker for RHR-750, LOOP 2 HOT LEG TO RHR SYSTEM, on MCC-5 in CMPT I
NO. 12C.
- d. Open the breaker for RHR-751, LOOP 2 HOT LEG TO RHR SYSTEM, on MCC-6 in CMPT 8M.
NO. SM. IGP-002 G P-002 Rev. 103 124 Page 65 of 1241
8.4.7 (Continued) 8.4.7 H\JIT VERI 6.
- 6. Adjust PC-i Adjust PC-145, increase Letdown 45, PRESSURE, to increase pressure to within 25 psig of current RCS Pressure.
- 7. PURIFICATION FLOW, to open Adjust HIC-142, PURIFICATION HCV-142, RHR TO LETDOWN LINE.
- 8. 45 to decrease letdown pressure to PC-145 Adjust PC-i 140 psig and less than 210 psig.
greater than 140
- 9. As Letdown increases, adjust PC-i 45 setting OR PC-145 isolate letdown orifices to maintain Letdown flow 120 gpm.
below 120 10.
- 10. Control Charging pump speed, letdown flow and excess letdown flow to maintain PZR level between 30% and 40%.
NOTE: Leaving HCV-142, RHR TO LETDOWN LINE, open until the RHR System SI-8628, RWST TO RHR valves, to open. SI-862A and Sl-862B, is less than 210 psig will allow Sl-862A
- 11. WHEN RHR System pressure is less than 210 psig as indicated on PI-602A Pl-602B, Pl-602A and PI-6028, THEN adjust HIC-142, PURIFICATION FLOW, to close HCV-142.
- 12. Close RHR-760, RHR SYSTEM TO LETDOWN LINE. (ACR 94-00533)
- 13. Adjust HIC-758, RHR HX DISCH FLOW to 0%
demand.
- 14. Open the RWST to RHR Pump Suction Valves AND record time.
-
- Sl-862A, RWST TO RHR SI-862A,
-
- SI-8628, Sl-862B, RWST TO RHR Time _ __
IGP-002 G P-002 Rev. 103 Rev. 103 I Page 66 of Page of 1241 124
SD-021 SD-021 CHEMICAL AND CHEMICAL VOLUME CONTROL SYSTEM AND VOLUME SYSTEM
/s~;~~w Pressure Letdown 5.1.4 Ow Pressure Letdown Valve (PCV-145) and Valve (PCV-145) and Low Relief Valve Letdown Relief Pressure Letdown Low Pressure L/<CVC-209)(CVC-209)
\
This valve is controlled from the RTGB in either automatic or manual to keep the water
~C This PCV -145 from flashing to steam. During in the piping downstream of the orifices to PCV-145 "V,\~' 300 psig plant operation this valve is adjusted to maintain approximately 300 normal plant upstream of the valve. For plant heatups and cooldowns the valve is adjusted to maintain the proper system pressure for evolutions in progress; i.e., running RCPs, etc.
PCV-145 is air operated and fails open. PT -145, located The pressure signal used to operate this valve in automatic comes from PT-145, PI-145 located on the RTGB. upstream of the valve. PT-145 drives pressure indicator P1-145 145, located on the RTGB, consists of a dial potentiometer for PCV-145, The controller for PCV-automatic setpoint control, pushbuttons for manual control and a controller output demand indication. Opening the valve results in a lower backpressure on PT-145PT -145 and APP-OOI-D6, LP closing the valve results in a higher backpressure. PT-145 alarms APP-001-D6, LTDN LN HI PRESS, at 400 psig. HI.PRESS, Low Pressure Letdown Relief Valve, CVC-209, is located just downstream of PCV PCV-145. CVC-209 has a setpoint of 200 psig and relieves to the VCT. (TCV- 143) 5.1.5 VCT/Demineralizer Diversion Valve (TCV-143) TCV-143 is a three way valve that allows the operator to bypass the demineralizers. It is controlled by a three position (VCT, AUTO, DEMIN) RTGB switch which is normally selected to AUTO. The demineralizers will be automatically bypassed if (135°F.). The demineralizers letdown temperature reaches a pre-determined setpoint (135°F). will be automatically un-bypassed when temperature falls to 130 degrees. The temperature used for this function is sensed by TE-143. TE-143 also provides the input for a temperature indicator on the RTGB. The valve fails to the VeT VCT position. 5.1.6 VCT/Deborating Demineralizer Diversion Valve (CVC-244) This solenoid-operated valve allows the operator to place the deborating demineralizer in service when needed. It is controlled by a two position (VCT/DEB DEMIN) RTGB switch. It is selected to VeT VCT except at end of cycle. CVC-244 fails to the VeT VCT position. More information on CVC-244 operation can be found in section 3.4.3 of this System Description. 5.1.7 VCT Vent Valves (CVC-258 and PCV-117) The VCT gas space can be vented to the Waste Disposal Gas System by operating the solenoid valve CVC-258. CVC-258 is controlled by a OPEN/CLOSE RTGB switch. PCV-1 17 senses VCT pressure and will shut if VCT pressure is reduced to 15 psig PCV-117 eves cvcs of 71 Page 37 of71 Revision 1100 INFORMATION USE ONLY
SO-021 SD-021 CHEMICAL AND VOLUME CONTROL SYSTEM seal operation. which is required for proper RCP seal operation. 5.1.8 Hydrogen and Nitrogen Pressure Regulating Valves (PCV-1 18 and PCV-1 (PCV-118 19) PCV-119) Hydrogen gas is supplied to the VCT during normal operations. The Hz H2 pressure is regulated to approximately 22-28 psig by PCV-1 PCV-118.18. During shutdown operations nitrogen gas is supplied to the VCT through PCV-1 PCV-11919 which regulates the N2 pressure to approximately 22-28 psig. 6 Charging Flow Charging Yalve (HCV-121) Flow Valve (HCY-121)
, This air operated valve is normally open and is controlled by a RTGB potentiometer. \\) Throttling with this valve will increase backpressure on the charging line and cause the $ -4 ~~
RCP seal flow to increase. V1failsopE HCV-12l fails open. ' ~ CAUTION HCV-12l is normally full open. Extra care should be taken when HCV-121 throttling due to the charging pumps being positive displacement pumps; rapid pressure increase will occur if a proper flow path is not maintained. 5.1.10 Seal Water Return Isolation Valve (CVC-381) A motor operated valve is provided. It is normally open and will shut on a Phase "B" B containment isolation signal. 55.1.11
.1.11 Charging Line Isolations Three return paths to the RCS are available on the charging line. Since no relief valve (CVC-3 12) is provided on this section of the charging line, a locked open manual valve (CVC-312) bypasses CVC-31OA.
CVC-310A. This valve should not be closed except by specific procedural control. (CVC-3 1OA) 5.1.11.1 Charging Line to Loop 11 Hot Leg (CVC-31OA) CVC-310A, is normally closed but may be open to provide an Air operated valve, CVC-31OA, alternate flow path to the RCS from the charging line. It is controlled from the RTGB CVC-310A fails open. by a two position (OPEN/CLOSE) switch. CVC-31OA (CVC-3 lOB) 5.1.11.2 Charging Line to Loop 2 Cold Leg (CVC-310B) CVC-3 lOB, is normally open to provide a flow path to the RCS. It Air operated valve, CVC-31OB, eves cvcs of 71 Page 38 of71 Revision 1100 INFORMATION USE ONLY
_____ _______ ___ ________ ________ ______ evesFLOW CVCS FLOWDIAGR DIAGRAM AM tel CVCS-FIGURE-l CVCS-FIGU RE-1 TOVcT TOTOPRT* PRT .. -r-....., I I 204A 204B Non-Regen. HX 203A 203B_____ 212 223223 PCV- 258 250 LCV. 200C J cvc- t(245 Mixed Mixed ECY-244 LOOPl LOOP 1 460A 460B HCV 142 11 A 255 249 BedBed COLDLEG~ COLD LEG TE Compressor s F Demins. Demins. Gas TOCVCS 312 PC!- 56 259C HUT Analyzer 226 227 199 T.. 2166 225225 117 FCV-114B LOOPl LOOP 1 280 112 115 115 Deborating Deborating HOTLEG..., HOT LEG ............... 260A ___ Demins. Demins. 216216 RREGEN EGEN \
- VCT _
l 1 E 228 AUXSPR AUX SPRAY4lA AY Il'. I HX HX ~'" Cation Cation LOOP 2 ~\~ Seal Water 237A Bed Bed LOOP2 COLD LEG 238A 237A Demin. Demin. COLD LEG EXCESS EXCESS lix 116 LTDNHX LTDN HX 389 389 LCV- FCV FromLoop From Loop2 2 I-f 115C FCV-113B 114A 247D I h_-1 ij ColdLeg Cold Leg 137 121 318 1 266 j:i,t
,.11 From Pnmary Water Pumps To RCDT i - rb, I F BLENDER FromRCP From Seals RCPSeals 320320 271 272 272 Chemical Charging Charging Mixing Suction Pulsationrumps Pulsation Pumps Dampener Stabilizer Dampener :7; 286 267 286 "
11 3A 8 269__ ToRCP To JI-<xl-"'---< Sealse.**.[ RepSeals From From RWST 352 353 352 cm BA FromBA TransferPumps ransfer Pumps 351 35 INFORMATION iNFOR MATION USE USE ONLY ONLY
RHR SYSTEM - NORMAL (AT POWER) LINEUP
-
RHR-FIGURE 6
~--~------------------------~I~~I--~
SI-887 TOSI PUMP 8&C * ~ .. SUCTIONS ISI*891 C
-++-
SI-8910 SI AND TO SIANO RHR-7548 CONTAINMENT RHR*764 SPRAY PUMP PUMP SUCTIONS SUCTIONS
~
'!"
~
....
o RHR PUMP 8
~FROMRWST FROM RWST
~
'!"
~
'1-+--f><1-l--I RHR*754A RHR*757A RHRPUMPA
~
- --'~ .
MINIFLOW RECIRC FROM CONTAINMENT SUMP RHR HEAT-UP LINE RHR-743 TO RC LOOP 1
!l!
- "
COLD LEG
~
TO RC LOOP 3 !l! COLD LEG :::"
....
U1 o TO RCLOOP2 COLD LEG FROM FROM RCRC LOOP RHR*7448 RHR-744B SI*8768 SI-876B SI*8758 51-8758 2 HOT LEG LEG INFORMATION USE ONLY
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 30. Given
- 30. Given the the following:
following:
-A
- A Small Small Break Break LOCA LOCA occurred occurred 33 hours hours ago.
ago. RCS pressure
- RCS
- pressure isis 210 210 PSIG.
PSIG. alignment of the ECCS
- The alignment
- ECCS for Cold Cold Leg Leg Recirculation Recirculation is is complete complete lAW lAW EPP-9, EPP-9, TRANSFER TO COLD LEG RECIRCULATION.
Which ONE (1) (1) of the following describes the current RHR/ECCS RHR/ECCS alignment? RHR Pump and ONE (1) SI Pump ONE (1) RHR Pump operating in series (Piggy-back mode), mode), with the ... the... A. RHR AND SI Pump suctions from the CV sump, discharging to RCS cold legs via RHR HX (RHR Pump), and the BIT. B. RHR Pump suction from the CV sump, discharging through RHR HX to SI Pump suction, SI Pump discharging to RCS cold legs via the BIT. C. RHR Pump suction from the CV sump, discharging through RHR HX to RCS cold legs AND to SI Pump suction, SI Pump discharging to RCS cold legs via the BIT. D. RHR Pump suction from the CV sump, discharging through RHR HX to SI Pump suction, SI Pump discharging to RCS hot legs. 30 30
HLC-08 NRC HLC-08 NRC Written Written ExamExam
- 30. 005 Kl.06 IHIGHJN/AJ 001/RHR/2/1/3.5/3.6/RO/HIGHJN/A/NEW
- 30. 005 K1.06 OO1IRHRJ2/1/3.5/3.6IRO NEW -- 2008IRHR-0 2008/RHR-008 08 Given the Given the following:
following:
-
- AA Small Small Break Break LOCA LOCA occurred hours ago.
occurred 33 hours ago.
-
- RCS RCS pressure pressure isis 210 210 PSIG.
PSIG.
-
- The The alignment alignment of of the the ECCS ECCS for Cold Leg for Cold Recirculation is Leg Recirculation complete lAW is complete lAW EPP-9, EPP-9, TRANSFER TO TRANSFER COLD LEG TO COLD LEG RECIRCULA RECIRCULATION. TION.
Which ONE Which ONE (1) (1) of of the the following describes the following describes RHR/ECCS alignment? current RHR/ECCS the current alignment? ONE (1) ONE (1) RHR RHR Pump Pump andand ONE ONE (1) (1) SI operating in Pump operating SI Pump in series (Piggy-back mode), series (Piggy-back with the... mode), with the ... A. RHR A. RHR AND SI SI Pump Pump suctions suctions from the CV from the discharging to sump, discharging CV sump, to RCS cold legs RHR HX legs via RHR HX Pump), and the BIT. (RHR Pump), BIT. B:I RHR BY Pump suction from the CV sump, discharging RHR Pump discharging through RHR HX HX to SI Pump suction, discharging to RCS cold legs via the BIT. SI Pump discharging C. RHR Pump suction from the CV sump,dischar C. sump,4discharging ging through RHR HX HX to RCS cold legs AND to SI Pump suction, SI Pump discharging to RCS cold legs via the BIT. D. RHR Pump suction from the CV sump, discharging through RHR HX to SI Pump suction, SI Pump discharging to RCS hot legs. The correct answer is B. A: Incorrect - No CV sump suction to the SI pumps.
-
B: Correct - - This is the proper alignment and injection path due to RCS pressure being greater than the RHR Pump shutoff head (110 PSIG). C: Incorrect - RCS pressure is above RHR shutoff head.
-
0: D: Incorrect - Correct alignment for Hot leg recirculation 11
-
11 hours after the accident. Exam Exam Question Question Number: Number: 30 30
Reference:
Reference:
SD-002, SD-002, SI, SI, Pages Pages 9, 9, 10, Figure 5. 11, Figure 10, 11, 5. KA KA Statement: Statement: Knowledge Knowledge of the physical of the connections and/or physical connections and/or cause-effect relationships cause-effect relationships between between the the RHRS RHRS and and the systems: ECCS. following systems: the following ECCS. History: History: NewNew - Written
- Written for for HLC-08 HLC-08 NRC exam.
NRC exam.
- Tuesday, Tuesday, June June 17,20081:21:08 17,2008 1:21 :08 PM PM 34 34
SD-002 SD-002 SAFETY INJECTION SYSTEM SAFETY SYSTEM steam pipe For any rupture of a steam and the associated pipe and uncontrolled heat associated uncontrolled removal from the heat removal the core, the SI system adds shutdown reactivity so that, with a stuck rod, no offsite power, consequential damage to the RCS and minimum engineered safety features, there is no consequential and the core remains in place and intact. components are incorporated in the instrumentation and components Redundancy and segregation of instrumentation design to assure that postulated malfunctions will not impair the ability of the system to meet the design objectives. The system is effective in the event of loss of nonnalnormal plant auxiliary power coincident with the loss of coolant, and can accommodate the credible failure of any single component or instrument channel to respond actively in the system, During the recirculation phase of a LOCA, the system can accommodate a loss system. of any part of the flow path, since backup alternate flow path capability is provided. Pipe whip protection for the ECCS components is provided as is protection against seismic events, protection against missiles, and loads that may result from the effects of a LOCA. aLOCA. The accumulators, which are passive components, discharge into the cold legs of the reactor coolant piping when RCS pressure decreases to 630-640 psig, thus assuring rapid core cooling for large pipe breaks. They are located inside the containment, but outside the crane wall. Therefore each accumulator is protected against possible missiles. 2.3 System Flow p~Paths.. 2.3.1 Injection Phase When in the Injection Phase, there are three modes of component operation. The modes are High Head/Low Flow Active Injection (SI Pumps), Passive Accumulator Injection and Low Head/High Flow Active Injection (RHR Pumps). NOTE: One, two or all three modes may be in operation at any given time. (SI-Figure-i) Upon the initiation of High Head/Low Flow Active Injection Mode, the (SI-Figure-1) SI Pumps take a suction on the RWST through SI-864A and SI-864B and inject into the cold legs via pump discharge cross-connect valve SI-878A and SI-878B, SI-867 SI-867A A and SI-867B, the Boron Injection Tank, SI-870A and SI-870B. During Passive Accumulator Injection the pressurized nitrogen blanket will automatically discharge water from the Accumulator into the cold legs. SI Page 9 of 43 Revision 14 14 INFORMATION USE ONLY
SD-002 SD-002 SAFETY INJECTION SYSTEM SAFETY SYSTEM During Low During Low Head/High Head/High Flow Active Injection, the Flow Active Pumps take the RHR Pumps suction from the take aa suction the RWST via SI-864A RWST via SI-864A and and SI-864B, SI-862A SI-862A and SI-862B, SI-862B, RHR-752A and and RHR-752B. RHR-752B. From the RHR pumps From borated water flows through the pumps the borated the RHR heat exchangers, RHR heat exchangers, RHR-744A and 744A and RHR-744B and into the RCS cold cold legs. This This path path can can be be traced on SI SI-Figure-2. 2.3.2 Recirculation Phase phase, if the RWST volume of During any mode of the injection phase, of borated water 27 % an operator will switch from the Injection Phase to the Recirculation decreases to 27% Phase. The source of borated water will be changed from the RWST to the CV Sump. The SI and CV spray pumps can not take a suction from the CV sump. In order to obtain CV spray or SI Pump operation when RWST inventory is depleted, the pumps must be aligned in what is commonly referred to as the Piggy "Piggy Back Back" Mode. In this mode of operation an RHR pump takes a suction on the containment floor and discharges to the suction of the SI and CV Spray Pumps. Flow> 2.3.2.1 RHR Flow > 1200 gpm (SI-Figure-2) RHR pumps take a suction from the CV sump via SI-860A and SI-861A for RHR Pump "A" A and SI-860B and SI-861B for RHR Pump "B". B. From the RHR R}IR pumps the borated water flows through the RHR heat exchangers, RHR-744A and RHR-744B and into the legs. (Reference EPP-9) RCS cold legs.(Reference RIIR Flow < 2.3.2.2 RHR <1200 1200 gpm (SI-Figure-3) RHR pumps take suction from the CV sump as described above. From the RHR pumps the CV sump water is supplied to the SI Pumps suction via SI-863A or SI-863B. The path down stream of the SI pumps is the same as for the Injection Phase. (Reference EPP-9) 2.3.3 Long Term Recirculation Phase with RCS pressure < <125 125 psig (SI-Figure-4) RHR pumps take suction from the CV sump. From the RHR R}IR pumps the CV sump water is supplied to the SI Pumps suction via SI-863A or SI-863B. The SI pumps will discharge to the RCS hot legs (loop 2 & & 3) via SI-869, and then then through SI-866A or SI- SI 866B. The RHR pump discharge will be throttled through RHR-759 A & & B to the RCS cold legs via RHR-744A and RHR-744B. (Reference EPP-lO) EPP-10) 2.3.4 ong ong Term Recirculation Phase with RCS pressure> with ReS pressure > 125125 psig psig (SI-Figure-5) (SI-Figure-5) SI SI 10 of Page 10 Page 43 of 43 Revision 14 Revision 14 INFORMATION USE ONLY
SD-002 SD-002 INJECTION SYSTEM SAFETY INJECTION SAFETY SYSTEM RHR pumps RHR pumps taketake suction suction from from the the CV sump. From CV sump. From the RHR pumps the RHR pumps the the CV CV sump sump water is supplied water is supplied to the SIto the SI Pumps Pumps suction suction via via SI-863A SI-863A or or SI-863B. SI-863B. The The path path for cold for cold leg injection leg injection down down stream stream of of the the SI pumps isis about SI pumps the same as for the Injection about the same as for the Injection Phase Phase into the cold legs. into the cold legs. When When in in hot hot leg leg recirculation recirculation the SI the pump discharge SI pump aligned to discharge isis aligned to supply water supply water to to the the RCS RCS hot loop 22 and legs loop hot legs ioop 3 via SI-869, and then and loop 3 via SI-869, and then through SI- through SI 866A or SI 866A or SI-866B.-866B. Hot Hot leg leg and and cold cold leg leg injection injection from the from the SI alternated every pumps isis alternated SI pumps every 16 hours. 16 hours. 2.4 2.4
\ System Description
System Description
The SI The SI System System is is comprised comprised of of three sources of three sources borated water of borated water (RWST, Accumulator,, (RWST, Accumulator and CV and CV Sump) Sump) and and the associated flow path the associated path necessary to to deliver borated water to deliver borated to the the Reactor Core. Some major components of Some major of the SI System SI System and their locations locations are:
*
- RWST - north of the Auxiliary Building
-
*
- SI Pumps- northwest Auxiliary Building, elevation 226 226'
*
- Accumulatorss - CV, one north, one north-northwest, and one south-southw Accumulator -
north-northw est, south-southwest est elevation 251.5 251.5' Under controlled plant conditions and if the Reactor Coolant volume is at an acceptable level, the SI System is in a stand-by or a shutdown condition. However, under a LOCA condition, the SI System will automatically align appropriate flow paths to insure flow from the borated water sources to the Reactor core. A signal which initiates operations for the Injection Phase is generated in one of six ways: (Refer to SD-006, Safeguard System Description). 1.
- 1. 2-out-of-3 Low Pressurizer Pressure (1715 psig)*
- 2. 2-out-of-3 2-out-of-3 High High Steam Steam Line Pressure (100 Differential Pressure Line Differential psid, PH (100 psid, PH - PL
- on 1/3 PL on 1/3 lines) **
3.
- 3. High High Steam Steam Flow Flow from 2-out-of-3 S/G's from 2-out-of-3 (37.25% to SIGs (37.25% 109%) coincident to 109%) coincident withwith Low Low Tavg in 2-out-of-3 loops (543 °F)
Tavg in 2-out-of-3 loops (543 OF) or or Low Low Steam Steam Pressure Pressure in in 2-out-of-3 2-out-of-3 S/Gs S/G's (614 (614 psig) psig) ** ** 4.
- 4. 2-out-of-3 2-out-of-3 High High Containment Containment PressurePressure (4 psig)
(4 psig) 5.5. 2-out-of-3 2-out-of-3 on on 2-out-of-2 2-out-of-2 Hi-Hi Containment Pressure Hi-Hi Containment Pressure (10 psig) (Initiates (10 psig) Spray (Initiates Spray and SI) ** and SI) ** 6.
- 6. Manual Manual actuation actuation
** Automatic Automatic initiation initiation maymay be blocked when manually blocked be manually when the plant isis below the plant 2000 psig below 2000 psig SI SI Page Page 11 of 43 11 of43 Revision 14 Revision 14 INFORMATION INFORMATION USE USE ONLY ONLY
LONG TERM LONG TERMRECIR CULATION, RCS RECIRCULATION, RCS PRESS PRESSURE> 125 PSIG URE >125 PSIG OR ONLY OR ONLY 11RHR RHRPUMP PUMP AVAIL ABLE AV AILABLE SI-FIGURE-SI-FIGURE-5S RWST 51-863MB opeN SI ACCUMULATORS RHR-759A RHR-744A&B RHR-751 OP 1,2,3 COLD lEGS ALTERNATE ALTERNATE BETWEEN HOT LEG AND COLD LEG RHR-750 INJECTION INJECTION EVERY EVERY 16 HOURS 16 HOURS LOOP 2 HOTLEG INFORMATION USE ONLY INFORMATION
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 31. The
- 31. The plant plant isis operating operating at at 100%
100% RTP RTP with with aa normal normal electrical electrical lineup. lineup. Breaker 52/10,
- Breaker
- 52/1 0, 4kV 4kV Bus Bus 1-2 1-2 Tie Tie Bkr, Bkr, trips trips OPEN.
OPEN. An inadvertent
- An
- inadvertent 8afetySafety Injection Injection signal signal occurs.
occurs. Which ONE Which ONE (1) of the (1) of the following following describes describes the the source source of of power power to to the the 81 SI Pumps? Pumps? A. SI Pumps A. 81 Pumps "A" and "e" A and C are powered from are powered from off-site off-site power. power. B. SI Pump B. 81 Pump "A" A is powered from EDG "A", SI Pump "e" A, 81 C is powered from off-site power. SI Pump C. 81 Pump "A" A is is powered powered from off-site power, power, 81 Pump "e" SI Pump C is powered from EDG is powered EDO "B". B. SI Pumps "A" D. 81 A and "e" C are powered from EDG "A" A and "B", B, respectively. 31 31
HLC-08 NRC Written Exam
- 31. 006 K2.0l OO1IEMERG CORE COOLING/2/113.6/3.9IROIHIGB/N/NNEW K2.01 OOllEMERG - 20081S1-006 COOLINGI2/113.613.9IROIHIGHINIAJNEW - 2008/S1-006 The plant is operating at 100% RTP with a normal electrical lineup.
- Breaker 52110,
- 52/1 0, 4kV Bus 1-2 Tie Bkr, trips OPEN.
- An inadvertent Safety Injection signal occurs.
-
Which ONE (1) of the following describes the source of power to the SI Pumps? A. 81 SI Pumps "A" A and "c" C are powered from off-site power. B~ B 81 SI Pump "A" A is powered from EDG "A", A, SI Pump "c"C is powered from off-site power. SI Pump "A" C. 81 A is powered from off-site power, 81 SI Pump "c"C is powered from EDG "B". B. D. 81 SI Pumps "A" A and "c" C are powered from EDG "A" B, respectively. A and "B", The correct answer is B. A: Incorrect - When breaker 52/10 trips, 4kV Bus 2 de-energizes, this de-energizes 480V Bus
-
1 and E-1. EDG "A" 1 A starts and energizes 480V Bus E-1. ONLY E-1 is energized from the EDG B: Correct - - When breaker 52/10 trips, 4kV Bus 2 de-energizes, this de-energizes 480V Bus 1 and E-1. EDG "A" 1 A starts and energizes 480V Bus E-1. Bus E-2 remains energized from off-site power. C: Incorrect - EDG "B"
- B starts on SI signal but does NOT energize 480V Bus E-2.
D: Incorrect - EDG "B"
- B starts on SI signal but does NOT energize 480V Bus E-2.
Exam Question Number: 31
Reference:
OP-603, Page 15; GP-005, Page 54, 8ection Section 8.4.42; SD-039 KVAC, Pages 12-14, Figure 2. KA Statement: Knowledge of bus power supplies to the following: ECCS pumps. History: New - Written for HLC-08 NRC exam.
-
Tuesday, June 17, 2008 1 :21 :08 PM 1:21:08 V 35
REFERENCE REFERENC E USEUSE Section 8.1.2 Section 8.1.2 Page lof2 Page 1 of 2 8.1.2 8.1.2 Transfer of Transfer of Bulk BulkAuxiliary Electrical Load Auxiliary Electrical from Startup Load from Transformer to Startup Transformer to Unit Unit Auxiliary Trans.fQr.m~J{ TC Auxiliary Transformer{ TC Transfer "Transfer of of Bulk Auxiliary Electr'ical Load Bulk Auxiliary Electrical Load from Startup from Startup Transformer Transformer to to Unit Unit Auxiliary Transformer" \f Auxiliary Transformer \1 3
\f CC \1 "3" }}
8.1.2.1. Initial 8.1.2.1. Initial Conditions Conditions NOTE: NOTE: This section This section of of OP-603 OP-603 has screened lAW been screened has been lAW PLP-037 criteria and PLP-037 criteria and determined to determined to be a be a Case Case Three Three activity. activity. No No additional additional management management involvement is involvement is required required beyond that routinely beyond that provided by routinely provided by first line supervision. first line CAUTION All clearances associated with this operation shall be canceled and tags removed before placing the system into operation.
- 1. Unit 2 is synchronized with the system AND is between 90 and 110 MWe lAW GP-005.
- 2. The Unit Auxiliary AND Main Bank Transformers cooling fans AND oil pumps are running AND have been checked.
- 3. The Bus Duct Cooling Fans are running AND have been checked.
8.1.2.2. Instructions CAUTION Extreme Extreme caution caution shall shall be be taken taken toto ensure ensure all breaker interlocks all breaker function as interlocks function designed. as designed. 1.
- 1. INSERT key INSERT into UNIT key into AUX TRANSF UNIT AUX synchroscope switch TRANSF synchroscope AND switch AND TURN switch TURN switch to to UNIT AUX BUS UNIT AUX BUS 11 pOSition.
position.
)
IOP-603 OP-603 IJ. Rev. 78 Rev. 78 Page 15 Page 15 of 165 of 165/
(NIT NOTE: Power Ramp Rate Limits are restricted after core fuel movement to 3.5%/hr from 50% to 100% power. During subsequent power increases, this ramp limit may apply depending on the maximum power level achieved and length of operation at that power level. (ESR 98-00395) (SOER 90-2, Rec. 2C) CAUTION If Power Ramp Rate Restrictions are in effect, then Power shall be increased based on the highest indication of Reactor Power. 8.4.40 IF all indications of Reactor Power agree within 5% of each other AND Turbine Control is in OPER AUTO, OR management approval has been obtained, THEN CONTINUE the load increase as follows:
- 1. IF the power ramp rate restrictions are in effect, THEN RECORD the rate limitations AND power limits:
___ %/hr from _ _% to _ _ % rated power
- 2. ADJUST the SETTER indication using the REF v and/or REF A pushbuttons to indicate NO greater than 30.0 load.
- 3. DEPRESS the GO and/or HOLD pushbuttons AND the REF V and/or REF A. A as necessary to continue the load increase to 30% Reactor Power, OR as directed by the Reactor Engineer.
8.4.41 IF all indications of Reactor Power agree within 5% of each other AND Turbine Control is in TURB MANUAL, THEN INCREASE load using the GV A. A to 30% Reactor Power, OR as directed by the Reactor Engineer.
~~'~~~~HEN 8.4.42 IHEN the Generator is carrying between 90 MWe and 110 MWe, ~
AHEN . '_~HEN TRANSFER the Bulk Auxiliary Electrical Load from StartlJQ,. Startu
--- Transformer to Unit Auxiliary Transformer lAW OP-603 while continuing withthis with this procedure.
IGP-005 GP-005 I Rev. 85 Page 54 of 70 I
SD-039 SD-039 23 0/4 KVAC 230/4 ELECTRICAL SYSTEM KV AC ELECTRICAL SYSTEM The primary The primary windings of of the the UAT are delta UAT are while the connected while delta connected secondary is the secondary two half-is two half-capacity wye connected capacity wye connected windings. Each Each secondary secondary winding winding is is grounded grounded through an an inductor. inductor. 3.6 3.6 SUT SUT MFG MFG Westinghouse TYPE TYPE FOA FOA RATING Windings: Primary Windings: 3PHASE , 60HZ, FOA, 55°C H=44MVA, 3PHASE, 55"C Rise, 49.2MVA FOA, FOA, 65°C 65"C Rise 120.75/117.875/115.00/112.125/109.250 120.75/117.875/115.00/112.125/109.250 KV SET ON 115.000KV Secondary Windings: X,Y= 22MVA FOA 55°C Rise, 65"C Rise, 4.368KV
- 24. 640MVA 65°C 24.64OMVA Voltage Ratio & Connections KY 115 KV Wye - 2 half capacity 4.368 KV
-
Wye The SUT is a three phase step-down transformer. The primary side of this transformer 115KV Span Bus. The secondary voltage is reduced to 4368 is connected to the Unit 11115KV volts (name plate rating). This transformer is used at all times and normally carries all plant loads when the unit is off-line. The windings are wye-wye connected. This transformer is also filled with oil. There are four circulating pumps and cooling coils associated with this transformer. There is one fan for each cooling coil. Oil filled bushings are also used to insulate the electrical cables from the casing. There is a set of motor operated disconnects on the supply side of this transformer to isolate it from the 115KV Span Bus. The disconnects are to only be opened when there is no load on the transformer. The motor is a DC motor powered from "A" A Station Battery and is operated from the RTGB. A means of disconnecting the motor and manual operation is also provided. When the generator is not on-line, all five 4160V buses are powered from this transformer, unless we are using back feed through the U UAT AT during maintenance on the SUT. With the generator on-line and the UAT in-service, only 4160V Bus 3 will ?~normallY normally be supplied from this transformer. ('. . . . ! (' 3.7 .)4160V 4160V Buses (see Figures 5 &6) There There are are five five (5) (5) medium medium voltage voltage (4KV) buses that supply power to the major major plant components, 4KV motors seven (7) SSTs motors and seven plants low voltage SSTs that provide the plant's
, service.
service. These buses buses contain current transformers (CTs), PTs and other components that provide signals signals for for local local metering, RTGB metering, protection devices that detect detect KVAC KVAC Page 12 of 39 Page 120f39 Revision 14 Revision 14 INFORMATION USE ONLY
SD-039 SD-039 23 230/4 KV AC ELECTRICA 0/4 KVAC ELECTRICAL L SYSTEM SYSTEM over current, over current, over over voltage voltage forfor grounds, under voltage grounds, under (UV) and voltage (UV) frequency (UF). under frequency and under (UF). Annunciation in the Control Room is Annunciation in the Control Room is provided provided for for 4KV 4KV motor motor over over current current conditions, conditions, 4KV UV 4KV UV conditions, conditions, 4KV4KV UF conditions, and UF conditions, 4KV cooling and 4KV cooling fan 4KV pump failure. 4KV fan failure. pump motor, SST and incoming motor, SST and incoming supply supply breakers breakers have have current current indication indication on on their their respective respective cubicles that cubicles receive inputs that receive inputs from CTs on from CTs supply cables. the supply on the The PT cables. The PT and Fan cubicles and Fan cubicles provide voltage provide voltage indication. indication. The loads The loads supplied supplied byby each bus can each bus be found in can be in Electrical Electrical Distribution Procedure EDP Distribution Procedure EDP-001. 001. (See Figure (See Figure 2) 2) UAT and/or via the UAT supplied via The 4160V system is supplied andlor the SUT, each of which each of which have two windings. 4KV Buses 11 and 4 can secondary windings. can be supplied from the UAT via be supplied via 4KV breakers 52/7 respectively. 4KV Bus 52120 respectively. 5217 and 52/20 Bus 55 is supplied from 4KV4KV BusBus 44 through through 52124. 4KV Buses 2 and 33 can be supplied 4KV breaker 52/24. supplied from the SUT via 4KV 52112 and 52/17 respectively. 4KV Buses 11 & 2 are normally tied together breakers 52/12 via tiebreaker 52/10. 4KV Buses 33 & 4 can be connected via tiebreaker 52/19. 52119. During normal power operation 4KV Buses 1, 2, 4 and 5 are supplied via the th~ :UAT, UAT and 4KV Bus 33 is supplied via the SUT. nie The 480V system is supplied from the 4160V 4160-480Y/277V SSTs. system via 3-phase, 4160-480Y/277V 4160V Bus No.1 supplies 2B SST, via feeder breaker 52/4. 4160V Bus No.2 supplies 2A && 2F SSTs, via feeder breaker 52113, 52/13, fused primary switch 2A, and nonfused primary switch 2F. 4160V Bus No.3 supplies 2C & & 2G SSTs, via feeder breaker 52/15, fused primary switch 2C, and nonfused primary switch 2G. 4160V Bus No.4 supplies 2D SST, via feeder breaker 52128. 52/28. 4160V Bus No.5 supplies 2E SST, via feeder breaker 52/32. 3.7.1 4KV Bus 1, 2, 3 and 4 Breakers: Westinghouse, Westinghouse, Air Circuit Breakers Type 50 DH-350E (horizontal drawout) Three-pole, electrically electrically operated Interrupting Rating 350 MVA 350MVA Continuous Continuous current current @ @ 60cycles 60cycles 1200 ampere with 1200 ampere with Solenoid Solenoid Operating Operating Mechanism, Mechanism,
&& 3000 ampere with 3000 ampere with Motor Motor Operated Operated Stored Stored (Spring) Closing Energy tSpring)
Energy Closing Mechanism Mechanism Rated Rated voltage voltage 4.16KV
- 4. 16KV Max Max design design voltage voltage 4.76KV 4.76KV Interrupting Interrupting current current @
@ rated rated volt.
volt. 48,000 Amperes 48,000 Amperes Maximum Maximum interrupting current interrupting current 50,000 Amperes 50,000 Amperes KVAC KVAC Page 13 Page of 39 13 of39 14 Revision 14 Revision INFORMATION USE INFORMATION USE ONLY ONLY
SD-002 SAFETY INJECTION SYSTEM A SI area cooling fan (HVH-6A or 6B, See SD-036 HVAC HV AC Systems) will start if a SI Pump or Containment Spray (CS) Pump starts. When one of the room HVH units is out of service the respective SI and CS pumps are considered inoperable. However it is not necessary to rack out the affected pump breakers as only one HVH room cooler is required to support both SI pump motors and both CS pump motors.(ESR 95-00928) Electrical Power Supplies are:
._iATr
---"A" SI Pump - 480V Bus El
-.
B SI Pump - 480V Bus El or E2 (Depending on which pump it is replacing)
"B" -
C SI Pump - 480V Bus E2
,--"C" -
NOTE: The following starting duty limitations apply to the SI Pump.
- 1) IF the pump has not been run in the last hour, THEN 3 consecutive starts are allowed.
- 2) IF the pump has been started 3 times in the last hour AND neither of the last 2 starts was a run of at least 15 minutes, THEN no further starts are allowed for one hour.
- a. Any run in the previous hour is considered one of the 33 allowed starts.
- 3) IF the pump was run at least 15 minutes and stopped, THEN 2 consecutive starts are allowed with no waiting period.
The function of the SI pumps is to complete the refill of the reactor vessel and ultimately return the core to a subcooled state. The flow from one SI pump and one RHR pump is sufficient to complete this refill function. Moreover, there is sufficient excess water delivered by the accumulators to tolerate a delay in starting the pumps. The starting sequence of the pumps and related emergency power equipment is designed so that delivery of the full rated flow is reached within 26 seconds after the process parameters reach the setpoints for the injection signal. This includes the time needed for the pump to run up to full rated delivery. 3.3 Boron Injection Tank (BIT) (No Longer Used as a Boron Injection Tank) Number/Type 1/Vertical lIVertical Volume, tank 900 gallons Design pressure 1750 psig Design temperature 300°F Fluid Borated Water Material Austenitic stainless steel SI Page 14 of 43 Revision 14 INFORMATION USE ONLY
ELECTRICALDISTRIBUTION ELECTRICAL DISTRIBUTION KVAC-FIGURE-2 KVAC-FIGURE-2 TO 220KV TO 115 TO 115ICVSPAN KVSPANBUS BUS SWITCHYARO 1 MAIN I) 12 BUS 2 ~\IBUS 1 j t:Y"'i--......... L~J BUS" I
,)20 BUS 5 l!~J..-.-..I--
AI"t)~:i: ~:~ 2Ci"~, -)=1 6:.: . B.fI'- _ 20~8 ~ R ~ 2E n 130B /37B 1)2B )8B )9B ) ) ) 2F US 1 BUS2AI ~B ~5B ~US" BUS51 2F rd i i i ) ~L{'~ 2G I) i) IfI 1 r.h ~
;" [iJ 1.!~1111F'1 '" If-l 2 3 20 ~ ))) fll.1c1 15 17
) ~ ~ I~H 1~~cll~;cll~!CII~igl
~
pp-22 I"\-jMcCI 19 r-~----------------------------I"\~ 1 ) I
)
I~~cl E-1 E-2 ?32A OS BUS 28B 1"\:4 i) i) i 18~7B
)
~7B
?22B ?29B )
~
18 KIRK-KEY i?T~S'ER BREAKERS
) MCC-5
) )
rllrtJ Iifc, "5) i1D 6 7 8 9 KVACFO2 KVACF02
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 32. Given
- 32. Given the the following:
following: The plant
- The
- plant isis inin MODE MODE 33 following following aa load load rejection rejection and and Reactor Reactor Trip Trip from from 100%
100% RTP. RTP. During the
- During
- the load load rejection/trip rejection/trip event, event, aa Pressurizer Pressurizer PORV PORV opened opened for for several several seconds seconds and and reseated.
reseated. Pressurizer Relief
- Pressurizer
- Relief Tank Tank Pressure, Pressure, Temperature Temperature and and Level Level have have increased:
increased: Pressure == 4.8
- Pressure
- 4.8 PSIG.
PSIG. Temperature =
- Temperature
- 153 OF
= 153 °F (APP-003-B3, (APP-003-B3, PRT PRT HIHI TEMP TEMP isis illuminated.)
illuminated.) Level == 80%
- Level
- 80%
The CRSS
- The
- CRSS directs directs implementation implementation of of OP-103, OP-103, PRESSURIZER PRESSURIZER RELIEF RELIEF TANK TANK CONTROL CONTROL SYSTEM SYSTEM to reduce PRT reduce PRT temperature.
Which ONE (1) of the following methods Which methods will be used used to reduce PRT PRT temperature? A. Continuously fill the PRT with Primary Water and drain the PRT to the RCDT as necessary to maintain level between 70%-80%. B. Drain the PRT to the RCDT to 70%, then alternately refill with Primary Water and drain to RCDT. C. Fill the PRT with Primary Water to 90%, then alternately drain the PRT to the RCDT and refill with Primary Water. D. Monitor Automatic Primary Water spray, drain PRT to RCDT as necessary to maintain level between 70%-80%. 32 32
HLC-08NRC HLC-08 NRCWritten WrittenExam Exam
- 32. 007
- 32. 007K4.01 K4.01OOllPRT/QUENCH 001/PRT/QUENCHTANK/2/112.6/2.9/RO/HIGHlNIAlNEW TANK!2/112.612.9/ROIHIGHJNIAINEW- 20081PZR-008 - 2008/PZR-008 Giventhe Given thefollowing:
following:
- The
- Theplantplantisis inin MODEMODE33following following aaload load rejection rejectionand and Reactor ReactorTrip Tripfrom from 100%
100% RTP. RTP. During the
- During
- the load load rejection/trip rejection/trip event, event, aa Pressurizer PressurizerPORV PORVopened openedfor forseveral severalseconds seconds and and reseated.
reseated. Pressurizer Relief
- Pressurizer
- Relief TankTank Pressure, Pressure, Temperature Temperature and and Level Level havehave increased:
increased: Pressure == 4.8
- Pressure
- 4.8 PSIG.
PSIG. Temperature
- Temperature
-
== 153 153 of (APP-003-B3, PRT F (APP-003-B3, 0 PRT HI HI TEMP TEMP isis illuminated.)
illuminated.) Level == 80%
- Level
- 80%
The CRSS
- The
- CRSS directsdirects implementation implementation of of OP-103, OP-i 03, PRESSURIZER PRESSURIZER RELIEF RELIEF TANK TANK CONTROL CONTROL SYSTEM to SYSTEM to reduce reduce PRT PRT temperature.
temperature. Which ONE Which ONE (1) (1) ofof the the following following methods methods will will be be used used toto reduce reduce PRT PRT temperature? temperature? A. Continuously fill the PRT A. Continuously PRT with Primary Primary Water and and drain drain the the PRTPRT to to the the RCDT RCDT as as necessary necessary to maintain level to maintain level between between 70%-80%. 70%-80%. BY Drain 8:1 Drain the the PRT PRT to the RCDT to 70%, then alternately alternately refill with Primary Primary Water and and drain drain toto RCDT. RCDT. Fill the C. Fill the PRT PRT with with Primary Primary Water to 90%, then alternately alternately drain the PRT to the RCDT RCDT and and refill with refill with Primary Primary Water. D. Monitor D. Monitor Autom Automatic atic Primar Primary y Water spray, drain PRT to RCDT as necess necessary ary to mainta maintain level in level betwee n between 70%-80%. 70%-8 0%. The The correct correct answer answer is B. A: A: Incorre Incorrect ct - AA contin
-
continuous uous drain drain andand fill is incorre fill is incorrectct becaus because e the the tank tank will will fill fill faster faster than than the the drain drain capabi lity. NO capability. NO proced procedures ures suppor supportt this this action. action. B: B: Correc Correctt - - For For high high PRTPRT temper ature, OP-10 temperature, OP-103 3 directs directs drainin draining the PRT g the PRT to to 70%-7 70%-74%, then 4%, then to fill with PW to to fill with PW to cool cool the the PRT.PRT. C: Incorre C: Incorrect ct - For
-
For rapid rapid cooling cooling and and ifif level level allows allows,, the the PRT PRT isis filled filled first first then then allowe allowed to soak d to 'soak' for 10 minute s and then drained for 10 minutes and then drained. Precautions . Precau tions and and Limita Limitations state that tions state that the the tank tank should should NOT NOT be be filled filled above above 80% 80% level. level. D: D: Incorre Incorrect ct - RNP
-
RNP has has NONO automa automatic tic Primar Primary y Water Water Spray Spray availab available to the le to the PRT. PRT.
- Tuesday, Tuesday,June June17,2008 17,20081:21:081:21 :08PM PM 36 36
HLC-08 NRC HLC-08 NRC Written Written Exam Exam Exam Question Exam Question Number: Number: 32 32
Reference:
OP-103,
Reference:
OP-i 03, Pages Pages 6-10; 6-10; APP-003-83, APP-003-B3, SO-059 SD-059 PZRlPRT, PZRIPRT, Figure Figure 1.1. KA Statement: KA Statement: Knowledge Knowledge of of PRTS PRTS design designfeature(s) feature(s) and/or and/or interlock(s) interlock(s) which which provide providefor forthe the following: Quench following: Quench tank tank cooling. cooling. History: New History: New - Written
- Written for for HLC-08 HLC-08 NRCNRC exam.
exam.
- Tuesday, Tuesday,June June17,2008 1:21 :09 PM 17,20081:21:09 PM 37 37
REFERENCE USE REFERENCE USE Section Section 8.2.1 8.2.1 Page Page 1 of 1 of 33 8.0 8.0 INSTRUCTIONS INSTRUCTIONS 8.1 8.1 STARTUP STARTUP Refer to Refer to GP-001. GP-001. 8.2 8.2 NORMAL OPERATION NORMAL OPERATION 8.2.1 Draining the PRT Draining PRT When Pressurizer Pressurizer Temperature is is Greater Than Or Equal to Equal 200°F to 200°F
- 1. Verify the following initial
~::::=-____1:...:.._---..:V.:::.e:..:..ri!y initial .<?~~~iti~n~~!~_s_a~~~ied:
conditions are satisfied:
/ NOTE:
adding PRT temperatures of greater than 120°F should be reduced by alternately Primary Water to the PRT and draining the PRT. (SER 93-007) adding ( Maximum cooling effect can be achieved by leaving the added Primary Water in the PRT for at least 10 minutes prior to draining. (SER 93-007) ",
)"'"
'
- a. All the Prerequisites of Section 4.0 are complete.
- b. The Pressurizer temperature is greater than or equal to 200°F AND PRT level is above 70%.
~ c. Primary Water addition to the PRT is NOT in progress.
(SER 93-007) NOTE: The following step is a continuous action step and should be performed when conditions are met. 2.
- 2. IF the PRT temperature is greater than or equal to 160°F, 160°F, THEN Go To Go To StepStep 8.2.1.6.
8.2.1.6. OP-i 03 IOP-103 Rev. Rev. 16 16 Page Page 66 of of 23 23\
REFERENCEUSE REFERENCE USE Section Section8.2.1 8.2.1 Page Page22ofof33 NOTE: NOTE: PlacingRC-523, Placing RC-523, PRT PRTDRAIN, DRAIN,control controlswitch switchininOPEN OPENalso alsoopens opens LCV-1 003B, RCDT PUMP B SUCT ION, LCV-10038, RCDT PUMP "8" SUCTION, and starts REACTOR and starts REACTORCOOLANT COOLANTDRAIN DRAIN TANKPUMP TANK PUMP"8" Bififthe thecontrol controlswitches switchesare areininAUTO. AUTO. 3.3. IFIFthe the normal normal drain drain path path via viathe the RCDT available, AND RCDT isis available, AND aa Contai Containment nment Phase Phase AA Isolation Isolation signal NOT present, signal isis NOT present, THEN THEN perform the perform the following: following: a.a. Open RC-523, Open RC-523, PRT PRT DRAIN. DRAIN. b.
- b. WHEN PRT WHEN PRT level level returns returns toto between between 70% 70% and and 74%,
74%, THEN THEN close RC-523. close RC-523. NOTE: NOTE: Instrument Air Instrument Air is is loss loss to to containment containment duringduring aa Containment Containment Phase Phase AA Isolation signal Isolation signal unless unless PCV-1716 PCV-1 716 has has been been RESET RESET OR OR placed in OVERRIDE. placed in OVERRIDE. 4.
- 4. IF the normal IF normal drain path path via the RCDT is NOT available, is NOT available, OROR aa Contai Containmentnment Phase Isolation signal is present, A Isolation present, THEN perform perform following when Instrument the following Instrument Air has been restored restored to the the valves valves below:
- a. Open WD-1 WD-1708,708, RCDT DRAIN TO CV SUMP. SUMP.
- b. Place LCV-1 003B, RCDT PUMP B LCV-10038, "8" SUCT SUCTION, to the ION, to the CLOS E positio CLOSE position. n.
c.
- c. Open Open RC-52 RC-523, 3, PRT PRT DRAIN.
DRAIN. d.
- d. WHEN WHEN PRT PRT level level returns returns toto betwee between 70% and n 703o and 74%,
74%, THEN THEN perform the perform the follow ing: following: w 1)
- 1) Close Close RC-52 RC-523. 3.
2)
- 2) Close Close WD-1 WD-1708.708.
3)
- 3) Place Place LCV-1 003B, RCDT LCV-10038, RCDT PUMPPUMP B "8" SUCT SUCTION, ION, toto the the AUTO AUTO positio position n 5.5. IF IFPRTPRTtemper ature isisgreater temperature greaterthanthan 120°F, 120°F,THENTHENadd add Primar Primary y
Water to Water tothe the PRT PRTininaccord ance with accordance withthis this proced procedure. ure. OP-i 03 IOP-103 Rev. Rev.16 16 Page77ofof23231 Page
" '\...~" . ~,.. REFERENCEUSE REFERENCE USE Section Section8.2.1 8.2.1 Page Page33ofof33 CAUTION CAUTION PumpingPRT Pumping PRTcontents contentsthrough throughContainment ContainmentIsolationIsolationvalves valvesfollowing followingaaPRT PRT temper ature increas e in excess of 160°F can temperature increase in excess of 160°F can cause failure cause failureofofthe thevalves valvestotoseatseatdue duetoto debrisaccumulation debris accumulationfrom from aafailed failed PRT PRTliner. liner. (ESR (ESR 96-00608) 96-00608) 6.6. IFIFthe the PRT PRTtemperature temperature has has been been greater greaterthanthan oror equal equal 160°F 160°F AND the AND the liner liner hashas NOT NOT been been satisfactorily evaluated, satisfactorily evaluated, THEN THEN perform the perform the following: following: a.
- a. Verify CV Verify CV Sump Sump equipment equipment alignedaligned as as follows:
follows: 1)1) CV Sump CV Sump PumpPump breakers breakers OPEN. OPEN.
-- CV SUMP CV SUMP PUMP PUMP "A" A on on MCC MCC 22 inin CMPT CMPT 3M 3M
-
- CV SUMP CV SUMP PUMP PUMP "8" B on on MCC MCC 11 in in CMPT CMPT 5H 5H 2)
- 2) CV Sump CV Sump Pump Pump Discharge Discharge valves valves CLOSED CLOSED
-
- WD-1728, CONTAINMENT WD-1728, CONTAINMENT SUMP SUMP PUMP PUMP DISCHARGE AUTO ISOLATION DISCHARGE ISOLATION
-
- WD-1723, CONTAINMENT WD-1723, CONTAINMENT SUMP PUMP PUMP DISCHARGE AUTO ISOLATION DISCHARGE ISOLATION
- b. WD-i 708, RCDT DRAIN TO CV SUMP.
Open WD-1708, SUMP.
- c. Place LCV-10038, LCV-1003B, RCDT PUMP B "8" SUCTION, SUCTION, to to the the CLOS CLOSE E positio n.
position.
- d. Open RC-52RC-523, 3, PRT PRT DRAIN.
DRAIN. e.
- e. WHEN WHEN PRT PRT level level returns returns to to betwee between 70% and n 70% and 74%,
74%, THEN THEN perform perform the the follow ing: following: 1)
- 1) Close Close RC-52 RC-523. 3.
2)
- 2) Close Close WD-i WD-1708.708.
3)
- 3) Place Place LCV-1 003B, RCDT LCV-10038, RCDT PUMPPUMP B "8" SUCT SUCTION, ION, to to the the AUTO AUTO positio position n f.f. Place Place aa Cautio Cautionn Tag Tag on on RC-52 RC-523 switch that 3 switch that reads reads If "If the the PRT require s drainin PRT requires draining g itit shall shall be be aligned aligned to to the the CV CV sump sump only, only", This This caution caution will will remain remain inin effect effect until until the the PRT PRT interna internal l coating coatingevalua evaluation tion isiscomple complete.te.
g.g. Consu Consult lt RESS RESSfor foraaPRTPRTinterna internal coatingevalua l coating evaluation. tion. OP-i 03 IOP-103 Rev. Rev.16 16 Page88ofof23 Page 23/
____ CONTINUOUS USE CONTINUOUS USE Section Section 8.2.2 8.2.2 Page Page 1 of 1 of 22 CHK CHK (v') (V) 8.2.2 8.2.2 Adding Primary Adding Primary Water Water to the PRT to the PRT 1.
- 1. Verify the Verify the following following initial initial conditions conditions are are satisfied:
satisfied: NOTE: NOTE: PRT temperatures PRT temperatures of of greater greater than than 120°F 120°F should should bebe reduced reduced by by alternately alternately adding Primary adding Primary Water Water toto the the PRT PRT andand draining draining the the PRT. PRT. (SER (SER 93-007) 93-007) Maximum cooling Maximum cooling effect effect can can be achieved by be achieved leaving the by leaving the added added Primary Water in Primary Water in the the PRT PRT for at least 10 minutes at least 10 minutes prior prior to to draining. draining. (SER(SER 93-007) 93-007) a.
- a. All the Prerequisites of Section 4.0 are are complete.
- b. Pressurizer Relief Tank level is less Pressurizer less than 80%.
~c. Draining the PRT is NOT in progress. (SER 93-007)
CAUTION Operating two Primary Water Pumps can cause inadvertent filling of the RCS if the RCS is depressurized and vented through a PORV when two Primary Water Pumps are operating. Water may makeup to the RCS via the PRT spargers if the PRT is filled faster than it can vent.
- 2. Verify a Primary Water Pump is OPERATING OPERATING..
- 3. Open RC-519A & B, 8, PW TO CV ISO.
- 4. Open RC-519C, PW TO PRT ISO.
5.
- 5. Monitor Monitor PRT PRT level level for anan increase.
increase. 6.
- 6. IF the expected IF the expected increase increase does does NOT occur, THEN NOT occur, stop filling THEN stop filling AND AND investigate.
investigate. OP-i 03 IOP-103 Rev. Rev. 16 16 Page Page 99of of23 231
CONTINUOUS USE CONTINUOUS USE Section Section 8.2.2 8.2.2 Page Page 22 of of 22 CHK CHK (v') V) NOTE: NOTE: Increasing PRT Increasing PRT level will cause PRT level will PRT pressure pressure to increase, increase, possibly possibly to the high pressure high pressure alarm setpoint of 5 psig.
- 7. WHEN PRT level is between 70% and 80%, THEN perform the following: .j
- a. Stop the Primary Water Pump.
Pump.
- b. Close RC-519A & & B.
- c. Close RC-519C.
- 8. IF PRT level is greater than or equal to 83% OR PRT temperature is greater than 120°F, THEN lower the PRT level in accordance with this procedure.
- 9. RC-51 9A or RC-519B IF RC-519A RC-51 9B do not fully close, THEN relieve the hydraulic lock in accordance with this procedure.
OP-103 IOP-103 Rev. Rev. 16 16 PagelOof23J Page 10 of 231
APP-003-B3 APP-003-B3 ALARM ALARM PRTPRTHIHITEMP TEMP AUTOMATICACTIONS AUTOMATIC ACTIONS 1.1. NotApplicable Not Applicable CAUSE CAUSE 1.1. OpeningofofPressurizer Opening PressurizerSafety Safetyor orPORV PORV 2.2. PressurizerSafety Pressurizer SafetyororPORV PORVleakage leakage OBSERVATIONS OBSERVATIONS 1.1. PRT Level PRT Level (LI-470) (LI-470) 2.2. PRT Pressure PRT Pressure (PI-472) (P1-472) 3.
- 3. PRT Temperature PRT Temperature (TI-471)
(TI-471) 4.
- 4. Pressurizer Safety Pressurizer Safety Valve Valve Line Line Temperatures Temperatures (TI-465, (TI-465, TI-467, TI-467, TI-469)
Tl-469) 5.
- 5. PORV Discharge PORV Discharge Line Temperature (TI-463)
Line Temperature (TI-463) ACTIONS ACTIONS 1.
- 1. Alternately add Primary Alternately Primary Water to the PRT PRT and drain the PRT PRT using using OP-103.
OP-i 03. DEVICE/SETPOINTS DEVICE/SETPOINTS 1.
- 1. TC-471 I/ 150°F TC-471 150°F POSSIBLE PLANT POSSIBLE PLANT EFFECTS EFFECTS 1.
- 1. None None Applicable Applicable REFERENC REFERENCES ES 1.
- 1. CWD CWD B-i 90628, Sheet B-190628, Sheet 461, 461 , Cable Cable LL 2.
- 2. OP-103, OP-103, Pressurizer Pressurizer Relief Relief Tank Tank Control Control System System IAPP-0 APP-003 03 I Rev.
Rev.3737 I Page17 Page 531I 17ofof53
__ __________ _ SYSTEM SYSTEM SIMPLIFIED SIMPLIFIED DIAGRAM DIAGRAM PZR-FIGURE-l PZR-FIGURE- 1 TE TE 469 467 465 IVSW RC-516 RC-51 R 1 C-533I RC-533 6 Gas Gas -- Analyzer Analyzer 4 I 1480 RC-551A RC-551B RC.551C I 455C 456 RC RC525 E_RC j TE I- Nitrogen Vent Vent.. "'4 536 Aux Header RC-549 Spray j LOOpBB Manifold PCV-455A RC-524 Leg
-1RC-55O it 4b 454 LoopC PCV-455B
<Cold r
XXX;E, LT PZR -© RDT PrimarY> Water Water RC-519A RC-523 RC-523 Primary )'--~.~~~'~"~'C'-----Ifj"---
© © RC-519A RC-5198 RC-519B
/LII1 e Line Loop Loop cc lpz01 I Ipzrf011 Hot Hot Leg Leg INFORMATION INFOR MATION USE ONLY
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 33. Given the
- 33. Given the following:
following: The plant
- The
- plant isis inin EPP-10, EPP-1O, LONG TERM RECIRCULATION.
LONG TERM RECIRCULATION. APP-002-E5, SI
- APP-002-ES,
- SI PMP PMP COOL COOL WTR WTR LO FLOW alarm LO FLOW alarm isis received.
received. Which ONE Which ONE (1)(1) of of the the following following describes describes the the cause cause and and effect effect ofof the the alarm? alarm? A. Loss of A. Loss of CCW CCW to to the the SI SI Pump Pump Bearing Bearing Heat Heat Exchangers; Exchangers; can can result result inin overheating overheating the the pump pump bearings. bearings. B. Loss of B. Loss of CCW CCW to to the the SI Pump Seal S Pump Seal Coolers; Coolers; can can result result in in loss loss of of SI SI Pump Pump seals. seals. C. Loss C. Loss of of SW SW to to thethe SISI Pump Pump Bearing Bearing Heat Heat Exchangers; Exchangers; cancan result result in in overheating overheating the pump pump bearings. D. Loss of SW to the SI Pump Seal Coolers; can result in loss of SI Pump seals. 33 33
HLC-08 NRC Written Exam 33.008
- 33. 001lCCW/2/112.7/2.5IROILOWINIAINEW - 2008/CCW-009 008 A4.05 001/CCW/2/1/2.7/2.51R0/LOWJN/AJNEW -
Given the following: EPP-10, LONG TERM RECIRCULATION.
- The plant is in EPP-1O,
-
- APP-002-E5, SI PMP COOL WTR LO FLOW alarm is received.
-
Which ONE (1) of the following describes the cause and effect of the alarm? A. Loss of CCW to the SI Pump Bearing Heat Exchangers; can result in overheating the pump bearings. B Loss of CCW to the SI Pump Seal Coolers; can result in loss of SI Pump seals. B:' C. Loss of SW to the SI Pump Bearing Heat Exchangers; can result in overheating the pump bearings. D. Loss of SW to the SI Pump Seal Coolers; can result in loss of SI Pump seals. The correct answer is B. A: Incorrect - CCW supplies SI Pump Seal Coolers, NOT Bearing Heat Exchangers.
-
B: Correct - - CCW Low flow (50 GPM) to the Seal Coolers initiates the alarm. C: Incorrect - SW does NOT supply SI Pump Bearing Heat Exchangers. SW does supply SI
-
Pump Thrust Bearing cooling bath, but has NO alarm. D: Incorrect - SW does NOT supply SI Pump Seal Coolers. SW does supply SI Pump Thrust
-
Bearing cooling bath, but has NO alarm. Exam Question Number: 33
Reference:
APP-002-E5; SD-013 CCW, Page 13. KA Statement: Ability to manually operate and/or monitor in the control room: Normal CCW-header total flow rate and the flow rates to the components cooled by the CCWS. History: New - Written for HLC-08 NRC exam.
-
Tuesday, June 17,2008 17, 2008 11:21:09
- 21 :09 PM 38
APP-002-E5 APP-002-E5 ALARM ALARM SI PMP SI PMP COOL COOL WTR WTR LOLO FLOW FLOW AUTOMATIC ACTIONS AUTOMATIC ACTIONS 11.. Applicable None Applicable None CAUSE CAUSE 1.
- 1. Misaligned valve Misaligned valve or or leak leak in in lines CCW to supplying CCW lines supplying to or or from from the the SI SI Pumps.
Pumps.
~
OBSERVATIONS OBSERVATIONS 1.
- 1. None applicable (see actions)
None ACTIONS 11.. IF long IF long term post accident recirculation is NOT recirculation is NOT in in progress, THEN dispatch personnel to check CCW flow to the SI Pump Seal Coolers, FIC-658.
- 2. IF SI Pumps Pumps are operating under non-emergency conditions OR long term recirculation, THEN stop the pumps.
- 3. IF a loss of CCW has occurred, THEN refer to AOP-014.
- 4. IF valve alignment is NOT correct, THEN verify correct valve alignment using OP-306.
- 5. IF a CCW leak is present, THEN isolate the leak.
DEVICE/SETPOINTS
- 1. FIC-658 I/50 50 gpm POSSIBLE PLANT EFFECTS
":"~'"' ~'4'.,
- Loss of SI Pump Seals. (If in recirculation mode
~ .
?2.-~~cihI<,......,...,rtrw-i;..m.,.-++=-.CAl--1~14{iPlPEI=I--e~-S~-Lce==~~____.-J REFERENCES 1.
- 1. AOP-0l AOP-014, 4, Component Cooling Water System Malfunction
- 2. ITS LCO 3.5.2, 3.5.3
- 3. Flow Drawing, 5379-376, Sh 4
- 4. CWD B-i 90628, 488G B-190628,
- 5. OP-306, Component Cooling Water System IAPP-002 APP-002 Rev. 54 Rev. 54 Page 55 Page 55 of 651 of 65
SD-013 COMPONENT COOLING WATER SYSTEM used. When the evaporators were in service, CCW was supplied to the concentrator section of the evaporator to condense the steam that is boiled off in the concentrator. The distillate was further cooled in the condensate cooler before it was pumped to the monitor tanks (MT). The CCW flow to the concentrator was throttled for proper operation of the evaporator. 3.6.7 Sample Heat Exchangers CCW supplies cooling water for the following sample heat exchangers:
- 1. Reactor Coolant
- 2. Pressurizer Liquid Space
- 3. Pressurizer Steam Space
- 4. Steam Generator Blowdown (one for each A, B, & C)
- 5. Post Accident Sampling System Each cooler can be isolated by manually operated valves.
3.6.8 Waste Gas Compressor CCW is'is supplied to these compressors for the purpose of cooling the water used for sealing the shaft seals on either side of the compressor and also for makeup to the separator tank automatically when water is needed. The gas compressor has to be running before automatic makeup will function. 3.6.9 Residual Heat Removal Pumps CCW is supplied to the sealing water heat exchanger on these pumps. Emergency cooling connections are also available so these pumps may be operated using an external cooling source if CCW ever has to be isolated from these components. ~~~~-;~-:-;:O~(~Dii~) Safety Inj ection (S I) CCW is supplied to the ~~§eal wat~r he~t ~xchan@r y.tcrhca xchaner on each of the 3 SI pumps. Emergency cooling connections are also available so these pumps may be operated using an external cooling source if CCW ever has to be isolated from these components. 3.6.11 Containment Spray (CS) Pumps CCW is supplied to the seal water heat exchanger on each of the CS pumps to cool the seal water being used to seal and cool the mechanical seal on the pump shaft. 3.6.12 Spent Fuel Pit Heat Exchanger ccw CCW of 38 Page 13 of38 Revision 9 INFORMA INFORMATION TION USE ONLY ONL Y
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 34. Given
- 34. the following:
Given the following: The plant
- The
- plant isis in in MODE MODE 3. 3.
The crew
- The
- crew is is performing performing aa plant plant heatup.
heatup. Pressurizer level
- Pressurizer
- level is is 50%.
50%. BOTH Pressurizer
- BOTH
- Pressurizer LiquidLiquid Space Space and Steam Space and Steam temperature indicators Space temperature indicators read read 622 622 of.
°F.
Which ONE (1) (1) of the pressure pressure indicators indicators most most accurately accurately represents represents current current Pressurizer Pressurizer Pressure? Pressure? P1-444 = 1783 A. PI-444 1783 PSIG. Pi-445 B. PI-445 =
= 1798 PSIG.
P1-455 C. PI-455 =
= 1813 PSIG.
P1-456 D. PI-456 =
= 1828 PSIG.
34 34
HLC-08 NRC Written HLC-08 NRC Written Exam. Exam.
- 34. 010
- 34. 010 KS.01 K5.01 001IPZR 001/PZR PRESSURE PRESSURE CONTROU2/1/3.S/4.0IROIHIGH/N/A/NEW CONTROL/2/1/3.5/4.0/ROIHIGHLN/AINEW - 2008ITHERMO
- 2008/THERMO CHAP CHAP 3-008 3-008 Given the Given the following:
following: The plant
- The
- plant is is in in MODE MODE 3. 3.
The crew
- The
- crew isis performing performing aa plant heatup.
plant heatup. Pressurizer level
- Pressurizer
- level is is 50%.
50%.
- BOTH Pressurizer Liquid Space and Steam Space
- Space temperature indicators indicators read read 622 of.
°F.
Which ONE (1) of the pressure indicators indicators most accurately represents current Pressurizer Pressure? P1-444 == 1783 A. PI-444 1783 PSIG. PSIG. P1-445 == 1798 PSIG. B PI-445 8:0' P1-455 == 1813 PSIG. C. PI-455 D. PI-456 P1-456 == 1828 PSIG. The correct answer is B. A: Incorrect - Subtracted 14.7 PSI from corrected answer.
-
B: Correct - - Using Steam Tables, interpolate for 622 of. °F. 620 of
°F == 1786 .. 9 PSIA, 624 0°F=
1786.9 F= 1839.0 PSIA. Therefore 622 of °F =
= 1812.95 PSIA. Convert 1812.95 PSIA to PSIG: 1812.95 PSIA - 14.7 PSI =
- = 1798.25 PSIG C: Incorrect - Listed answer without adjusting for PSIA.
-
D: Incorrect - Added 14.7 PSI instead of subtracting to obtain PSIG.
-
Exam Question Number: 34
Reference:
Steam Tables; SD-059 PZRIPRT, PZRlPRT, Figure 1. 1. KA Statement: Knowledge of the operational implications of the following concepts as the apply to the PZR PCS: Determination of condition of fluid in PZR, using using steam tables. History: History: New - Written for HLC-08 NRC exam.
-
Tuesday, June 17, Tuesday, June 17, 2008 1:21 :09 PM 20081:21:09 PM 39 39
SYSTEM SIMPLIFIED SYSTEM SIMPLIFIED DIAGRAM DIAGRAM PZR-FIGURE- 1 PZR-FIGURE-I IVSW Gas Analyzer Vent.. 111'4 Header 8 PZR RC-523 Primary ) .... Water J
. ..-'. fj'lo--
RC-519A RC-5198 loop c lpzrf01 I Hot leg INFO RMATION USE INFORMATION USE ONLYONLY
HLC-08 NRC HLC-08 NRCWritten Written Exam Exam
- 35. Given
- 35. Giventhethefollowing:
following: Theplant
- The
- plantisisoperating operating atat6% 6% RTP RTP preparing preparingforforTurbine Turbine roll.
roll. PZR level
- PZR
- level channel channel LT-459 LT-459 failed failed 44 hours hours ago.
ago. The The bistables bistables have have been been tripped and all tripped and all actions are actions are complete complete per perAOP-025, AOP-025, RTGS RTGB INSTRUMENT INSTRUMENT FAILURE.FAILURE. PZR level
- PZR
- level isis currently currently 25%25% on on Channels Channels LT-460 LT-460 and and 461.
461. Which ONE Which ONE (1) (1) of the following of the following describes describes the the effects effects on the plant on the plant ifif PZR PZR level level channel channel LLT-461 T-461 fails HIGH? fails HIGH? A. Reactor Trip A. AA Reactor Trip duedue to to high high PZR PZR level. level. B. Reactor Trip B. AA Reactor Trip due due toto low low PZR PZR level. level. C. The C. The Reactor Reactor willwill NOT NOT trip, trip, signal signal isis blocked blocked by P-7. by P-7. D. The D. The Reactor Reactor willwill NOT NOT trip, trip, signal signal is is blocked blocked by P-1O. by P-1 O. 35 35
HLC-08NRC HLC-08 WrittenExam NRCWritten Exam
- 35. 012 K6.01 OO1IRX
- 35. 012 K6.01 001/RX PROTECTION/2/1/2.8/3.3IROIHIGH/NINCOOK PROTECTION/2/1/2.8/3.3IROIHIGHINIA/COOK- 20021RPS-006 - 2002/RPS-006 Giventhe Given thefollowing:
following: Theplant
- The
- plantisisoperating operatingatat6% 6% RTPRTPpreparing preparingfor forTurbine Turbine roll.
roll. PZR level
- PZR
- level channel channel LLT-459 failed44hours T -459 failed hoursago.ago. TheThebistables bistables havehave been beentripped tripped and andall all actions are actions are complete complete per perAOP-025, AOP-025, RTGB RTGB INSTRUMENT INSTRUMENT FAILURE. FAILURE.
PZR level
- PZR
- level isis currently currently25% 25% on on Channels Channels LT-460LT-460 andand 461.
461. Which ONE Which ONE (1) (1) of of the the following following describes describes the the effects effects onon the the plant plant ifif PZR PZR level level channel channel LT-461 LT-461 fails HIGH? fails HIGH? A. AA Reactor A. Reactor Trip Trip due due toto high high PZRPZR level. level. B. AA Reactor B. Reactor Trip Trip due due toto low low PZR PZR level. level. C The Cr The Reactor Reactor will will NOT NOT trip, trip, signal signal isis blocked blocked by P-7. by P-7. D. The D. The Reactor Reactor wi" will NOT NOT trip, trip, signal signal isis blocked blocked by P-1 0. by P-10. The correct The correct answer answer is C. C. A: Incorrect A: Incorrect - A - A High High Level trip signal is generated from the channel failure, but itit is is blocked blocked by by P-7. P-7. B: Incorrect B: Incorrect - A - A trip trip will NOT occur due to low level. C: C: Correct Correct - - With Channel LT-459 in the tripped condition the High level Rx Trip signal Signal will will be be made up for 11 channel (1/2 coincidence on remaining channels). The The level level control selector switch for the Pressurizer is in the 461 REPLACE 459 position position with with channel LT-461 LT-461 as as the controlling channel. When it fails high aa High High Level Level Rx Trip signal is is generated generated but itit is is blocked by by P-7 P-7 (Reactor (Reactor and and Turbine Turbine power power both both below below 10%). 10%). D: 0: Incorrect Incorrect - Signal
-
Signal is is blocked blocked by by Permissive Permissive P-7, P-7, (Turbine (Turbine Power) Power) NOT NOT RIO, P-10, (NI (NI Power). Power). Exam Exam Question Question Number:Number: 35 35
Reference:
Reference:
SD-all SO-011 RPS, RPS, Pages Pages 20-21, 20-21, 29,29, Figure Figure 31.31. KA KA Statement: Statement: KnowledgeKnowledge of of the the effect effect ofof aa loss loss or or malfunction malfunction of of the the following following will will have have onon the the RPS: RPS: Bistables Bistables and and bistable bistable testtest equipment. equipment. History: History: Modified; Modified; removedremoved LCO LCO actions. actions.
- Tuesday, Tuesday,June June17, 17,2008 20081:21:09 1:21 :09PMPM 4040
SD-Oil SD-011 REACTOR REAC TOR PROT PROTEC ECTIO TION N SYSTE SYSTEM M 4.1.5.10 4.1.5.1 0 RCP Bus RCP Bus Under Underffreque requen cy Trip ncy Trip (Not (Not aa direct direct reacto reactorr trip) trip) (Figur (Figuree 28) 28) a.a. The RCP The RCP Bus Bus Under Underffreque requen cy Trip ncy Trip trips the RCPRCP breake breakers. rs. RCP RCP breaker openopen signal trips signal trips the reactorr which the reacto which provid provides protec protection tion for for the the Reacto Reactorr agains against DNB DNB as aa result as result of of an an underf underfrequen requency on on more more than than one one RCP RCP Bus. Bus. This This trip occurs when an when an underf underfreq uenc requen condition exists on 22 out of 33 RCP Buses cyy condit Buses when aboveabove 10% (P-7). 10% (P-7). This This trip is automa automatically tically blocked below 10% 10% (P-7). (P-7). This trip assure assuress a Reacto r Trip SignalSignal is generated beforebefore the Low Flow Trip Setpoi nt is reached.
- b. Setpoi nt - 58.2 Hertz
- Hertz 4.1.5.11 4.1.5.1 1 High PZR Pressu Pressure (Figure 29) re Trip (Figure
- a. The High PZR Pressure Trip provides protec protection tion for the Reactor Coolant System (RCS) against over pressu pressuriza rizatio tion n and limits the range of required protection protec tion from the OTilT OTLT Trip. This trip occurs when 2 out of 3 PZR Pressure Signals exceed the trip setpoint.
- b. Setpoint - - PC-455A, PC-456A, PC-457A/23 7A/237766 psig 4.1.5.122 4.1.5.1 Low PZR Pressu Pressure re Trip (Figure 30)
- a. The Low PZR Pressu Pressurere Trip provides protec protection tion against excessive void formation in the Reactor which could lead to a DNB ratio (DNBR) of
<
< 1.17 and limits the necessary range of protect protectionion afforded by the OT OTiTil T.. This trip occurs when 2 out of 33 PZR Pressure Signals decreases below the trip setpoint.
This trip is automatically blocked below 10% (P-7). This trip is dynamically compensated based on the rate of change in pressure.
- b. Setpoint - - PC-455C, PC-456C, PC-457C PM-455A, PM-456A, PM-457A 7A Trip Setpoint 1844 psig psig Lead Time Constant 10 sec.
Lag Time Time Constant 11 sec. ,'/4.1 4.1.5
.5.13
.13 High Pres Pressusuriz rizer er (PZR) Water Level Trip Trip (Fig (Figur uree 31) 31)
- a. The The High High PZR PZR Water Water Level TripTrip provid provides es aa back-up to the High PZR Pressu re RPS RPs Page Page 2020 of of30 30 Revision Revisi on 88 INFOR INF ORM MA ATI TIO ON N US USE E ON ONL LY Y
SD-Oil REACTOR REACTOR PROTECTION PROTECTION SYSTEM SYSTEM Trip Trip and prevents the and prevents PZR Safety the PZR Safety andand Relief Relief Valves Valves from from relieving relieving water water forfor credible accident credible accident conditions. conditions. This trip occurs This trip occurs whenwhen 22 out out ofof 33 PZR PZR Water Level Water Level Signals exceeds the Signals exceeds the trip trip setpoint. setpoint. This This trip trip isis automatically automatically blocked blocked below below 10% 10% (P-7). (P-7). b.b. Setpoint - Setpoint - LC-459A, LC-460A, LC-459A, LC-460A, LC-461A/91 LC-461A/91 % % of of span span 4.1.5.14 4.1.5.14 SteamlFeedwater Flow SteamlFeedwater Flow Mismatch Mismatch Trip Trip (Figure (Figure 32) 32) a.a. The Steam/Feedwater The Steam/Feedwater Flow Mismatch Trip Flow Mismatch Trip provides provides protection protection for for the the Reactor Reactor against an against anticipated Loss an anticipated Loss ofof Heat Sink. This Heat Sink. This triptrip occurs occurs when when lout 1 out ofof 22 flow flow elements sense that Feedwater elements sense that Feedwater Flow Flow is is < < Steam Steam Flow Flow and and lout 1 out ofof 22 Steam Steam Generator(S/G) Level Elements decrease below the setpoint Generator(S/G) setpoint in anyany S/G.
- b. Setpoint - - FC-478A, FC-478B/O.64 FC"7478A, FC-478B/0.64 x 10 1066 lbs/Hr FC-488B/0.64 x 10 FC-488A, FC-488B/O.64 1066 lbs/Hr FC-498B/0.64 x 10 FC-498A, FC-498B/O.64 1066 lbs/Hr AND LC-475B/30% of Span LC-474B, LC-475B/30%
LC-484B, LC-485B/30% LC-485B/30% of Span LC-495B/30% of Span LC-494B, LC-495B/30% 4.1.5.15 S/G Low-Low Water Level Trip (Figure 33)
- a. The S/G Low-Low Water Level Trip provides protection for the Reactor by preventing operation without adequate heat removal capability in the event of a sustained Steam/Feedwater Steam/Feedwater Flow mismatch which is sufficiently small not to be sensed by the Steam/Feedw Steam/Feedwater ater Flow Mismatch Trip. This trip occurs when 2 out of 33 S/Gs Narrow Range Level Elements on 1lout S/Gs decrease below out of 33 S/G the setpoint.
setpoint. b.
- b. Setpoint Setpoint - - LC-474A, LC-474A, LC-475A, LC-475A, LC-476A/16 LC-476A/16% % ofof Span Span LC-484A, LC-484A, LC-485A, LC-485A, LC-486A/16 LC-486A/16% of Span
% of Span LC-494A, LC-494A, LC-495A, LC-495A, LC-496A/16 LC-496A/16% % ofof Span Span 4.1.5.16 4.1.5.16 Safeguards Safeguards SignalSignal Trip Trip a.a. The The Engineered Engineered Safeguards Safeguards Signal Signal Trips Trips ensure ensure thatthat the the Reactor Reactor will will be be shut shut down during a severe accident. This down during a severe accident. This trip is initiatedtrip is if the initiated if the Engineered Engineered Safety Safety Features Features Actuation Actuation System System isis automatically automatically or or manually manually actuated.
actuated. b.
- b. Setpoint Setpoint - Refer
-
to SD-006, Refer to SD-006, Engineered Engineered SafetySafety Features Features System System RPS RPS Page Page 21 21 of of3030 Revision 88 Revision INFORMAT INFORMATION ION USE USE ONLY ONLY
SD-Oil SD-011 REACTORPROTECTION REACTOR PROTECTIONSYSTEM SYSTEM ATTACHMENT10.1 ATTACHMENT 10.1 Page22of3 Page of 3 REACTORPROTECTION REACTOR PROTECTIONSYSTEM SYSTEMPERMISSIVES PERMISS1VES PERMISSIVE NUMBER PERMISSIVE NUMBER DERIVATION DERIVATION FUNCTION FUNCTION P-7 P-7 2/4 Power 2/4 Power Ranges Ranges above above Enables Enables the the following following trips: trips: setpoint (10% setpoint (10% from from P-lO) P-1O) 1.1. RCS RCS LowLow Flow Flow OR OR 2.
- 2. RCP RCP Breakers Breakers OpenOpen 1/2 Turbine 112 Turbine First First Stage Stage 3.
- 3. UVUV Pressure above Pressure above setpoint setpoint 4.
- 4. Turbine Turbine TripTrip (10%)
(10%) 5.
- 5. PZR PZR LowLow Pressure Pressure 6.
- 6. PZR PZR High High Level Level 3/4 Power 3/4 Power Ranges Ranges below below Blocks the Blocks the following following reactor reactor setpoin setpoint t (10%) from P-lO from P-1O trips:
AND 1.
- 1. RCS Low Flow 2/2 Turbine Turbine First Stage 2. RCP Breakers Breakers Open Pressure below setpoint Pressure setpoint 3. UV (10%) 4. Turbine Turbine Trip 5.PZR Low Pressure Pressure 6.PZR High Level P-8 P-8 2/4 Power Range Rangess above Enabless Reacto Enable Reactorr Trip on on low low setpoin setpointt (40%)
(40 %) flow in a single loop 3/4 3/4 Power Power Range Rangess below below Blocks Blocks Reacto Reactorr Trip Trip onon low low setpoin setpointt (40%) (40 %) flow in flow in aa single single loop loop RPS RPS Page Page2929of0[30 30 Revision88 Revision INFO RMATION USE INFORMATION USE ONL ONLY Y
PRESSURIZERHIGH PRESSURIZER HIGHWATER WATERLEVEL LEVELREACTOR REACTORTRIP TRIPLOGIC LOGIC RPS-FIGURE-3 1 RPS-FIGURE-31 PRESSURIZERHIGH PRESSURIZER HIGHWATER WATER LEVEL REACTOR LEVEL REACTOR TRIP TRIP LOGIC LOGIC PRESSURIZER LEVEL PRESSURIZER LEVEL INSTRUMENTS INSTRUMENTS II IIII III III 2/3 P-7 AND REAC TOR TRIP REACTOR TRIP Irpsf3l rpsf31 I
au QU REPORT ONS REPORT ONS for CookExam200.?-J for CookExam2002)
- 1. 045 001lSRO/045IINPO 1.045 OOl/SRO/04511NP0 - DIRECT/53141bob028-'2:.'Z:22lRO#"NNSRO#
- DIRECT/53 14/000028 -2.2.22/RO#NA/SRO# 04113H 041/3H Given the Given the following following plant plant conditions:
conditions: The plant
- The
- plant is is operating operating at at 6% power preparing 6% power preparing for for Turbine Turbine roll.
roll. PRZ level
- PRZ level
- channel (1) NLP-151 NLP-151 failed 4 hours bistables have ago. The bistables have been been tripped and all actions are complete complete as per 01-0HP-4022-013-01 01-OHP-4022-01 3-01 0, Pressurizer Pressurizer Level Level Instrument Malfunction.
Instrument PRZ level is
- PRZ
- is currently 25% on channel (2) NLP-152 NLP-152 and (3) NLP-153.
Which ONE of the following describes the effects on the plant if PRZ level channel (3) NLP-153 fails high? Assume NO operator actions. A. A Reactor Trip due to high pressurizer level. B. A Reactor Trip and Safety injection due to a loss of pressurizer level. C. The Reactor will not trip, continue with the plant startup. D~ D The Reactor will not trip, however the plant must be placed in hot shutdown. ANSWER: D - With Channel 11 NLP-151 in the tripped condition the High level Rx Trip
-
signal will be made up for 11 channel (1/2 coincidence on remaining channels). The level control selector switch for the pressurizer is in the 2/3 position with channel 3 NLP-153 as the controlling channel. When it fails high a High Level Rx Trip signal is generated but it is blocked by P-7 (Reactor and Turbine power both below 10%). Plant Shutdown is required due to Tech Spec 3.3.1 (3.0.3). A - Incorrect - A High Level trip signal is generated from the channel failure (and an
- -
actual high level would occur - charging lowers, letdown isolates, pressurizer fills from
-
seal injection) but it is blocked by P-7. BB - Incorrect - A trip & SI will not occur due to loss of level.
- -
C - Incorrect - Startup can not continue due to Tech Specs and a trip if power is
- -
increased to >10%. > 10%. Lesson Plan/Obj: RO-C-00202 / #27
Reference:
SOD-00202-003, Pressurizer Level Control Pressurizer (PRZ) Level Control Malfunction
- Equipment Control
- Control
- Knowledge of
- of limiting limiting conditions for operations operations and and safety safety limits.
limits. Category Category 1:1: SRO SRO Category Category 2: 2: 045 045 Category Category 3:3: INFO INFO - DIRECT
- DIRECT Category Category 4:
4: 5314 5314 Category Category 5:5: 000028 000028 - 2.2.22
- 2.2.22 Category Category 6:
6: RO# RO#NANA Category Category 7:7: SRO# SRO#041 041 Category Category 8: 8: 3H 3H
- Tuesday, Tuesday, June June 10, 2008 7:24:07 AM 10,20087:24:07 AM 11
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 36. Given
- 36. Given thethe following:
following: The plant
- The
- plant isis operating operating at at 100%
100% RTP. RTP. ITS 3.3.2
- ITS
- 3.3.2 requires requires allall channels channels of of ESFAS ESFAS instrumentation instrumentation to to be be OPERABLE.
OPERABLE. Surveillance testing
- Surveillance
- testing of ESFAS Train of ESFAS Train "A" A isis scheduled scheduled to to commence commence inin 11 hour.
hour. What specific What specific provision provision of ITS or of ITS or facility facility license license allows allows for for the the scheduled scheduled testing testing of of an an ESFAS ESFAS train without entry into train without entry into the the associated associated Conditions Conditions and and Required Required Actions? Actions? A. The A. The Facility Facility License License specifically specifically exempts exempts Surveillance Surveillance Testing Testing fromfrom entry entry into into ITS ITS LCOs. LCOs. LCO entry is NOT required if the LCO entry is NOT required if the COMPLETION COMPLETIO TIME isis met. N TIME met. B. SR B. SR 3.0.2 3.0.2 allows allows surveillances surveillances to to be performed within be performed within 1.25 1 .25 times times thethe specified specified interval. interval. LCO LCO entry is entry is NOT NOT required. required. C. ITSITS 3.3.2, SURVEILLANCE SURVEILLANCE REQUIREMENTS, REQUIREMENTS, allows entry into into associated Conditions and Required Actions to be Required delayed up be delayed up to to 66 hours, hours, provided provided the redundant redundant Train is is OPERABLE. OPERABLE. D. ESFAS Train testing places the actuation bistables in the TRIPPED condition, which provides the Safeguards Function. LCO entry is NOT required. provides 36 36
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 36. 013
- 36. 013 G2.2.38 G2.2.38 001IESFAS/2/1/3.6/4.5IROIHIGHIN/A/NEW OO1IESFAS/211/3.6/4.5IROIHIGHIN/AINBW *2008IESF*008 - 2008/ESF-008 Given the Given the following:
following: The plant
- The
- plant isis operating operating at at 100%
100% RTP.RTP.
- ITS
- 3.3.2 requires ITS 3.3.2 requires all channels of all channels ESFAS instrumentation of ESFAS instrumentation to to be be OPERABLE.
OPERABLE. Surveillance testing
- Surveillance
- testing of ESFAS Train of ESFAS Train "A"A isis scheduled scheduled to to commence commence in in 11 hour.
hour. What specific What specific provision provision of of ITS ITS or facility license or facility license allows allows forfor the the scheduled scheduled testing testing of of an an ESFAS ESFAS train without train without entryentry into into the associated Conditions the associated Conditions and and Required Required Actions? Actions? A. The A. Facility License The Facility License specifically specifically exempts exempts Surveillance Surveillance Testing Testing fromfrom entry entry into into ITS ITS LCOs. LCOs. LCO entry is LCO entry NOT required is NOT required ifif the the COMPLETION COMPLETION TIME TIME is is met. met. B. SR B. SR 3.0.2 allows surveillances 3.0.2 allows surveillances to to be be performed performed within within 1.25 1.25 times times the the specified specified interval. interval. LCO LCO entry is NOTNOT required. C ITS C~ ITS 3.3.2, SURVEILLANCE SURVEILLANCE REQUIREMENTS, REQUIREMENTS, allows entry into into associated Conditions and Required Actions to be delayed up to 6 hours, provided the redundant Train is OPERABLE. OPERABLE. D. ESFAS Train testing places the actuation bistables in the TRIPPED condition, which provides the Safeguards Function. LCO entry is NOT required. The correct answer is C. A: Incorrect - No exception for entry into LCO
- LCQ REQUIRED ACTION simply for surveillance testing exists in the Facility License.
B: Incorrect - SR 3.0.2 does allow for surveillances to be performed within 1.25
-
1 .25 times the specified interval, but the specification is applied for completion times only, NOT to determine if LCO entry is required. C: Correct - - ITS 3.3.2, SURVEILLA SURVEILLANCES, NCES, NOTE 2 states: When "When a channel or train is placed in an inoperable status solely for the performance of required SURVEILLA SURVEILLANCES, NCES, entry into the associated Conditions and Required Actions may be delayed for up to 6 hours provided the redundant train is OPERABLE OPERABLE." . D: Incorrect Incorrect - Safeguards devices may
-
may be considered OPERABLE if placed in their safeguards actuate position (e. (e. g.g. closing an an inoperable isolation isolation valve valve would would allow the valves safeguards allow the valve's safeguards function to to be be considered considered met), met), but but the the function function bistables for the the Train Train inin test are tripped test are tripped (and (and untripped untripped when when complete) complete) individually. individually. Exam Exam Question Question Number:Number: 36 36
Reference:
Reference:
ITS ITS 3.3.2, 3.3.2, Pages Pages 3.3-20 3.3-20 andand 3.3-24; 3.3-24; SR 3.0.2, Page SR 3.0.2, Page 3.0-4. 3.0-4. KA KA Statement: Statement: Knowledge Knowledge of of conditions conditions and and limitations limitations in in the the facility facility license. license. History: History: NewNew - Written
-
Written forfor HLC-08 HLC-08 NRC NRC exam. exam.
- Tuesday, Tuesday, June June 17,20081:21 17, 2008 1:21:10 :10 PM PM 41 41
ESFAS ESFAS Instrumentation Instrumentation 3.3.2 3.3.2 .- INSTRUMENTATION 3.3 INSTRUMENTATION 3.3 3.3.2 Engineered 3.3.2 Engineered Safety Safety Feature Feature Actuation Actuation System System (ESFAS) (ESFAS) Instrumentation Instrumentation LCO LCO 3.3.2 3.3.2 The The ESFAS ESFAS instrumentation instrumentation for for each each Function Function in in Table Table 3.3.2-1 3.3.2-1 shall be shall be OPERABLE. OPERABLE. APPLICABILITY: APPLICABILITY: According to Table 3.3.2-1. ACTIONS
------. ----.. -------.. -----------. --. NOTE -. --. --.. -.... -. ---..... -... -. ------.
Separate Condition entry is allowed for each FunctionFunction..
........ -- .................................................................... .
CONDITION REQUIRED ACTION COMPLETION COMPLETION TIME TIME A. One or more Functions A.I A.1 Enter the Condition Immediately with one or more referenced in
-. required channels or Table 3.3.2-1 for the trains inoperable, inoperable. channel(s) or train(s).
train(s ). B. One channel or train B.1 Restore channel or hours 48 hours inoperable, inoperable. OPERABLE train to OPERABLE status. status. OR OR B.2.1 B.2.1 Be in Be in MODE MODE 3.3. 54 hours 54 hours AND AND B.2.2 B.2.2 Be in Be in MODE MODE 5.5. 84 hours 84 hours (continued) (continued) HBRSEP HBRSEP Unit No. 22 Unit No. 3.3-20 3.3-20 Amendment No. Amendment No. 176 176
ESFAS Instru Instrummenta tionn entatio 3.3.2 SURVE ILLANC SURVEILLA NCEE REQUIR REQUIREMEMENT ENTSS
...... -... ---. -. ---... ...... ..... ---. NOTESNOTES * .... -.... -..... ..... -..... .. -.. -.. .
- 1. Refer to Table 3.3.2 3.3.2-1 *1 to determine which SRs apply for each ESFAS Funct Functiion.
on.
- 2. When aa chann channeell or train is placed in an inope inoperrable able status solely solely for the performance perform ance of requir require edd Surve Surveiillanc llanceses,, entry into assoc iated associa ted Condi Condittions ions and Requi Requirred ed Actions may be delayed for up to 6 6 hours provided the redun redunddant ant train is OPERA OPERABLEBLE ..
...... ..... -_ ...... ...... .. - ..... ..... ..... ..... .....
..... ..... . - ...... . - ...... -
SURVE ILLANC SURVEILLA NCEE FREQUE NCYY FREQUENC SR 3.3.2.1 Perfor Performm CHANN CHANNELEL CHECK CHECK.. 12 hours SR 3.3.2.2 Perform ACTUA Perform TION LOGIC TEST. ACTUATION 31 days on a STAGG EREDD TEST STAGGERE BASIS SR 3.3.2.3 Perfor Performm MASTE MASTERR RELAY TEST. 18 months SR 3.3.2.4 Perfor Performm COT. 92 days SR 3.3.2.5 Perform SLAVE Perform SLAVE RELAY TEST. 18 months SR 3.3.2.6 ....* ...... .. -....* NOTE* NOTE ...... ...... ...... . Verif icatio Verificat ionn of setpo setpoinintt not requir edd for require manual initiation functi functioons ns..
...... . - ...... ...... ...... . - ...... ..... __ .....
Perfor Performm TADOT TADOT.. 18 months SR 3.3.2.7 Perfor Performm CHANN CHANNEL EL CALIBR ATION CALIBRATIO N.. .- 18 months HBRSE HBRSEPP Unit No. 2 2 3.3*24 3.3-24 Amendment No. 176
SR SR Applicability Applicability 3.0 3.0 3.0 SURVEILLANCE 3.0 SURVEILLANCE REQUIREMENT REQUIREMENT (SR) (SR) APPLICABILITY APPLICABILITY SR 3.0.1 SR 3.0.1 SRs SRs shall shall be be met met during during the the MODES MODES or or other other specified specified conditions conditions in in the the Applicability Applicability for for individual individual LCOs, LCOs, unless unless otherwise otherwise stated stated in in the the SR. SR. Failure Failure to to meet meet aa Surveillance, Surveillance, whether whether such such failure is failure is experienced experienced during during the the performance performance of of the the Surveill Survei 11 ance ance oror between between performances performances of of the the Survei 11 ance, shall Surveillance, shall be failure to be failure to meet the meet the LCO. LCO. Failure Failure toto perform perform aa Surveillance Surveillance within the within the specified specified Frequency Frequency shall shall bebe failure failure to to meet meet thethe LCO except as provided in LCO except as provided in SR 3.0.3. Surveillances SR 3.0.3. Surveillances do do not not have have to to be be performed performed on on inoperable inoperable equipment equipment or or variables variables outside outside specified specified limits. limits. SR 3.0.2 SR 3.0.2 The speci fi ed Frequency for each SR is met if the specified the Survei 11 ance Surveillance is performed within 1.25 1.25 times the interval specified in in the the Frequency, as measured from the previous performance or or as as measured from the time a specified condition of the Frequency Frequency is met. For Frequencies specified as "once," once, the above intervalinterval extension does not apply. If aa Completion Time requires periodic performance on on aa "once once per . . . " basis, the above Frequency extension applies
. . . appl ies to to each each performance after the initial performance performance..
Specification are stated in the individual Exceptions to this Specification individual Specification Specifications. s. SR SR 3.0.3 3.0.3 If it If it is is discovered di scovered thatthat aa Surveillance Survei 11 ance was was not not performed performed withinwi thi n its specified its specified Frequency, Frequency, thenthen compliance compliance withwith thethe requirement requirement to declare to declare the the LCO LCO not not met met may may be be delayed, delayed, fromfrom thethe time time of of discovery, up to 24 hours or up discovery, up to 24 hours or up to to the the limit limit ofof the the specified specified Frequency, Frequency, whichever whichever is is less. less. This This delay delay period period is is permitted permitted to allow to allow performance performance of of the the Surveillance. Surveillance. (continued) (continued) HBRSEP HBRSEP Unit Unit No. No. 22 3.0-4 3.0-4 Amendment No. Amendment No. 203 203
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 37. Given
- 37. Given the thefollowing:
following: The plant
- The
- plant isis operating operating atat 100%
100% RTP.RTP. HVH-3 has
- HVH-3
- has been been experiencing experiencing intermittent intermittentproblems problems and and the the fan fan has has been been stopped.
stopped.
- II && CC isis troubleshooting
- troubleshooting the the problem.
problem. APP-002-E6, HVH-1/2/3/4
- APP-002-E6,
- HVH-1/2/3/4 EMERGENCY EMERGENCY CONTROL CONTROL isis illuminated.
illuminated. CV RECIRC
- CV
- RECIRC FAN FAN HVH-3 HVH-3 indication indication on on the RTGB isis extinguished.
the RTGB extinguished. An inadvertent
- An
- inadvertent SafetySafety Injection Injection isis received.
received. Which ONE Which ONE (1) of the (1) of the following following describes describes thethe current current status status of of HVH-3? HVH-3? The Fan The Fan isis...
...
A. stopped and A. stopped and will will NOT NOT start start due due to to the the LOCAL-REMOTE LOCAL-REMOTE switch switch being being inin LOCAL. LOCAL. B. stopped, but B. stopped, but can can be started started from the RTGB using using the control control switch. C. running because C. running because the SI signal is independent of the LOCAL-REMOTELOCAL-REMOTE switch. D. running D. running because because it started on Low Air Flow following completion of the SI sequencer. 37 37
HLC-08NRC HLC-08 WrittenExam NRCWritten Exam
- 37. 022 A3.01 001/CTMT COOLING/2/1/4.1/4.3IROIHIGHJN/A/NEW- 200S/CVHVAC-00S 37.022 A3.01 OOllCTMT COOLING/2/1/4.1I4.3IROIHIGHlNINNEW - 2008/CVHVAC-008 Giventhe Given thefollowing:
following:
- The
- Theplant plantisisoperating operatingatat100% 100% RTP.RTP.
- HVH-3 has
- HVH-3 hasbeen been experiencing experiencing intermittent intermittentproblems problemsand andthe thefan fan has has been been stopped.
stopped.
- I I &&CC isistroubleshooting
- troubleshooting the the problem.
problem. APP-002-E6, HVH-1/2/3/4
- APP-002-E6,
- HVH-1/213/4 EMERGENCY EMERGENCYCONTROL CONTROL isis illuminated illuminated..
CV RECIRC
.. CV
- RECIRC FAN FAN HVH-3 HVH-3 indication indication on on the the RTGB RTGB isis extinguished.
extinguished.
- An
- An inadvertent inadvertent Safety Safety Injection Injection isis received.
received. Which ONE Which ONE (1) (1) of of the the following following describes describes thethe current current status status of of HVH-3? HVH-3? The Fan The Fan isis...
...
A'I stopped and A stopped and will will NOT NOT start start due due to to the the LOCAL-REMOTE LOCAL-REMOTE switch switch being being in in LOCAL. LOCAL. B. stopped, B. stopped, but but can can be started from the be started the RTGB RTGB using using the control control switch. switch. C. running C. running becausebecause the SI signal is independent independent of the LOCAL-REMOTE LOCAL-REMOTE switch. D. running because D. because it started on Low Air Flow following completion of the SI sequencer. sequencer. The correct The correct answer is A. A: Correct - A: Correct The Local-Remote Local-Remote switch inhibits autom automatic atic starts of the HVH-3 fan fan when when in
-
in LOCAL. B: B: Incorrect Incorrect - In LOCAL,
-
LOCAL, the only place that compo nent can be operate component operated d is the Local Control Station. Station. C: Incorrect C: Incorrect - LOCAL-REM
-
LOCAL-REMOTE OTE Switch Switch must must bebe placed placed inin REMOTE REMOTE for for ANY ANY Auto Auto signals signals to to actuate equipm actuate equipment. ent. D: D: Incorrect Incorrect - Low - Low AirAir flow flow will will alarm alarm (APP-002-C5 (APP-002-CS), ), but but provides provides NO NO Auto Auto start start feature feature of of the the Fan. Fan. Exam Exam Question Question Number: Number: 37 37 Refere
Reference:
nce: APP-002-E6 APP-002-E6; ; APP-0 02-C5. APP-002-CS. KA KA Statem Statement: ent: Ability Ability to to monitor monitorautoma automatictic operation operation ofofthe the CCS, CCS, including: including: Initiation Initiation of of safegu ards mode safeguards mode of ofoperati on. operation. History: History: New New -Written
-
Writtenfor for HLC-08 HLC-08 NRC NRC Exam. Exam.
- Tuesday, Tuesday,June June17, 2008 1:21 :10 PM 17,20081:21:10 PM 42 42
APP-002-E6 APP-00 2-E6 ALARM ALARM
- 1. HVH-112/3/4
/2/3/4 EMERGENCY CONTR CONTROL OL AUTOMATI AUTOM ATICC ACTIONS 11.. None Applica Applicable ble CAUSE CAUSE
- 1. HVH-1, 2, 3, OR 4 Emergency Control Switch Switches es in LOCAL LOCAL position position..
OBSERVAT OBSER VATIOIONS NS
- 1. HVH Status Lights out on RTGB.RTGB.
- 2. Local Switch position position ACTIONS
- 1. Determine reason for Local Control.
- 2. IF switche switchess have NOT been intentio intentionally positioned, nally position ed, THEN return emerg emergeency ncy control control switche switchess to normal..
normal
- 3. WHEN the switch has been restored to normal normal,, THEN reset the HVH Damper using OP-921OP-921..
- 4. IF HVH Units are required to be operable AND the alarm is illumina illuminated, ted, THEN monitor all CV HVH Cooler Status Lights on RTGB until the switch is repositioned.
DEVICE/SETP DEVIC E/SETPOINT OINTS S
- 1. None Applica Applicable ble POSSIBLE PLANT POSSI PLANT EFFECTS
- 1. Fan can NOT be operated from Control Room.
- 2. Fans will NOT auto start on safety injectio injection. (Inoperable)
- n. (Inoper able)
- 3. Fan motor overloa overload/trip d/trip alarm will NOT actuate on motor overloa overload.
d. REFERENCES ENCES
- 1. ITS LCO 3.6.6
- 2. CWO CWD B-1906 B-190628, 28, Sh 511,51 511, 512, 2,513, 513, 514,51 514, 515D 50
- 3. OP-921 OP-921,, Containment Air Handlin Handlingg IAPP-002 I Rev. 54 I Page 56 of 651 65 I
APP-002-C5 APP-002-C5 ALARM ALARM HVH-3AIR HVH-3 AIRFLOWFLOWLOSTLOST AUTOMATICACTIONS AUTOMATIC ACTIONS
- 11. . NoneApplicable None Applicable CAUSE CAUSE 1.1. Roughingfilter Roughing filterclogged clogged (Only (Onlyinstalled installedduring during plant plantshutdown) shutdown) 2.2. Mechanicalfailure Mechanical failure fan/motor fan/motor 3.3. Flowswitch Flow switch failure failure OBSERVATIONS OBSERVATIONS 1.1. HVH Alarms HVH Alarms forfor High High Vibration Vibration 2.
- 2. HVH Status HVH Status Lights Lights onon RTGB RTGB ACTIONS ACTIONS 1.
- 1. IF the IF the Hi Vibration alarm Hi Vibration alarm (APP-002-A?)
(APP-002-A7) isis also also received received for for HVH-3, THEN stop HVH-3, THEN stop HVH-3. HVH-3. 2.
- 2. IF available, THEN IF available, THEN startstart aa standby standby Containment Containment Recirc Recirc Cooler Cooler Fan.
Fan. 3.
- 3. Initiate actions Initiate actions to determine cause/validity cause/validity of alarm 4.
- 4. IF fan IF fan is inoperable, THEN refer to ITS LCO 3.6.6.
is inoperable, DEVICEJSETPOINTS DEVICEISETPOINTS 1.
- 1. FS-4715/
FS-4?15/ POSSIBLE POSSIBLE PLANTPLANT EFFECTS EFFECTS 1.
- 1. Possible Possible entry entry into into TECH SPEC LCO.
2.
- 2. CV CV elevated elevated temperature.
temperature. REFERENC REFERENCES ES 1.
- 1. ITS ITS LCO LCO 3.6.6 3.6.6 2.
- 2. Flow Flow Diagram Diagram G-1 90304, Sh G-190304, Sh 11 3.
- 3. CWD CWD B-i 90628, Sh B-190628, Sh 513 513 IAPP-002 APP-002 Rev.
Rev.54 54 Page33 Page 651 33ofof65
HLC-08 HLC-0 NRC Writte 8 NRC Written n Exam Exam
- 38. Given
- 38. Given thethe followi following:
ng:
-A
- A Reacto Reactorr Trip Trip and and Safety Safety Injectio Injection have occurr n have occurred.ed.
- The crew
- The crew isis perfor performin mingg action actions of PATH-s of PATH-i. 1.
- CVCV Spray Spray initiate initiated on increa d on increasing Containm sing Conta inmen entt pressu pressure.
re.
-
- CV
- CV Spray Spray Pump Pump "A"A breake breakerr hashas tripped tripped..
- CV
- CV Spray Spray Pump Pump "B"B isis operat operating normally.
ing norma
- other ECCS
- All other ECCS equipm equipme nt is ent is operat operatinging as require required.d.
Which ONE (1) of the followi Which following ng isis the impac impactt on the plantplant and the action action require required? d? Accident Accide analysis nt analys has determ is has determineined d that Conta Containminmen entt pressu pressure.. re .... A. MAY exceeexceed design.. Immed d design Immediat transition ely transit iately ion to FRP-J FRP-J.i RESPON
.1, RESP ONSE SE TO HIGH CONTAINM AINME ENT PRE NT PRES SSU SURERE,, due to the RED condit condition ion..
B. will NOT exceeexceed design.. Contin d design Continue ue in PATH-PATH-i1 until SPDSSPDS is reset and transit procedur transition ion to anothe anotherr proced uree is directe directed. d. C. MAY exceeexceed design.. Contin d design Continue PATH-i ue in PATH- 1 until SPDS SPDS is reset and transittransition ion to anothe anotherr procedur proced e is direc ure ted. is directe d. D. will NOT excee exceed design.. Transi d design Transitio n to FRP-J tion FRP-J.i.1 if CV Spray Spray PumpPump "A" A CANNOT be restarted. restart ed. 38 38
HLC-O HLC-08 S NRCNRC Writte Written Exam n Exam 3S.
- 38. 026026 Al.OI Al .01 OOIlCT 001/CTMT MT SPRAY SPRAY/2/l/3
/2/113..9/4.2I ROJH 9/4.2IR IGHIN OIHIGH /A/RNPP AUDIT
/N/NRN AUDIT BANK/
BANK CSS-00
/CSS-0055 Given the Given the followi following:
ng:
-A
- A Reacto Reactorr Trip Trip and and Safety Safety Injecti Injectionon have have occurr occurred.ed.
- The crew
- The crew isis perfor performin mingg action actions s ofof PATH-PATH-i. 1.
- CV Spray
- CV Spray initiate initiatedd on on increa increasing Containm sing Conta inmen entt pressu pressure.
re.
- CV Spray
- CV Spray Pump Pump "A" A breake breakerr has has tripped.
- CV Spray
- CV Spray Pump Pump "8" B is is operat operating normally.
ing norma
- other ECCS
- All other ECCS equipmequipme entnt is is operat operating ing asas require required.d.
Which ONE ONE (1) (1) ofof the followi followingng is is the impac impactt on the plant plant and the action action require required?d? analysis Accident analys is has determ determine ined d that Conta Containminmenentt pressu pressure.. re ...
.
A. MAY MAY excee exceed design.. Immed d design Immediat transition ely transit iately FRP-J.1, ion to FRP-J RESPON
.1, RESP ONSE SE TO HIGH CONTAINM ENT AINMENT PRES PRESSU SURE RE,, due to the RED condit ion.
8:1 B will NOT excee exceed design.. Contin d design Continue PATH-i ue in PATH- SPDS is reset and transit 1 until SPDS procedur transition ion'to to anothe anotherr proced e is ure directedirec ted. d. C. MAY excee exceedd design design.. Contin Continue PATH-i ue in PATH- SPDS is reset and transit 1 until SPDS transition ion to anothe anotherr procedur proced uree is directe directed. d. D. will NOT excee exceedd design design.. Transi Transitio tionn to FRP-J.1 if CV Spray Spray Pump Pump "A"A CANN OT be restarted. restart ed. The correc correctt answe answerr is 8. B. A: Incorrect - Minimum safeg safegu uard equipmeent ardss equipm nt (1 train of CV Spra
-
Spray y and 2 HVH units) is requiredd to mainta require maintain design param in design paramete rs. CV Spray eters. Spray Pump Pump B"8" and all othe otherr ECCS equi equipm pmeentnt is oper operatating ing.. B: 8: Corr ectt - Correc - Pres Pressu surere will NOT exce excee edd desig design n if 11 train of CV spray and 2 HVH units are oper operatating ing.. The crew shou should ld cont contininue ue in PATH PATH--i1 until told to trans transit ion to anot ition anothe herr proc proced edur ure e if appl icabl applica e. ble. C: Incorrect - Minimum safeg safegu uard ards s equi equipm pmeentnt (1 train of CV Spra
-
Sprayy and 2 HVH units) is requ requireiredd to main mainta tain in desig design n para param mete rs. CV Spra eters. Spray y Pum Pump p B "8" and all othe otherr ECCS ECCS equi equipm pmeent nt is oper operatating ing.. D: 0: Incorrect ct - Tran Transi sitio tionn to FRP-J.1 does NOT NOT depedepen ndd on the resta
-
restart rt of of CV CV Spra Spray Pump A. y Pump "A". ItIt depe depen nds ds on CV presspressu urere exce excee edin g 42 PSIG ding PSIG or or NO NO CV CV Spra Spray availab y avail le above able above 10 10 PSIG. PSIG. Tuesda
- Tuesday, y, June June 17,200 17,20081:21:
81:21:1 100 PM PM 43 43
HLC-08NRC HLC-08 NRCWritten WrittenExam Exam ExamQuestion Exam QuestionNumber: Number:38 38
Reference:
PATH-1
Reference:
PATH-i BD, BD,Pages Pages7,7,88for forgrid gridlocation locationE-3 E-3(E-1 (E-1 AND ANDE-2 E-2energized); energized);SD-024, SD-024, Contai nment Spray, Containment Spray, Page 7.Page 7. KAStatement: KA Statement:Ability Abilitytotopredict predictand/or and/ormonitor monitorchanges changesininparameters parameters(to(toprevent preventexceeding exceeding design limits)associated design limits) associatedwith withoperating operatingthe theCSS CSScontrols controlsincluding: including: Containmentpressure. Containment pressure. . History: Modified; History: Modified; removed removed operator operatoractions actionstoto restart restart CV CV Spray. Spray. Tuesda y, June June17, 17,2008 1:21:10 PM Tuesday, 20081:21:10 PM 44 44
GRID WOG BASIS/DIFF BASIS/ DIFFER ERENCES ENCES STEP E-2 2 RNPST RNP STEP EP TURBINE TURBI TRIPPED NE TRIPPE D WOG BASIS PURPOSE: PURPO SE: To ensure that the turbine is tripped BASIS: The turbine is tripped to prevent an uncontr uncontrolled cooldownn of the RCS due to steam flow olled cooldow that the turbine would require require.. DIFFERENC RNP DIFFER ENCES ES/REASON
/REASONS S There are essenti essentially differences.
ally no differen ces. Interpre Interpretation tation The ERG contains a substep substep to check ALL Stop Valves closed. closed. At RNP there are two stop valves, valves, if both are closed the turbine is conside considered tripped.. red tripped DETERMIN SSD DETER ATION MINAT ION This is not an SSD. D-2 2 RNP STEP (RNO) (RNO) TRIP OR RUN BACK TURBI TURBINENE WOG BASIS WOGB ASIS See ERG step 2 above. RNP DIFFER DIFFERENCENCES ES/REASON
/REASONS S The RNP step has added an additionadditional al action to run the Turbine back should the manual trip be unsuccessful.
SSD DETER DETERMIN ATION MINAT ION This is an SSD per criterion 10. E-3 3 RNP STEP El AND E-2 ENERG E-1 ENERGIZEDIZED IPATH-1-BD Rev 18 951 Page 7 of 95
GRID GRID WOG WOG BASIS/DIFFERENCES BASIS/DIFFERENCES ([;-3) (p3) STEP STEP WOG BASIS WOG BASIS PURPOSE: PURPOSE: ensure electrical To ensure To power to electrical power to at least one at least one emergency emergency bus bus BASIS: BASIS: AC must be power must AC power verified from be verified from either offsite sources either offsite sources or or the the diesel diesel generators generators to to ensure ensure adequate power adequate power sources sources to operate the to operate safeguards equipment. the safeguards equipment. At At least least one one train train ofof safeguards equipment is safeguards equipment required to is required to deal with emergency deal with emergency conditions. conditions. IfIf atat least least one one train train is not is available, the not available, the operator operator shouldshould trytry to to quickly quickly restore restore one train, e.g., one train, e.g., start start aa diesel diesel generator and generator load itit on and load emergency bus. the emergency on the at least bus. IfIf at least one one train train cannot cannot be be restored restored quickly, the quickly, operator should the operator transfer to should transfer ECA-O.O, LOSS to ECA-O.O, LOSS OF ALL AC OF ALL AC POWER. POWER. Guideline ECA-O.O Guideline ECA-O.O is is developed developed and structured to and structured to address address thethe condition condition where where all all ac ac emergency power emergency power is lost. ItIt is is lost. entered on is entered on the the symptom symptom of all ac of all ac emergency emergency bussesbusses being being deenergized. Its deenergized. objective is Its objective to cope is to cope with the loss with the loss ofof ac emergency power ac emergency power until until at at least least emergency bus one ac emergency bus cancan be energized. ECA-O.O be energized. ECA-O.O should not not be be entered ifif at least least one ac emergency bus is energized ac emergency energized since since the other other optimal optima! recovery recovery guidelines and and function function restoration guidelines restoration guidelines contain contain guidance guidance that that accommodates accommodates multiple multiple failures. failures. They They use use available equipment to mitigate events whether plant systems are at full capacity, minimum safeguards capacity or degraded capacity. The availability of minimum safeguards capacity is is not a requirement for being in the other optimal recovery guidelines and function restC?ration restoration guidelines. For example, the core cooling function restoration guidelines provide guidance for the use of available equipment in degraded systems to mitigate inadequate core cooling (ICC) (e.g., ICC analyses show that only one high head SI pump is needed to prevent ICC even though one high head SI pump may not be sufficient to mitigate design basis transients within their design basis acceptance criteria). It is also desirable to have power to all ac emergency busses. If power is available to It only one train, the operator should initiate attempts to restore power to the other train while continuing with the next step in the guideline to deal with the emergency condition. DIFFERENCES/REASONS RNP DIFFERENCES/REASONS There are essentially no differences. SSD DETERMIN DETERMINATION ATION This is not an SSD. F-2 F-2 33 RNP STEP EITHER E-1 OR E-2 E-2 ENERGIZED ENERGIZED (with transition to EPP-1) WOG WOGBASIS BASIS step 33 above. See step RNP DIFFERENC ES/REASONS DIFFERENCES/REASONS There There are are essentially essentially no no differences. differences. SSD DETERMIN SSD DETERMINATION ATION This This is is not not an an SSD. SSD. F-3 F-3 33 RNP RNP STEP STEP ATTEMPT ATTEMPT TO TO RESTORE RESTORE POWER POWER TO TO DE-ENERGI DE-ENERGIZED ZED BUS BUS WOG WOG BASIS BASIS See step 33 above. See step above. RNP RNP DIFFERENC ES/REASONS DIFFERENCES/REASONS There There are are essentially essentially no no differences. differences. IPATH-i -BD PATH-1-BD Rev Rev 18 18 Page 88 of Page 951 of 95
SD-024 SD-024 CONTAINMENTSPRAY CONTAINMENT SPRAYSYSTEM SYSTEM 1.0
1.0 INTRODUCTION
INTRODUCTION ContainmentSpray Containment SpraySystem System(CSS)(CSS)flow flowserves servestotoreduce reducethethecontainment containmentpressure pressureand and temper ature follow temperature following a LOCA oring a LOCA ormain mainsteam steamline linebreak break(MSLB) (MSLB)totonear nearnormal normal conditions. In conditions. addition, the Inaddition, theCSS CSSflow flowremoves removesradioactive radioactiveiodineiodinefrom fromthe thecontainment containment atmosp here follow ing a LOCA atmosphere following a LOCA to limit off-site to limit off-siteexposures exposures totowithin withinthe guidelines of theguidelines of 10CFRPart lOCPR Part 100. 100. The Thecomponents componentsof ofthe theCSSCSS include includethe thecontainment containmentspray spray (CS) (CS) pumps, Spray pumps, SprayAdditive AdditiveTank Tank (SAT), (SAT), eductors, eductors, sprayspray ring ringheaders headers andandnozzles, nozzles, instrum entatio instrumentationnand andthe the necessary necessary piping piping and and valves. valves. In Inaddition, CSS the CSS utilizes addition, the utilizes the the Refuel ing Water Storag e Tank (RWS T) Refueling Water Storage Tank (RWST) during the post-accident during the post-accident injection injection phase phase and and the the RHR System RHR System (pumps, (pumps, heat heat exchangers exchangers and and associated associated valves valves andand piping) piping) for long term for long term post-accident recirculation post-accident recirculation phase phase of containment spray. ofcontainment spray. 2.0 2.0 GENERAL DESCRIPTION GENERAL DESCRIPTION 2.1 2.1 System Purpose System Purpose The primary The primary purpose purpose of of the the CSS CSS isis to to spray spray cool cool water water into into the the containment containment atmosphere atmosphere when approp when appropriate inriate the in the event event of of aa LOCA LOCA or or MSLB MSLB and and thereby thereby ensure ensure that that containment pressure containment pressure does not exceed its design value which is 42 psig at 263°P. 263°F. ThisThis protection is protection is afforded afforded for for all pipe break sizes up to and including including the double ended ended rupture of rupture of the the largest largest RCS pipe or a complete complete severance severance of a main steam line. line. Although the Although the water water in in the the core after a LOCA is quickly quickly subcooled subcooled by the Safety Safety Injecti on System Injection System, the , the CSS design is based on the conservative assumption conservative assumption that that the the core core residua residuall heat heat is is release released d to the contain containment ment as steam. AA second second purpos purpose e served served by by the CSS is to remov remove e elemen elemental iodine from the tal iodine contain ment atmosp here should containment atmosphere should be released it be release d in in the the event event ofof aa LOCA LOCA.. ~ 2.D esigDesign Basis~ n Basis The The design design basis basis provid provides es suffici ent heat sufficient heat remov removal al capaci capacityty tot<?~ntain maintain thethe post-ac post-accident cident containment pressu
~ontainment pressure re below below thethe desig npre, assumi desig!1 pressure, assuming ng that that the the core core residua residual heat is l heat is release releasedd toto the the contain containment ment as as steam.
steam. Adequ Adequate ate post-ac post-accident containment cident contain ment heatheat remov removal al capabi lity utilizes capability utilizes two two separa te, full-ca separate, pacity, engine full-capacity, ered safety engineered safety feature feature (ESF) (ESP) system systems. s. One One system system being being the the CSS, CSS, andand thethe second second being being thethe Contai Containment nment Air Air Recirc Recirculation ulation Coolin Cooling g Ventila Ventilationtion System System (see(see SD-03 SD-036 6 HVAC HVAC System Systems). These two s). These two system systems serve asas s serve indepe ndent backup s to independent backups to each otherforeach other for contain ment heat containment heatremov removal functions. al functio Either ns. _Eitlr system systemisis ful1y fully capable able of ofaddres addressing post-accident containment sLppst-accident containment hetJad& One of heat loads One ofthe the Spray pumps is at least
. Spray pumps is at least equivalent equiva lent tototwo twofan-co olers for fan-coolers forheat heatremov removal capability.
al capabi lity. CSS css Page Page7 7ofof26 26 Revision9 9 Revision INFO INFORMATION RMATION USE USE ONL ONLY Y
QUESTIONS REP9RT QUESTIONS REPORT for AUDIT (:! for AUDIT @00 00 ( ) ) 11.. 026 026A2.04A2.040011/1/1/// 00 lI//Hill Given the Given the followingfollowing conditions: conditions:
** AA reactor reactor triptrip and and safety safety injection injection have occurred.
have occurred.
- The crew is performing
- The crew is performing actions of actions PATH-i.
of PATH-1.
** CVCV Spray Spray isis manually manually initiated initiated on rising Containment on rising Containment pressure.
pressure.
- CV Spray Pump A breaker
- CV Spray Pump "A" breaker has a trip indication. has a trip indication.
** CV Spray Pump CV Spray Pump "B" operating normally B isis operating normally with with required required flow.
flow.
** All other ECCS All other ECCS equipment equipment isis operating operating as as required required Which ONE Which ONE (1) (1) ofof the the following following isis the the impact impact on on the the plant plant and and the the action action required?
required? A. Containment pressure A. Containment pressure may may exceed exceed design. design. Immediately Immediately transition transition toto FRP-J.1, FRP-J.1, Response to Response to High High Containment Containment Pressure, Pressure, due due toto the the RED condition. RED condition. B Containment B:I Containment pressure pressure will will not not exceed exceed design. design. Attempt one one reset reset and and restart restart of of "A" A CV Spray Pump Breaker. Continue Continue in PATH-1 PATH-i until SPDS is reset and and transition to to another procedure another procedure is required. C. Containment C. Containment pressure may exceed design. Attempt one reset and restart of of "A" A CVCV Spray Pump Spray Pump breaker. If restart unsuccessful, unsuccessful, transition to FRP-J.1, Response to to High Containment Pressure. High D. Containment pressure will not exceed design. Do NOT attempt reset and restart of D. of A CV Spray Pump unless entry to FRP-J.1 is required on transition from PATH-i.
"A" PATH-1.
B B isis correct. correct. Pressure will not exceed design if 11 train of spray is available, eliminating A and A and C. D D is incorrect because the crew may elect to reset and restart CV Spray Spray prior prior to to entry entry to FRP-J.1(Wh FRP-J.1 (Which ich will not be required anyway) SRO SRO QuestionQuestion 089 089 Tier Tier 22 GroupGroup 11 K/A KIA Importance Importance Rating Rating - SRO
- SRO 4.2 4.2 Ability Ability to (a) predict to (a) predict the the impacts impacts of of the the following following malfunctions malfunctions or or operations operations on on the the CSS; CSS; and and (b) (b) based based on on those those predictions, predictions, use use procedures procedures to to correct, correct, control control or or mitigate mitigate the the consequence consequences s of of those those malfunctions malfunctions or or operations:
operations: Failure Failure ofof spray spray pump. pump. Reference(s) Reference(s) - PATH-i - PATH-1 Proposed Proposed ReferencesReferences to to bebe provided provided to to applicants applicants during during examination examination - None
- None Learning Objective Learning Objective - -
Question Question Source Source - New-New Question History Question History - - Question Question CognitiveCognitive Level Level - Comprehens
- Comprehension ion 10 CFR Part 55 Content 10 CFR Part 55 Content - 43.5 - 43.5 Comments Comments - -
Tuesday, June10, Tuesday.June 10,2008 20089:02:43 9:02:43AM AM 1
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 39. Given the
- 39. Given the following:
following:
- AA SGTR
- SGTR has has occurred occurred andand thethe crew crew isis performing performing actions actions lAW lAW PATH-2.
PATH-2. Prior to
- Prior
- to RCS RCS cool cooldown down toto target target temperature, temperature, aa NOTE NOTE warns warns against against exceeding exceeding Steam Steam Line flow Line rates inin excess flow rates excess ofof the the High High Steam Steam Line Line flow flow setpoint.
setpoint. What condition What condition isis the the NOTE NOTE written written to to prevent? prevent? A. RCS A. RCS cool cooldown rate from down rate from being being exceeded. exceeded. B. An B. An SI SI initiation initiation on High Steam on High Steam LineLine Delta Delta P. P. C. An C. An SI SI initiation initiation on High Steam on High Steam flow. flow. D. MSIVs D. MSIVs isolation. isolation. 39 39
HLC-08 NRC HLC-08 Written Exam NRCWritten Exam
- 39. 03902.4.20
- 39. 039 G2.4.20OOllMAINIREHEAT 001/MAIN/REHEATSTEAM/2/1/3.S/4.3/ROILOW/NINNEW STEAMJ2/1/3.8/4.31R0/LOW/N/AINEW - 200S/PATH-2-003
- 2008/PATH-2-003 Given the Given the following:
following:
- AA SGTR
- SGTR has has occurred occurred andand thethe crew crew isis performing peorming actions actions lAW lAW PATH-2.
PATH-2. Prior to
- Prior
- to RCS RCS cooldown cooldown to target temperature, to target temperature, aa NOTE NOTE warns warns against against exceeding exceeding Steam Steam Line flow Line flow rates rates inin excess excess ofof the High Steam the High Steam Line Line flow flow setpoint.
setpoint. What condition What condition isis thethe NOTE NOTE written written to prevent? to prevent? A. RCS A. RCS cooldown cooldown rate from being rate from being exceeded. exceeded. B. An B. An SI initiation on SI initiation High Steam on High Steam Line Line Delta Delta P.P. C. An C. An SI initiation on SI initiation on High High Steam Steam flow. flow. D D~ MSIVs isolation. MSIVs isolation. The correct The correct answer answer is is D. D. A: Incorrect A: Incorrect - Rapid
- Rapid ReSRCS cooldown is expected during this event, cooldown rates will be be exceeded, but the NOTE does NOT address this concern.
exceeded, B: Incorrect S: Incorrect - SI- SI setpoint will be exceeded, however SI is blocked lAW actions of PATH-2 PATH-2 prior prior to to commencing cooldown. C: Incorrect - SI C: Incorrect - setpoint will be exceeded, however SI is blocked lAW actions of PATH-2 SI setpoint PATH-2 prior prior to commencing cooldown. D: D: Correct Correct - - MSIVs will isolate if the setpoint is exceeded, potentially stopping the cooldown cooldown ifif the crew is using Condenser Steam Dumps. Exam Exam Question Question Number: Number: 39 39
Reference:
Reference:
PATH-2, PATH-2, Grid Grid locations locations D-2 and D-3; D-2 and D-3; PATH-2 PATH-2 BD, SD, Pages Pages 69-70. 69-70. KA KA Statement: Statement: Knowledge Knowledge of of the the operational operational implications implications ofof EOP EOP warnings, warnings, cautions, cautions, and and notes. notes. History: History: New New - Written
-
Written for for HLC-08 HLC-08 NRC NRC Exam. Exam. '~-----' 4545
RNP WOG RNP WOG BASIS/DIFFERENCES BASIS/DIFFERENCES STEP STEP STEP STEP WOGBASIS WOG BASIS(continued) (continued) KNOWLEDGE: KNOWLEDGE:
*
- ItItisisnotnotintended intendedfor forthe theoperator operatortotoreevaluate reevaluatethe therequired requiredcore coreexitexittemperature temperature preciselyinterpolate ororprecisely interpolatebetween betweenvaluesvalueslistedlistedininthe thetable.
table.
** When Whenthe therequired requiredcore coreexit exittemperature temperatureisisreached, reached,the theintact intactsteam steamgenerator generator pressure(or pressure (orfeed feedflow flowtotoaafaulted faultedsteamsteam generator) generator)should shouldbe becontrolled controlledtoto maintainthat maintain thattemperature.
temperature.
** Cooldown ofofthe Cooldown the RCSRCSshouldshouldbe becompleted completed before beforecontinuing continuing ininthe the guideline.
guideline.
** Natura l circula tion flow in the Natural circulation flow in the ruptured loops may rupture d loops maystagnate stagnate during during thisthis cooldown.
cooldown. The The hothot leg leg temperature temperature inin that that loop loop may may remain remain significantly significantlygreater greaterthanthan the the intact loops. intact loops. InIn addition, addition, safety safety injection injection flowflow into into the the cold cold leg leg maymay cause cause thethe cold cold legleg fluid fluid temperature temperature to to decrease decrease rapidly rapidly inin that that same same loop.loop. Steps Steps to to depressurize the depressurize the RCS RCS and and terminate terminate SI SI should should be be performed performed as as quickly quickly as as possible after possible after thethe cooldown cooldown has has been been completed completed to to minimize minimize possible possible pressurized-thermal shock pressurized-thermal shock of of the the reactor reactor vessel. vessel.
** RCS cooldown RCS cooldown should should proceed proceed as as quickly quickly as as possible possible and and should should not not be be limited limited by the 1100°F/
by the OO°F/hr Technical Specification hr Technical Specification limit. limit. Integrity Integrity limits limits should should not not be be exceeded since exceeded since the the final final temperature temperature will will remain remain aboveabove 350°F. 350°F.
** The RCP The RCP trip criteria criteria (Step(Step 1) 1) does not not apply apply after a controlled controlled cooldown cooldown is is initiated.
initiated.
** IfIf more more than than one steam generator generator is ruptured, ruptured, the lowest ruptured ruptured steam generatorgenerator pressure should be used to determine pressure determine the required required core exit temperature.
temperature. IfIf cooldo cooldown wn to aa target core exit temper temperatureature is already in progre progress ss when aa subseq subsequent uent SGTR is diagnosed SGTR diagnosed the operato operatorr should stop the cooldo cool downwn until the subseq subsequent uent rupture ruptured d steam genera generator tor is isolate isolated d since contin continuing cooldown uing the cooldo would lower wn would lower the the pressu pressure in re in the newest newest rupture ruptured d steam generagenerator and result in unnece tor and unnecessary releasess ssary release prior prior to to its its isolatio isolation n from from the the intact intact steam steam genera generators. tors. TheThe target target corecore exit exit temper temperature ature should should be be reexam reexamined ined to determ determine ine ifif the the temper temperature should ature should be be reduce reduced d based based on on the the subseq uent rupture subsequent ruptured steam genera d steam generator pressure. tor pressu re. IfIf aaRCS RCS depres surization isis in depressurization in progre progress,ss, althou althoughgh itit does does notnot impact impact the the pressu pressure in the re in the newest newest rupture ruptured d steam steam genera tor, for generator, for the the sake sake ofof simpli simplicity city itit should should be be stoppe stopped and the d and the plant plant stabiliz stabilized ed byby the the operato operator r until until the the newest newest rupture ruptured steam genera d steam generator tor isis isolate isolated. d. RNP RNP DIFFE RENCES/REASONS DIFFERENCES/REASONS There There are are no no signifi cant differe significant nces. differences. SSD SSD DETERMIN DETERMINATION ATION This This isis not notan an SSD. SSD. D2 D2 2N6 2N6 RNP RNPSTEP STEP
~ NOTE:
NOTE:AFTER AFTERTHE THELOW LOWSTEAMLIN STEAMLINE E PRESS PRESSSISISIGNAL SIGNALISISBLOCKED,BLOCKED,MAIN MAINSTEAM STEAM ISOLATION ISOLATIONWILL WILLOCCU OCCUR R IFIFTHE THEHIHISTEAMSTEAMFLOW FLOW RATE RATESETPOSETPOINT INT ISISEXCEEDED EXCEEDED IPATH-2-BD PATH-2-BD Rev. Rev.1717 Page6969ofof 110 Page 1101 I
RNP WOG RNP WOG BASIS/DIFFERENCES BASIS/DIFFERENCES STEP STEP STEP STEP WOG BASIS WOGBASIS PURPOSE: PURPOSE: To theoperator alertthe Toalert operatortotothe potentialfor thepotential forinadvertent inadvertentsteam line isolation steamline isolation duringthe during thesubsequent subsequentsteam steamgenerator generatordepressurization. depressurization. BASIS: BASIS: An automatic An protection feature automaticprotection featureisis provided providedtotoclose closethe main steamline the main steamlineisolation isolation valveswhen valves when thethesteam steam pressure pressure rate signal isis exceeded. ratesignal exceeded. InIn the the following following step, step, the the operatorisis instructed operator instructedtoto dump dump steam steam from from the intactsteam the intact steam generators generators whichwhich may may result inin exceeding result exceeding the the rate rate setpoint. setpoint. Therefore, Therefore, this this note note isis intended intended to to alert alertthe the operator of operator possibility. this possibility. ofthis KNOWLEDGE: KNOWLEDGE: The rapid The rapid cooldown cooldown should should be continued using be continued using the the atmospheric atmospheric steam steam dumps dumps ifif MSIV closure MSIV closure occurs. occurs. DIFFERENCES/REASONS RNP DIFFERENCES/REASONS RNP The RNP The RNP notenote isis worded worded inin the the form form of high flow of aa high flow instead instead of of aa pressure pressure rate rate of of decrease decrease to reflect to reflect the RNP signal. the RNP signal. There There are are no significant differences. no significant differences. DETERMINATION SSD DETERMINATION SSD This is This is not not an an SSD. SSD. D2 D2 66 RNP STEP RNPSTEP DETERMINE THE REQUIRED CORE EXIT DETERMINE EXIT TEMP WOG BASIS WOG BASIS See above See above RNP DIFFERENCES/REASONS RNP DIFFERENCES/REASONS There are There are no significant significant differences. SSD SSD DETERMIN DETERMINATION ATION This This isis not not an SSD. SSD. D3 D3 1N6 1N6 RNP RNP STEPSTEP WHEN WHEN PZR PZR PRESS PRESS DECREASE DECREASES S TOTO LESS LESS THAN THAN 20002000 PSIG, PSIG, THENTHEN BLOCK BLOCK PZR PZR PRESS/HI PRESS/HI STEAMLIN STEAMLINE E DP DP SIGNALS SIGNALS IPATH-2-BD PATH-2-BD Rev. Rev.17 17 Page70 Page 70ofof110 110 I
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 40. Given
- 40. Given the following:
the following: The plant
- The
- plant isis operating operating at at 65%
65% RTP. RTP. The Feedwater
- The
- Feedwater System System isis inin aa Normal Normal lineup.
lineup.
- The
- following Main The following Feedwater Pump Main Feedwater Pump "A" A parameters parameters are are reported:
reported: Feed pump
- Feed
- pump suction suction pressure pressure isis 225225 PSIG.
PSIG.
- DP
- DP indication indication on on FS-1444A FS-1444A equatesequates to to Main Main Feedwater Feedwater Pump Pump Flow Flow of of 2850 2850 GPM.
GPM. What isis the What the expected expected response response of of the the Feedwater Feedwater System System and and what what actions actions are are required? required? MFP "A" MFP will... A will ... A. trip onon low suction pressure coincident with low low flow; enter AOP-01 0, MAIN MAIN FEEDWATER/CONDENSATE MALFUNCTION. FEEDWATER/CONDENSATE MALFUNCTION. B. trip on low suction pressure ONLY; enter AOP-01 O. 0. C. remain running; verify HCV-1459, HCV-1 459, FEEDWATER FEEDWATER HEATER BYPASS is OPEN. FCV-1 444, MFP "A" D. remain running; verify FCV-1444, A RECIRC VALVE is OPEN. 40 40
HLC-08NRC HLC-08 NRCWritten WrittenExam Exam
- 40. 059 A2.05 OO1IMAIN FEEDWATERJ2/1/3.1/3.4IROILOWIN/AINEW- 200S/FW-007 40.059 A2.05 OOlIMAINFEEDWATERl2/1/3.1/3.4IROILOW/N/A/NEW - 20081FW-007 Giventhe Given thefollowing:
following:
- The
- Theplant plantisisoperating operatingatat65% 65%RTP.RTP.
- The
- TheFeedwater FeedwaterSystem SystemisisininaaNormal Normallineup.
lineup.
- The
- Thefollowing followingMain MainFeedwater FeedwaterPump Pump"A" Aparameters parametersare arereported:
reported: Feedpump
- Feed
- pumpsuction suctionpressure pressureisis225 225 PSIG.
PSIG.
- DP DPindication indication on on FS-1444A FS-1444A equates equatestoto Main Main Feedwater FeedwaterPump Pump Flow Flowofof 2850 2850 GPM.
-
GPM. What isis the What the expected expected response response of of the the Feedwater FeedwaterSystem System and and what what actions actions areare required? required? MFP "A" MFP A will will...
...
AY trip A'1' trip on on low low suction suction pressure pressure coincident coincident with with lowlow flow; flow; enter enter AOP-01 AOP-010, 0, MAIN MAIN FEEDWATERICONDENSATE MALFUNCTION. FEEDWATERICONDENSATE MALFUNCTION. B. trip B. trip on on low low suction suction pressure pressure ONLY; ONLY; enterenter AOP-01 AOP-01 O. 0. C. remain running; C. remain running; verifyverify HCV-1459, HCV-1459, FEEDWATER FEEDWATER HEATER HEATER BYPASS BYPASS isis OPEN. OPEN. D. remain D. remain running; running; verify verify FCV-1444, FCV-1444, MFP "A" A RECIRC RECIRC VALVE is OPEN. OPEN. The correct The correct answer answer is is A. A. A: A: Correc Correctt - Sympt Symptoms oms of a FWP suction line break. Both setpoin setpointsts needed for for FWP trip.
-
FWP trip. Enter AOP-0 Enter AOP-0110. O. B: B: Incorre Incorrect ct - Need
-
Need coincid coincidentent signals signals (both low low pressu pressure re and and low low flow) to to trip trip MFP. MFP. C: C: Incorre Incorrect ct - MFP
-
MFP trips, trips, therefo re first therefore first part part is is incorre ct. HCV-1 incorrect. HCV-1459 OPENS 459 OPEN S atat 300 300 PSIG PSIG MFPMFP suction pressu suction pressure. re. HCV-1 HCV-1459 459 will will bebe OPEN OPEN in in an an attemp attemptt to to supply supply the the MFP MFP more more flow. flow. D: D: Incorre Incorrect ct - MFP
-
MFP trips, trips, therefo re first therefore first part part isis incorre ct. FCV-1 incorrect. FCV-1444 OPENS 444 OPEN S atat 1475 1475 GPM GPM andand CLOS ES at 3100 CLOSES at 3100 GPM. GPM. Exam Exam Questi Question on Numbe Number: r: 4040 Refere
Reference:
nce: APP-0 APP-007-B307-B3 and and D5; D5;AOP-0 AOP-010, 10, Page Page3.3. KA KA Statem Statement: ent: Ability Abilitytoto (a) (a) predict predictthetheimpact impacts s ofofthe thefollow followinging malfun malfunctions ctions or oroperati operations on ons on the theMFW; MFW; and and (b) (b)based basedon onthose thosepredict ions, use predictions, useproced procedures to correct, ures to correct, contro l, orormitiga control, te the mitigate theconseq uences ofofthose consequences thosemalfun malfunctions ctions ororoperati operations: ons: Ruptur Rupture e ininthe theMFW MFWsuction suctionor ordischa rge line. discharge line. History History: : New New -Writte
- n for Written forHLC-0 HLC-08 8 NRC NRCexam exam Tuesday, June 17,2008 1:21:11 PM Tuesday, June 17, 2008 1 :21 :11 PM 4646
APP-00 7-B3 APP-007-B3 ALARM ALARM FW PMP FW PMP AA LO LO sueT SUCT PRESPRESS TRIP S TRIP AUTOMATI AUTOM ACTIONS ATICC ACTIO NS 1.
- 1. Feedwater Feedw ater Pump Pump "A" trips A trips CAUSE CAUSE 1.
- 1. Loss of Loss of Conde Condensate nsate Pump Pump 2.
- 2. Condensate Conde nsate System System pipe pipe break break OBSERVAT OBSER VATIOIONS NS 1.
- 1. Pump Breake Pump Breaker Status Status Lights Lights 2.
- 2. Steam Genera Steam Generator Level Level Trends Trends 3.
- 3. Condensate Conde nsate Heade Header Pressu Pressure ACTIONS ACTIO NS
- 1. IF FW PUMP "A" A has tripped AND the Main Generator is in parallel with the grid, THEN refer to AOP-0110. 0.
- 2. IF FW PUMP "A" A has tripped AND the Unit is shutdown, THEN perform the followin following:
g:
- 1) IF required, THEN feed the S/Gs using AFW Pump(s)
- 2) IF the cause of the trip is NOT known, known, THEN dispatch personnel to inspect the pump for indications indicati ons of the cause.
DEVICE/SETP DEVIC E/SETPOINTOINTS S
- 1. PSL-1 PSL-14 497-1 /235 psig*
97-1 1235 psig
- 2. FS-144 FS-1444A 4A I/ 3100 gpm
--> *Both low pressure and flow must be presen to
*Both presentt cause pump trip.
POSSI POSSIBLE PLANT EFFECTS BLE PLANT 1.
- 1. Plant Trip REFERENCEENCES S 1.
- 1. AOP-010, 10, Main Main Feedwater/Condensate Malfunction ction 2.
- 2. CWD CWD B-i 90628, B-1906 28, Sheet Sheet 615, 615, Cable Cable M M
IAPP APP-0 -007 07 I Rev. 35 Rev. 35 I Page 16 Page 16 of 571I of 57
APP-0 APP-007-05 07-D5 ALARM ALARM FW HDR FW HDR LO LO PRES PRESS S AUTOMATI AUTOM ATICC ACTIO ACTIONS NS 11.. None Applica None Applicableble CAUSE CAUSE 1.
- 1. Loss of Loss of Feedw Feedwaterater Pump Pump 2.
- 2. Excessive Excess ive load load for for numbe number of of FW FW Pumps Pumps operati operating ng 3.
- 3. System break/l System break/leakage eakage 4.
- 4. Heater Drain Heater Drain Pump Pump trip trip 5.
- 5. Malfunction Malfun ction ofof LCV-15 LCV-1 530A, HDT LEVEL 30A, HOT LEVEL CONTR CONTROL OL VALVE VALVE OBSERVAT OBSER VATIOIONS NS 1.
- 1. Main Feedw Main Feedwater Header Pressu Pressure (PI-142 (P1-1420) 0)
- 2. Steam Generator Level Level trends ACTIONS ACTIO NS
- 1. IF a Feedwater transient is indicate indicated, d, THEN refer to AOP-01 AOP-01 O.0.
- 2. IF power level has been increased too high with one FW Pump, THEN start an additional Pump.
- 3. IF a system break has occurre occurred, d, THEN perform the followin following:
g:
- 1) Attemptt to isolate the break.
Attemp
- 2) IF the break can NOT be isolatedisolated,, THEN perform one of the follow following:
ing:
- a. conditions IF conditi ons permit, permit, THEN shutdown the unit and isolate the leak.
- b. IF the Unit can NOT be safely shutdoshutdown, THEN trip the plant and refer to EOP Network.
Networ k. DEVIC OEVICE/SETPE/SETPOINT OINTS S 1.
- 1. PSL-1 PSL-14 420 20 /I 925 psig POSSI POSSIBLE BLE PLAN PLANT T EFFECTS 1.
- 1. Plant Plant Trip Trip REFERENCE ENCES S 1.
- 1. AOP-0 AOP-0110, 0, Main Main Feedwater/Condensa ndensate te Malfunction ction 2.
- 2. CWD CWO B-1906 8-190628, 28, Sheet Sheet 602, 602, Cable Cable JJ 3.
- 3. ESR ESR 01-001 01-00184, 84, FW FW Heade Headerr Low Low Pressu Pressure re Alarm Alarm Setpoi Setpoin ntt Chang Changee 4.
- 4. EOP EOP Netwo Networ rkk IAPP APP-0 -007 07 Rev.
Rev. 3535 Page Page 34 34 of 571 of 57
Rev. Rev. 25 25 AOP-O1O AOP-010 MAIN FEEDWATER/cONDENSATE MAIN FEEDWATER/CONDENSATE MALFUNCTION MALFUNCTION Page Page 33 of of 21 21 Purpose and Purpose and Entry Entry Conditions Conditions (Page (Page 11 of of 1) 1) 1.
- 1. PURPOSE PURPOSE This procedure This procedure provides provides the the instructions instructions to to mitigate mitigate abnormal abnormal conditions in conditions in the the Main Main Feedwater Feedwater andand Condensate Condensate System.
System, including including Main FWP Main FWP trips. trips, Condensate Condensate Pump Pump trips. trips, Heater Heater Drain Drain Pump Pump trips. trips, control system control system malfunctions malfunctions andand valve valve failures. failures. 2.
- 2. ENTRY CONDITIONS ENTRY CONDITIONS Any abnormal Any abnormal condition in Main Feedwater/Condensate Feedwater/Condensate system resulting in aa system resulting in system flow flow transient.
transient, with the the exception exception of of Instrument Failures. Instrument
- END -
- -
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 41. Given
- 41. Given the the following:
following:
- AA Reactor
- ReactorTrip Trip has has occurred occurred and and the the crew crew has has entered entered PATH-1.
PATH-i.
- All
- SIG levels All S/G levels indicate indicate Off-Scale Off-Scale LOW.
LOW. The SDAFW
- The
- SDAFW Pump Pump isis running.
running. FCV-6416, SDAFW
- FCV-6416,
- SDAFW PUMP PUMP DISCH DISCH FLOW FLOW VALVE VALVE isis CLOSED.
CLOSED. MDAFW Pump
- MDAFW
- Pump "A" A has has tripped.
tripped. MDAFW Pump
- MDAFW
- Pump "8" B flow flow indicates indicates 200 200 GPM.
GPM. Which ONE Which ONE (1) (1) of the following of the following describes describes the the AFW AFW system system status status inin support support of of minimum minimum Heat Heat Sink requirements? Sink requirements? FCV-641 6 isis... FCV-6416 ... A. NOT A. NOT in in its its intended intended position position and and must must bebe throttled throttled OPEN OPEN to to meet meet minimum minimum heat heat sink sink requirements. requirements. B. NOT B. NOT in in its intended position, but minimum heat sink requirements its intended requirements are met by MDAFW MDAFW Pump "B". Pump B. C. in C. in its its intended intended position; FCV-1425,FCV-1 425, AFW PUMP B DISCH FLOW VALVE must be throttled OPEN to OPEN to establish establish minimum heat sink requirements. requirements. D. in D. in its intended position; minimum heat sink requirements are met by MDAFW Pump "B". B. 41 41
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 41. 061 A3.01 41.061 00l/AFW/21114.2/4.2JROIH[GHIN/AJRNPAUDIT A3.01 001lAFW/2/114.2/4.2IRO/HIGH/N/A/RNP AUDIT- 2001lAFW-008
- 2001/AJW-008 Given the Given the following:
following: Reactor Trip
- AA Reactor
- Trip has occurred and has occurred and thethe crew crew has entered PATH-1.
has entered PATH-i.
- All
- SIG levels All S/G levels indicate indicate Off-Scale Off-Scale LOW.LOW.
SDAFW Pump The SDAFW
- The
- running.
Pump isis running. FCV-6416, SDAFW
- FCV-6416,
- SDAFW PUMP PUMP DISCH DISCH FLOWFLOW VALVEVALVE isis CLOSED.
CLOSED. MDAFW Pump
- MDAFW
- Pump "A" has tripped.
A has tripped. MDAFW Pump
- MDAFW
- Pump "B" B flow indicates 200 flow indicates 200 GPM.
GPM. Which ONE Which ONE (1) (1) of the following of the following describes describes the the AFW AFW system system status status in in support support of of minimum minimum HeatHeat Sink requirements Sink requirements? ? FCV-6416 is FCV-6416 is...
...
A NOT in its intended position and must be throttled OPEN to meet minimum heat sink A'I requirements. requirements. B. NOT in its intended position, but minimum heat sink requirements are met by MDAFW Pump "B". B. C. in its intended position; FCV-1425, FCV-1 425, AFW PUMP B DISCH FLOW VALVE must be throttled OPEN to establish minimum heat sink requirements. requirements. D. in its intended position; minimum heat sink requirements are met by MDAFW Pump "B". B. The correct answer is A. A: A: Correct - - When S/G levels decrease following a trip, the normally normally open SDAFW SDAFW PumpPump discharge valve should throttle to maintain 500 GPM. It should NOT be closed, and and minimum minimum heat heat sink sink requirements for SIG S/G levels levels off-scale off-scale low low are are at at least least 300 300 GPM G PM total. B: B: Incorrect Incorrect - Minimum
- Minimum heat heat sink sink will will NOT NOT be met until be met until AFW AFW flow flow is is increased increased toto at at least least 300 300 GPM.
GPM. C: C: Incorrect Incorrect - FCV-6416
- FCV-6416 should should bebe OPEN OPEN maintaining maintaining 500 500 GPM.FCV-1 GPM.FCV-1425 could be 425 could be throttled throttled to to meet meet minimum minimum heat heat sink, sink, but but FCV-641 FCV-6416 6 isis NOT NOT in in its its intended intended position.
position. D: D: Incorrect Incorrect - FCV-6416
- FCV-6416 should should bebe OPEN OPEN maintaining maintaining 500 500 GPM.
GPM. Minimum Minimum heatheat sink sink is is NOT NOT met met with with ONLY ONLY 200 200 GPM GPM flow.flow. Tuesday,Jun Tuesday, June 17,2008 e 17, 2008 1:21:11 1:21 :11 PM PM 47 47
HLC-08 NRC Written Exam HLC-08 NRC Exam Exam Question Exam Number: 41 Question Number: 41 Heat Sink
Reference:
Heat
Reference:
Sink CSFST, SO-042, AFW, CSFST, SD-042, Page 15. AFW, Page 15. Statement: Ability KA Statement: KA Ability to operation of monitor automatic operation to monitor of the the AFW, AFW, including: AFW startup including: AFW startup and and flows. History:
- Tuesday, Tuesday, June June 17, 17, 20081:21:11 2008 1:21:11 PM PM 48
HEATSINK CSF-3,HEAT CSF-3, SINK ENTER ENTER
~+
NO NO NO .AL FW FLOW SIGs GREATER THAN 300 GPM CR0.2 E6 YES YES NO NO NO NO PRESS IN ALL S/Gs LESS TI-IAN 1085 PSIG RED RED GO TO GOTO FRP-H.1 FRP-H.1 YELLOW YELLOW YELLOW YELLOW YELLOW YELLOW YELLOW YELLOW GOTO GO TO GO GOTOTO GOTO GO TO GO TO GOTO GREEN FRP-H.5 FRP-H.5 FRP-H.4 FRP-H.4 FRP-H.2 FRP-H.2 GREEN FRP-H.3 FRP-H.3 CSF-SAT CSF-SAT J ICSFST CSFST Rev.44 Rev. Page55ofof9 Page 91
SD-042 SD-042 AFWSYSTEM AFW SYSTEM 3.3 3.3 ControlValves Control Valves TheAFW The AFWsystem systemcontains containsan automaticelectro-hydraulic anautomatic electro-hydraulicflow flowcontrol controlvalve valvefor foreach each MDAFWpump MDAFW pumpand andthetheSDAFW SDAFWpump. pump. Each Eachvalve's valvescontroller controllerisislocated locatedininthe thecontrol control room and all other compo nents are room and all other components are located in proximitylocated in proxim itytototheir theirrespective respectivepump.pump. These These valvesand valves andtheir their associated associatedcontrols controlsare areused usedtotoset setAFW AFWpump pumpdischarge dischargeflowrate flowrateand and automatically maintain automatically maintainthe therate rateasas S/G SIGpressure pressurevaries. varies. TheseThesevalves valvesprovide provideflow flow control for control for the the AFW AFW system system and and NPSH NPSH (anti-cavitation) (anti-cavitation) protection protection forfor the the pumps. pumps. These control These control valves valves have have electro-hydraulic electro-hydraulic actuators actuators whichwhich can can be be automatically automatically positioned based positioned based upon upon thethe respective respective AFW AFW pumppump discharge discharge flow.flow. AA local local manual manual operator operator isis provided provided for for operating operating the the control control valve valve in in the the event event that that the the contro l system fails. The contro control system fails. The control system can l system can also also be be operated operated in in manual manual fromfrom the the RTGB. If RTGB. If RCS RCS temperature temperature isis greater greater than than 350°F, 350°F, then then using using manual manual places places thethe plant plant inin a Tech Specs LCO action statem a Tech Specs LCO action statement (3.7.4). ent (3.7.4). WithWith normal normal plant plant conditions, manual isis conditions, manual used to used fill the to fill the Steam Steam Generators. Generators. MDAFW pump MDAFW pump discharge discharge flow control control valves (1424 and 1425) 1425) control control the flow flow from from each MDAF each MDAFW pump to W pump to the SIGs. S/Gs. These normally closed valves begin to open when normally when thethe MDAFW pumps MDAFW pumps are are started. started. The valves "fail-closed" fail-closed on loss of electric power or or loss loss of control of control signal. signal. FCV-1424 FCV-1424 is poweredpowered from IB#2 and FCV-1425 FCV-1425 from IB#3. IB#3. When When the RCS the RCS temperature temperature is > 350°F, each control control valve is norma normally lly in AUTO and set at 325 325 and set at gpm. When gpm. When the RCS the RCS temper temperatureature is =s 350°F, these contro controllers llers shall be in AutoAuto and and set set to a flow rate of to a flow rate of 100 gpm 100 gpm to ensure reliabl e reliable flow contro controll as system pressu pressure varies. re varies.
'---? SDAF SDAFW W pump pump discha rge flow contro discharge controll valve (6416) contro controls ls the flow from the the SDAF SDAFW W pump to the S/Gs. pump to the S/Gs. This This norma normally lly open open valve valve begins begins to to adjust when when thethe SDAF SDAFW pump isis W pump started started.. This This valve valve will will fail-o pen on "fail-open" on aa loss loss of of electric electrical power or al power or loss loss ofof the the contro controll signal. FCV-6 416 signal. FCV-6416 isis powere powered d from from LP-26 LP-26.. In In modes modes 1, 1, 22 and and 3, 3, FCV-6 FCV-6416 is normally 416 is norma lly in AUTO and set at in AUTO and set at 500 gpm. 500 gpm. 4.0 4.0 INSTR UMENTATION INSTRUMENTATION 4.1 4.1 AFW AFW Flow Flow Indicat ion System Indication System There There are are three three dual dual flow flow edge edgemeters meters 5000-500 gpm, gpm, one oneper per S/G S/G for for the the MDAF MDAFW
-
W pumps and pumps and SDAFW SDAF W pump, pump, located locatedon onRTGB RTGB. . SIG S/G 11AFW AFWFlow Flow -Motor MotorDriven Driven, , FI-142 FI-1425A; 5A; Steam SteamDriven Driven, FI-1426A
, FI-142
-
6A S/G S/G22AFW AFWFlow Flow -Motor MotorDriven Driven, , FI-142 FI-1425B; 5B; Steam SteamDriven Driven, FI-1426B
, FI-142
-
6B S/G S/G33AFW AFWFlow Flow -Motor MotorDriven Driven, , FI-142 FI-1425C; 5C; Steam SteamDriven Driven, FI-1426C
, FI-142
-
6C AFW AFW Page Page1515ofof3838 Revision1111 Revision INFOR INFORMATION MATION USE USEONLY ONLY
QUESTIONS REPORT for AUDIT ),o(
)CJo{
001/Hill/I 061 A2.05 0011////1// Given the following conditions:
- A reactor trip has occurred.
- The crew has entered PATH..;1 PATH-i and is preparing to reset SPDS and transition to the appropriate procedure.
- All SG levels indicate Off-Scale Low
- The SDAFW Pump is running with discharge valve FCV-6416 FCV-641 6 closed.
A
* "A" MDAFW Pump tripped.
* "8" B MDAFW Pump flow indicates 200 GPM with discharge valve FCV-1425 FCV-i 425 open.
Which ONE (1) of the following describes the event in progress and the action required? A'I FCV-6416 AY FCV-641 6 has failed and must be throttled open to meet minimum heat sink requirements. 8. B. FCV-6416 has failed and should be opened, but minimum heat sink requiremnents are met by 18" B MDAFW Pump. C. FCV-6416 is in its intended position; FCV-1425 must be throttled open to establish minimum heat sink requirements. D. FCV-6416 is in its intended position; minimum heat sink requirements are met by B MDAFW Pump "8" A is correct. When SG levels decrease following a trip, the normally open SDAFW discharge valve should throttle to maintain SG levels. It should not be closed, and minimum heat sink requirement for SG levels off-scale low are at least 300 gpm total. Common Question 018 Tier 2 Group 1 1 K/A Importance Rating - RO 3.1 1 KIA - / SRO 3.1 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW: and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: Automatic control malfunction. Reference(s) - Heat Sink CSFST, AFW SD
-
Proposed References to be provided to applicants during examination - None - Learning Objective - - Question Source - New - Question History - - Question Cognitive Level - Comprehension
-
10 CFR Part 55 Content - 41/43 - 4 1/43 Comments - - Category 1: Category 2: Category 3: Category 4: Category 5: Category 6: Category 7: Category 8: 2008 12:56:47 PM Tuesday, June 17, 200812:56:47 1
HLC-08 HLC-08 NRCNRC Written Written Exam Exam
- 42. Which
- 42. Which ONE ONE (1) of the (1) of the following following describes describes the the power power supplies supplies for for the Circulating Water the Circulating Water Pumps?
Pumps? A. CW A. CW Pump Pump "A" A -- 4KV Bus 4KV Bus 11 OW Pump B CW Pump "B" - - 4KV Bus 4KV Bus 22 CW Pump CW Pump "C" C - - 4KV Bus 4KV Bus 33 B. CW B. CW Pump "A" Pump 4KV Bus A - 4KV
- Bus 11 OW CW Pump "B" Pump B - 4KV
- 4KV Bus Bus 33 CW CW Pump 4KV Bus C - 4KV Pump "C" - Bus 55 OW Pump C. CW Pump "A" A - 4KV Bus 2
-
OW CW Pump "B" B - 4KV Bus 3
-
CW Pump C - 4KV Bus Pump "C" - Bus 4 OW D. CW Pump A - 4KV Bus 11 "A" - CW Pump "B" - 4KV Bus 4 B - CW Pump C - 4KV Bus 5 "C" - 42 42
HLC-08 NRC HLC-08 Written Exam NRCWritten Exam
- 42. 062
- 42. 062K2.01 K2.01OOllAC ELECTRICALDIST/2i1/3.3/3.4fRO/LOW/NINNEW 001/ACELECTRICAL DIST/211/3.3/3.4/ROILOW/N/AINEW- 2008/CW-007
- 2008/CW-007 WhichONE Which ONE (1) ofthe (1) of thefollowing describesthe following describes the power powersupplies suppliesfor forthe the Circulating Circulating Water WaterPumps?
Pumps? A. CW A. CW Pump Pump "A" A -- 4KV Bus 11 4KV Bus CW Pump CW Pump "B" B -- 4KV Bus 4KV Bus 22 CW Pump CW Pump "C" - C - 4KV Bus 4KV Bus 33 B. CW B. CW Pump Pump "A" A - 4KV
- 4KV BusBus 11 CW Pump CW Pump "B" B - 4KV
- 4KV BusBus 33 CW Pump "c" CW Pump C - 4KV
- 4KV Bus Bus 55 C. CW C. CW Pump Pump "A" A - 4KV
- 4KV BusBus 22 CW Pump CW Pump "B" B - 4KV
- 4KV BusBus 33 CW Pump CW Pump "C" C - 4KV
- 4KV Bus Bus 44 D
D~ CW Pump CW Pump "A" A - - 4KV Bus 4KV Bus 11 CW CW PumpPump "B" B - - 4KV Bus 4KV Bus 44 CW Pump CW Pump "C" C - - 4KV Bus 4KV Bus 55 The correct The correct answer answer is is O. D. A: Incorrect A: Incorrect - CW
- CW Pump Pump "A" A is is powered powered from 4KV Bus Bus 1, 1, CW CW Pump Pump "B" B is is powered powered from from 4KV 4KV Bus 4, CW Pump "C" C is powered from 4KV Bus 5.
B: Incorrect B: Incorrect - CW
- CW Pump "A" A is powered from 4KV Bus 1, CW Pump "B" B is powered from 4KV 4KV Bus 4, CW Pump "C" C is powered from 4KV Bus 5.
C: Incorrect C: Incorrect - CW Pump "A"
- A is powered from 4KV Bus 11,, CW Pump "B" B is powered from 4KV 4KV Bus Bus 4, CW Pump C"C" is powered from 4KV Bus 5.
D: 0: Correct Correct- - CW CW Pump A "A" is powered from 4KV Bus 1, 1, CW Pump B "B" is powered from 4KV 4KV Bus Bus 4, CW Pump C "G" is powered from 4KV Bus Bus 5. Exam Exam Question Number: 42
Reference:
Reference:
EDP-OO1, EOP-001, Pages Pages 4, 4,77 and 8; SD-057, and 8; SO-057, CW, GW, Page Page 10. 10. KA Statement: KA Statement: Knowledge Knowledge of of bus bus power power supplies supplies to to the the following: following: Major Major system system loads. loads. History: History: New New - Written
-
Written for for HLC-08 HLC-08 NRC NRC Exam. Exam.
- Tuesday, Tuesday,June June17, 17,2008 1:21:12 PM 20081:21:12 PM 49 49
1.0 4160V AC Buss No.1 416OVACBussNo.1 Location: 4160V Switchgear Room Power Supply: As per RTGB Line Up Loads: Cubicle Breaker CWD Reactor Coolant Pump "A" NA 1 1 52/1 109
.~ Circulating Water Pump "A" NA 2 52/2 811 Feedwater Pump "A" As 3 52/3 615 Station Service Transformer 2B 4 52/4 933 Heater Drain Pump "A" As 5 52/5 625 Condensate Pump "A' A 6 52/6 605 Unit Aux to 4KV Bus 1 1 7 52/7 926 PTs and Fan Equipment 8 N/A 948 PTs and Fan Equipment and Metering 9 N/A*
N/A 948 4KV Bus 11 - 2 Tie
- 10 52/10 928 IEDP-001 Rev. 4 Page 4 of 81 8
4.0 4.0 4160V AC 4160V AC BUSS NO.4 BUSS NO.4 41 60V Switchgear Room Location: 4160V Location: Room Power Supply: Power per RTGS Supply: As per Line Up RTGB Line Up Loads: Cubicle Sreaker Breaker CWD Bus 3 - 4 Tie 4KV Sus - 19 19 52/19 931 Bus 4 Unit Aux to 4KV Sus 20 52/20 930 PTs and Fan Equipment 21 N/A 949 Condensate Pump "S" B 22 52/22 606
~ Circulating Water Pump "S" B 23 52/23 813 Feed to 4KV SusBus 5 24 52/24 1344 Heater Drain Pump "S" B 25 52/25 626 Feedwater Pump "S" B 26 52/26 620 Reactor Coolant Pump "S" B 27 52/27 101 Station Service Transformer 20 2D 28 52/28 1041 IEDP-001 EOP-001 Rev.
Rev. 44 Page Page 77 of of 881
5.0 4160V AC BUSS NO.5 st Level, 1st Location: Turbine Bldg., 1 Grid Location 3B Power Supply: As per RTGB Line Up Loads: Cubicle Breaker CWD 4KV Bus 4 to 4KV Bus 5 29 N/A 1344 1344 PTs and Control Power Transformer 30 N/A N/A SPARE 31 52/31 N/A Station Service Transformer 2E 32 52/32 1399
~ Circulating Water Pump "C"
- C 33 52/33 815 SPARE 34 52/34 52134 N/A IEDP-001 Rev. 4 8 81 Page 8 of 8
SD-057 CCULATIIS[G WATER SYSTEM CIRCULATING With one CWP in operation, it will pass approximately 200,000 gpm. Consequently, hypochlorite flow per intake bay will increase as the number of the amount of sodium hypochiorite CWPs in service decreases. When used to chlorinate the SW system, the "A" A pump injects hypochlorite hypochiorite solution 30 SW headers downstream of the automatic strainers. The amount and into the 30" frequency of injection is dependent upon SW system flow rates and is determined by, by Chemistry personnel. 3.0 COMPONENT DESCRIPTION 3.1 Circulating Water Pumps Manufacturer Westinghouse Type Vertical Model 90 MT 90MT Total Head 35.3 feet Flow - 3 pumps
- 160,700 GPM each Total Flow - 3 pumps
- 482,100 GPM Motor Rating 1750 HP RPM 220 There are three identical vertical single-stage CWPs. For three pump operation, they are designed to provide approximately 160,000 gpm each with a 35 ft. TDH at a peak efficiency of 85 %. Based upon the CW system resistance, single pump operation can 85%.
provide approximately 200,000 gpm with a 22.5 ft TDH at an efficiency of 72 %. 72%. Gland seal and bearing cooling water is supplied (15 gpm) to each CWP from the SW system and returns to Lake Robinson. A backup supply is available from the Unit No. 11 potable water. Water is drawn from Lake Robinson and passes through the traveling screens. Two concrete walls separate the intake into three bays. A single CWP is located in each bay. The intake structure is Seismic Class I and is therefore not subject to collapse under the design earthquake loading.
~ CWP "A" -
A is powered from 4160V Bus No. No.1, 1, CWP "B"B is powered from 4160V Bus No. No.4 4 and CWP "C" C is powered from 4160V Bus No. No.5.5. cw CW of 28 Page 10 of28 Revision 44 INFORMATION USE ONLY
HLC-08 NRC HLC-08 NRC Written ExamExam
- 43. ONE
- 43. ONE (1)
(1) minute minute following following aa Reactor Reactor Trip, Trip, BOTH BOTH 52/8, 52/8, SOUTH SOUTH OCBOCB and and 52/9, 52/9, NORTH NORTH OCB OCB breakers remain breakers remain CLOSED. CLOSED. ONE (1) Which ONE (1) of of the the following following describes describes the failure that caused caused BOTH BOTH of these breakers breakers to remain CLOSED? remain CLOSED? A. Loss of DC Bus "A".A. B. Loss of DC Bus "B".B. C. Loss of the operating Battery Charger for DC Bus "A". A. D. Loss of the operating Battery Charger for DC Bus "B". B. 43 43
HLC-08NRC HLC-08 NRCWritten WrittenExam Exam
- 43. 063 K3.02 001/DC ELECT DIST/2/l/3.5 /3.7IROILOW
- 43. 063 K3.02 OOllDC ELECT DIST/21113.5/3.7IROfLOWfNINRNP IN/AJRNPAUDITAUDIT- 2001lKVAC-006
- 2001/KVAC-006 ONE(1)
ONE (1)minute minutefollowing followingaaReactor ReactorTrip, Trip,BOTH BOTH52/8, 52/8,SOUTH SOUTHOCB OCBandand52/9, 52/9, NORTH NORTHOCB0GB breakersremain breakers remainCLOSED. CLOSED. WhichONE Which ONE(1) (1)ofofthe thefollowing followingdescribes describesthe thefailure failurethat thatcaused causedBOTH BOTH ofofthese thesebreakers breakerstoto remain CLOSED? remain CLOSED? A. Loss A. Loss ofofDC DC Bus Bus"A".A. B Loss BY' Loss of of DCDC BusBus "B". B. C. Loss C. Loss of the operating of the operating Battery Battery Charger Charger forfor DC DC BusBus "A". A. D. Loss D. Loss ofof the the operating operating Battery Battery Charger Charger forfor DC DC Bus Bus "B". B. The correct The correct answer answer isis B. B. A: Incorrect A: Incorrect - OCB
- OCB 521852/8 and and OCB OCB 52/952/9 receive receive their their control control power power from from DCDC Bus Bus B.
B. B: Correct B: Correct - - 0GB 52/8 OCB 52/8 and and OCB OCB 52/9 52/9 receive receive their their control control power power from from DCDC Bus Bus BB C: Incorrect C: Incorrect - Loss Loss of the operating of the operating Battery Charger Charger for DC Bus B does NOT de-energize de-energize the
-
the Bus. Bus. D: Incorrect D: Incorrect - Loss
- Loss ofof the the operating operating Battery Charger Charger for DC Bus B does NOT de-energize de-energize the the Bus.
Bus. Exam Exam Questi Question on Numb Number: er: 43 Refere nce: SD-03
Reference:
SD-039, 9, KVAC, PagePage 11;11; EPP-2 7, Pages 3-4; EPP-2 EPP-27, EPP-27 7 BD, Page 4. KA KA Statem ent: Knowl Statement: Knowledge of the edge of the effect effect that a loss loss oror malfun ction of malfunction of the the DC DC electric electrical system al system will will have have on on the the follow ing: Compo following: Componentsnents using using DCDC contro controll power. power. Histor y: History:
- Tuesday, Tuesday,June June17, 17,2008 1:21:12 PM 20081:21:12 PM 5050
SD-039 SD-039 23 0/4KV 23014 KVACAC ELECTRICAL ELECTRICALSYSTEM SYSTEM
~ Thetwo The twogenerator generatorbreakers breakers (52/8 (52L8 and and52/9) receive receive 125VDC 125VDC control controlpower powerfromfrom "B"
~Station Battery. The Theremairung remaining230KV 230KVbreakers breakersreceive receive 125VDC 125VDC control power fromaa control power from battery in the 230KV Switchyard battery in the 230KV Switchyard Building. Building.
OPEN: In OPEN: Inorder order toto receive receive an anopen openindication indicationon onthe the RTGB RTGB all allthree phases of three phases ofthe the OCB OCB must be open. must be open. The The open open indication indication isis fed fed from from three three (3)(3) contacts contacts that that are are wired wired inin series. series. CLOSED: The CLOSED: The closed closed indication indication isis fed fed from from parallel parallel contacts contacts from from allall three three phases, phases, thus if only one phase were thus if only one phase were to close the to close the closed closed indication indication wouldwould occur. occur. ThereThere isis aa protection scheme protection scheme that that monitors monitors the difference between the difference between the the 33 phases. phases. If If only only oneone phase phase were to close the delta between the were to close the delta between the phases would be phases would be sensed sensed and and an an open open single single to to the the OCB would OCB would be be generated generated within within 33 cycles. cycles. Technical Information Technical Information relative relative toto the the OCBs OCBs is is available available at at the the Transmission Transmission Department Department Substation Maintenance Substation Maintenance Group who Group who maintains this equipment. this equipment. 3.5 3.5 Unit Auxiliary Unit Auxiliary Transformer MFG MFG Westinghouse Westinghouse TYPE TYPE FOA RATING RATING Primary Windings: H= 44MVA, 3PHASE, 60HZ, FOA, 55'C 55CC Rise, 49.2MVA FOA, 65'C 65CC Rise 21.95/21.42/ 21.95/21.42120.90/20.38/19.85KV 20.90/20.38/19.85KV SET ON 20.38KV Secondary Windings: X,Y= 22MVA FOA 55CC 55'C Rise, 24.64OMVA 24.640MVA 65t 65'C Rise, 4. 160KV 160KV Voltage Voltage ratioratio & connection 20.38 20.38 KV delta delta - 22 half
- half capacity capacity 4.16 4.16 KV KV Wye Wye The The UATUAT isis aa single, single, three-phase three-phase step-down step-down transformer.
transformer. The The input input to to this this transformer transformer isis directly directly fromfrom thethe IPB IPB between between the the main main generator generator and and thethe main main transformer; transformer; the the voltage is reduced to approximatel voltage is reduced to approximately 4160 volts. Thisy 4160 volts. This transformer transformer is is used used when when the the unit unit isis on-line on-line to to carry carry plant plant auxiliary auxiliary load. load. ItIt could could also also bebe used used with with the the unit unit shutdown shutdown provided provided the the main main generator generator leads leads were were disconnected disconnected.. This This transformer transformer isis filled filled with with oiloil to provide to provide aa medium medium for for cooling cooling thethe windings. windings. There There are are two two oil-circulatin oil-circulating pumps g pumps that that circulate circulate the the oil oil from from thethe transformer transformer through through cooling cooling coils coils and and backback toto the the transformer. transformer. Each Each set set of ofcooling cooling coils coils has has three three fans fans that that move move air air through through the the cooling cooling coils coils toto remove remove the heat generated by the windings. When this transformer the heat generated by the windings. When this transformer isis in-service, in-service, itit normally normally supplies suppliespower powerto to 4160V 4160V Buses Buses 1,1, 2,2, 4,4, &
& 5.5.
KVAC KVAC Page Page1111ofof39 39 Revision1414 Revision INFOR INFORMATION MATION USE USE ONLY ONLY
Since an Since an SI does not SI does not occur occur onon aa loss loss of DC Bus of DC Bus B, B, entry entry to the procedure to the procedure will will bebe via via EPP-4, EPP-4, Reactor Reactor Trip. Trip. Certain Certain actions will actions will be completed while be completed while inin EPP-4 EPP-4 via Foldout A. via Foldout These actions A. These actions are: are:
- a. Transfer of
- a. Transfer Instrument Bus of Instrument Bus 33 toto MCC-8.
MCC-8.
- b. Shutdown of
- b. Shutdown Emergency Diesel of Emergency Diesel B. B.
STEP SPECIFIC STEP SPECIFIC DESCRIPTION DESCRIPTION AND AND RNP RNP DIFFERENCES DIFFERENCES The following The following pagespages will will provide provide thethe RNP RNP step step number number and and the STEP basis the STEP basis for for each each step step where where applicable. applicable. This This isis aa Robinson Robinson specificspecific EOP, EOP, therefore therefore there there isis no corresponding ERG no corresponding ERG series series of steps. This of steps. This procedure procedure covers covers an an event event that is that not covered is not covered by ERGs (Loss the ERGs by the (Loss of of DC). DC). TheThe entire entire procedure procedure may may bebe categorized categorized as as anan SSD SSD 10.10. The The steps steps within this within procedure will this procedure will not interfere with not interfere performance of with performance the EOPs of the EOPs sincesince this this procedure procedure does does notnot consider consider anyany other other event in event in progress progress other other than than aa loss loss of of DCDC Bus B. The Bus "B". The loss loss of of aa DC DC BusBus atat RNP RNP is is considered considered "beyond beyond design design basis" basis and is not and not analyzed analyzed in in the the U UFSAIR. FSAR. RNP RNP BASIS BASIS STEP STEP 1 STEP BASIS This step provides transitional direction for the subsequent step. If the Loss of DC occurred from an at power condition, the main generator output Circuit Breakers, 52/8 and 52/9, will be closed and action will be necessary to trip them. If the event started from a low power or shutdown condition the subsequent step will not be necessary. 2 STEP BASIS Onaloss On a loss of DC Bus B Bthethe North and South Generator Circuit Breakers, Breakers,_52 52/8/8and52/9, and 52/9, will receive a lockout signal. Due to the loss of DC these breakers will not open. This in turn causes backup relaYing relaying
. to open other breakers to isolate the generator. In order to accomplish actions later in the procedure and to allow reclosing the backup Circuit Breakers these breakers must be opened.
There are no local controls that will open the breakers without control power. There is, however, a maintenance control (for testing) at each phase of the Circuit Breakers. This feature will trip the Circuit Breakers one phase at a time. Since this function was not intended to be performed by Site Personnel the Load Dispatcher will be notified to request assistance in opening the breakers. 3 STEP BASIS This continuous action step is provided to initiate efforts to repair the faulted DC Bus. It is placed early in the procedure so that efforts can be be made made to contact Maintenance personnel. personnel. The high level level step step provides provides direction direction to diagnose the cause and and provides provides transitional guidance.guidance. There are are three three possible failure mechanisms mechanisms that that are are the the most most likely likely causes: causes:
** Fault Fault onon BB Battery Battery
- Fault Fault onon BB Battery Battery BusBus
** Fault on MCC-6 Fault on MCC-6 The failure, The failure, or tripping, or tripping, of of the the in-service in-service Battery Battery Charger, Charger, isis not not aa likely likely cause cause of of the the loss loss of of DC DC since since warning warning would would be be provided provided via via an an annunciator annunciator with with ample ample time time for for Operator Operator action action toto transfer transfer the the Chargers.
Chargers. N4 N4 STEP STEP BASISBASIS The The notenote reminds reminds the the Operator Operator that that AFW AFW Pump Pump BB willwill not not be be available available due due to to aa loss loss ofof Control Control Power. Power. 44 STEP STEP BASISBASIS This This stepstep assures assures the the maintenance maintenance of of the the secondary secondary heat heat sink sink byby maintaining maintaining S/G S/G level level at at the the standard standard range range used used throughout throughout the the EOP EOP Network. Network. In In this case AFW this case AFW PumpPump AA and and the the SDAFW SDAFW pump pump areare specified specified since since AFW AFW Pump Pump BB isis lost. lost. IEPP-27-BD EPP-27-BD I Rev Rev 10 10 I Page 44 of Page of 9 91I
Rev. Rev. 10 10 EPP-27 EPP-27 LOSS OF LOSS OF DC DC BUS BUS "B" B
.. _.. -"._-_." .... -._--
Page Page 33 of of 29 29 Purpose and Purpose and Entry Entry Conditions Conditions (Page (Page 11 of of 1) 1) 1.
- 1. PURPOSE PURPOSE The purpose The purpose of this procedure of this procedure is is to to provide provide instructions instructions in in the the
~ . event of event of aa loss loss of DC Bus of DC Bus B.B. This This procedureprocedure is is applicable' applicable anytime anytime the EPPs the EPPs are are applicable applicable (greater (greater than than 350°F). 350°F). 2.
- 2. ENTRY CONDITIONS ENTRY CONDITIONS This procedure This procedure is entered on is entered on indication indication of of aa loss loss of of DC DC Bus Bus B B from from the following the following procedures:
EPP-4. Reactor Trip Response
- a. EPP-4.
a.
- b. EPP-7.
- b. EPP-7. SI Termination
- END -
- -
Rev. 10 EPP-27 LOSS OF DC BUS "B" B Page 44 of 29 STEP H INSTRUCTIONS I I RESPONSE NOT OBTAINED I
- 1. Check Electrical Status At Time Go To Step 3.
DC Power Was Lost - AUXILIARIES
-
ON THE UNIT AUXILIARY TRANSFORMER
- 2. Inform Load Dispatcher Of The Following:
- a. AA loss of DC Control Power has occurred
~ b. Switchyard OCBs 52/8 AND 52/9 have failed to trip
- c. Backup relaying has caused a North Bus Lock Out which tripped the following Switchyard Circuit Breakers:
- 52/3. ROCKINGHAM 230KV
- 52/6.
52/6, #1 230-115KV BANK 230KV 23 0KV
- 52/7. DARLINGTON SCPSA 230KV
- 52/12. DARLINGTON COUNTY PLANT SOUTH 230KV
- 52/14.
52/14, DARLINGTON COUNTY PLANT NORTH 230KV
- d. Request that Load Dispatcher send a Maintenance Crew to locally trip OCBs 52/8 Q AND 52/9
** 3. Check The Cause Of The DC Bus WHEN the cause is determined.
determined, Failure - KNOWN
-
THEN notify Maintenance to correct the problem. Observe the NOTE prior to Step 44 and Go To Step 4.
QUESTIONS REPORT) QUESTIONS REPQRT for AUDIT ('2 forAUDIT 6 0( (2OoL) 1.1. 062 062 Kl.03 K1.03 001lEDPI062 OO1IEDP/062 K1.03/3.5 K1.03/3.5 14.0/3/18/03
/ 4.0/3/18/03 ROM/COMPREHENSION//!
ROM/COMPREHENSION/// Given the Given the following following plant plant conditions: conditions: One minute One minute following following aa reactor reactor trip, trip, BOTH BOTH 230KV 230KV generator generator output output breakers breakers remain remain closed closed Which ONE Which ONE (1) (1) ofof the following describes the following describes thethe failure failure that that caused caused both both ofof these these breakers to remain breakers to remain closed? closed? A. Loss of A. Loss of "A" A DC DC BusBus B! B~ Loss of Loss B DC of "B" DC BusBus Loss of C. Los~ of the running running Battery Charger Charger for the "A" A DC Bus D. Loss of the running Battery Charger for the "B" B DC Bus B is correct.
- a. OCB 52/8 and OCB 52/9 re~eive receive their control power from plant DC. Comes from from DC Bus "B". B.
- c. Most 230KV breakers receive their control power from a battery in the switchyard.
OCB52/8 and OCB 52/9 receive their control power from DC Bus "B". B.
- d. If there is a failure of 86P, breakers would still open on 86BU Common Question 019 Tier 2 Group 1 1 KIA Importance Rating - RO 3.5 / SRO 3.5 K/A -
Knowledge of the physical connections and/or cause-effect relationships between the AC distribution system and the following systems: DC DC distribution. Reference(s) - KVAC SD - SO Proposed Proposed References to be be provided provided to to applicants during during examination examination - None
-
None Learning Objective Learning Objective - - Question Question SourceSource - Modified
-
Modified Bank Bank Question History Question History - KVACO1O- - KVAC010-6 6 Question Question Cognitive Cognitive Level Level- Comprehens
- Comprehension ion 10 CFR Part 10 CFR Part 55 55 Content Content 41 Comments Comments - -
Category Category 1:1: EDP EDP Category 2:2: 062 Category 062 Ki Kl.03
.03 Category Category 3:3: 3.5 4.0 3.5 /14.0 Category 4:
Category 4: 3/18/03 ROM 3/18/03 ROM Category Category 5:5: COMPREHE COMPREHENSION NSION Category 6:6: Category Category Category7:7: Category 8:8: Category
- Tuesday, Tuesday, June 10,2008 June 10, 20089:30:52 9:30:52AM AM 1
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 44. Given
- 44. Given the the following:
following: The plant
- The
- plant isis operating operating atat 100%
100% RTP. RTP. 480V Bus
- 480V
- Bus E-1 E-l Main Main Breaker Breaker trips trips on on overcurrent.
overcurrent. EDG "A"
- EDG
- A starts starts and and re-energizes re-energizes 480V 480V Bus Bus E-1.
E-1. The EDG
- The
- EDG "A" Jacket Water A Jacket Water Coolant Coolant PumpPump shaft shaft shears shears during during EDG EDG start.
start. APP-Cl 0-F2,
- APP-01
- 0-F2, EDGEDG AA COOL COOL WTR WTR HIILOHI/LO TEMP TEMP illuminates.
illuminates. APP-Cl 0-A2,
- APP-01
- 0-A2, EDGEDG A A TROUBLE TROUBLE illuminates.
illuminates. Which ONE Which ONE (1) (1) of the following of the following isis the the impact impact of of the the pump pump shaft shaft failure failure on on EDG EDG Automatic Automatic operation? operation? EDG "A"A will will....
....
A. shutdown when coolant water pressure decreases to 12 12 PSIG. B. shutdown when coolant water temperature reaches 205 OF. °F. C. continue to operate due to EDG engine trips being defeated. D. continue to operate due to run priority from the Undervoltage start. 44 44
HLC-08NRC HLC-08 NRCWritten WrittenExam Exam
- 44. 064 G2.1.7 OO1IEMERG DIESEL GEN/2/1/4.4/4.7/ROIHIGHIN/AINEW
- 44. 064 G2.1.7 OOllEMERG DIESEL GEN/211/4.4/4.7IRO/HIGH/N/AINEW - 200SIEDG-007 - 2008IEDG-007 Giventhe Given thefollowing:
following:
- The
- Theplant plantisisoperating operatingatat100% 100%RTP. RTP.
480VBus
- 480V
- BusE-1 E-1 Main MainBreaker Breakertripstripsononovercurrent.
overcurrent.
- EDG
- EDG"A" Astarts startsand andre-energizes re-energizes480V 480VBus BusE-1.E-1.
- The
- TheEDG EDG "A" AJacket JacketWaterWaterCoolant CoolantPump Pumpshaft shaftshears shearsduring during EDGEDGstart.
start. APP-010-F2,
- APP-01
- 0-F2, EDG EDG AACOOL COOLWTR WTRHilLa HI/LOTEMP TEMPilluminates.
illuminates. APP-010-A2
- APP-01
-
0-A2, , EDGEDG AATROUBLE TROUBLE illuminates. illuminates. Which ONE Which ONE (1) (1) ofof the the following following isis the the impact impact ofof the the pump pump shaft shaftfailure failure on on EDG EDG Automatic Automatic operati operation? on? EDG "A"wi" EDG A will....
....
A. shutdown A. shutdown when when coolant coolant water water pressure pressure decreases decreases to to 12 12 PSIG. PSIG. B. shutdown B. shutdown when when coolant coolant water water temperature temperature reaches reaches 205 205 of. F. 0 CY C~ continue to continue to operate operate due due to EDG engine trips being being defeated. defeated. D. continue D. continue to to operate operate due due toto run priority from the Undervoltage Undervoltage start. The The correct answer is correct answer is C. C. A: A: Incorre Incorrect ct - With
-
With the the EDG EDG in a standb standby y condit ion, the engine trips (12 PSIG is an condition, an actual actual engine trip setpoin engine trip setpoint) t) are are defeate defeated d to preven preventt spurio spurious affecting us trips from affecti ng thethe EDG EDG operati operationon during during emerge emergency ncy condit ions. conditions. B: B: Incorre Incorrect ct - With
-
With the the EDG EDG in in aa standb standby y condit ion, the condition, the engine engine trips trips (205 (205 °Fof isis an an actual actual engine trip) are defeate d to preven engine trip) are defeated to prevent spurious t spurio us trips trips from from affecti affecting the EDG ng the EDG operati operation on during during emerge emergency ncy condit ions. conditions. C: C: Correc Correct t - Diesel Diesel engine engine trips trips are are defeate defeated to preven d to prevent t spuriou spurious trips during s trips during emerge emergency
-
ncy operati on and the EDG will operation and the EDG will continue to continu e to run. run. D: D: Incorre Incorrectct - EDG
-
EDG starts starts onon Underv oltage, howev Undervoltage, however er UV UV hashas nono input inputtoto engine engine trips trips or or run run priority. priority. Exam Exam Questi Questionon NumbeNumber: r: 44 44 Refere
Reference:
nce: OP-60 OP-604, 4, Page Page8,8,StepStep3.11; 3.11 ;SD-00 SD-005,5, EDG, EDG, Pages Pages30-31. 30-31. KA KAStatem ent: Ability Statement: Abilitytotoevalua te plant evaluate plantperform ance and performance andmakemakeoperati operational judgments onal judgm basedon on ents based operati operating ng charac teristics, reactor characteristics, reactorbehavi or, and behavior, andinstrum instrument interpretation. ent interpretation. History: History:New New -Writte
-
Written n forforHLC-0 HLC-08 8 NRC NRCExam. Exam.
- Tuesday, Tuesday,June June17, 2008 1:21 17,20081 :21:12
- 12PM PM 5151
3.8 3.B 480 VAC 4BO VAC isis available available to to MCC-5, MCC-5, MCC-6, MCC-6, E-1,E-1, and and E-2E-2 and and the the Diesel Diesel Equipment Equipment breakers are breakers are closed closed lAWlAW OP-603 OP-603... 3.9 3.9 Fire Protection Fire Protection System System isis lined lined upup for operation lAW for operation lAW OP-B09. OP-809. 3.10 3.10 The Supply Ventilation The Supply Ventilation Fans (HVS-6 Diesel Fans (HVS-6 Diesel "A", A, HVS-5, HVS-5, Diesel Diesel UB U) and the B) and the Exhaust Ventilation Ventilation FansFans (HVE-1B, (HVE-1 8, Diesel Diesel UA U A // HVE-17, U) are operable Exhaust HVE-1 7, Diesel Diesel UBB) are operable lAWlAW OP-906. OP-906. An exception is An exception described below. is described below.
- B Emergency "B" Emergency Diesel Diesel has been evaluated has been evaluated to to remain remain operable operable with with HVS-5 HVS-5 operable AND HVE-17 operable HVE-17 inoperable, inoperable, provided provided thethe EDG EDG "B"B room room door door remains remains closed except for normal ingress and egress AND the HVE-17 HVE-1 7 discharge damper is damper is failed open. Failing open open. Failing open the HVE-1 7 discharge the HVE-17 discharge damper damper will require require compensator compensatory y actions lAW FP-012.
lAW FP-012. (ESR (ESR 99-00241) + ~ 3.11 The Engine Trip Defeat Key Switch is in the TRIPS DEFEAT position. 3.12 Generator Bearing Oil level is greater than or equal to the UStopped oil levelu mark. Stopped oillevel 4.0 PRECAUTIONS AND LlMITATIONS{ LIMITATIONS{ LIMITATIONS \f C PRECAUTIONS AND LIMITATIONS" TC "PRECAUTIONS
\1 "1" \1 1 } )
4.1 The Emergency Diesel Generators shall meet the OPERABILITY requirements of Improved Technical Specifications LCO 3.B.1 3.8.1 or LCO 3.B.2.3.8.2. In the event that an Emergency Diesel Generator becomes inoperable, action shall be taken in accordance with Improved Technical Specifications LCO 3.B.1 3.8.1 or LCO 3.B.2: 3.8.2; 4.2 The Emergency Diesel Generator fuel oil supply shall meet the OPERABILITY requirements of Improved Technical Specifications LCO 3.B.3. 3.8.3. 4.3 The Local/Remote LocaVRemote Switch on the Engine Control Panel shall be left in REMOTE position at all times unless the Diesel Generator is under Clearance, Test or as directed by this procedure. When the Local/Remote LocaVRemote Switch position is changed, the Air Start Solenoids will momentarily deenergize. Therefore, to minimize minimize the potential for inadvertent EDG start, the Local/Remote Switch position shall be changed using a QUICK motion. 4.4 4.4 IfIf the engine is is to be started started with lube lube oil temperature temperature at or below 130°F, 130°F, the speedspeed
- of of the engine should be be reduced to keep the the lube lube oil oil pressure below below 55 psig until until the oil temperature is above the oil temperature is above 130 F. 130°F.
D 4.5 4.5 When the Lube Lube OilOil Filter Filter pressure differential differential exceeds exceeds 10 10 psid, psid, cartridge replacement is is required. required. OP-604 IOP-604 Rev. Rev. 7070 I Page 8Bof Page of 152 1521
SD-005 SD-005 EMERGENCY DIESEL GENERATOR EMERGENCY GENERATOR SYSTEM SYSTEM 4.2 4.2 Diesel Engine Diesel Trips Engine Trips 4.2.1 Engine 4.2.1 Engine Overspeed Overspeed trips the fuel racks at 1035-1053 Mechanically trips 1035-1053 rpm. When the engine is manually tripped by the emergency stop push-button, it also trips the fuel racks to the No-Fuel position. Stopping the the diesel by either either method dictates that the reset lever be used to fuel racks. This trip the fuel reset the trip cannot defeated. cannot be defeated. 4.2.2 High Crankcase Pressure During normal operation the diesel crankcase is maintained with a slight vacuum from 0.4 to 4.0 inches of H20. If the pressure increases to +0.5 + 0.5 inches of H20, a trip signal is generated and stops the diesel (energizes the governor shutdown solenoid which causes the governor to reposition the fuel rack to No-Fuel position). This trip is placed in service 20 seconds after diesel starting by a time delay relay. This trip is bypassed when the Trips Defeat Switch is in the Trips Defeat position. 4.2.3 Low Lube Oil Pressure Upon diesel starting, this trip is bypassed by a time delay relay for 20 seconds to allow the diesel to come up to speed and develop enough oil pressure to reset the trip. This trip is normally set at 18 psig. If the trip setpoint is reached then the engine shuts down (energizes the governor shutdown solenoid which causes the governor to reposition the fuel rack to No-Fuel position). This trip is bypassed when the Trips Defeat Switch is in the Trips Defeat position. 4.2.4 Low Jacket Water Pressure This trip is defeated for 20 seconds after the diesel reaches 810 rpm by a time delay relay. This allows the diesel to come up to speed and stabilize. If coolant pressure decreases to approximately 12 12 psig during operation, a shutdown of the diesel will result (energizes the governor shutdown solenoid governor shutdown solenoid which causes causes the governor to reposition the fuel rack to No-Fuel reposition No-Fuel position). This This trip is bypassed when the Trips Defeat Switch Switch is in the Trips Defeat position. "-7 4.2.5 4.2.5 High High Jacket Water Water Temperature During normal operation During operation (2500 (2500 KW) cooling cooling water temperature out out of of the the engine engine should should bebe 182°F 182°P toto 185°F 185°P (alarms at 195°F (alarms at 195°F HiHi and and 105°F 105°P Lo). Lo). IfIf the the temperature increases toto 205°F, 205°P, aa temperature temperature switch switch will will shutdown shutdown thethe diesel diesel (energizes (energizes the the EDG EDG Page 30 Page 30 of of 74 74 Revision 11 Revision 11 INFORMATION USE ONLY
SD-005 SD-005 EMERGENCYDIESEL EMERGENCY DIESELGENERATOR GENERATORSYSTEM SYSTEM governorshutdown governor shutdownsolenoid solenoidwhich whichcauses causesthe thegovernor governortotoreposition repositionthe thefuel fuelrack racktoto No-Fuelposition). No-Fuel position). ThisThistrip tripisisplaced placedininservice service20 20seconds secondsafter afterdiesel diesel startingby starting byaa
~ time delay relay. This trip is bypass time delay relay. This trip is bypassed when the ed when theTrips TripsDefeat DefeatSwitch SwitchisisininthetheTrips Trips Defeatposition.
Defeat posiüon. 4.2.6 Engine 4.2.6 EngineStart StartFailure Failure IfIfthe enginespeed theengine speedhas has notnotincreased increasedtoto >>200 200rpm rpm(LSR) (LSR) within within 10 10 seconds seconds of ofthe the start start signal (TD2), signal (TD2), thenthenaagovernor governor shutdown shutdownoccurs occurs (energizes (energizes the governor shutdown the governor shutdown solenoid which solenoid whichcauses causes thethe governor governor toto reposition reposition the the fuel fuel rack rack toto No-Fuel No-Fuel position). position). This trip bypassed when This trip isis bypassed when the the Trips Trips Defeat Defeat SwitchSwitch isis inin the the Trips Trips Defeat position. Defeat position. Governor Shutdown Governor Shutdown isis resetreset by depressing the by depressing the ALARM ALARM RESET RESET push push button button on on the the Engine Control Engine Control Panel. Panel. NOTE: Diesel NOTE: Diesel trips trips (High (High Crankcase Crankcase Pressure, Pressure, Low Low Lube Lube OilOil Pressure, Pressure, Low Low
~ Jacket Water Pressu re, and gh Jacket Water Pressure, and ,High Jacket Water Jacket Water Temperatur~,
Temperature, and and Start Start Failure) Failure) are normally are normally defeated defeated by by aa key-operated key-operated switch switch (Trips (Trips Defeat Switch)) on DefeatSwitch on the the diesel contro l panel. For norma diesel control panel. For normal testing the l testing the trips trips are are placed placed in in ser~ce service after after the the diesel has diesel has started started andand assumed assumed load as as allowed allowed by Technical Technical Specifications. Specifications. This action This action reduces reduces exposure exposure of the EDGs to undue risk of damage damage thatthat might might render it render it inoperable. inoperable. 4.2.7 10 4.2.7 10 Second Second Overcrank Overcrank If If the engine speed the engine speed has not increased to >> 200 rpm (LSR) within 10 second nO,t increased secondss of of the the start start signal (TD2), signal (TD2), then then the air start soleno ids open, preven solenoids preventing ting further loss of startinstarting air g air until until the the malfun ction causin malfunction causing g the overcr ank is correct overcrank corrected.ed. There is is enough stored stored airair for for eight cold starts. eight cold starts. However,Howev er, the EDG will only attempattemptt to auto startstart once. once. ThisThis isis due due to to the the engine engine contro controll system system which which isis design designed ed to to stop stop crankin cranking within 10 seconds. g within 10 seconds. Failure Failure of of the the engine engine to to start start within within the the timing timing period period of of the the overcr overcrank time (10 ank time (10 second seconds) s) indicat indicateses aa malfun ction. Shutdo malfunction. Shutdown wn conser conservesves the the startin starting air supply g air supply so so the the engine can be subseq uently engine can be subsequently started after started after the the malfun ction isis correct malfunction corrected. This trip ed. This trip will will not not preven prevent t aa manua manuall start start ofofthethe EDG, EDG, and and isis not not defeata defeatable. ble. 4.3 4.3 Genera Generator tor Trips Trips 4.3.1 4.3.1 Revers Reverse e Power Power This This trip trip opens opensthe the genera generatortor output outputbreake breaker r toto preven prevent t motori motorizing zing thethegenera generator and tor and possib ly damag ing the possibly damaging the diesel. diesel. NOTE NOTE: : After Afteraagenera tor trip generator tripfrom fromReversReversee Power Power, , when whenthe thegenera generator outputbreake breaker trips, tor output r trips, the trip relay is automa the trip relay is automatically tically reset. reset. The Theflagflagon onthetheassocia associated relayon ted relay onthe theGenera Generator tor EDG EDG Page Page3131ofof7474 Revision1111 Revision INFO INFORMATION RMATION USE USE ONL ONLY Y
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 45. Given
- 45. Given the thefollowing:
following: The plant
- The
- plant isis operating operating atat 100%
100% RTP. RTP.
- AA release
- release of of Waste Waste Condensate Condensate TankTank (WCT)
(WCT) "A" A isis inin progress. progress. APP-036-E7, RAD
- APP-036-E7, RAD MONITOR MONITOR TROUBLE, TROUBLE, isis received.
received. The BOP
- The
- BOP Operator Operator reports reports the the FAIL FAIL light light for for R-18, R-18, LIQUID LIQUID WASTE WASTE DISPOSAL DISPOSAL EFFLUENT monitor, EFFLUENT monitor, isis ON.
ON. Which ONE Which ONE (1) (1) ofof the the following following describes describes the the status status of of RCV-018, RCV-018, LIQUID LIQUID WASTE WASTE RELEASE RELEASE ISOLATION ISOLATION VALVE? VALVE? RCV-018 will RCV-018 will...
...
A. NOT automatically A. NOT automatically close.close. The The release release must must be be terminated terminated manually. manually. B. automatically close B. automatically close when when the monitor monitor FAIL FAIL light light is illuminated. illuminated. NOT automatically close, and C. NOT and CANNOT be closed from the Waste Disposal Panel. D. automatically close, and must be reset by cycling the valve controller's D. controllers potentiometer. potentiometer. 45 45
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 45. 073 A4.01 001/PROCE SS RAD MONITORJ 2/1/3.9/3.9/R 45.073 A4.01 OOlIPROCESS RAD MONITORl2/113.9/3.9IROIIllGHlNIA/RNP OffflGWN/AJINP AUDIT 2006/RMS-009 AUDIT - 2006IRMS-009 Given the Given following:
the following:
- The
- plant isis operating The plant operating at 100% RTP.
at 100% RTP.
-A
- release of A release Waste Condensate of Waste Tank (WCT)
Condensate Tank (WCT) "A"A isis in progress. in progress. APP-036-E7, RAD
- APP-036-E7,
- RAD MONITOR TROUBLE, isis received.
MONITOR TROUBLE, received. The BOP
- The
- Operator reports BOP Operator reports the FAIL light the FAIL for R-18, light for R-18, LIQUID LIQUID WASTE WASTE DISPOSAL DISPOSAL EFFLUENT monitor, EFFLUENT monitor, is ON.
is ON. Which ONE Which ONE (1) (1) of of the the following describes describes the status of the status of RCV-018, RCV-018, LIQUID LIQUID WASTE WASTE RELEASE RELEASE ISOLATION ISOLATION VALVE? RCV-018 will RCV-018 will...
...
A NOT automatically close. The release must be terminated manually. Art B. automatically close when the monitor FAIL light is illuminated. C. NOT automatically close, and CANNOT be closed from the Waste Disposal Panel. D. automatically close, and must be reset by cycling the valve controller's controllers potentiometer. potentiometer. The correct answer is A. The A: Correct - - Fail light means loss of power and/or loss of indication. Valve will NOT close. Release must be terminated. B: Incorrect - RCV-01
-
RCV-018 8 will close on a High Radiation Alarm, NOT a fail light. C: C: Incorrect Incorrect - RCV-01
-
RCV-018 8 can be operated at any time with control switch on the Waste Disposal Disposal Panel. D: Incorrect - RCV-01
- RCV-018 8 will NOT Automaticall Automatically y CLOSE and is controlled by the CLOSE-AUT CLOSE-AUTO-OPEN O-OPEN switch instead of of potentiomete potentiometer. r. RCV-01 RCV-014 controlled by 4 is controlled by a potentiomete potentiometer. r.
Exam Exam Question Question Number: Number: 45 45
Reference:
Reference:
SD-019, SD-019, RMS,RMS, Page 40; APP-036-E7 Page 40; APP-036-E7.. KA KA Statement: Statement: Ability Ability to to manually manually operate operate and/or and/or monitor monitor in in the the control control room: room: Effluent Effluent release. release. History: History:
- Tuesday, Tuesday, June June 17, 2008 1:21 :12 PM 17,20081:21:12 PM 52 52
SD-019 RADIATION MONITORING SYSTEM
- 2. Rate-meters (located in RMS consoles 1, 2, and 3)
- a. Nuclear Re Resegch rch Co Corporation, oration, R-lR-1 throu throughh R-9, R-ll, R-11, R-12, R-15, R-R R-178R-20, 16, R-17 R-18:' R-20 R-21 R-21, R-30, R-31A, R-31B R-31B, R-31C, and R-33
** Red light - ALARM/RESET
-
-==,.
- Amber light - FAIL- No automatic actions occur.
-
** White light - PWR ON (power on)
-
** White light - CKT TEST (circuit test)
-
** White light - CHECK SOURCE
-
** White light - H. V. Off (High Voltage Off)
-
** Digital Indicator 10- 10-1 to 10 iO4 mr/hr (R-l (R-1 through R-S)
R-8)
** Digital Indicator 10° 100 to 10iO5 mr/hr (R-9, R-30, R-31A, R-31B, R- R 31C and R33)
** Digital Indicator 10 1066 cpm (R-ll, 101 to 10 (R-11, R-15, R-16, R-17, and R-R 18)
IS)
** Digital Indicator 10 iO7 cpm (R-12, R-20, and R-21) 101 to 10
- b. Victoreen, R-32A and R-32B (located in RMS console 1)
** Yellow light - ALERT
-
** Red light - HIGH
-
** Blue light - CHANNEL TEST
-
** Green light - SAFE/RESET
-
** Red button - E.C.S. (Electronic Check Source)
-
** Analog Indicator 10° to 10 iO7 R/hr
- 3. Indicators, Digital (located in RMS consoles 2 and 3; FIGURES 10 & 22)
- a. R-14C, R-14D, and R-14E 1011 to 10 10 1066 cpm
- b. R-19A, R-19B, R-19C 1011 to 10 10 iO7 cpm
- 4. Indicators, Light (located in RMS consoles 2 and 3)
- a. R-14C, R-14D, R-14E, R-19A, R-19B, R-19C, and R-14 Skid
** Red light - ALARM (except R-14 Skid)
-
** Amber light - FAIL
-
- 5. Pump Controllers, Indicator Lights (located in RMS consoles 2 and 3)
- a. R-11/R-12 R-ll/R-12 RMS Page 40 of 59 Revision 7 INFORMATION ONLY
APP-036-E7 APP-036-E7 Page Page 11 of of 33 ALARM ALARM RAD MONITOR RAD MONITOR TROUBLETROUBLE *** WILL REFLASH
*** WILL REFLASH ***
AUTOMATIC ACTIONS AUTOMATIC ACTIONS 1.
- 1. IF the IF the R-14C R-14C FAIL alarm isis ILLUMINATED, FAIL alarm ILLUMINATED, THEN THEN R-14C R-14C closes closes RCV-014, RCV-014, WASTE WASTE GAS GAS DECAY DECAY SYSTEM ISOLATION SYSTEM ISOLATION VALVE,VALVE, to to stop stop any any gas release inin progress.
gas release progress. CAUSE CAUSE ~1.
- 1. all channels For all For channels (R-1 through R-9; (R-1 through R-1 1; R-12; R-9; R-11; R-1 2; R-15; R-1 5; R-16; R-1 6; R-17; R-1 7; R-18; R-1 8; R-20; R-20; R-21; R-21; R-30; R-31 R-30; R-31A, B, C; A, B, R-32A, B; C; R-32A, B; R-33):
R-33): . - Loss of Loss of Counts Counts Loss of Loss of Power Power
- 2. For Channel R-14C, D, E:
Loss of Counts Loss of Power Low Sample Flow Low F-14 Flow
Low Battery
- 3. For PLANT VENT EFFLUENT MONITORING EQUIPMENT FAIL:
F-14 Kurz Power Failure Heat Trace Trouble Stack Flow Trouble
- 4. For R-19A, B, C:
Loss of Counts Loss of Power
Skid Flow Low Skid Flow High High Temperature Check Check Source CountsCounts NOTNOT within limits limits OBSERVATIONS 1.
- 1. FAIL FAIL light for associated light for associated RMS channel illuminated.
RMS channel illuminated. 2.
- 2. Plant Plant Vent Vent Effluent Effluent Monitoring Monitoring Equipment Equipment FAILFAIL light light for R-14C/D/E illuminated.
for R-14C/D/E illuminated. IAPP-036 APP-036 Rev. 62 Rev. 62 Page Page 4545 of 961 of 96
APP-036-E7 APP-03 6-E7 Page 2 of 3 Page ACTIONS ACTIO NS NOTE: R-14C/ NOTE: R-14C/D/ED/E do NOT have to be be declared outout of of service service ifif only only the Plant Vent Effluen Equipment Effluent Monito Monitoring Equipm ent FAIL FAIL light is illumina illuminated unless further investig ted unless investigation ation by E&CE&C determines the channel(s) inoperable. are inopera ble. 1.
- 1. IF the Plant Vent Effluent Monito IF Monitoring Equipm Equipmentent FAIL light for R-14C/D/E illumina illuminates, tes, THEN NOTIFY E&C to investiginvestigate ate cause of alarm.
2.
- 2. IF aa channe IF channel FAIL lightlight has illumina illuminated, ted, THEN PERFORM the followin following:
g: 1)
- 1) Attemptt to RESET the alarm.
Attemp
- 2) IF the FAIL light extingu extinguishes ishes,, THEN channel is operable AND no further actions are require d.
- 3) IF the FAIL FAIL light will NOT extingu extinguish, ish, THEN DECLA DECLARE RE the channel inoperainoperable ble until the results of the subsequent E&C status check is known. known.
- 3. IF any channel has failed, THEN REVIEW TECH SPECS AND ODCM to determine the appropriate actions for any release in progres progresss through through affected channels with an illumina light. illuminated ted FAIL
-
ODCM Table 2.6-1 for liquid release s
-
ODCM Table 3.10-1 for gaseous releasess
- 4. DECLARE DECLA RE any channel with an illumina illuminated ted FAIL light inopera inoperable ble until the cause for the FAIL light is determined. It may be necess necessaryary to keep the affected channel energized if a continu allowed lAW is allowed continueded release JAW applicable TECH SPECS AND ODCM.
- ~5.
- 5. R-1 8 FAIL light is ILLUM IF R-18 ILLUMINATE INATED, THEN SECUR SECURE E any release in progre progress via this pathway.
- 6. A-il OR R-12 FAIL lights are illumina IF R-11 illuminated, ted, AND a Containment Purge is in progres PERFORM the followin PERFO progress,s, THEN following:
g:
- 1) IF the plant is in Modes 1 1 throug through h 4, THEN SECUR SECURE E any Containment Purge in progres progress. s.
Contai nment Purge is NOT allowed allowed in Modes 11 throug through h 4 unless R-11 R-1 1 AND R-12 are in service (ITS LCO 3.3;6)( 3.3.6)(ACR 94-00833).
- 2) IF movement of recently irradiat irradiated ed fuel is in progres progress, s, THEN STOP movement of that fuel.
- 7. RI is inopera IF R-1 inoperable, ble, AND the plant is in Modes 1 1 throug through h 4 OR movement of fuel assem assembblies lies is in progress, progres s, THEN VERIFY Y Contro Controll Room Ventilation System is in the Pressu (ITS LCO 3.3.7) Pressu rization rizatio n Mode.
- 8. NOTIFY E&C of monitor(s) status.
- 9. Releases may be continued JAW lAW applicable TECH SPECS AND ODCM.
10.
- 10. IF desired, THEN REMOVE the affected channe channell from service using OWP- OWP-00l4.14.
IAPP-036 Rev. 62 I Page 46 of 96 961
APP-036-E7 Page 3 of 3 DEVICE/SETPOINTS OEVICE/SETPOINTS
- 1. RefertoOMM-014 Refer to OMM-014 POSSIBLE PLANT EFFECTS
- 1. Entry to TECH SPEC LCO REFERENCES
- 1. ITS LCO 3.3.6, 3.4.15, ODCM 2.6 and 3.10
- 2. ACR 94-00833, No CV Purge with R-11 R-1 2 OOS R-1 1 and R-12
- 3. 94-01 308, R-18 FAIL Condition ACR 94-01308,
- 4. 82-85, 87, 279, 350, 361, 525, 530, 535, 637, 1058,1693-1695,1724, CWD B-190628, Sheets 82-85,87,279,350,361,525,530,535,637, CWO 1058, 1693-1695, 1724, 1727, 1728, 1734, 1735, 1740, 1741,1741A 1727,1728,1734,1735,1740, 1741, 1741A
- 5. OMM-014, Radiation Monitoring Setpoints
- 6. ESR 95-00227
- 7. OWP-014, Radiation Monitoring System (RMS)
- 8. CR 97523, R-14C Failure Due To Low Counts
- 9. EC 52464, Replace R-14 Plant Vent Monitor IAPP-036 APP-036 I Rev. 62 Page 47 of 96961I
REPRT ,.\ QUESTIONS RElj-pRT QUESTIONS for AUDIT for (oo 4odrr) AUDIT (06 ;f(jdrrJ
- 1. 073
- 1. 073 A2.02 A2.02 001lSD-019/073 A1.01/3.2/3.1/07/01/O3MCMJMEMORY/01-01 NRC 001/SD-0191073 Al.01l3.2/3.1I07/01l03MCM/MEMORY/OI-01 NRC EXAM/I EXAMJ/
Given the Given the following following plantplant conditions: conditions:
- plant is The plant
- The is in in MODE MODE 1, 1, 100%RTP 1 0O%RTP
** A release release of Waste CondensateCondensate Tank (WCT) 'A' is in A is in progress progress
** Annunciator APP-036-E7, RAD RAD MONITOR MONITOR TROUBLE, is is received
*
- The BOP Operator reports the FAIL light for R-18, Liquid Waste Disposal Monitor, isON is ON Which one of the following describes the status of the Liquid Waste Release Isolation, RCV-01 8?
RCV-018? At. RCV-018 A'I RCV-O1 8 will not automatically close. The release must be stopped manually B. RCV-018 will automatically close when the monitor FAIL light is illuminated RCV-01 8 is not immediately affected and will close if high radiation is sensed by C. RCV-018 R-18 D. Automatic operation of RCV-018 RCV-01 8 is defeated, but the release may continue unless an actual High Radiation condition exists A. Correct.
Reference:
SD-019, APP-036-E7. Fail light means loss of power and/or loss of indication. Valve will not close. Release must be terminated. Common Question 022 Tier 2 Group 11 K/A KIA Importance Rating - RO 2.7 - 2.7// SRO 2.7 Ability to (a) predict the impacts of the following malfunctions or operations on the PRM
. system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure.
Reference(s) - - Proposed References to be provided to applicants during during examination - - Learning Objective Learning Objective - - Question Question SourceSource - - Question History Question History - - Question Question Cognitive Cognitive Level Level - - 10 10 CFR CFR Part Part 5555 Content Content - - Comments Comments - - Category Category 1:1: SD-019 SD-019 Category Category 2: 2: 073 073 A1.01 Al.Ol Category Category 3:3: 3.2/3.1 3.2/3.1 Category Category 4: 4: 07/01/03MCM 07/01/O3MCM Category 5: Category 5: MEMORY MEMORY Category Category 6: 6: 01-01 NRC 01-01 NRC EXAM EXAM Category Category 7:7: Category Category 8: 8:
- Tuesday, Tuesday, June June 10,2008 10:07:17 AM 10,200810:07:17 AM 1
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 46. Given
- 46. Given the the following:
following: The plant
- The
- plant isis operating operating atat 100%
100% RTP. RTP. APP-008-E8, NN SW
- APP-008-E8,
- SW HDR HDR STRAINER STRAINER PIT PIT HI HI LVL LVL has illuminated.
has illuminated. APP-008-F8, NORTH
- APP-008-F8,
- NORTH SW HDR LO SW HDR LO PRESS PRESS has illuminated.
has illuminated. Which ONE Which ONE (1) of the (1) of the following following are are Required Required Actions? Actions? A. Close V6-12D, A. Close V6-12D, NORTHNORTH SW SW HEADER HEADER ISOLATION ISOLATION VALVE VALVE then then Go to Section Go to Section F, F, SERVICE SERVICE WATER PITS FLOODING IN WATER PITS FLOODING IN INTAKE AREA. INTAKE AREA. B. Close V6-12B B. Close V6-12B AND AND V6-12C, V6-12C, SWSW X-CONN X-CONN Valves, Valves, then then Go Go to to Section Section F, F, SERVICE SERVICE WATER PITS WATER PITS FLOODING FLOODING IN INTAKE AREA IN INTAKE AREA Close V6-12B AND V6-12C, SW C. Close SW X-CONN Valves, then Go Go to EPP-28, EPP-28, LOSS LOSS OFOF ULTIMATE HEAT ULTIMATE HEAT SINK. D. Close V6-12D, NORTH SW HEADER ISOLATION VALVE AND Verify SW Pumps "C" C and D are stopped.
"0" 46 46
HLC-08 NRC Written Exam 46.076 A2.0l ~Ol/SERVICE
- 46. 076 A2.01 WATERJ2/1/3.5/3.7/ROILOWIN/AJNEW - 2008/AOP-022-003 001/SERVICE WATERf2/l/3.S/3.7IRO/LOW/N/NNEW -
Given the following:
- The plant is operating at 100% RTP.
-
- APP-008-E8, N SW HDR STRAINER PIT HI LVL has illuminated.
-
- APP-008-F8, NORTH SW HDR LO PRESS has illuminated.
-
Which ONE (1) of the following are Required Actions? A. Close V6-12D, NORTH SW HEADER ISOLATION VALVE then Go to Section F, SERVICE WATER PITS FLOODING IN INTAKE AREA. B Close V6-12B AND V6-12C, SW X-CONN Valves, then Go to Section F, SERVICE B:' WATER PITS FLOODING IN INTAKE AREA C. Close V6-12B AND V6-12C, SW X-CONN Valves, then Go to EPP-28, LOSS OF ULTIMATE HEAT SINK. D. Close V6-12D, NORTH SW HEADER ISOLATION VALVE AND Verify SW Pumps "c" C and D are stopped.
"D" The correct answer is B.
A: Incorrect - V6-12D is closed later in the procedure after closing V6-12B and V6-12C for
-
leak isolation. B: Correct - - Step 1 1 of AOP is an Immediate Action step. (1) Check APP-008-E8, N N SW HDR STRAINER PIT HI LVL extinguished. (RNO) Then immediately close V6-12B and V6-12C. Incorrect-- Seperation of headers by closing X-connects is correct, but only Go to EPP-28 if C: Incorrect NO SW available. D: Incorrect - V6-12D closed and verifying pumps stopped are subsequent steps AFTER
-
immediate actions. Exam Question Number: 46
Reference:
AOP-022, Pages 3, 4 and 38; APP-008-E8; APP-008-F8. KA Statement: Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: Loss of SWS. History: New - Written for HLC-08 NRC Exam.
-
Tuesday, June 17, 200811:21 17,2008 :21 :13 PM 53
AOP-02 AOP-022 Rev. 31 2 LOSS OF SERVIC SERVICE E WATER Page 33 of 78 Purpo Purposse e and Entry Condi Condittions ions (Page 11 of 1)
- 1. PURPO PURPOSE SE This proced ure provides instru instructio ction nss in the event of a break of eithe r the North or South Service Water Heade rs upstre am upstrea m OR downstream of check valve valvess SW-541 SW-541 or SW-545 SW-545 or floodi ng floodin g in the Intake Area Servi Servicce e Water Pits.
- 2. ENTRY ENTRY CONDI TIONSS CONDITION This proced ure is entere enteredd whenever there is an indic ation that a break of a Service Water Header has occur occurrred.
ed.
- END -
- -
Rev. Rev. 3030 AOP-022 AOP-022 LOSS LOSS OF OF SERVICE SERVICE WATER WATER Page Page 44 of of 78 78 fJ-C INSTRUCTIONS INSTRUCTIONS I I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED NOTE Step Step 11 is is an an immediate immediate action action step. step. 1.
~ 1. Check The Check The Following Following Alarms Alarms - Perform Perform the the following:
following: EXTINGUISHED: EXTINGUISHED:
~a.
- a. Close Close thethe following following SW SW X-CONN X-CONN
- APP-008-E7. S APP-008-E7. S SW SW HDR Valves:
STRAINER PIT STRAINER PIT HI LEVEL HI LEVEL
** V6-12B
~.
. APP-008-E8, N APP-008-E8. N SW HDR STRAINER PIT HI LEVEL ** V6-12C
- b. Go To Section F.
*
- 2. Check SW - ANY AVAILABLE
- AVAILABLE IF a total loss of Service Water Water occurs due to hostile action. action, THEN Go To EPP-28.
EPP-28, Loss of of Ultimate Heat Sink.
- 3. Make Make PA Announceme Announcement nt For Procedure Procedure Entry NOTE AA SW Header leak leak may bebe identified by observing the sequence sequence inin which which SW Header low pressure alarms are received, SW received. and evaluating SW SW Header Header pressure pressure indications.
indications. 4.
- 4. Check Check Leak Leak Location Location - IDENTIFIED
- IDENTIFIED Perform local Perform local inspections inspections as as necessary to necessary to determine determine leak leak location.
location. WHEN the WHEN the leak leak location location isis identified. THEN identified, THEN observe observe thethe NOTE prior NOTE prior to to Step Step 55 and and GoGo ToTo Step 5. Step 5.
AOP-022 Rev. Rev. 3030 AOP-02 2 LOSS LOSS OFOF SERVIC SERVICEE WATER WATER Page Page 3838 of of 7878 -{_STEP_H INSTRU INSTRUCTIOCTION NSS SECTIO SECTION [ I N FF RESPON SE NOT OBTAIN RESPONSE ED OBTAINED I SERVIC SERVICE E WATER WATER PITS PITS FLOOD ING IN FLOODING IN INTAKE INTAKE AREA AREA (Page (Page 11 of of 10) 10) 1.
- 1. Verify Verify PA Announceme nt For Procedur Proce duree Entry Entry Perfor Performedmed
~
2 2.. Verify Verify SW X-CONN X-CONN ValveValves s - CLOSED
- CLOSED::
- V6-12B V6-12B
- V6-12C V6-12C NOTE The source source of floodi flooding ng in the Intake Intake Struc ture may be Servic Structure e Water Service Water,.
Fire Water Water,. or Intake Intake Struc Structure ture leakag leakage.e.
- 3. Evalu Evaluateate Contr Control ol Room Indic ation ationss AND Perfor Perform m Local Local Inspe Inspectio ctions ns To Determ Determin ine e Source Source Of Floo Flood ing Prior ding Prior To ContinContinui uing ng
- 4. Check Source Source Of FloodFloodinging - -
Go To Step 26. SERVIC SERVICE E WATE WATERR
- 5. Check Servic Servicee Water Leak Go To Step 14.
Locattion Loca ion - ON SOUT
-
SOUTH HEADER H HEAD ER
- 6. Verify Veri fy The Follo Follow ing::
wing
- a. SW PUMP CC - RUNN- RUNNININGG
- b. SW PUMP DD - RUNN
- b. - RUNNININGG
- c. SW PUMP PUMP AA - STOPP
- STOPPE D ED
- d. SWSW PUMP PUMP BB - STOPP
- STOPPE D ED
APP-008-E8 APP-008-E8 ALARM ALARM NNSW SWHDR HDRSTRAINER STRAINERPIT PITHI HILEVEL LEVEL AUTOMATICACTIONS AUTOMATIC ACTIONS 11.. None Applicable None Applicable CAUSE CAUSE 1.1. Failure of Failure sump pump of sump pump inin north north service service water water strainer strainer pit pit 2.2. System leakage System leakage inin excess excess of of sump sump pump pump capacity capacity OBSERVATIONS OBSERVATIONS 1.
- 1. Check water Check water level level in in pit.
pit. ACTIONS ACTIONS 1.
- 1. Refer to Refer to AOP-022.
AOP-022. DEVICE/SETPOINTS DEVICE/SETPOINTS 1.
- 1. LS-1 652A I/11 foot LS-1652A foot above floor POSSIBLE PLANT POSSIBLE PLANT EFFECTS EFFECTS 1.
- 1. Continued flooding Continued flooding could jeopardize operability of valves V6-12A, V6-12B, V6-1 2A, V6-1 2C, &
V6-12C, 2B, V6-1 V6-12D
& V6-1 2D 2.
- 2. Potential Potential toto enter enter TECH SPEC LCO condition REFERENC REFERENCES ES 1.
- 1. ITS ITS LCO3.7.7 LCO 3.7.7 2.
- 2. AOP-022, AOP-022, LossLoss of of Service Service Water Water 3.
- 3. HBR2-11098 HBR2-11098,, SH. SH.1111 4.
- 4. CWD CWD B-190628, B-190628, Sh. Sh. 833 833 I
APP-O APP-008 O8 Rev. Rev.37 37 Page43 Page 43ofof5151 I
APP-008-F8 APP-008-FS ALARM NORTH SW HDR LO PRESS AUTOMATIC ACTIONS
- 1. None Applicable CAUSE
- 1. Loss of SW Pump(s)
- 2. CCW Heat exchanger Outlet Valves open too far
- 3. Rupture of Service Water Piping
- 4. Season increase in SW temperature (slow transient)
OBSERVATIONS
- 1. Service Water Pressure (PI-1616, P1-1684)
(P1-1616, PI-1684)
- 2. Service SeMce Water Pump Breaker(s) Indicating Lights ACTIONS
- 1. IF an operating SW Pump has tripped, THEN perform the following:
11)) START a Standby Pump.
- 2) Dispatch operator to check breaker(s)
SW Pump A - 480V Bus E1
- El (CMP 20B) SW Pump C - 4S0V
- 480V Bus E2 (CMP 24A)
SW Pump B - 480V Bus E1
- El (CMP 19C) SW Pump 0 D - 480V Bus E2 (CMP 25B)
-
- 3) Throttle CCW Heat Exchanger Return Valves, as necessary, to maintain 40 to 50 psig in the SW Headers.
- 2. IF a rupture in a SW Header has occurred, THEN refer to AOP-022.
- 3. coollng valves to throttle open, THEN locally IF an increase in SW temperature has caused SW cooling throttle SW-739 AND SW-740 as necessary to maintain SW pressure 40 psig to 50 psig.
DEVICE/SETPOINTS
- 1. PSL-16l6/4opsig PSL-1616 140 psig POSSIBLE PLANT EFFECTS
- 1. Loss of Service Water
- 2. Overheat of CCW
- 3. Possible entry into TECH SPEC LCO REFERENCES
- 1. ITS LCO 3.7.7
- 2. AOP-022, Loss of Service Water
- 3. CWO 8-190628, Sheet 841, cable L CWD B-190628,
- 4. Flow Diagram G-190199 IAPP-008 Rev. 36 Page 51 of 51 I
HLC-08NRC HLC-08 NRCWritten WrittenExam Exam
- 47. Given
- 47. Giventhe thefollowing:
following:
- AAline
- linebreak breakon onthetheInstrument InstrumentAir Airheader headerinside insideContainment Containmenthas hasresulted resultedininaafull full depressurizationofofContainment depressurization ContainmentInstrument InstrumentAir.
Air. Thecrew
- The
- crewhas hasisolated isolated Instrument InstrumentAirAirtotoContainment.
Containment. Which ONE Which ONE (1) (1) ofof the thefollowing following can can be be operated operated remotely? remotely? A. PressurizerSpray A. Pressurizer Spray valves. valves. B. Pressurizer B. Pressurizer PORVs. PORVs. C. Letdown Line C. Letdown Line Isolation Isolation valves. valves. D. Charging D. Charging Line Line Isolation Isolation valves valves 4747
HLC-08NRC HLC-08 WrittenExam NRCWritten Exam
- 47. 078Kl.03 47.078 001/INSTRUMENTAIR/2/1/3.3/3.4IROILOW/NINNEW K1.03OOllINSTRUMENT AIRJ2/1/3.3!3.4/RO/LOW/N/AINEW- 2008/PZR-OlO
- 2008/PZR-010 Giventhe Given thefollowing:
following:
- linebreak
- AAline breakon onthe InstrumentAir theInstrument Airheader headerinside insideContainment Containmenthas hasresulted resultedininaafull full depressu rizationofofContainment depressurization ContainmentInstrument InstrumentAir.Air.
Thecrew
- The
- crewhas hasisolated isolatedInstrument InstrumentAir AirtotoContainment.
Containment. Which ONE Which ONE (1) (1) ofofthe thefollowing following cancan be operated remotely? be operated remotely? A. Pressurizer Spray A. Pressurizer Spray valves. valves. B B~ Pressurizer PORVs. Pressurizer PORVs. C. Letdown Line C. Letdown Line Isolation Isolation valves. valves. D. Charging D. Charging Line Line Isolation Isolation valves valves The correct The correct answer answer isis B. B. A: Incorrect A: Incorrect - PZR - PZR Spray Spray Valves Valves use Instrument Instrument Air as motive force. Valves have failed failed CLOSED. CLOSED. B: Correct B: Correct - - PZR PORVs PZR PORVs use Nitrogen Nitrogen from SI Accumulator Accumulator fill line and have aa dedicated dedicated Nitrog Nitrogen en Accumulator Accumulator for each valve. Instrument Instrument Air serves as backup. backup. C: Incorre C: Incorrect ct - ' Letdown
- Letdown line line isolatio isolation n valves use Instrument Instrument Air and ALL fail CLOSED.
CLOSED. D: 0: Incorre Incorrect ct - CVC-3
-
CVC-310A 10A and 310B fail OPEN OPEN.. CVC-31 CVC-3111 fails CLOSCLOSED. charging ED. ALL chargin line g line isolatio isolations ns are non-fu nctional with Instrum non-functional Instrumentent Air isolate isolated. d. Exam Exam Questi Question on Numb Number: er: 47 47 Refere nce: AOP-0
Reference:
AOP-017, 1 7, Attach ment 1, Attachment 1, Pages Pages 34, 36; SD-05 34,36; SD-059, 9, PZR, PZR, Page Page 10 10 and and Figure Figure 4. 4. KA KA Statem Statement:ent: KnowlKnowledge edge of of the the physic al connec physical tions and/or connections and/or cause-cause-effect relationships effect relatio nships betwee n the between the lAS andlAS the following and the following system systems:s: Contai Containment air. nment air. History: History: NewNew - Writte
-
Written n for for HLC-0 HLC-08 8 NRC NRC Exam. Exam.
- Tuesday, Tuesday,June June17,2008 1:21 :13 PM 17, 20081:21:13 PM 54 54
Rev. Rev. 35 35 AOP-017 AOP-017 LOSS LOSS OF OF INSTRUMENT INSTRUMENT AIR AIR Page Page 34 34 of of 61 61 ATTACHMENT ATTACHMENT 11 MAJOR MAJOR COMPONENTS COMPONENTS AFFECTED AFFECTED BY BY LOSS LOSS OF OF IA IA (Page (Page 11 of of 5) 5) 1.
- 1. Chemical and Chemical and Volume Volume Control Control System System Components Components FAIL FAIL POSITION POSITION APP-O03-F3. CHG PMP LO SPEED - ILLUMINATED
- a. APP-003-F3. - ILLUMINATED (Loss of air to to pressure switch switch ,downstream downstream of of IIp I/P Convertor)
Convertor)
- b. CHARGING PUMP SPEED CONTROL - NO FAILURE (Back-Up Air)
-
Air)
~c.
- c. CVC-200 A. B B && C.
C, LTDN ORIFICES - CLOSED -
,sr z O(SI'R. i'C' I ~d.
- d. CVC-204 A A && B.
B, LTDN LINE ISOs - CLOSED -
- e. CVC-303 A. A, BB && C. SEAL LEAKOFFS - OPEN -
CVC-3O7, PRI SEAL BYP ISO - CLOSED
- f. CVC-307. -
*
~ CVC-31OA, LOOP 1
- g. CVC-310A. 1 HOT LEG CHG - OPEN -
DI51R:' D'-7' h. CVC
/o CVC-310B,
- 31 OB. LOOP 22 COLD LEG CHG - OPEN -
i.
....,. i. CVC-311, CVC - 311. AUX PZR SPRAY - CLOSED
-
- j. CVC-387.
CVC-387, EXCESS LTDN STOP - CLOSED -
- k. CVC-389, CVC-389. EXCESS LTDN DIV - FAILS TO VCT
-
- 1. CVCS CVCS HUT LEVEL CONTROLL CONTROLLERS ERS - FORCED LOW
-
- m. FCV-ll3A,
- m. FCV-113A. BA TO BLENDER - OPEN - OPEN n.
- n. FCV-ll3B, FCV-113B.' BLENDED BLENDED MU MU TOTO CHGCHG SUCTIONSUCTION - CLOSED - CLOSED o.
- o. FCV-114A, FCV-114A. PW PW TO TO BLENDER BLENDER - CLOSED
- CLOSED
- p. FCV-114B,
- p. FCV -114B. BLENDED BLENDED MU MU TO TO VCT VCT - CLOSED
- CLOSED
- q. HCV-105,
- q. HCV-I0S. BORIC BORIC ACID ACID TK TK BB RECIRC RECIRC - CLOSED - CLOSED
- r. HCV-11O,
- r. HCV-110. BORIC BORIC ACID ACID TK TK AA RECIRC RECIRC - CLOSED - CLOSED fJ/fff"V'" ~ s . HCV-121.HCV-121. CHARGING CHARGING FLOW FLOW - OPEN
- OPEN
- t. HCV-137,
- t. HCV-137. EXCESS EXCESS LTDN LTDN FLOW FLOW -- CLOSED CLOSED u.
- u. LCV-115A, VCT/HLDP TK LCV-llSA. VCT/HLDP TK DIV DIV - FAILS
- FAILS TO TO VCT VCT (CONTINUED (CONTINUE D NEXT NEXT PAGE)PAGE)
Rev. Rev. 35 35 AOP-017 AOP-017 LOSS LOSS OF OF INSTRUMENT INSTRUMENT AIR AIR Page 36 of Page 36 of 61 61 ATTACHMENT ATTACHMENT 11 MAJOR MAJOR COMPONENTS COMPONENTS AFFECTED AFFECTED BY BY LOSS LOSS OF OF IA IA (Page (Page 33 of of 5) 5) 6.
- 6. Isolation Valve Isolation Valve Seal Seal Water Water System System Components Components FAIL FAIL POSITION POSITION
- a. PCV-1922 A
- a. PCV-1922 A && B.
B, IVSW IVSW AUTO AUTO HEADER HEADER ISOLsISOLs - OPEN
- OPEN 7.
- 7. Main Steam Main Steam System System Components Components FAILFAIL POSITION POSITION
- a. MAIN STEAM
- a. STEAM ISOLATION ISOLATION VALVES - CLOSED - CLOSED
- b. STEAM LINE PORVs - CLOSED
-
8.
- 8. Primary Sample System Components FAIL POSITION
- a. PS-956
- a. PS-956 A A through H. H, PRIMARY SAMPLE ISOLATIONSISOLATIONS - CLOSED
- CLOSED 9.
- 9. Radiation Monitoring System Components FAIL POSITION Radiation RMS-1,2,3 &
- a. RMS-1.2.3
- a. & 4.
4, R-11/R-12 ISOL VALVES - CLOSED - 10.
- 10. Reactor Reactor Coolant System Components FAIL POSITION
~ a. PCV-455 AA && B,
- a. PCV-455 B. PZR SPRAYS -- CLOSED D
1J~I'I11r
/
- b. RC-516 && 553,
- b. 553. PRT TO GAS ANALYZER - CLOSED -
- c. RC-519 AA && B,
- c. B. PWPW TO CV ISOs - CLOSED
-
- d. RC-544,
- d. RC-544. RVRV FLANGE FLANGE LEAKOFF LEAKOFF - OPEN
- OPEN e.
- e. RC-550, RC-550. PRT PRT NITROGEN NITROGEN SUPPLY SUPPLY - CLOSED
- CLOSED 11.
- 11. Residual Residual Heat Heat Removal Removal System System Components Components FAIL FAIL POSITION POSITION
- a. HCV-142,
- a. HCV-142. PURIFICAT PURIFICATION FLOW - CLOSED ION FLOW - CLOSED
- b. HCV-758,
- b. HCV-758. RHR RHR HXHX DISCH DISCH FLOW FLOW - CLOSED
- CLOSED
- c. FCV-605,
- c. FCV-605. RHR RHR HXHX BYPASS BYPASS FLOW FLOW - CLOSED
- CLOSED
SD-059 PRESSURIZER SYSTEM level, which reduces the elevation head loss that spray flow must overcome. Normal spray flow is unlikely or will not occur at all when C
'C' RCP is stopped and PZR level is less than 30%. Therefore, PZR pressure response may not be as expected for the above condition. (Ref. SCR 90-031) 3.4 PZR Surge Line Nozzle Diameter 14 in.
Pipe Schedule 140 Surge Line 12 in. Surge Line Nominal Thickness 1.125 in. Design Pressure 2485 psig Design Temperature 680°F 680 0 P The PZR surge line, which connects the bottom of the PZR to RCS loop C hot leg, is sized such that it will pass the maximum anticipated surge flow of 20,000 gpm with a minimal pressure drop. A resistance temperature detector is installed in the surge line and provides indication and a low temperature alarm in the Control Room. Low temperature is indicative of stagnation of the PZR fluid. The surge nozzle, located in the bottom of the vessel, is protected against thermal shock by a thermal sleeve. A retaining screen above the nozzle prevents foreign matter in the PZR from entering the RCS piping. Incoming surge flow displaces the water in the vessel as it enters the heater bundle area. 3.5 PZR Safety and Relief Valves
~ Three spring loaded safety valves and two PORVs provide for over pressure protection.
The motive force for the PORVs is nitrogen with an IA backup. 3.5.1 Safety Valves (RC-551A, B, & (PZR-Figure 3 and 5)
& C) (PZR-Pigure Number 3 Capacity 293,330 lb/hr each at 33%
% accumulation Set Pressure 2485 psig Back Pressure Normal 3 psig Relieving 350 psig (maximum)
The safety valves, set for the system design pressure of 2485 psig, are spring loaded, enclosed pop type, with backpressure compensation. The combined capacity of the valves is equal to, or greater than, the maximum surge rate resulting from complete loss PZR Page 10 of 27 Revision 9 INFORMATION USE ONLY
PZR PZRPORV PORVPNEUMATIC PNEUMATIC SYSTEM SYSTEM PZR-FIGURE-4 PZR-FIGURE-4 TO PCYf av-! av-l pzrfO4 pzrf04 INFORMAT INFORMATIONION USE ONLY
HLC-08NRC HLC-08 NRCWritten Written Exam Exam
- 48. Given
- 48. Giventhethefollowing:
following: Theplant
- The
- plantisis inin MODE MODE4,4, cooling cooling down down lAW lAW GP-007, GP-007, PLANT PLANT COOLDOWN COOLDOWN FROMFROM HOT HOT SHUTDOWN TO SHUTDOWN TO COLD COLD SHUTDOWN.
SHUTDOWN.
- AA spurious
- spurious R-11R-1 1 alarm alarm causes causes aa CV CV Ventilation Ventilation Isolation Isolation signal.
signal. V12-8 and
- V12-8
- and V12-9, V12-9, CV CV PURGE PURGE OUTLET OUTLET VALVES, VALVES, bothboth have have dual dual OPEN/CLOSED OPEN/CLOSED indications.
indications. Which ONE Which ONE (1) (1) of of the the following, following, ifif any, any, isis required? required? A. Close and A. Close and deactivate deactivate EITHER EITHER V12-8 V12-8 OR OR V12-9 V12-9 within within 11 hour. hour. B. Close B. Close and and deactivate deactivate BOTHBOTH V12-8 V12-8 AND AND V12-9 V12-9 within within 11 hour. hour. C. Using C. Using CVCV Purge Purge Valve Valve blocking blocking mechanism, mechanism, override override EITHER EITHER V12-8 V12-8 OR OR V12-9 V12-9 CLOSED CLOSED within 1 hour. within 1 hour. D. Plant D. Plant is is in in MODE MODE 4; No No action action required. required. 4848
HLC-08 NRC HLC-08 Written Exam NRCWritten Exam
- 48. 103
- 48. 103K3.01 K3.01 001/CONTA INMENT/2/1/3.3/3.7IROILOWIN/A(NEW -2008/CV-008 001lCONTAINMENT/2/1/3.3/3.7IRO/LOW/N/NNEW -
2008/CV-008 Given Given the the following: following:
-
-The plant isis inin MODE The plant MODE 4,4, cooling down lAW cooling down PLANT COOLDOW GP-007, PLANT lAW GP-007, COOLDOWN FROM HOT N FROM HOT SHUTDOWN TO SHUTDOWN COLD SHUTDOWN TO COLD SHUTDOWN. . .
-
- AA spurious spurious R-l R-111 alarm alarm causes causes aa CV CV Ventilation Isolation signal.
Ventilation Isolation signal.
-
- V12-8 V12-8 and and V12-9, V12-9, CV PURGE OUTLET CV PURGE VALVES, both OUTLET VALVES, both have dual OPEN/CLOS have dual OPEN/CLOSED ED indications.
indications. Which ONE Which ONE (1) (1) of of the following, ifif any, the following, is required? any,.is required? At Close A Close and and deactivate EITHER V12-8 deactivate EITHER V12-8 OR OR V12-9 within 11 hour. V12-9 within hour. B. Close B. Close and and deactivate deactivate BOTH BOTH V12-8 AND V12-9 V12-8 AND within 11 hour. V12-9 within hour. C. Using C. Using CV CV Purge Valve blocking mechanism, override EITHER V12-8 OR override EITHER OR V12-9 V12-9 CLOSED CLOSED within 11 hour. hour. Plant is in MODE 4; No action required. D. Plant D. The correct answer is A. The correct A: A: Correct Correct - - CONTAINMENT ISOLATION VALVES, Condition B applies. Either ITS 3.6.3, CONTAINMENT valve must be closed and deactivated within 1 requirements. 1 hour to meet ITS requirements. B: B: Incorrect closed/deactivated in each line. Incorrect - Only 11 valve must be closed/deactivated
-
C: C: Incorrect Incorrect - Blocking mechanisms
- mechanisms only block the valves OPEN.
D: D: Incorrect Incorrect - CV - CV isolation required in isolation required MODES 1,2,3 in MODES and 4 for containment 1,2,3 and be met. integrity to be containment integrity Exam Exam Question Question Number: Number: 48 48
Reference:
Reference:
ITS ITS 3.6.3; 3.6.3; OP-921, 9, Page 49. Page 49. KA KA Statement: Statement: Knowledge Knowledge of of the the effect loss or that aa loss effect that malfunction of or malfunction of the the containment system containment system will will have have onon the the following: Loss of following: Loss containment integrity of containment under shutdown integrity under shutdown conditions. conditions. History: History: New New - Written
- Written forfor HLC-08 HLC-08 NRC Exam.
NRC Exam. 55 55
Containment Containment Isolation Isolation Valves Valves 3.6.3 3.6.3 3.6 CONTAINMENT 3.6 SYSTEMS CONTAINMENT SYSTEMS 3.6.3 Containment Isolation 3.6.3 Containment Valves Isolation Valves LCO LCO 3.6.3 3.6.3 Each Each containment containment isolation isolation valve valve shall shall be be OPERABLE. OPERABLE. APPLICABILITY: APPLICABILITY: MODES 1. MODES 2. 3. 1, 2. and 4. 3, and 4. ACTIONS ACTIONS
-------------------------------------NOTES NOTES-------------------. ----------------
Penetration flow I.1. Penetration flow path(s) path(s) maymay be be unisolated unisolated intermittently intermittently under under administrative controls. administrative controls. 2.
- 2. Separate Separate Condition Condition entryentry isis allowed allowed for for each each penetration flowflow path.
- 3. Enter applicable Conditions and Required Actions for systems made inoperable by containment isolation valves.
- 4. Enter applicable Conditions and Required Actions of LCO 3.6.1. 3.6.1, Containment, when isolation valve leakage results in exceeding "Containment," exceeding the the overall containment leakage rate acceptance criteria.
- 5. Enter applicable Conditions and Required Actions of LCO 3.6.8, "Isolation Isolation Valve Seal Water (IVSW)
(lVSW) System," System, when required IVSW supply to to aa penetration flowpath is isolatedisolated..
................... __ ......... _--_ .... -- ............. ---- .. - .. _ .............. .
CONDITION CONDITION REQUIRED ACTION COMPLETION COMPLETI TIME ON TIME A. A. --------.NOTE NOTE --------- A.1 A.l Isolate the affected Isolate hours 44 hours Only applicable Only applicable to to ~enetration flow path penetration path penetration penetration flow paths paths byy use use of of at at least least with with two two containment containment one closed one closed and and isolation isolation valves. valves. de-activated de-activated
........ _ ............. automatic valve, valve, closed manual closed manual valve, valve, One or more One or more blind flange, blind flange, oror penetration penetration flowflow paths paths check valve check valve with with flow flow with with one one containment containment through the through the valve valve isolation isolation valve valve secured.
secured. inoperable. inoperable. AND AND (continued) (continued) HBRSEP HBRSEP Unit Unit No. No. 22 3.6-7 3.6-7 Amendment No. Amendment No. 176 176
Containment Isolation Valves 3.6.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 ........ NOTE* NOTE ........ Isolation devices in high radiation areas may be verified by use of administrative means means..
........ - ........ ----
Verify the affected Once per 31 days penetration flow path for isolation is isolated. devices outside containment AND Prior to entering MODE 44 from MODE 55 if not performed within the - previous 92 days for isolation devices inside containment B. *********NOTE********* NOTE B.1 Isolate the affected 11 hour Only applicable to genetration flow path penetration penetration flow paths byy use of at least with two containment closed"and one closed isolation valves. de*activated iied _.----.- ....... _ ...... automatic valve. closed manual valve. One or more or blind flange. penetration flow paths with two containment isolation valves inoperable. (continued) HBRSEP Unit No. 22 3.6*8 3.6-8 176 Amendment No. 176
Section 8.4.5 Page 1 1 of 3 CONTINUOUS USE 8.4.5 BIOCkin~'d"rge Blockin Open rge Supply and Exhaust Valves{ TC "Blocking Blocking Open
'p'urge PiTSup Sup an Exhaust Valves Valves" \f C C \l
\1 "3" }
3 } (CR 95-01213)
- 1. Initial Conditions
- a. This revision has been verified to be the latest revision available.
_ _ _ _ _ _ _ (Print) (Print) _ _ _ _ _ _ __ Name Signature Date
- 2. Instructions NOTE: Refer to Attachment 10.1, Purge Valve Blocking Mechanism, for identification of component parts.
NOTE: Steps without sign offs may be repeated as necessary to accommodate blocking or disengaging the block of any of the purge valves.
~ a. Blockin~Da containment purge valve, THEN IF BIockinbpn .
PERFORM the following:
- 1) VERIFY that the purge valve to be blocked open is open.
- 2) REMOVE the hex nut locking pin.
- 3) RAISE the hex nut sufficiently to allow the jackscrew to be inserted to engage with the valve actuator.
- 4) ROTATE jackscrew clockwise until it engages with the valve actuator.
- 5) ALIGN the hex nut with locking pin holes in the jackscrew and install locking pin.
IOP-921 rOP-921 Rev. 47 57 Page 49 of 571
HLC-08NRC HLC-08 NRCWritten WrittenExamExam
- 49. Which
- 49. WhichONE ONE(1)(1)ofofthe thefollowing followingisisthe theprincipal principalconcern concernwhen whenAPP-001-A2, APP-OO1-A2,SEAL SEALWTR WTRINJ INJ FILTER HI DELTA-P is in FILTER HI DELTA-P is in alarm? alarm?
A.A. RCPs RCPs may mayNOTNOTbe be receiving receivingadequate adequateseal seal injection injectionflow. flow. B. Accumulation B. Accumulation ofofcontaminants contaminantson onthethe Seal Seal Injection Injection Filter Filtercould couldcause causeALARA ALARAconcerns. concerns. C. Seal C. Seal Injection Injection flow flow rates rates may may bebe inin excess excess ofof 10 10 GPM GPM toto each each RCP. RCP. D. Total D. Total Seal Seal Injection Injection flow flow rate rate may may exceed exceed 2020 GPM. GPM. 49 49
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 49. 004 004 K3.08 K3.08 001lCVCS/2/113.6/3.8fRO/LOWINIAfNEW 001/CVCS/2/1/3.6/3.8/RO/LOW/N/AJNEW - 2008/CVCS-008
- 2008/CVCS-008 Which ONE Which ONE (1)(1) of the following of the the principal following isis the concern when principal concern when APP-001-A2, APP-O01 -A2, SEAL SEAL WTR WTR INJ INJ FILTER HI FILTER HI OELTA-P DELTA-P is in alarm?
is in alarm? A'I RCPs may AY RCPs may NOT NOT be be receiving receiving adequate seal injection adequate seal injection flow. flow. B. contaminants on the Seal B. Accumulation of contaminants Injection Filter Seal Injection Filter could cause cause ALARA concerns. c. C. Seal Injection rates may Injection flow rates may be in excess of 10 be in 10 GPM to each RCP. RCP. D. Total Seal Injection flow rate may exceed 20 GPM. The correct answer is A. A: Correct -- High seal water injection filter dip is an indication of EITHER a clogged filter (Inadequate flow to RCP seals) or high total seal water injection flow rate (> (> 20 GPM/Pump). B: Incorrect - Increased dose rate from the filter may be an ALARA issue, but is NOT the
-
initial concern. C: Incorrect - 10 GPM IPump
- iPump is higher than normal, the action is to ensure < < 20 GPM/Pump.
D: Incorrect - Total seal injection is normally in excess of 20 GPM. 0: - Exam Question Number: 49
Reference:
APP-001 APP-001-A2; -A2; OP-301, Page 14, Step 5.59; SO-021, SD-021, CVCS, Page 11, Figure 10. KA Statement: Knowledge of the effect that a loss or malfunction of the CVCS will have on the following: RCP seal injection. History: New - Written for HLC-08 NRC exam.
-
56 56
APP-001-A2 APP-001-A2 ALARM ALARM SEAL WTR SEAL WTR INJ FILTER HI INJ ,FILTER zP HI ~p AUTOMATICACTIONS AUTOMATIC ACTIONS 1.1. None Applicable None Applicable CAUSE CAUSE 1.1. Filter Dirty Filter Dirty 2.2. High Seal High Seal Water Water Injection Injection Flow Flow OBSERVATIONS OBSERVATIONS 1.1. RCP Thermal RCP Thermal Barrier Barrier ~P (Pl-131A, PI-128A iP (PI-131A, P1-i 28A and and PI-125A) PI-125A) ACTIONS ACTIONS 1.1. Dispatch an Dispatch operator to an operator check Seal to check Seal Water Water Injection Injection Filter Filter ~P zP and and Seal Seal Injection Injection flow. flow. (PIC-157, FI-124, (PIC-157, FI-124, FI-127, Fl-i 27, and and FI-130 Fl-130 Charging Charging Pump Pump Room) Room)
- 2. IF RCP IF RCP SealSeal Injection Injection Flow Flow is high, THEN verify RCP is high, RCP Seal Seal Injection Injection Flow Flow isis less less than 20 gpm to each RCP.
each RCP.
\
- 3. IF RCP IF RCP Seal Injection Injection Filter ~PzP is high AND is NOTNOT caused by by high high flow, THEN shift filters using using OP-301.
OP-301.
- 4. IF RCP Seal Injection Filters are shifted due to high ~P, tIP, THEN initiate action to replace the affected filter cartridge.
affected 5.
- 5. IF RCP Seal Injection flow can NOT be maintained greater than 6 gpm to each RCP, THEN refer to AOP-018 AND ITS SR 3.4.17.1.
to AOP-018 DEVICE/SE TPOINTS DEVICE/SETPOINTS 1.
- 1. PIC-157/2op PIC-157 120 psid sid POSSIBLE POSSIBLE PLANT EFFECTS
~1.
- 1. Loss of of RCP Seal Injection Injection Flow REFERENC REFERENCES ES 1.
- 1. AOP-018, AOP-018, ReactorReactor Coolant Coolant Pump Pump Abnormal Abnormal Conditions Conditions 2.
- 2. OP-301, OP-301, Chemical Chemical andand Volume Volume Control Control System System (CVCS)
(CVCS) 3.3. CWD CWO B-I 90628, Sheet 8-190628, Sheet 595,595, Cable Cable AA 4.
- 4. ITS SR 3.4.17.1 ITSSR3.4.17.1 IAPP-OO1 APP-001 I Rev.
Rev. 41 41 I Page 55of Page 541 of54
5.56 When more than one one Charg Chargiingng Pump is opera operati ng, only one Charg ting, Chargiing ng Pump should be be opera operate ted d in automatic to preve prevenntt the Charg Chargiingng Pump Pumpss from "hunti hunting" ng and causing level swing swings s.. 5.57 The follow following ing starting duty limitat limitations ions apply to the Charg Chargiing ng Pump motor motorss:: 92-325 (ACR 92-32 5))
-
Maximum numb numbe err of starts per hour is 4.
- Minimum Minim um time betwebetwee enn starts is 5 minut minute es.s.
5.58 The following starting duty limitat limitations ions apply to the Boric Acid Trans Transffer er Pump motorss:: (ACR 92-32 motor 92-325 ) 5)
-
Maximum numb numbe err of starts per hour is 13.
-
Minimum Minim um time betwe betwee n starts is 3 minut en minute ess..
----> 5.59
.~ Normaall Seal Inject Norm Injectiion on flow should be maint mainta ined at 8 to 13 gpm, howe ained howev ver er the minimum Seal Inject Injectiion on flow is 6 gpm and the maximum Seal Injection flow is 20 gpm. (ACR 94-01 94-018 11) ITS LCO 3.4.17 requir 811) require ess seal injection flow of
~ 6 gpm to each RCP when in MODES 1, 2, 3, and 4.
5.60 shouldd be exerc Care shoul exercis ed when rinsing in a Mix Bed or Debo ised Debora ting Demineraliz rating eralizeerr prevenntt from reach to preve reachiningg the minimum VCT tempe temperratureature (60°F (60°F). ). Temp Tempe eratur ratures es less than 60°F can result in low seal injection tempe temperrature atures, s, which can cause No. 1 1 Seal Leako Leakoffff Flows to be below normal. 5.61 If the starting limitations stated below are excee exceed ed, Prima ded, Primarryy Wate Waterr Pump motor damag dama e can occur due to motor overh ge overheeating ating:: (REF: ACR 92-3292-3255))
-
Maximum numb numbeerr of starts per hour is 20.
-
Minimum time betwe betweeen n starts is 2 minut minutees.s. 5.62 This proce proced ure has been screen dure screeneded in accord ance with PLP-037 criteria accordance criteria and determined not applicaapplicableble (N/A) to PLP-037. 5.63 If additio additional nal Chargi Charging ng Pump Pump((s)s) are needed needed to comba combatt a casualt casualty, y, HCV-121 should be opened opened prior to starting starting additio nal Chargi additional Charging ng Pumps Pumps to ensure ensure the Chargi Charging ng Pump Relief Valves Valves will not lift. jIOP-3 OP-30 1 01 Rev. 90 I Page 1414 of 114 1141
SD-021 SD-021 CHEMICAL AND CHEMICAL AND VOLUME VOLUME CONTROL CONTROL SYSTEM SYSTEM dilute and dilute and borate. borate. These modes of These modes operation will of operation will bebe described described in the control in the control functions functions section. The three flowpaths for makeup flow section. The three flowpaths for makeup flow are as follows: are as follows: Normal Makeup Normal Makeup Flow Flow (Automatic) (Automatic) - The- makeup system The makeup system automatically automatically supplies supplies water water the current at the at current RCS RCS boron concentration to boron concentration to the charging pump the charging pump suction suction as as aa function function of of VCT level. VCT Primary makeup level. Primary water isis supplied makeup water supplied to the blender to the blender byby the the primary primary water water pumps through valve pumps through Concentrated boric FCV-1 14A. Concentrated valve FCV-114A. boric acid acid is is supplied supplied to to the the blender blender by by the boric acid the boric transfer pumps acid transfer pumps through through valve valve FCV-113A. FCV-1 13A. The The blended blended solution solution flows flows FCV-1 13B to through valve FCV-113B to the charging charging pump suction suction header. Emergency makeup from the from RWST can the RWST can be supplied to be supplied to the charging pump the charging pump suction suction header header through through valve valve LCV-115B. LCV-115B. Boration Flow - Identical to normal makeup flow except that primary makeup is not
-
supplied to the blender. Dilution Flow -Primary makeup water is supplied to the blender by the primary water pumps through valve FCV-1l4A. FCV-1 14A. FCV-1l4B, FCV-1 14B, blender outlet to the VCT opens supplying primary water directly to the VCT. This flowpath provides better control of positive reactivity addition by allowing the primary water to mix with boric acid in the VCT rather than providing primary water directly to the suction of the charging pumps. This flowpath also provides hydrogen addition to the primary makeup water as it enters the top of the VCT. Alternate Dilute - Identical to dilution flow but also supplies primary makeup to the
-
charging pump suction header as well as to the VCT spray nozzle. 2.3.5 Seal Water Injection (Figure 10) Total seal water flow rate can be adjusted by charging flow control valve HCV-121, which is normally full open. Manual valves CVC-297A, CVC-297A, B B& & C, located in the Charging Pump Room, are provided for adjusting the seal water flow for each RCP. The limits on on flow are 6 - 20 gpm for each RCP, but
-
but normal band band is 88 - 13
- 13 gpm. One charging pump operating operating at minimum speed will provide approximatel approximately y 18 - 24 18 - 24 gpm flow. HCV-121 and/or the seal injection manual control valves must be maintained open open enough enough to to pass pass all of the all of the charging charging pumppump flow to to prevent prevent lifting lifting aa charging charging pumppump relief relief (see (see CR CR 95-1752 in in the Operating Operating Experience Experience Section Section ofof this this SD).
SD). Flow Flow of of seal water isis from seal water from the the discharge discharge of of the the charging charging pumppump through through one one ofof two two seal seal water water injection injection filters to to just just below below thethe lower lower radial radial bearing bearing ofof the the RCP. RCP. Seal Seal water water bypass bypass flowflow is is from the high pressure the high pressure side side ofof the the number number 1I seal seal toto the the seal seal water water return return header. header. Seal Seal water return from water return from the the low low pressure pressure side side of of the the number number 11 seal seal goes goes to to the the seal water return header. seal water return header. eves CVCS Page Page 11 11 of of71 71 Revision 10 RevisionlO INFORMAT INFORMATION ION USE USE ONLY ONLY
SEALINJECTION SEAL INJECTION CVCS-FIGURE-l CVCS-FIGURE- 10 0 evC-307 CVC-307 II RCPBj RCP M MOV-381 SLAL1 SEALI RETURN RETURN A A I SEAl. F F SEAL WATER FILTER SEAl SEAL I I WATER FILTER BYPASS BYPASS FROM FROM 303A RCPRCPB&C B&C COMPONENT COOLING WATER TAi1fSE,ul-' L _ _ _ _ -' L_._.__J Tt L.. riW2! I- ___ J HVC-137 SEAL WATER HEAT
HVC-137
,--:----, IROM FROM lOOP TO FsEuI _ _I Il..SEALI_ JI LEG LOOP lEG 2 2 lOOP 'Q'7 RCDT l TO VCT EXCESS EXCESS I.EmOWN 389389 LETDOWN RCDT I TO VCT HEAT HEAT EXCHANGER EXCHANGER -.--J LLE3 r I
1 I
---~
SEAl. SEAL WATER WATER INJECTION INJECTION FILTERS FILTERS
~
4--1-- 297A
-i.i-Q-t.i I TOTORCPB&C RCP B & C I ~ IFI ...
fROM FROM CHARGING PUMP DISCH. CHARGING PUMP DISCH. TZ t________I I [ CVCSF10J CVCSFIO INFORMATIONUSE INFORMATION USEONLY ONLY
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 50. Given
- 50. Given the following:
the following: The plant
- The
- plant isis operating operating at at 100%
100% RTP. RTP. APP-003-C3 PRT
- APP-003-C3
- PRT HI HI PRESS PRESS illuminates illuminates andand PRT PRT pressure pressure isis still still increasing.
increasing. PRT level
- PRT
- level isis 70%
70% and and stable. stable. PRT Temperature
- PRT
- Temperature isis 105 105 of°F and and stable.
stable. Which ONE Which ONE (1) (1) of the following of the following describes describes the the event? event? A. AA PZR A. PZR PORV PORV or or Safety Safety valve valve isis leaking. leaking. B. The B. The PRT PRT Nitrogen Nitrogen supply supply regulator regulator has failed. has failed. C. Primary C. Primary Makeup Makeup WaterWater to to the the PRT PRT isis open/leaking. open/leaking. D. RCP D. RCP Seal Seal Return Return Relief Relief has has lifted lifted and and isis stuck stuck open. open. 50 50
HLC-08 NRC HLC-08 NRC Written Exam Written Exam
- 50. 007 Al.02 50.007 TANKI2/112.712.9IROIHIGHJNIAJNEW - 20081PZR-008 OO1IPRT/QUENCH TANKl2/1/2.7/2.9/RO/HIGH/N/A/NEW A1.02 OOllPRT/QUENCH - 2008JPZR-008 Given the Given following:
the following:
- The
- plant isis operating The plant operating at 100% RTP.
at 100% RTP. APP-003-C3 PRT
- APP-003-C3
- PRT HIHI PRESS illuminates and PRESS illuminates PRT pressure and PRT pressure isis still still increasing.
increasing. PRT level
- PRT
- level isis 70%
70% and stable.. and stable PRT Temperature
- PRT
- Temperature is is 105 105 of and stable.
°F and stable.
Which ONE Which ONE (1) (1) of of the following describes the following describes the the event? event? A. AA PZR A. PZR PORV PORV or or Safety valve is Safety valve leaking. is leaking. B The PRT B:I PRT Nitrogen supply regulator has failed. Primary Makeup C. Primary Makeup Water to the PRT PRT is open/leaking. is open/leaking. D. RCP Seal Return Relief has lifted and is stuck open. The correct The correct answer is B. A: Incorrect - No temperature or level increase is indicated.
-
B: Correct B: Correct -- Only pressure is increasing. Nitrogen pressure with no regulation could pressurize the PRT to rupture disk pressure. C: Incorrect - No level change is indicated. C: Incorrect - Incorrect - No level/tempera D: Incorrect - level/temperatureture change indicated. Exam Exam Question Number: 50
Reference:
Reference:
APP-003-C3 APP-003-C3;; SD-018, Compressed Gas, Pages 19-20, 19-20, Figure 2. KA KA Statement: Statement: Ability Ability to predict and/or monitormonitor changes in parameters (to prevent exceeding design design limits) associated associated with operating the PRTS controls including: including: Maintaining Maintaining quench quench tank pressure. History: History: New New - Written
- Written for for HLC-08 HLC-08 NRC NRC exam.exam.
57 57
APP-003-C3 ALARM PRT HI PRESS AUTOMATIC ACTIONS
- 1. Not Applicable CAUSE
- 1. In leakage from Makeup Water, Pressurizer Relief Valves, Pressurizer Safety Valves, RHR Loop Relief Valves, Letdown Relief Valves, Seal Water Return Relief Valve, SI Test Line Relief Valve, or SI Cold Leg Injection Header Relief Valve
- ~2.
- 2. 2 Supply to PRT N
Failure of N2
- 3. Opening of Pressurizer Safety or PORV OBSERVATIONS
- 1. (Ll-470)
PRT Level (LI-470)
- 2. (P1-472)
PRT Pressure (PI-472)
- 3. PRT Temperature (TI-471)
- 4. (TI-465, TI-467, TI-469)
Pressurizer Safety Valve Line Temperatures (TI-46S, Tl-469) S.
- 5. PORV Discharge Line Temperature (TI-463)
ACTIONS
- 1. IF a PZR PORV or Safety fails open while greater than 3S0°F, 350°F, THEN Refer To Path-1.
Path-i.
- 2. IF pressure is high, THEN vent the PRT as follows:
- 1) RC-549, PRT VENT Open RC-S49,
- 2) IF required, THEN verify a Waste Gas Compressor starts.
- 3) WHEN pressure is less than 3 psig, THEN close RC-S49.
RC-549.
- 3. IF necessary, THEN adjust Nitrogen Regulator to PRT.
- 4. IF necessary, THEN drain the PRT using OP-103.
OP-i03. DEVICE/SETPOINTS
- 1. PC-472 / 5 psig PC-472/S POSSIBLE PLANT EFFECTS
- 1. PRT Rupture Disk failure at 100 psig REFERENCES
- 1. Path-i, EOP Network Path-1,
- 2. CWD CW B-i 90628, Sheet 461, Cable P D B-190628, P
- 3. OP-i03, Pressurizer Relief Tank Control System OP-103, IAPP-003 Rev. 37 Page 25 of 53153
SD-018 SD-018 NITROGEN NITROGENAND ANDHYDROGEN HYDROGENSYSTEMS SYSTEMS ATTACHMENT ATTACHMENT10.2 10.2 Page Page11of2 of 2 HighPressure High Pressure&&Low LowPressure PressureN2 N2Loads Loads LOADSFROM LOADS FROMTHE THELOW LOWPRESSURE PRESSURE SOURCE/SETPOINT BACKUP SOURCE/SETPOINT BACKUP NITRO GEN NITROGEN SUPPLY SUPPL Y SteamDump Steam DumpAccumulators Accumulators PCV-1 PCV -1090090 175 175 psig Bank Bank "G" psig G Cylinders Cylinders- - PCV -1091 PCV-1 091 ... 160psig 160 psig NitrogenInjection Nitrogen Injectionto Condensers A&B to Condensers A&B Offsupply Off supply toto Steam Steam Same Same as Steam Dump as Steam Dump Dump Dump Accumulators Accumulators Accumulators Accumulators via via PRV-11054 reduced PRV-ll054 reduced toto 5050 psig psig Steam Dump Steam Dump Valves Valves PCV-1 PCV -1090/1 090/10 091 91 SIG PORV s (backu S/G PORVs (backupp to IA) to IA) reduced to reduced to 125 125 psig psig SIG Wet S/G Wet Layup Layup PCV-1 PCV -1090/1091 090/1091 reduce reduced to d to 55 psig via PCV-1019 PCV-1019 Resin Storage Resin Storage Tank: Tank PCV-1 PCV -1089 089 105 psig Bank: Bank "A" A Cylinders Cylinders - VCT
-
(via PCV-1 VCT (via PCV-1l9) 19) PCV PCV-1043 ... 100
-1043 ... 100 psig psig RCDT (via PCV-1 RCDT (via PCV-1014 014 - 3psig)
-
PRT (via PCV-4 PRT (via PCV-473) 73) Bank "B" Cylinders B Cylind ers -- H2 Recom H2 Recombinerbiner PCV-1044 90 psig psig PCV-1 044 ... 90
...
Gas Gas Compr essors Compressors Bubble Bubblersrs Gas Analyz Gas Analyzer er WGDT s (via WGDTs (via PCV-1 PCV-1046046 - 15
-
15 psig) psig) Gas Strippe rs Gas Strippers A "A" && B "B" (via (via PCV-1 046 PCV-1046- - 15 psig) 15 psig) Spray Spray Additi ve Tank Additive Tank (via (via PCV-1 046 - 15 PCV-1046 - 15 psig) psig) CVCS CVCS Holdup Holdup Tanks Tanks (via (via PCV- 1049 - 0.65 PCV-1049 - 0.65 psig) psig) COMPRESS COMPRESSED ED GASGAS Page Page1919ofof2020 Revision7 7 Revision INFO RMATION USE INFORMATION USE ONL ONLY Y
SD-018 SD-018 NITROGEN NITROGENAND AND HYDROGEN HYDROGEN SYSTEMS SYSTEMS ATTACHMENT 10.2 ATTACHMENT 10.2 Page 22 of2 Page of 2 High Pressure High Pressure && LowLow Pressure Pressure N2 NzLoads Loads LOADS FROM LOADS FROM THETHE ruGH HIGH PRESSURE PRESSURE SOURCE/SETPOINT SOURCE/SETPOINT BACKUP BACKUP NITROGEN SUPPLY NITROGEN SUPPLY Bank "G" Bank G Cylinders Cylinders (Steam (Steam Dump Dump Backup) Backup) PCV-1091 PCV-1091 - 160
- 160 psig psig Banks "C",
Banks D, "E" C, "D", E && "F" F Cylinders Cylinders -
- High High Pressure Pressure Header Header Backup PPS Backup PPS Banks Banks "A"A & B Cylinders
& "B" Cylinders High High Pressure Pressure Header Header PPS PPS PCV-1809 PCV-1809 - 100
- 100 psig psig IvSw IVSW Backup to:
Backup PCV-1043 - 100 PCV-1043 - 100 psig psig PCV-1044 - 90 90 psig Resin Storage Tank Resin VCT PCV-1 19) (via PCV-119) VCT (via RCDT (via PCV-1014 - 3psig) RCDT - PRT (via PRT (via PCV-473) H2 Recombiner . Gas Compressors Gas Compressors Bubblers Bubblers Gas Analyzer Gas Analyzer WGDTs (via PCV-1046 - 15 psig)
-
Gas A & "B" Strippers "A" Gas Strippers B (via PCV-1046 - - 15 psig) 15 psig) Spray Additive Tank (via PCV-1046 - 15 Spray Additive - psig) CVCS Holdup Tanks (via PCV-1049 - 0.65 - psig) SI Accumulator Accumulatorss PCV-937 - between 665 PCV-937 - 665 Pressurizer PORVs Pressurizer PORVs psig psig and and 685 685 psig psig COMPRESSED COMPRESSED GAS GAS Page 20 Page 20 of of20 20 Revision 77 Revision INFORMAT INFORMATION ION USE USE ONLY ONLY
NITROGEN SYSTEM NITROGEN SYSTEM GAS-FIGURE-2 GAS-FIGURE-2 Condenser Condenser A&B :c Ii" ~ ~ A&B ~ ~ E ~~
~ ~U O~
w w C -<> t c ii2 "'" 1i;.1i; ~~
<
~1.2 OZ
... <
~ ~ "'~ ~~
0 ...
'--AIA_ ~ N2 TO BUBBLER
~INSTRUMENT eves 0.65 HOLD-UP TANKS ~~~~~ __~________-L__~~~~~~
IVSW 1049 160# VCT~ PCV.1091 TO-4~ STEAM ... T PPS DUMPS S/G PORVs li!
- J S/G WET ........I -_ _~ VI
~:il LAYUP
.......
0...: 1097 175# BANKB BANK F BANK E BANK 0 BANK e BANK G BANKF
~\ 1\ I NS-17 STEAM STEAM PPS PPS BACKUP BACKUP PPS BACKUP DUMP DUMP TRUCK FILL II-I......1---'
BACKUP BACKUP LP-AMBIENT LIQUID HP*AMBIENT
\ I AIR AIR LP RESERVE LP RESERVE VAPORIZER 2 PWP N AIR VAPORIZER VAPORIZER gasf02 gasfO2 INFO INFORMATIONRMATION USE ONL ONLY Y
HLC-08NRC HLC-08 NRCWritten Written Exam Exam
- 51. Which
- 51. Which ONE ONE (1) (1) ofofthe thefollowing followingdescribes describesthe thedesign designfeatures featureswhich whichact acttoto limit limitS/G S/G blowdown blowdown rate for a Steam Break rate for a Steam Break accident? accident?
A. Swirl Vane A. Swirl Vane Separators Separators inin thethe upper upperS/GS/G internals. internals. B. AA set B. set ofof 77 venturis venturis inin the the S/G SIG outlet outlet nozzles. nozzles. C. Flow venturis C. Flow venturis inin eacheach steam steam line, line, located located atatthe the operating operating floor. floor. D. MSIVs D. MSIVs are are required required to to close close within within 55 seconds. seconds. 51 51
HLC-08 NRC HLC-08 Written Exam NRC Written Exam K1.01 OOlIMAINIREHEAT
- 51. 039 K1.01 51.039 STEAM/2/1/3.1/3.2/ROILOWIN/AJNEW- 2008/SGS-004 001/MAIN/REHEATSTEAMJ2/113.1I3.2fROILOWININNEW - 2008/SGS-004 Which ONE Which ONE (1) (1) ofof the following describes the following describes the the design design features features which which act act to limit S/G to limit SIG blowdown blowdown rate for rate for aa Steam Steam Break Break accident?
accident? A. Swirl Vane A. Swirl Vane Separators Separators inin thethe upper internals. SIG internals. upper S/G B B~ A set A set ofof 77 venturis venturis in SIG outlet the S/G in the nozzles. outlet nozzles. C. venturis in Flow venturis C. Flow in each each steam steam line, line, located located at at the operating floor. the operating floor. D. MSIVs D. MSIVs are are required required to to close within 55 seconds. close within seconds. The correct The correct answer answer is is B. B. A: Incorrect - Swirl vanes are designed to impart radial motion to the steam
-
steam to remove remove moisture. B: Correct B: Correct - - S/G Steam nozzles are provided with flow limiting devices to restrict the steam steam flow resulting from a Steam Line Break. C: Incorrect - Flow venturis in the lines at floor level produce a small delta P to the steam as
-
as aa means of measuring flow. Pressure drop (and the flow limiting effect) is designed to be small for efficiency reasons. D: Incorrect - MSIV closure time would have no effect on UPSTREAM breaks. 0: - Exam Question Number: 51 Exam
Reference:
SO-025, SD-025, Main Steam, Page 9, Figure 1; SO-048, SD-048, S/G, SIG, Page 8, Figures 4 and and 8. 8. KA Statement: Knowledge of the physical connections and/or cause-effect relationships KA between the MRSS and the following systems: SIG. S/G. History: History: New New - Written for HLC-08 NRC Exam.
-
58 58
SD-025 SD-025 MAIN MAIN STEAM STEAM SYSTEMSYSTEM The three The three steam steam lines connect toto aa 72-inch lines connect 72-inch header. header. The The 72-inch 72-inch header header then then divides divides into two headers (generally referred to as into two headers (generally referred to as the North and the North and South South Headers). Headers). The 72-inch header The 72-inch header has the following: has the following: 1.1. Drains Drains 2.
- 2. Vent valves (used Vent valves (used to ensure steam to ensure steam system system remains remains depressurized depressurized during during outage) outage) 3.
- 3. Taps for Taps for header header pressure pressure instrumentation instrumentation The North The North and South header and South header supply supply steam steam seals, seals, condenser condenser steam steam dumps, dumps, heating heating steam to steam to MSRs, MSRs, andand the turbine. These the turbine. These headers headers havehave drain drain taps taps to remove the to remove the moisture from the moisture from steam line the steam line continuously continuously and and cancan bebe drained drained to to the the atmosphere atmosphere when warming when warming steam steam lines.
lines. These These headers headers feed feed thethe left left and and right right side side of of the the turbine. The turbine. The steam steam is is exhausted exhausted below below the the LP LP turbines turbines directly directly to to the the Main Main Condensers. 3.0 COMPONENT DESCRIPTION COMPONENT DESCRIPTION 3.1 3.1 Flow Nozzles
.~ > Steam Flow Limiter Number 33 Type 7 venturies in a machined disc Size Maximum throat area of the 7 venturis is 1.4 sq. ft.
Venturi Material Inconel 600 casting Steam Flow Flow Nozzles Number Number 33 Type Flow Flow Tube, Fabricated insert Work Work pressure pressure 1085 1085 psig psig Work Work Temperature Temperature F 0 600 600°F Pipe Pipe Size Size 26" 26 Cone Cone andand Throat Throat Material Material 304 304 Stainless Stainless Throat Diameter Throat Diameter 16.469 16.469 +/- + 0.010 0.010 Each Each main main steam steam line line contains contains twotwo types types ofof steam steam flow flow nozzles. nozzles. One One type type isis aa steam steam flow limiting device flow lltin device located located within within the the generator generator shell shell steam steam outlet outlet nozzle. nozzle. The other The other fl2.w nozzle (venturi)
£zzleCvenmr i) isis located located further further downstream downstream in th~ steam in the steam pipeline pipeline just just above above the the containment containment operating operating floor.
floor. MSS MSS Page 990f44 Page of 44 Revision77 Revision INFORMAT INFORMATION ION USE USE ONLY ONLY
SYSTEM SYSTEM DIAGRAM DIAGRAM (SIG (S/G TOTO 72 72" HEADER) HEADER) MSS-FIGURE-l (Rev MSS-FIGURE-1 (Rev 0) 0) ATMOS ATMOS ATMOS ATMOS ATMOS ATMOS ATMOS ATMOS v ATMOS ATMOS 72" HEADER 72 HEADER PT NORTH NORTH { r, Iv
@
SAFETI SAFETIES ES MS SAMPLE MS nAn ATMOS S/G SOUTH SOUTH STEAMDRIVEN STEAM DRIVEN AUX. FEEDWATER AUX. FEEDWATERPUMPPUMP DD jmSSf01] jmssfOlI
SD-048 SD-048 STEAM STEAM GENERATOR GENERATORSYSTEM SYSTEM the RCS during the ReS accidentconditions, during accident conditions, asas required. required. This This ensures ensures the ability toto achieve the ability achieve safe shutdown safe shutdownof reactor and the reactor ofthe permits natural and permits natural circulation circulation of of the RCS when required. the ReS when required. The SIG limits The S/G limits steam steam flow flow for any downstream for any downstream Main Main SteamSteam Line Line Break Break (MSLB). (MSLB). The The H
~ S/G steam nozzles are provided with S/G steam nozzles are provided with flow flow limiting limiting devices devices to to restrict restrict the the steam steam flow flow resulting from resulting from aa steam steam line break. The line break. The flowflow restrictors restrictors protect protect the the containment containment from from exceeding its design pressure and prevent exceeding its design pressure and prevent excessive cooldown excessive cooldown rate rate ofof the the ReS RCS by by limiting the limiting the steam steam flowflow that that can can result result from from aa MSLB.
MSLB. Normal Operating Normal Operating Functions Functions The S/Gs The S/Gs convert converi the the heat heat generated generated in in the RCS into the ReS into steam steam as as required required for for the the turbine turbine and auxiliaries during and auxiliaries during all all modes modes of of Main Main SteamSteam System System operation. operation. The design The design of of the the S/Gs S/Gs includes includes primary and and secondary secondary provisions provisions for for the the removal of of moisture to preclude carryover in excess moisture to preclude carryover in excess of 0.25 percent of 0.25 percent of of thethe steam steam flow. flow. TheThe first first stage of of moisture separation occurs in the swirl vanes and the second second stage in the contoured contoured vane banks. 2.3 2.3 System Flow Paths (Figure 4) Primary Side Primary Reactor coolant enters the inlet side of the channel head at the bottom of the S/G Reactor 5/G through the inlet nozzle, flows through the U-tubes to the outlet side of the channel head and leaves the generator through another bottom nozzle. It then passes out head and out ofof the the S/G S/G toto the intermediate intermediate leg. The coolant leaves the S/G and flows to the RCP Rep suction suction through through the intermediate leg. Secondary Secondary Side Feedwater Feedwater to to the S/G enters the S/G enters justjust above above the the top top ofof the the U-tubes U-tubes through aa feedwater feedwater ring.ring. The The water water flows flows downward downward throughthrough an an annulus annulus between between the the tubetube wrapper wrapper and and the the shell shell and and then then upward upward through through the the tube tube bundle bundle wherewhere partpart ofof itit isis converted converted to to steam. steam. The The steam-water steam-water mixture mixture from from thethe tube tube bundle bundle passes passes through through aa steam steam swirl swirl vane vane assembly assembly whichwhich imparts imparts aa centrifugal centrifugal motion motion to to the the mixture mixture and and separates separates the the water water particles from the steam. The particles from the steam. The water spills water spills over over thethe edge edge of of thethe swirl swirl vane vane housing housing and and combines combines with with the the feedwater feedwater for for another another pass pass through through the the tube tube bundle. bundle. The The steam steam risesrises through through additional additional separators separators which which limit limit thethe moisture moisture content content of ofthe the steam to one fourth of one steam to one fourth of one percent or percent or less less under under all all design design load load conditions. conditions. SG SG Page Page88of 28 of28 Revision66 Revision INFOR INFORMATION MATION USE USE ONLY ONLY
Steam Generator Steam Generator Diagram Diagram SG-FIGURE-4 SG-FIGURE-4 SECONDARY SEPARATOR. PERFORATED PlATE (TYP. 8 PLACES) STEAM WITH MOSITUItE SECONDARY SEPARATOR SECONDARY SEPARTOR ............- - - - - VANES (TYP. 8 PLACES) WATER LEVEL LEVEL BOTTOM DECK PlATE WATER SECONDAR.Y SEPARATOR SECONDARY /MNWAY ------.~.t 5" SCH .0 DRAIN PIPES (TYP. 16 PLACES) WIDERANGE WIDE RANGE NARROWRANGE NARROW RANGE
~------WlDE RANGE LEVel UPPER TAP 300%
100% 1 100% _ CENTRAL DRAIN 90% 90'11 ~....JJJ.. __------STEAM VENT 09% 80'11 70% NORMAL OPERAnNG WATER LEVEL (APPROX)
~:~:li8~~i~~ (lYP.3 PlACES) 70%
90% 90'11 60% 60'11 THREE (3) PRIMAAY SEPARATOR SWIRL VANE BARRELS 00% 50% 40%
.0'11 PRIMARY SEPARATOR DOWNCOMER ---fl--it BARREL TYP. 3 PLS.
30% 30'11 80'11 20% ZO'Ii fEEDWATER DISTRIBUTION RING WITH J-NOZZLES 10% 10'1i 0% 0% NARROW RANGE LEVEL 70% WRAPPER LOWER TAPS 70'11
'...JIM!- __~~J-.fi:.:::"-ANTI-VIBRATION BAAS TRANSITION CONE 60%
60'11 00%- DOWNCOMER ANNULUS 40%
.0'11 -
QUATREFOIL TUBE SUPPORT PlATE 30% - STEAM WATER 30% MIXTURE WATER ENTERS HEATING AND 20% SOILING SECTION ZO'll STAY ROD (INSIDE SPACER PIPE) SPACER PIPE PERFORATED BOTTOM BLOWDOWN PIPE 6'HANOWAY 00% 10'11 - FLOW DISTRIBUTION BAFFLE SIX (6) TUBELANE FLOW WIDE RANGE LEVEL BLOCKING PLATES LOWER TAP 0% 0'11 - 6"HANDHOLE BOTTOM BLOWDOWN DIVIDER PLATE DIVIDER PLATE PRIMARY MANWAY NOZZLE DRAIN MANWAY DRAIN sgro4 sgIO4 _- .... ...... _., ...
STEAM FLOW STEAM FLOW LIMITER SG-FIGURE-8 SG-FIGURE-8 1.12
- (REF.)
sgfOB sgfOB
HLC-08NRC HLC-08 WrittenExam NRCWritten Exam
- 52. Given
- 52. Giventhethefollowing:
following:
- AALoss
- LossofofInstrument InstrumentBus Bus11 has hasoccurred.
occurred. Thecrew
- The
- crewisisperforming performingactions actionscontained containedininAOP-024, AOP-024, LOSS LOSSOF OFINSTRUMENT INSTRUMENTBUS. BUS.
The Pressurizer
- The PressurizerPressure PressureController Controller(PC-444J)
(PC-444J)AUTOAUTO light lightilluminates illuminatesfor forapproximately approximately
-
1515seconds, seconds, thenthen extinguishes, extinguishes, andandthen thenthe the MANUAL MANUALlight lightisis illuminated. illuminated. Which ONE Which ONE (1)(1) ofof the the following following describes describes the the event eventinin progress progress andand the the associated associated action, action, ifif any? any? A. Instrument A. Instrument Bus Bus 11 power power isis NOT NOT restored. restored. Operate Operate Pressurizer Pressurizer Heaters Heaters and and Spray Spray valves valves manua lly. manually. B. Instrument Instrument Bus Bus 11 power power isis restored. restored. PC-444J PC-444J AUTO AUTO has B. has failed, failed, continue continue to operate inin to operate MANUAL. MANUAL. C. Instrument Bus C. Instrument Bus 11 power power isis restored. restored. Restore Restore PC-444J PC-444J to to AUTO AUTO control. control. D. Instrument D. Instrument Bus Bus 11 power power is NOT restored. is NOT restored. Operate Operate PC-444J PC-444J in in MANUAL. MANUAL. 52 52
HLC-08NRC HLC-08 NRCWritten Written ExamExam
- 52. 062
- 52. 062A3.05 A3.05OOI/AC 001/ACELECTRICAL ELECTRICALDIST/2/1/3.5/3.6/RO/HIGH/N/AJRNP DIST/2/1/3.5/3.61R0/HIGHJN/A/RNPAUDIT AUDIT- 2001lAOP-024-004
- 2001/AOP-024-004 Given the following:
Given the following:
- AA Loss
- Loss ofof Instrument InstrumentBus Bus 11 hashas occurred.
occurred. The crew
- The
- crew isis performing performing actionsactions contained contained inin AOP-024, AOP-024, LOSS LOSS OF OF INSTRUMENT INSTRUMENT BUS. BUS.
The Pressurizer
- The
- Pressurizer PressurePressure Controller Controller (PC-444J)
(PC-444J) AUTOAUTO lightlight illuminates illuminates for for approximately approximately 15 seconds, 15 seconds, then then extinguishes, extinguishes, and and then then the the MANUAL MANUAL light light isis illuminated. illuminated. Which ONE Which ONE (1) (1) of of the the following following describes describes thethe event event inin progress progress and and the the associated associated action, action, ifif any? any? A. Instrument A. Instrument Bus Bus 11 power power isis NOT NOT restored. restored. Operate Operate Pressurizer Pressurizer Heaters Heaters and and Spray Spray valves valves manually. manually. B. Instrument B. Instrument Bus Bus 11 power power is restored. PC-444J is restored. PC-444J AUTO AUTO has has failed, failed, continue continue to to operate operate in in MANUAL. MANUAL. C Instrument CY- Instrument Bus Bus 11 power power is restored. Restore is restored. Restore PC-444J PC-444J to to AUTO AUTO control.control. D. Instrument D. Instrument Bus Bus 11 power power is NOT NOT restored. restored. Operate PC-444J in MANUAL. The correct The correct answer answer is is C. A: Incorrect A: Incorrect - The
- The controller controller has NOT failed, it indicated it was returning to the normal source source of power.
of power. B: B: Incorrect Incorrect - Power
-
Power has been restored to PC-444J which operated through its normal power power restoration restoration cycle. The controller does NOT NOT automatically swap swap to the Auto mode. mode. C: C: Correct Correct - - When When powerpower is is restored to PC-444J, PC-444J, the Auto indicatorindicator will flash indicating indicating power power is is returned returned to to the the normal normal mode. mode. TheThe controller controller will will stay stay in in Manual Manual control. control. Operator Operator actionaction isis required required lAW lAW AOP-024 AOP-024 to to restore restore controller controller to to Auto. Auto. D: D: Incorrect Incorrect - Power
-
Power is is restored restored instead instead ofof momentarily momentarily restored. restored. Power Power restoration restoration will will leave leave the the controller controller in in MANUAL. MANUAL. Controller Controller can can be be operated operated in in MANUAL MANUAL or or AUTOMATI AUTOMATIC C while while on on alternate alternate power power source. source. Exam Exam Question Question Number: Number: 52 52
Reference:
Reference:
AOP-024, AOP-024, Page Page 5;5; OP-0O1, OP-001, PagesPages 23-25. 23-25. KA KA Statement: Statement: Ability Ability toto monitor monitor automatic automatic operation operation ofof the the ac ac distribution distribution system, system, including: including: Safety-relate Safety-related d indicators indicators and and controls. controls. History: History: Direct Directfromfrom Bank. Bank. 59 59
Rev. 29 AOP-024 LOSS OF INSTRUMENT BUS Page 24 of 84 CONTINUOUS USE ATTACHMENT 11 EXTENDED LOSS OF INSTRUMENT BUS 11 (AND 6) CPage (Page 11 of 5) NOTE The following control functions/indications will be lost until Instrument Bus 11 and 66 are restored: Steam Dump Tavg mode of operation FRV A A Automatic control FRV Bypass Valve B B CFCV-489) (FCV-489) PCV-145 Controller Clocks (locks up) PZR Heaters
~ >PZR PZR Pressure Controller.
Controller, PC-444J Clocks (locks up) PZR Level Controller. Controller, LM-459G Clocks (locks up) PZR PORV. PORV, PCV-455C PZR Spray Valve Controller. Controller, PC-444G Clocks (locks up) PZR Spray Valve Controller. Controller, PC-444H Clocks (locks up) PZR Safety Acoustic Monitors Charging Pump Controller A. A, SC-151A SC-l5lA Clocks (locks up) S/G B B PORV FCV-113A FCV-ll3A Controller Clocks (locks up) VCT Level Controller. Controller, LC-112 Clocks (locks up) Excess Letdown Temperature Channel TI-139
- 1. Continue to operate PCV-464B.
PCV-464B, Steam Dump Controller. Controller, in Manual Pressure mode.
- 2. Continue to operate the FRV A A in MAN mode.
- 3. Contact Operations Staff for availability of a dedicated FRV watch. watch.
- 4. IF CHARGING PUMP A A is in service.
service, THEN perform the following:
- a. IF necessary.
necessary, THEN start CHARGING PUMP B B OR C.
- b. Stop CHARGING PUMP A.
- 5. Control PZR level by manual control of Charging Pump speed.
_________ CONTINUOUS USE CONTINUOUS USE Section Section 8.4.3 8.4.3 Page Page 11 of of 44 INIT NOTE: NOTE: This section This section hashas been been screened screened lAW lAW PLP-037 PLP-037 criteria criteria and and determined determined to to be aa Case be Case Three activity. No Three activity. No additional additional management management involvement involvement isis required required beyond beyond that routinely that routinely provided provided by first line by first line supervision. supervision. ITS LeO ITS LCO 3.8.7 3.8.7 and and LCO LCO 3.S.S 3.8.8 should should be referenced for be referenced for instrument instrument bus bus operability operability requirements requirements. . 8.4.3
~S.4.3 Transferring Instrument Instrument Bus 11 Power Supply{ TC "Transferring Transf erring Instrument Bus 11 Power Supply" Supply \f C \1 \l "3"3 }}
- 1. Initial Conditions
- a. This revision has been verified to be the latest revision available.
Date
- b. IF transferring to the alternate power supply, THEN VERIFY MCC-S MCC-8 is energized AND no other Instrument Bus is being supplied by MCC-8. MCC-S.
- c. IF transferring to the normal power supply, THEN VERIFY MCC-5 is energized.
- d. CHECK CHECK that Reactor Trip Breakers are OPEN OR Reactor Power is greater than P-i P-10.
0. e.
- e. PERFORM PERFORM The Following: Following:
1)
- 1) EVALUATE EVALUATE the the affect affect ofof aa loss loss of of Instrument Instrument Bus Bus 11 onon illuminated illuminated bistables bistables in in channels channels II, II, III, III, and and IVIV 2)
- 2) IF IF the the loss loss of of Instrument Instrument Bus Bus 11 concurrent concurrent with with illuminated illuminated bistables bistables inin channels channels II,II, III III or or IV IV will will cause cause aa transient, transient, THEN THEN CLEARCLEAR the the affected affected bistables bistables prior prior toto continuing.
continuing. OP-o01 IOP-001 Rev. Rev. 25 25 I Page 23 Page 23 of of43 431
_____ Section Section8.4.3 8.4.3 Page Page22ofof44 8.4.3.1 (Continued) 8.4.3.1 (Continued) INIT NOTE: NOTE: Performanceofofthis Performance thissection sectionwillwill result resultininthethefollowing: following:
- RCS Letdown RCS Letdown Isolation Isolation
- Momentary loss Momentary loss of of PZR PZR Heaters Heaters
- Mome ntary loss of all PZR Momentary loss of all PZR Pressure Pressure and and Level Level Controllers Controllers f.f. REVIEW EDP-008 REVIEW EDP-008 for for additional additional loads loads that that will will be be lost.
lost. 2.
- 2. Instructions Instructions NOTE: Loss of Loss of Instrument Instrument Bus Bus 11 will will result result in in isolating isolating letdown letdown and and tripping NOTE: tripping PZR PZR heaters from the PZR Low Level Relay heaters from the PZR Low Level Relay (LC-459C1-X). (LC-45 9C1 -X). ThisThis can only only be be avoided avoided by by manually overriding manually overriding the relay relay the the entire entire time time itit is is deenergized.
deenergized.
- a. ISOLATE Letdown ISOLATE Letdown using OP-301. OP-301.
- b. VERIFY PZR Heaters VERIFY Heaters are OFF.
- c. PLACE FRV A PLACE "A" contro ller in (FCV-478) controller (FCV-478) in MAN.
d.
- d. IF IF the plant plant is in Mode 1, is in 1, THEN verify the follow following:
ing:
-
Rod Rod Contro Controll in Manual. in Manual.
-
Turbin Turbine e Contro Controll in in Manua Manual. l. I OP-OO1 IOP-001 I Rev. Rev.25 25 I Page24 Page 24ofof43431
Section 8.4.3 Page 3 of 4 8.4.3.2 (Continued) INIT CAUTION Performance of the following step will result in a momentary loss of power to Instrument Busses 11 and 6.
- e. PLACE the INST BUS 11 PWR XFER SW to the desired position.
NORM/ALT NORM/ ALT (Circle one)
- f. RESET the Dropped Rod Alarm by momentarily placing the Dropped Rod Mode Selector switch for N-41 to RESET.
NOTE: When a Manual/Auto control station is reenergized, 15 to 20 sec. is needed for the AUTO light to go out and the Manual/Auto station to revert to the manual mode. g. g: RESTORE affected controllers on the RTGB to AUTO.
- h. RESTORE Letdown using OP-301.
I.i. IF desired, THEN PLACE Rod Control in AUTO.
- j. IF desired, THEN PLACE Turbine Control in AUTO.
OP-ooi IOP-001 Rev. 25 Page 25 of 43 431
QUESTIONS REPORT QUESTIONS REPORT AUDIT (;2 forAUDIT for (2oo) 00 t) 1. 1.057AA2.14001 057 AA2.14 001 A Loss A Loss of of Instrument Instrument BusBus 11 hashas occurred. occurred. The crew The crew is performing actions is performing actions contained contained in in AOP-024, AOP-024, Loss Loss of of Instrument Instrument Bus. Bus. The Pressurizer The Pressurizer Pressure Pressure Controller Controller PCPC -444J,
-444J, AUTO light light comes comes on on for for approximately approximately 15 seconds, 15 seconds, then goes out, and goes out, and then then the MANUAL light MANUAL light is is illuminated.
illuminated. Which ONE ONE (1) (1) of of the following describes the event event in in progress progress and and the the associated associated action? A. PC-444J AUTO controller has failed. Operate Pressurizer Pressurizer Pressure control in Manual as directed by AOP-019, AOP-01 9, Malfunction of RCS Pressure Control. B. Power is restored to PC-444J. The controller has failed to swap to AUTO. Operate Pressurizer Pressure control in Manual as directed by AOP-019, AOP-01 9, Malfunction of RCS Pressure Control. C~ CY Power is restored to PC-444J. Restore to Automatic control as directed by AC P-024. AOP-024. D. Power was momentarily restored to PC-444J. When the controller AUTO light is illuminated again, verify Auto control by adjusting the controller in accordance with AOP-024. C is correct SRO Question 080 Tier 1 1 Group 1 1 K/A KIA Importance Rating - SRO 3.6-Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: That substitute power sources have come on line on a loss of vital AC. Reference(s) - VAC SD.
- SO. AOP-024 Proposed Proposed References to be be provided to applicants during during examination examination - None
- None Learning Learning Objective -
-
Question Question Source Source - New
- New Question Question History History - -
Question Question Cognitive Cognitive Level Level - Comprehension
- Comprehension 10 10 CFR CFR Part 55 Content Part 55 Content - 43
- 43 Comments Comments - -
Category Category 1:1: Category Category 2: 2: Category Category 3: 3: Category Category 4: 4: Category 5: Category 5: Category Category 6: 6: Category Category 7: 7: Category Category 8: 8:
- Tuesday, Tuesday, Juno June 10, 2008 12:35:46 PM 10,200812:35:46 PM 1
Rev. 29 Rev. 29 AOP-024 AOP-024 LOSS OF LOSS OF INSTRUMENT INSTRUMENT BUS BUS Page 55 of Page 84 of 84 H__STEP_H INSTRUCTIONS INSTRUCTIONS i I RESPONSE NOT RESPONSE NOT OBTAINED OBTAINED 6.
- 6. Failed Instrument Determine Failed Instrument Bus Bus (IB) From (IB) From Any OfOf The The Following:
Following:
** Available indications indications OR
** Table Below Inst Indication To Check Bus 11 "A" S/G FR-478, A SIG Level 22 FR-488, "B" SIG Level B S/G 33 FR-498, "C" C S/G Level 44 TR-408, Tavg 66 LI-459A, PZR Level 77 LI-460, LI-460. PZR Level 8 LI -461, PZR Level LI-461.
9 LI-462, LI-462. PZR Level NOTE Affected controllers may be returned to AUTO anytime the Instrument Bus power is regained. Controllers will take 15 to 20 sec. to return to manual after after reenergizing.
** 7.
- 7. Check Emergency Busses E-l AND IF an
.
an Emergency Bus has E-2 E ENERGIZED FROM THE
- THE 4160V 4l60V deenergized, deenergized. THEN THEN check check the EDG BUSSES BUSSES STARTS STARTS and and its its output output breaker CLOSES.
CLOSES. IF IF the the EDG EDG has has NOT NOT auto-started, auto-started. THEN THEN initiate initiate aa start start from from the RTGB RTGB (will (will involve involve aa 4.5 4.5 minutes minutes delay). delay).
HLC-08 NRC Written Exam
- 53. Given the following:
- Reactor Trip and Safety Injection have occurred.
-
- The following alarms were received in the Control Room:
-
- APP-004-A1, S/G A STM LINE HI DELTA P
- P SFGRDITRIP
- APP-004-A5, S/G A LO LVL & STM>
- STM > FWF TRIP
- APP-006-A2, S/G A STM>
- STM > FW FLOW
- APP-006-E5, STM LINE LO PRESS
-
- The crew has completed Supplement G, STEAM GENERATOR ISOLATION.
-
Which ONE (1) of the following describes the Main Steam System component(s) controlling RCS Heat Removal? A. Condenser Steam Dumps from S/Gs "A", A, "B", B, and "C". C. B. S/G PORVs "A",A, "B", B, and "C". C. C Main Steam Safety Valves. B and "C" C. S/G "B" D. Condenser Steam Dumps from S/Gs "B" B and "C". C. 53
HLC-08 NRC Written Exam HLC-08 NRC'Written Exam
- 53. 039
- 53. 039 K3.06 K3.06 OOllMAINIREHEAT 001/MAIN/REHEAT STEAM/2/1I2.8/3.1IRO/HIGH/N/NRNP STEAMI2/1/2.8/3.1JRO/HIGHJN/AJRNPBAN:K/EPP-II-005 BANK/EPP-1 1-005 Given Given the following:
the following: Reactor Trip
- Reactor
- Trip and Safety Injection and Safety Injection have have occurred.
occurred. The following
- The
- following alarms alarms were received inin the were received the Control Control Room:
Room: APP-004-A1
- APP-004-A
-
1,, S/G SIG AA STM LINE HI STM LINE HI DELTA DELTA PP SFGRDITRIP SFGRD/TRIP APP-004-A5, S/G
- APP-004-A5,
- SIG AA LO LVL && STM LO LVL STM> FWF TRIP
> FWF TRIP APP-006-A2, S/G
- APP-006-A2,
- SIG AA STM STM> FLOW FW FLOW
> FW APP-006-E5, STM
- APP-006-E5,
- LINE LO STM LINE PRESS LO PRESS
- The crew
- crew has completed Supplement has completed Supplement G, STEAM STEAM GENERATOR GENERATOR ISOLATION.
ISOLATION. Which ONE (1) of the following describes the Main Steam System System component(s) component(s) controlling controlling RCS Heat Removal? A. Condenser Steam Dumps from S/Gs "A", A, "S", B, and "C". C. B. S/G PORVs "A", A, "S", B, and "C". C. C. S/G "s" B and "c" C Main Steam Safety Valves. D Condenser Steam Dumps from S/Gs D~ "s" B and "C". C. The correct answer is D. The A: Incorrect - Steam Dump NOT available from S/G "A".
- A. S/G "A" A isolated per Supplement G.
B: S: Incorrect - S/G PORV is available from S/Gs B
- "s" and C.
"C". S/G A "A" is isolated lAW Supplement G.
C: Incorrect - Steam Dumps are available to condenser from S/Gs B
- "s" and C "c" and Steam Line PORVs UBIJ "S" and C.
"C". Normal control system setpoints will prevent Main Steam Line Safety valves from lifting.
D: Correct - - S/C S/G A is isolated lAW "A" is lAW Supplement Supplement C. G. S/Cs S/Gs B "c" are aligned to dump "S" and C steam to condenser. Exam Exam Question Question Number: Number: 53 53
Reference:
Reference:
Supplement Supplement G, G, Page Page 37;37; SD-031, SD-031, SteamSteam Dump, Dump, Pages 8, 9 and Pages 8,9 and 19. 19. KA KA Statement: Statement: Knowledge Knowledge of of the the effect effect that that aa loss loss or or malfunction malfunction ofof the the MRSS MRSS will will have have on on the the following: following: SDS. SDS. History: History: Direct Direct from from Bank. Sank. 60 60
Rev. 35 EPP-Supplements SUPPLEMENTS Page 37 of 89 ]__STEP H INSTRUCTIONS I I CONTINUOUS USE CONTINUOUS USE RESPONSE NOT OBTAINED I Supplement GG Steam Generator Isolation (Page 1 1 of 12)
- 1. Go To Appropriate Step From Following Table:
S/G TO BE ISOLATED STEP S/G S/GA A 22 S/G s/GBB 18 S/G S/GCC 34
.~* 2. Check S/G A A - FAULTED
- WHEN Tavg less than 547°F. THEN perform Steps 3 3 AND 4.
WHEN S/G A A level is greater than 8% [18%J. [18%] . THEN observe the NOTE prior to Step 5 5 and perform Steps 55 though 9. Verify ruptured STEAM LINE PORV setpoint at 1035 psig using Status Board. Go To Step 11.
--3.
- 3. Verify Vl-3A.
V1-3A, MSIV - CLOSED
-
--4.
- 4. Verify MS-353A. MSIV Vl-3A V1-3A BYP --
CLOSED NOTE Local operation of the FRV and B/P valves below is via reverse acting handwheels.
-5.5. Verify FRV AA - CLOSED
-
--6.
- 6. Verify FRV AA BYP - CLOSED
-
SD-031 SD-031 STEAM DUMP STEAM DUMP SYSTEMSYSTEM the desired steam the desired pressure as steam pressure as set on the set on the steam steam dumpdump controller controller andand modulates modulates steamsteam dump valves dump valves open open as necessary to as necessary maintain steam to maintain steam pressure pressure at at setpoint. setpoint. Tavg Mode Tavg Mode of control has of control basically two has basically sub-modes: load two sub-modes: load rejection rejection and and turbine turbine trip. trip. The function of either of The function of either of these modes these modes is to control is to control TavgTavg to to some some desired desired value value setset by by the operator. the operator. If the plant were to experience If experience aa load load rejection there would initially initially exist exist aa power power mismatch between mismatch between the the reactor and turbine until the rods and turbine until the rods could could be inserted to be inserted to lower lower power. This reactor power. This mismatch would cause cause TavgTavg to to increase, increase, which which will cause cause the rod control system to insert rods to lower the temperature. If If the load rejection is larger than rod control is designed to handle, the steam dumps would open to give an artificial limit the Tavg.rise. load to limit Tavgrise. The amount of modulation open of the steam dump valves is controlled by the deviation of actual Tavg (median Tavg is used) from program Tavg (Tref). If the deviation exceeds a preset value another signal is sent to the steam dump (Tret). pop open. With the turbine at a lower power level and impulse pressure, valves to "pop" the program value for Tref will be lower than before the load rejection. As the rod control system inserts the rods, lowering Tavg, the deviation between actual and program temperature decreases and the steam dump valves modulate shut. The Turbine Trip submode basically performs the same as load rejection mode. When a turbine trip occurs, a power mismatch occurs between the reactor and the secondary system, even if a reactor trip occurs. Power in the reactor does not immediately go to zero, so heat must be removed from the RCS. Since turbine impulse pressure is zero after a trip, Tref goes to its minimum value. If sufficient deviation from no load Tavg is sensed, the steam dump valves will modulate open or "pop" pop open if the deviation exceeds a preset value. (SD-Figure-2 (SD-Figure-2)) The The system system has to meet three permissives "permissives" to be able to modulate the condenser steam steam dump valves: a circulating water pump must be running, adequate condenser vacuum must be available (>19.7Hg (> 19.7"Hg Vac; i.e. APP-008-B6APP-008-B6,, CONDENSECONDENSER R LO VACUUM TURB TURB TRIP,TRIP, extinguished extinguished)) and and the the system system mustmust be be turned turned on. on. InIn addition addition to to the the permissives being met, permissives being met, the steamthe steam dump system system must must be be armed "armed" to to allow allow dump valves valves to to open. open. In In the steam pressure the steam pressure mode mode of of control, control, the the system system isis armed armed when when Steam Steam Pressure Pressure Mode Mode is is selected selected andand the the steam steam dumpdlimp valves valves can can modulate modulate as as necessary necessary to to control control main steam header main steam header pressure pressure as as long long as as the the permissives permissives are are met. met. InIn the the Tavg Tavg mode mode of control further of control further stimulus stimulus isis required required to to arm arm the the steam steam dumps. dumps. If If aa load load rejection rejection isis sensed, sensed, as as determined determined by by turbine turbine impulse impulse pressure pressure decreasing decreasing by by aa Steam Steam Dumps Dumps Page Page 88 of of2626 Revision 77 Revision INFORMAT INFORMATION ION USE ONLY ONLY
SD-03 1 SD-031 STEAM DUMP STEAM DUMP SYSTEM SYSTEM prescribed amount prescribed amount in preset time, in aa preset time, the the load rejection submode load rejection submode will will "arm" arm and and actuates actuates to help to help control control Tavg along the Tavg along the Tavg Tavg program. program. If If aa turbine turbine trip trip occurs, occurs, the the turbine turbine trip trip submode "arms" submode arms and and actuates actuates to reduce Tavg to reduce Tavg to to the the no-load no-load value. value. Since PT-447 Since PT-447 armsarms the Steam the Steam Dumps Dumps and PT-446 programs and PT-446 programs TrefTref forfor the the Steam Steam Dumps, Dumps, the the failure failure ofof aa single instrument single instrument will not cause will not cause the the Steam Steam Dumps Dumps to to open open when when in in the the Tavg Tavg mode mode (see(see SD-Figure-6). SD-Figure-6). (SD-Figure-3) (SD-Figure-3) The term "arm", The term arm, when when used used with thethe steam steam dumps, dumps, refersrefers toto nitrogen nitrogen being being aligned to the steam dump positioner and the high temperature trip open 3-way 3-way valves. When nitrogen is aligned to the positioner, the output of the different steam steam dump controllers can then control the positioner to allow can allow the nitrogen to flow flow to the diaphragm of the valve and modulate the valve based on the temperature deviation. If the "trip trip open" open signal is present, the 3-way valve can*put can put full nitrogen pressure to the booster, which in turn permits full nitrogen pressure to pass and be applied to the diaphragm of the valves, which causes the valves to pop open. (SD-Figure-4) The steam dump valves, when actuated by the Tavg deviation from Tref in the load rejection submode, operate in banks. The fIrst first bank arms on a 15 15% % load rejection and opens at"aata deviation of 5°F and is full open at 11.6°F. The second bank arms on a 35% load rejection and begins to open at 11.6°F deviation and is fully open at 15.9°F. The 4th bank, SIG S/G PORVs, is modulated by the SDCS on a 50% load rejection and starts to open at 15.9°F and is fully open at 20.5°F deviation. The same staggered operation occurs in the turlSine turoine trip submode with slightly different setpoints, except that Bank 4, SIG S/G PORVs, will not be controlled by the steam dump system. An interlock exists which turns off condenser steam dumps when Tavg reduces to less than 543°F. This interlock prevents the steam dump actuation from causing an overcooling event. event. The interlock can be be bypassed once once Tavg is less than 543°F 543°F with a spring-loaded switch on on the RTGB, which allows bank 11 steam dump valves to be turned backback on. on. This This allows allows steam steam dumps to to be be used used to to perform perform aa plant plant cooldown cooldown afterafter definite operator defInite operator action is performed is performed to confirm confIrm thatthat a reduction in in Tavg below below 543°F 543°F isis warranted. warranted. Once the plant Once the plant has been cooled has been cooled to to 450°F 450°F duringduring a controlled controlled cooldown cooldown (GP-007), (GP-007), the the other other bank bank ofof condenser condenser dumpdump valves valves can can bebe used used after after I&C I&C installs installs jumpers/lifts jumpers/lifts leads in Miscellaneou leads in Miscellaneous s Relay Relay Rack Rack 50.50. Steam Steam Dumps Dwnps Page Page 99 of of26 26 Revision 77 Revision INFORMAT INFORMATION ION USE ONLY ONLY
SD-03 1 SD-031 STEAM STEAMDUMP DUMPSYSTEM SYSTEM 6.0 6.0 SYSTEMOPERATION SYSTEM OPERATION 6.1 6.1 NormalOperation Normal Operation The operation The operationof the S/G ofthe SIG PORVs PORVsand andsteamsteamdumps dumpsare aredirected directedby by the the General General Proced ures. They can be used Procedures. They can be used for plant cooldown for plant cooldo wnor ortotomaintain maintainRCS RCS temperature temperature atataa specifiedvalue specified value by bymaintaining maintainingan anartificial artificial load. load. Use Use of ofthe the steam steam dumps dumps isis preferred, preferred, if availab le, since second ary coolan if available, since secondary coolant is conserved. t is conser ved. During aa plant During plant startup, startup, Steam Steam Dumps Dumps are are initially initially in in the the Steam Steam Pressure Pressure ModeMode withwith the the potent iomete r set at 7.17 (1005 psig), potentiometer set at 7.17 (1005 psig), corresponding corresponding to to the the no-load no-load TavgTavg value value ofof 547°F. As 547°P. As power power approaches approaches 15 15% %(Not (Notee that that itit isis not not possible possible to to arm arm the the steam steam dump dump system in the Tavg mode system in the Tavg mode if you are if you are less less than than 15 15% load), Steam
% load), Steam Dumps Dumps are are transferred transferred to the Tavg to the Tavg ModeMode by by the the following following sequence:
sequence: When When Steam Steam Dumps Dumps indicate indicate closed, closed, depres s MAN on PC-46 depress MAN on PC-464B, Positionn the 4B, Positio the STEAM STEAM DUMP DUMP MODE MODE Selector Selector to to RESET RESET and then and then toto T-AVG, T-AVG, Verify Verify the SteamSteam Dump Valves Valves RemainRemain CLOSED, CLOSED, Depress AUTO Depress AUTO on PC-46 4B, Adjust on PC-464B, Adjust PC-464B PC-46 STEAM HEADER 4B STEAM HEADER PRESS PRESS controller controller to aa potentiometer potentiometer setting of setting 7.28 (1020 of 7.28 (1020 psig). During aa plant During plant shutdown shutdown when between between 10 and 15% power, the steam dumps are are shifted to shifted to the the Steam Pressu Pressure re Mode controller is adjusted and the controller adjusted to a potentiometer potentiometer setting setting of of 7.17 7.17 (1005 (1005 psig). When a plant cooldo cool down wn is comme commenced, nced, the steam dumps dumps (or S/G PORV (or S/G PORVs) are s) are used to contro controll the plant cooldo cooldown wn until RHR is placed in in service service.. When When Tavg Tavg is is less less than than 543°F, 543°P, the low Tavg interlo interlock ck must be bypassed, allowing bypassed, allowing the the cooldo wn to be cooldown to be perform performed ed with steam dump bank bank 1. 1. After the plant has reache reached d 450°F, o conden ser steam 450 P, condenser steam dump bank 2 can dump bank 2 can be be used used to to help help with with the the cooldo cooldown wn byby I&C I&C installi installing ng jumpe jumpers rs and and lifting lifting leads leads inin the the Miscel laneous Relay Miscellaneous Relay Rack Rack (MRR(MRR-50). This
-50). This tempo rary feature temporary feature is removed is remov ed once once the the plant plant reache reaches s MODE MODE 55 (< (~2000P) 200°F) 6.2 6.2 Abnor Abnormal mal Operat Operation ion 6.2.1 6.2.1 Second Secondary ary Load Load Reject Rejectionion During During aa secondsecondary ary load load rejectio rejectionn oror turbine turbine runrun back, back, thethe steam steam dump dump system system will will actuate actuate toto provid provide e an anartifici al load artificial load ononthe the RCS RCS and,and, in inconjun conjunction with rod control, ction with rod control, reduce reduceTavg Tavgtoto within within5°F 5°Pof ofTref, Tref, ififthetheSDCS SDCSisis ininthe theTavg Tavgmode.
mode. The Thefive five steam steamdump dumpvalvesvalvesand andthe theS/G S/GPORVPORVs s cancanbe beoperate operated fromthe d from thesteam steamdump dump contro controls ls during duringthis thisevoluti on. The evolution. Themagnit magnitude ude of ofthe thesudden suddenreducti reduction of turbine on of turbine firstfirst stage pressu re will determ ine stage pressure will determine which valvesare which valves arearmed: armed: >>15<35 15<35, Bank1;1; >35,
, Bank >35,BankBank Steam SteamDumps Dumps Page Page19190[26 of 26 Revision7 7 Revision INFO INFORMATION RMATION USE USE ONL ONLY Y
QUESTIONS REP9RT QUESTIONS REPQRT ) for AUDIT for 2cx/) 1 ( AUDIT (;'00/ 1.
- 1. 040 040 AK2.01 AK2.01 001111/111/
001/I/I//il The Reactor The Reactor Trip Trip and Safety Injection and Safety Injection have occurred. have occurred. The following The following alarms alarms werewere received received inin the the Control Control Room: Room:
** APP-004-A1, S/G APP-004-A1, S/G AA HI HI STM LINE HI STM LINE HI DELTA DELTA PP SFGRDITRIP SFGRDITRIP
** APP-004-A5 , SIG A LO LVL APP-004-AS, S/G A LO LVL & STM > FWF TRIP & STM > FWF TRIP
** APP-006-A2, S/G APP-006-A2, S/G A A STM STM> FW FLOW
> FW FLOW
** APP-006-E5, STM APP-006-ES, STM LINE LINE LO PRESS LO PRESS The crewcrew has completed Supplement has completed Supplement G, Steam generator G, Steam generator Isolation.
Isolation. Which ONE Which ONE (1)(1) ofof the following describes the following describes the the Main Main Steam Steam System System component(s) component(s) controlling RCS Heat Removal? A. Condenser Steam Dumps from"A", fromA, "B",B, and "C" C SGs. A, "B", B. "A", B, and "C" C SG PORVs. B and "C" C. "B" C SG main Steam Safety Valves. D Condenser Steam Dumps from liB" Dy' B and "C" C SG. A. Incorrect. Steam Dump not available from A SG. A S/G isolated per Supplement "G". G. B. Incorrect. Steam Dump available from condenser. C. Incorrect. Steam Dump available from condenser. D. Correct. Common Question 048 Tier 1 1 Group 1 1 K/A KIA Importance Importance Rating - RO 2.6 I/ SRO 2.6
-
Knowledge of the interrelations between the Steam Line Rupture and the following: Valves. Reference(s) - Supplement G,
- G, SD-031 pg. pg. 18; 18; No No LP for Supplements Supplements found.
found. Proposed Proposed References References to to bebe provided provided to to applicants applicants during during examination examination - NONE
- NONE Learning Objective Learning Objective - -
Question Question SourceSource - Bank
- Bank Question History Question History - -
Question Question Cognitive Cognitive Level Level - Comprehens
- Comprehension ion 10 CFR Part 55 Content 10 CFR Part 55 Content - 55.41 - 55.41 Comments Comments - -
Category Category 1: 1: Category Category 2: 2: Category Category 3:3: Category Category 4: 4: Category 5: Category 5: Category Category 6: 6: Category Category 7:7: Category Category 8: 8:
- Tuesday, Tuesday, June 10, 2008 June 10, 12:56:17 PM 200812:56:17 PM 1
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 54. Given
- 54. Given thethe following:
following:
- Large Break
- AA Large Break LOCA LOCA hashas occurred occurred with with all equipment operating all equipment operating as as designed.
designed. Containment pressure
- Containment
- pressure peaked peaked at at 38 PSIG and 38 PSIG and isis now now at at 11 11 PSIG.
PSIG. The crew
- The
- crew has transitioned to has transitioned to EPP-9, EPP-9, TRANSFER TRANSFER TO TO COLD COLD LEGLEG RECIRCULATION, RECIRCULATION, due due to RWST to RWST levellevel <<27%.
27%. Ability to
- Ability
- to recirculate recirculate from from the Containment ECCS the Containment ECCS SumpSump exists.
exists. Which ONE Which ONE (1) of the (1) of the following following describes describes thethe manipulation(s) manipulation(s) necessary necessary lAW lAW EPP-9, EPP-9, to to allow allow stopping aa CV stopping CV Spray Spray Pump Pump without without locking locking out out the the pump? pump? Reset SI. A. Reset SI. B. Reset SI, PhasePhase A, and Phase B. C. Place Containment Spray Key Switch to the OVRD/RESET OVRD/RESET Position. D. Reset SI and momentarily place Containment Spray Key Switch to the OVRD/RESET OVRD/RESET Position. 54 54
HLC-08 NRC HLC-08 Written Exam NRC Written Exam 54.026
- 54. A2.04 001/CTMT 026 A2.04 SPRAY/2/113.9/4.2IROIHIGHlNINRNP BANK/CSS-007 OOl/CTMT SPRAYI2I1I3.9/4.21R0/HIGHINIAJRNP BANKlCSS-007 Given Given the the following:
following:
-
- AA Large Large Break Break LOCA LOCA has has occurred equipment operating all equipment with all occurred with operating asas designed.
designed.
-- Containment Containment pressure peaked at pressure peaked at 38 PSIG and 38 PSIG and is now at is now 11 PSIG.
at 11 PSIG.
-
- The The crew crew has transitioned to has transitioned to EPP-9, TRANSFER TO EPP-9, TRANSFER COLD LEG TO COLD LEG RECIRCULA RECIRCULATION,TION, due due to RWST to RWST level level << 27%.
27%.
*- Ability Ability to to recirculate from from the Containment ECCS the Containment Sump exists.
ECCS Sump exists. Which ONE Which ONE (1) (1) of of the the following the manipulation describes the following describes manipulation(s)(s) necessary necessary lAW EPP-9, to lAW EPP-9, to allow allow stopping aa CV Spray Spray Pump without locking out the pump? A. Reset SI. A. B. Reset SI, Phase A, and Phase B. B. C~ Place Containment Spray Key Switch to the OVRD/RESE C OVRD/RESET T Position. D. Reset SI and momentarily place Containment Spray Key Switch to the OVRD/RESE OVRD/RESET T Position. The correct answer is C. A: Incorrect - Resetting SI does NOT have any effect on CV Spray.
-
B: Incorrect - CV Spray must be reset prior to resetting Phase B.
-
C: Correct Correct-- CV pressure remains higher than 10 PSIG. Signal must be overridden to allow CV Spray Pump to be stopped and NOT locked out. 0: D: Incorrect - Reset 81
- SI does NOT have any effect on reset of CV Spray. Unless the Key Switch Switch remains remains in position CV OVRD position in the OVRD Spray Pump CV Spray Pump will be be locked out due to locked out CV remaining> 10 CV pressure remaining> PSIG.
10 PSIG. Exam Exam Question Question Number: Number: 54 54
Reference:
Reference:
EPP-9, EPP-9, Step Step 3; 3; SD-006, SD-006, ESFAS, Page 22, ESFAS, Page Figures 44 and 22, Figures 5. and 5. KA KA Statement: Statement: AbilityAbility to to predict and/or monitor predict and/or changes in monitor changes in parameters parameters (to (to prevent exceeding prevent exceeding design design limits) limits) associated the CSS operating the with operating associated with controls including: CSS controls including: Containment Containment Pressure. Pressure. History: History: Direct Direct from from Bank. Bank. 61 61
Rev. Rev. 31 31 EPP-9 EPP-9 TRANSFER TO TRANSFER TO COLD COLD LEG LEG RECIRCULATION RECIRCULATION Page Page 44 of of 40 40 STEP H INSTRUCTIONS INSTRUCTIONS I RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED I
********************** *******************************************
************************************************************************** *********
CAUTION CAUTION Steps 11 Through Steps Through 24 24 must must bebe performed performed without without delay delay to to accomplish accomplish switchover prior switchover prior to to RWST RWST level level reaching reaching 9%. 9%.
*********** ********************************************
**************************************************************************
*******************
NOTE
** Foldouts are Foldouts are NOTQ[ applicable applicable during during the the performance performance ofof this this procedure.
procedure.
** Functional Restoration Procedures are Functional are NOT
.1QL applicable applicable until until after after Step 42.
Step 42.
*
- 1.1. Check Capability Check Capability To Establish Go To EPP-15.
EPP-15, Loss Of Emergency Emergency Recirculation Recirculation - EXISTS-Coolant Recirculation. Recirculation.
** Establishment of 354 inches Establishment in the in the CV Sump is possible AND
** Establishmen Establishmentt of at least one one flow flow path from the CV CV Sump Sump toto the RCS is possible 2.
- 2. Reset Reset SAFETY SAFETY INJECTION INJECTION
--? 3 . Place Place TheThe CONTAINM CONTAINMENT ENT SPRAY SPRAY Key Key Switch Switch To To The The OVRD/RESE OVRD/RESET T Position Position 4.
- 4. Verify Verify RCPsRCPs - ALL
-
ALL STOPPED STOPPED
SD-.006 SD-006 ENGINEEREDSAFETY ENGINEERED SAFETY FEATURES FEATURES SYSTEM SYSTEM 880A, 880B, 880A, 880B, 880C, 880C, 880D, 880D, 845A, 845A, and and 845B. 845B. ThisThis will will deliver deliverborated boratedwater water withwith sodium sodium hydroxide hydroxide toto the the CV atmosphere to CV atmosphere to depressurize depressurize and remove free and remove free iodine. iodine. AA Containment Containment Spray Spray signal signal can canbebe reset/overridden reset/overridden after after actuation actuation ififitit becomes becomes necessary to necessary to stop stop oror realign realign equipment equipment actuated actuated by by the the Containment Containment Spray Spray signal. Resetting/Overriding signal. Resetting/Overriding the signal will the signal will not not terminate terminate Containment Containment spray spray or or cause any cause any component component actuated actuated by the Containment by the Containment Spray Spray signal signal toto change change state. state. OnceOnce thethe signal signal isis overridden, overridden, no no further further automatic automatic Containment Containment Spray Spray
> actuations actuations will will occur occur until until all all automatic automatic actuation actuation signals signals have have cleared.
cleared. A A key key operated CV operated CV SPRAY SPRAY RESET RESET switchswitch onon the the RTGB RTGB isis used used to reset a CV to reset a CV Spray Spray signal. Operation signal. Operation of of the the switch from the switch from the NORMAL NORMAL positionposition will will actuate actuate an an annunciator on annunciator APP-002-Cl; FEEDWATER on APP-002-Cl; FEEDWATER ISO/CV ISO/CV SPRAYSPRAY OVRD/RESET. OVRD/RESET. Until the Until the Containment Containment Spray signal isis reset/overridden, Spray signal reset/overridden, any any Containment Containment Spray Spray actuated equipment actuated equipment stopped stopped fromfrom thethe RTGB RTGB cannotcannot be be restarted restarted without without removing and removing and reinstalling reinstalling thatthat equipment's equipments control control power fuses.fuses. This This is due due to the anti-pump feature the anti-pump feature of of the the equipment equipment breakers. breakers. The The Phase Phase "B" Containment B Containment Isolation must be reset individually after the Containment Spray signal is cleared Isolation or overridden. Phase "B" B Containment Isolation is reset from a pushbutton on the RTGB. This is normally required in the EOP network when < < 4 psig in the Containment. This allows stopping components and restoring Phase "B" Containment. B isolation valves. 3.
- 3. Phase "B" B Containment Isolation - This signal will further isolate the
-
containment by shutting containment isolation valves as follows:
** CC-716A CC to R.C.P. "A", B, "c" A, "B", C and C.R.D. CoollsolCool Isol
** CC-716B CC to R.C.P. A, "A", B, "B", C"C" and C.R.D. Cool Coollsol Isol
** CVC-381 RCP Seal Water Return
** CC-735 CC from R.C.P. A, "A", B,"B", C "C" Thermal Barrier Isol. Iso1.
- CC-730 CC from R.C.P. A, "A", B, "C" Oil Cool Isol.
"B", C Iso1.
- FCV-626 FCV-626 CC CC From From R.C.P. A, "A", B,"B", C "C" Thermal Thermal Barrier Barrier Isol.
6.3 6.3 Station Station Blackout Blackout Occurs Occurs on on aa sensed sensed loss loss of of ACAC power ( < 328V or power (<328V or degraded degraded grid grid setpoint of <430V setpoint of< 430V for ten ten seconds) seconds) to to the the emergency emergency busses busses (El(El and/or and/or E2).E2). Degraded Degraded Grid Grid protection protection isis toto open open the the normal normal supply supply breaker breaker to to the the emergency emergency bus. bus. The The UV UV relays relays (2) (2) will will now now see see aa complete complete loss loss of of voltage voltage andand start start the the blackout blackout sequence. sequence. Note Note that that 125 125VDC VDC power power must be present must be present forfor the the blackout blackout sequencer sequencer to to operate. operate. ESF ESF Page Page2222ofof40 40 Revision 10 Revision 10 INFORMAT INFORMATION ION USE USE ONLY ONLY
ENGINEERING SAFETY ENGINEERING SAFETY FEATURES FEATURES ESF-FIGURE-4 ESF-FIGURE-4 CONTAINMENT CONlROL ROOM 1WIl0AC11\lI1Y AA£A NMENT' PRESSURE .. I_ tMNUAl.. AClUAilON FROM CONTROL BOARD .. t..DE'I'ECTORS .. I.MONITOR .. S1EAM UHE ISOlAlIOH 3
~~,:=--....--} , _. Ii ..
I r I.-.- I I t MR. (SHEET 14) ] ORE ) TED BY CONTAINMENT ISOlATION SIGNAl. (PHASE A&B) 9.9.COMPONEN TS ACTUATED tO:rEOBY~ CONTAINMENT lSOIAllON SIGNAL (PlIASt MB)AND AN/) COMPONENlS ACTUATEOBYBYSISISIGNAl. ARE INDMOUAU.Y CONTAINM ENT VENTILATI ON ISOLATION ARE AU. SEALED SEAI..EOININ(LATXNED ) SOSOTHAT LOSS CF THE ACTUATION (LATCIltD) 0 '£D BY CONTAINI.IENT IN (LATCHED) , So THATV£HTILAllON ISOlATION AA£ AU. SIGNAl. D IN ESE (lATCHED). COMPONEN 1KA.Tl.OSS SORETURN lOSSOFOF'THE mE ACTUATIO N SIGNAL ACTUATION SIGNAl SIGNALWIU.WIU.NOt NarCAUSE CAUSETHESE COMPONENTS TO RETURN tS TO TO10THETHEPOSITION NTESE THE ACTUATIO10 OF COI.II'OtlENlS RETURNTOTOTHE N SIGNAL. THEPOSITION POSllIONHELD H£t.() ACTUATIO POSIllONHELD N SIGNAL HELDPRIOR PRIORTO10THE THEAENt 111£ NM!.IlrOFOf"THE OF THEAPEACTIIAlION ACTUAllON SIGNAL. k Nt PC951B FED BY SIGHAI.. THE DIESEL TOMATEC.AlIY iS'UJCOMPONEN TS ACTUATED COI.IPONENlS AClUAltDBYBYSISISIGNAL SIGHAI..CON?. CONT.Wttt ~ ANfl
\IFtlI'.tAcit " PC-95IB ARE fEO BY THE DIESEL AUTnl.lAlIr....IIY ANn
SAFEGUARD ACTUATION SAFEGUARD ACTUATION SIGNALS SIGNALS ESF-FIGURE-5 ESF-FIGURE-5 I': STEAM GENERATOR PRESSURI~ER PRESSURIZER "1---- CONTAINMENT CoNtAINMENT I 5TFAM GENERATOR -,- - CV HI HI PRESS. OR LOW PRESSURIZER . 0/ HIGHHI STEAM HI PRESS. OR LINE FLOW HIGH STEAM UNE' LINE I..OW PRESSURIZER . HIGH COINCIOEN UNE flOW STFAUr WITH LOW DIRENUAL DIFFERENTIAl.. PRESSURE COINCIOBIT SiEM UNE WITH I..OW LINE PRESSURE PRESSURE PRESSURE
""''''URE STE"AM ......~
- CR LOW LOW TAVG TAVG i!
OR (SHEET (SHEEr 7) 7) (SHEET 6) i<NOTE 7) ( 7)
~=~ i~~
1-2 MIN.
' - - - - - - - - - - - t l S.I. (AUTO &: MAN.)
, STEAM v
/
STE'AM LINE UNE ISOLATION ISOLATION INFO INFORMATION RMATION USE USE ONLY ONLY
- QUESTIONS REPORT QUESTIONS REPORT AUDIT (0 f0rAUDIT for (/I Pr,: . . f}ueJrr) 11.. 026 026 Al.04 A1.04 001/111/111 00 1//I//I/I Given the Given the following following conditions:
conditions:
** AA LBLOCA LBLOCA has has occurred occurred with with all equipment operating all equipment operating as as designed.
designed.
** Containment Containment pressure pressure peaked peaked at at 38 psig and 38 psig and is is now now at at 11 11 psig.
psig.
** The crew The crew has transitioned to has transitioned EPP-9, TRANSFER to EPP-9, TRANSFER TO TO COLD COLD LEG LEG RECIRCULATION, RECIRCULATION, due due to RWST to RWST <27%. <27%.
** Ability to recirculate recirculate from the Containment Containment SumpSump exists.
exists. Which ONE (1) of the following describes describes the manipulation(s) manipulation(s) necessary to allow stopping aa CV stopping CV Spray Spray Pump without locking out the pump? Reset SI A. Reset Reset 81, B. Reset Phase A, and Phase B SI, Phase C Place Containment Spray Key Switch to the OVRD/RESET CY' OVRD/RESET Position D. Place Containment Spray Key Switch to the OVRD/RESET OVRD/RESET Position momentarily, momentarily, then back to normal C is correct. EPP-9 step 3. Common Question 013 Tier 2 Group 1 1 K/A KIA Importance Rating - RO 3.1 / SRO 3.17
-
Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated associated with operating the CSS controls including: Containment humidity. Reference(s) - EPP-9 step 3
-
Proposed ReferencesReferences to be provided to applicants during to be during examination examination - None
- None Learning Learning ObjectiveObjective - -
Question Question Source Source - New - New Question Question History History - - Question Question CognitiveCognitive Level Level - Memory
- Memory 10 CFR 10 CFR Part Part 55 55 Content Content 41 Comments Comments - -
Category Category 1:1: Category 2: Category 2: Category Category 3: 3: Category Category 4: 4: Category Category 5: 5: Category Category 6: 6: Category Category 7: 7: Category Category 8: 8:
- Tuesday, Tuesday, June June 10, 2008 1:11:02 PM 10,20081:11:02 PM 1
HLC-08 NRC HLC-08 NRC Written Exam Exam
- 55. Given
- 55. Given the following:
leak in
- A leak
- in the EDG EDG "A" A Air Start Start Receiver Receiver has has reduced reduced starting starting air air pressure pressure to to 105 105 PSIG.
PSIG. LCO 3.8.3, DIESEL
- LCO
- DIESEL FUEL FUEL AND STARTING STARTING AIR, Condition Condition D, D, has has been been entered.
entered.
- The leak has been repaired.
-
As air pressure is restored, at which ONE (1) of the following pressures will the LCO be exited? A. 210 PSIG. B. 216 PSIG. PSG. C. 220 PSIG. D. 242 PSIG. 55 55
HLC-08 NRC Written Exam
- 55. GEN/2/1/2.7/2.9IROILOWIN/A/NEW - 20081EDG-009 001/EMERO DIESEL GEN/2/1/2.7/2.9/ROILOW/N/NNEW 064 K6.07 OOllEMERG - 2008/EDG-009 Given the following:
- A leak in the EDG "A"
- A Air Start Receiver has reduced starting air pressure to 105 PSIG.
- LCO 3.B.3,
- 3.8.3, DIESEL FUEL AND STARTING AIR, Condition D, has been entered.
- The leak has been repaired.
-
As air pressure is restored, at which ONE (1) of the following pressures will the LCO be exited? A 210 PSIG. A'I B. 216 PSIG. C. 220 PSIG. D. 242 PSIG. The correct answer is A. A: Correct -- 3.8.3 is entered when pressure is ~ 210 PSIG and ~ 100 PSIG. LCO 3.B.3 Incorrect-- 216 PSIG is AIR START LO PRESS alarm setpoint. B: Incorrect C: Incorrect - 220 PSIG is the START pressure setpoint for Air Start Compressor in AUTO.
-
D: Incorrect - 242 PSIG is the STOP pressure setpoint for Air Start Compressor in AUTO.
-
Exam Question Number: 55
Reference:
ITS 3.B.3, 3.8.3, Condition D; ITS Bases 3. B Dl; SD-005, EDG, Page 27. 8 .3, D1; KA Statement: Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: Air receivers. History: New - Written for HLC-OB
- HLC-08 NRC Exam.
62
Diesel Fuel Oil, and Starting Air 3.8.3 - 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil and Starting Air LCO 3.8.3 The common stored diesel fuel oil and starting air subsystem for each diesel generator (OG) COG) shall be within limits. APPLICABILITY: When associated DG is required to be OPERABLE. ACTIONS
------------------------. ----------.. NOTE ----------------------.. ------------.
Separate Condition entry is allowed for each OG. 0G. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more OGs DG5 with A.I A.1 Restore fuel oil 48 hours - OG DG fuel oil level
< 19,000 gal and
<
level to within limits.
> 14,145 gal in the
>
Unit 22 DG fuel oil storage tank. B. One or more DGs with B.1 Restore fuel oil 48 hours DG Fuel oil level level to within
* < 34,000 gal and
< 1 imits.
limits.
> 29,145 gal in the
>
combination of the Unit 1 1 IC turbine fuel oil storage tanks and the Unit 22 DG fuel oil storage tank. (continued) HBRSEP Unit No. 22 3.8-16 Amendment No. 176
Oil. and Starting Air Diesel Fuel Oil, 3.8.3 - ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. One or more DGs with C.1 Restore stored fuel 30 days new fuel oil pro~erties to oil properties
~roperties not within properties imits.
within limits. imits. limits. D.D. DGs with One or more DG5 starting air receiver Q~
.1 Rest9re starting ~ air )48 recelver pressure to pressuretoressureto receiver 48 hours hours pressure << 210 psig == 210 psig.
and == 100 psig. ~ E. Required Action and E.1 Declare associated Immediately associated Completion DG(s) inoperable. Time not met. OR - Common stored DGs diesel fuel oil or starting air subsystem for each DG not within limits for reasons other than A, B. Condition A. B, C. or D. - HBRSEP Unit No. 22 3.8-17 3 .8-17 Amendment No. 176
Diesel Fuel Oil and Starting Air B B 3.8.3 BASES ACTIONS C.l J. (continued) may involve feed and bleed procedures. procedures, filtering. filtering, or combinations of these procedures. Even if aa DG DC start and load was required during this time interval and the fuel oil properties were outside limits, there is aa high likelihood that the DG DC would still be capable of performing its intended function. Qi With starting air r(~ceiver receiver pressure < < 210 psig, sufficient capacity for eight successive DG DC start attempts does not exist. However, as long as the receiver pressure is
> 100 psig, there is adequate capacity for at least one
>
start attempt, and the DG can be considered OPERABLE while the air receiver recei ver pressure pr(~ssure is restored to the requ ired 1limit. required i mi t . A period of 48 hours is considered sufficient to complete A restoration to the required pressure prior to declaring the DG DC inoperable. This period is acceptable based on the remaining air start capacity, the fact that most DG DC starts are accomplished on the first attempt, attempt and the low probability of an event during this brief period. E.1 With aa Required Action and associated Completion Time not met, or one or more DG'sDCs fuel oil. oil, or starting air subsystem not within limits for reasons other than addressed by Conditions A A through D, the associated DGs may be incapable of performing its intended function and must be immediately declared inoperable. SURVEILLANCE SR 3.8.3.1 REQUIREMENTS REQU IREMENTS This SR provides verification that there is an adequate inventory of fuel o'ioil1 in the storage tanks to support one DG's DGs operation for "77 days at full load. The 7 7 day period is sufficient time to place the unit in aa safe shutdown condition and to bring br'ing in replenishment fuel from an offsite location. (continued) HBRSEP HSRSEP Unit No. 2 2 8 3.8-35 B :3.8-35 Revision No. 00
SD-005 SD-005 EMERGENCY EMERGENC DIESELGENERATO Y DIESEL GENERATOR R SYSTEM SYSTEM
,
cylinder compressors cylinder compressors (driven (drivenby by A. A.C. motors), two C. motors), air dryers two air (cooled by dryers (cooled by service service water), two water), two air air storage storage reservoirs (34fe), reservoirs (34ft
)
3 pressure relief
, pressure valves, check valves, shut-off relief valves, check valves, shut-off valves, pressure gauges, valves, pressure gauges, and and the the necessary necessary stop-start stop-start switches.
switches. The The start-stop start-stop pressure pressure
/
.....::::> to~psig reservoir 220 to4psig pressure. The reservoir pressure. The air
. F switches (PS-switches (PS-1961A(B>> 196 1A(B)) are are set to maintain set to maintain220 air compressor compressor package package may may be be started started from from MCC-5 MCC-5 (Diesel (Diesel A)
"A") and and MCC-6 MCC-6 (Diesel (Diesel liB "). The B). The low low air air pressure pressure alarm alarm PS-4503A(B PS-4503A(B) (APLA) isis set
) (APLA) to give set to alarm at an alarm give an 216 ~ bbZ
&11.2 - (rTf(, ",y'
psig. A
*psig. A low low air air pressure pressure alarm can be alarm can verified by be verified by the instrument panel the instrument gauge reading.
panel gauge reading .
.Eine Engine starting starting isis accomplished accomplished by compressed air supplying compressed by supplying air to of the to 66 of cylinders in 12 cylinders the 12 in the correct the correct firing firing order.
order. Starting Starting airair isis also supplied to also supplied lube oil two lube to two oil boosters (Governor boosters (Governor and Upper Crank and Upper Crank Bearings) Bearings) when when the the engine engine is is started. started. Technical Technical Specification Specification LCO LCO 3.8.3 and 3.8.3 and SRSR 3.8.3.3 3.8.3.3 require starting air require starting pressure to air pressure 210 psig for b~ ;;:: 2iQpg to be EDG operability. for EDG operability. 3.7.2 Air Start Valves 3.7.2 Valves and and Air Start Solenoid Valves Start Solenoid Valves Two air start valves and Two and air start solenoid valves are provided provided per engine. They are are powered powered from MCC-A, MCC-A, Dist. Dist. Panel Panel A A (ckt (ckt 24)
- 24) for EDG A, and MCC-B, Dist Dist Panel Panel BB (ckt 12) for EDG B. They will close in 10 10 seconds or when> 200 rpm. Air can be cross tied by opening DA-28 (chain operated valve in A "A" diesel room). A second isolation valve, DA-40, was installed in series with DA-28 to provide assurance of no train interaction between the A and B B EDG starting air subsystems, downstream of the EDG starting air receivers. (EC52503 due to be completed 9/20104) 9/20/04) 3.7.3 Hand Start Valves (DA-41, DA-42, DA-43, DA-44)
There are two hand start valves on each emergency diesel generator. These valves can be used to start the diesel generator manually in case of electrical failure. The valves are normally open. The handle is a spring return to open handle. When a handle is moved to the closed positions, if held in that position, it will vent the air from the outside of the elastomeric tube of the associated DG air start valve, causing the air start valve to open and admitting starting air to the EDG EDO cylinders. The valves can also be used for rotating the engines without starting them if proper precautions are taken. taken. 3.7.4 3.7.4 Air Air Start Start Control Control Valve Valve This This valve valve has has no no internals internals and and simply functions as simply functions as aa piece piece of pipe (per of pipe discussion with (per discussion with Fairbanks Morse). Fairbanks Morse). 3.7.5 3.7.5 Air Air Start Start Distributor Distributor There There isis one one cam cam operated operated distributor distributor per engine which per engine provides pilot which provides air to pilot air open the to open the air air start start check check valves valves forfor each each supplied cylinder. As supplied cylinder. cam rotates, As cam rotates, distributor valves are distributor valves are opened against spring opened against spring pressure, pressure, according according to to firing firing order. order. EDG EDO Page 27 Page of74 27 of 74 Revision 11 Revision 11 INFORMATION INFORMATiON USE USE ONLY ONLY
HLC-08 NRC Written Exam
- 56. Given the following:
- The plant has been restarted following a forced outage.
-
- Loop flow measurements have determined that RCP "B"
- B impeller has degraded such that its RCS loop flow has DECREASED by 5% from its original value.
- The other RCS loop flows remain UNCHANGED.
-
Which ONE (1) of the following would be a result of the decreased flow rate in Loop "B"? B? A. Demand on the PZR Control Group heaters at 2235 PSIG will be lower. B. The reactor core will operate closer to DNB when at full power. C. Core Delta-T at full power will be lower. D. The reactor core will operate further from DNB when at full power. 56
HLC-08 NRC HLC-08 NRC Written Written ExamExam
- 56. 002
- 56. 002 K6.07 K6.07 001lREAC 001/REAC COOL COOL PUMP/2/2/2.512.8IROILOW/N/A/BYRON-2003/THERMO PUMP/2/2/2.5/2.81R0/LOWIN/AIBYRON-2003/THERMOCHAP CHAP 8-014 8-0 14 Given the Given the following:
following: The plant
- The
- plant hashas beenbeen restarted restarted following following aa forced forced outage.
outage. Loop flow
- Loop
- flow measurements measurements have have determined determined that RCP "s" that RCP B impeller impeller hashas degraded degraded suchsuch that its that its RCS RCS looploop flow flow has has DECREASED DECREASED by by 5%
5% from from its its original original value. value. The other
- The
- other RCSRCS loop loop flows flows remain remain UNCHANGED.
UNCHANGED. Which ONE Which ONE (1) (1) of of the following would the following would bebe aa result result of the decreased of the decreased flow flow rate rate inin Loop Loop "S"? B? A. Demand on A. Demand the PZR on the PZR Control Control Group Group heaters heaters at at 2235 2235 PSIGPSIG will will be be lower. lower. B:t The reactor B The reactor corecore will operate closer to DNS DNB when at at full full power. power. Core Delta-T C. Core Delta-T at full power will be lower. lower. D. The reactor core will operate further from DNS D. DNB when at full power. The correct The correct answer answer is S. B. A: Incorrect - RCPs "s" A: Incorrect - B and "C"C supply PZR spray valves. However, based on plant design, RCP "s" B provides limited flow, plus under steady state/2235 PSIG conditions, the spray valves are closed and bypasses provide minimal flow to keep the lines warm - NOT an impact on current draw on the PZR Control Group heaters.
-
S: Correct B: Correct - - Putting out the same MWt with a reduced flow rate means reduced heat transfer capabilities and therefore operation closer to DNS. DNB. C: Incorrect C: Incorrect - Delta-T should actually be higher in this situation.
-
D: D: Incorrect Incorrect - Mass-Mass flow rate reduction for the the same powerpower results in operation CLOSER to DNB. DNS. Exam Exam Question Question Number:Number: 56 56
Reference:
Reference:
Thermodyna Thermodynamics, mics, Chapter Chapter 8,8, Pages Pages 40-41. 40-41. KA KA Statement: Statement: Knowledge Knowledge of of the the effect effect or or aa loss or malfunction loss or malfunction on on the the following following RCSRCS components: components: Pumps. Pumps. History: History: Direct Direct fromfrom Bank. Sank. 63 63
----,. I INSTRUCTOR I IMTI I(TAR GUIDE
(I IIDE KEY POINTS, AIDS, QUESTIONS/ANSWERS
- d. As steam bubble is swept from fuel :
rod surface it agitates laminar ~ layer, increasing turbulent flow
- e. The mixing of coolant in turbulent flow increases heat transfer rate
!,
- f. Reactor coolant flowrate affects heat transfer rate in fuel channel
- g. When heat is transferred from fuel cladding to coolant, it must pass
\
through laminar flow region before 1 reaching turbulent bulk flow region
- h. The thickness of laminar region is ~
proportional to its resistance to heat flow i
- i. As flow rate increases, outer portions of laminar layer are disturbed, resulting in more turbulent flow, thinner laminar layer and increased heat transfer coefficient I f, Objective 18.e
- 3. Reactor coolant flowrate also has direct affect on fuel temperature
- a. Rate of heat transfer is proportional Equation 8-7 I TP 8-29 to reactor coolant flowrate and differential temperature between .~ Q == mCp~T Q mcT fuel and coolant:
- 4. Where: ,
- a. QQ = heat transfer rate (Btu/hr)
= (Btulhr)
- b. ri1 th = mass flow rate (lbn/hr)
= (lbjhr)
- c. cc,p = specific heat capacity for
=
coolant at constant pressure (B tu/lb m OF) (BtUIlbm °F) ;
- d. ~zTT = differential temperature
=
between fuel and coolant (OF) (°F)
-.......--
PWR /I THERMODYNAMICS /I CHAPTER 8 40 of 69 © 1999 GENERAL PHYSICS CORPORATION
/I THERMAL HYDRAULICS 3 REV 3
IMTQIICbTflI (IIIDE KEY POINTS,,AIDS, KEYPOINTS AIDS, INSTRUCTOR I GUIDE; QUESTIONS/ANSWERS QUESTIONS/ANSWERS
~ 5. If reactor power is held constant, .**
reducing reactor coolant flow rate increases differential temperature
- a. Fuel temperature increases to make ;
up for decreased reactor coolant ' flowrate
- 6. Heat flux in fuel rod is proportional to neutron flux present in that region
- a. The heat flux for any point in fuel is also proportional to neutron flux at that point
- b. Thus heat flux, neutron flux, and heat generation rate are proportional in fuel rod
- 7. This is shown in Figure 8-16, which Figure 8-16/
8-16 / TP 8-30 shows shapes of neutron flux and heat HEAT GENERATED generation from centerline to edge of L.DUE TO FISSION GAMMA RAY HEATING fuel pellet I OFC LANT
- a. Note that no heat generation is IIAD4AL DISTN4C shown in clad and gap, and that small amount of heat is generated COOLANT (WATER) in coolant by gamma and neutron 4J_ZIRCALOY4 -4 CLADDING heating /lfo<t,-'--ZIRCAI.OY
, HELlUM*PRESSURIZED HELIUM-PRESSURIZED GAP
;
- 8. Fuel densification is another factor that i can affect overall L\T and thus z\T centerline temperature
- a. During initial stages of nuclear fuel operation, fuel becomes denser, increasing gap between fuel pellets and cladding
- b. This can change L\TzT across gap, Equation 8-8/ 8-8 I TP 8-31 and thus centerline temperature:
~T zTgap =--x-_&
Q rug
- xk-
- 9. Where: gap AA g g THERMODYNAMICS / CHAPTER 8 PWR / THERMODYNAMICS 41 of 69 © 1999 GENERAL PHYSICS CORPORATION CORPORATION HYDRAULICS
/I THERMAL HYDRAULICS REV 3 3
"Bv jrl rot1 t3 0 :5 RO SRO: TIER: GROUP: Topic No: KA No:
KANo: RO: SRO: Cog Level: Quest No: ROSRO: Both 2 1 1 003000 003000K5.0I 003000KS.0l 3.3 3.9 High 1 1 SystemIEvolution Name: SystemlEvolution Category Statement: Reactor Coolant Pump System (RCPS) Knowledge of the operational implications of the following concepts as they apply to the RCPS: KA Statement: The relationship between the RCPS flow rate and the nuclear reactor core operating parameters (quadrant power tilt, imbalance, DNB rate, local power density, difference in loop T-hot pressure) UserID: BY03NRC-OOI BYO3NRC-001 Topic Line: - The plant was restarted following a forced outage.
-
- The plant was restarted following a forced outage. - Question Stem: _ Loop flow measurement has determined the 'c' - C RCP impeller has degraded such that its RCS loop flow has DECREASED by 5% from its original value. - The other three RCS loop flows remain UNCHANGED. - Which one of the following would be a result of the decreased flow rate in the 'c' C loop? Demand on the Pressurizer variable heaters at 2235 psig will be lower. A: The reactor core will operate closer to DNB when at full power. B: Delta-Tin the 'c'C RCS loop at full power will be lower. C: Steam pressure in the 'c' S/G at full power will be higher. C SIG D: Answer: Task No: Question Source: Question Difficulty B Obj No: A.PD3-07 modified: {from Kewaunee 12118/97, question 10 ID 10835 in INPO eaxni bank - modifed stem to apply to 4 loop plant and replaced eaxm - Medium Time: Cross Ref: A. distractor A.} SD reviewed format OK 7/18103,7/18/03, tech review OK by TL 7/22103
Reference:
ILT Fundamentals Lesson Plan Power Distribution Chapter 3, Thermal Limits; page 15-16. Il-PD-XL-03 I1-PD-XL-03 A: INCORRECT- 'c' C & 'D' Pzr spray. However, based on plant design, the 'c' D RCPs supply pzr C RCP provides limited flow, plus under Explanation: state/2235 psig conditions, the sprays are closed and bypasses provide minimal flow to keep the lines warm - not an impact on steady statel2235 - current draw on the variable heaters. B: CORRECT - putting out the same MWt with a reduced flowrate means reduced heat tranfer capabilities and therefore operation closer
-
toDNB. C: INCORRECT - Delta-T should actually be higher in this situation.
-
D: INCORRECT - Higher Delta-T means Tcold should be lower and therefore steam pressure should be lower.
-
Date Written: 7/14/2003 Author: T. Foss App. Ref: None
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 57. During
- 57. During withdrawal withdrawal of of the the Control Control Banks, Banks, APP-005-F2, APP-005-F2, ROD ROD BOTTOM BOTTOM /I ROD ROD DROP will DROP will CLEAR when CLEAR when Control Control Bank Bank "A" A reaches reaches ...
A. 20 steps A. 20 steps as as sensed sensed by by the the Pulse Pulse To To Analog Analog Converter. Converter. B. 35 B. steps as 35 steps as sensed sensed by by the the Pulse Pulse To To Analog Analog Converter. Converter. 20 steps C. 20 C. steps as as sensed sensed by by the the IRPls. IRPI5. D. 35 D. 35 steps steps as as sensed sensed by the IRPls. by the IRPIs. 57 57
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 57. 014 K1.01 57.014 Ki .01 OOlfROD 001/ROD POSITION INDICAT/2/2/3.2/3 .6IROILOW/N/A1NBW - 200S/IRPI-007 POSITION INDICAT/2/2/3.2/3.6fRO/LOWININNEW - 2008/IRPI-007 withdrawal of During withdrawal During of the Control Banks, the Control ROD BOTTOM APP-005-F2, ROD Banks, APP-005-F2, BOTTOM /I ROD DROP will ROD DROP will when Control CLEAR when CLEAR Bank "A" Control Bank reaches....
A reaches A. 20 A. 20 steps steps as sensed by as sensed by the Pulse To the Pulse To Analog Converter. Analog Converter. B. 35 B. steps as 35 steps sensed by as sensed the Pulse by the To Analog Pulse To Converter. Analog Converter. CY C~ 20 steps 20 steps as sensed by as sensed IRPIs. the IRPls. by the D. 35 D. steps as 35 steps as sensed sensed by by the IRPIs. the IRPls. The correct correct answer answer isis C. C. A: Incorrect - The P to A converter only inputs to the Rod Bottom Bypass Bistable. Control
-
Bank A does NOT have Rod Bottom Bypass Bistable. B: Incorrect - The P to A converter only inputs to the Rod Bottom Bypass Bistable. Control
-
Bank A does NOT have Rod Bottom Bypass Bistable. Setpoint of 35 steps is for Bypass Bistable setpoint. C: Correct - - Control Bank "A" A does NOT have a Rod Bottom Bypass Bistable. APP-005-F2 will clear when ALL Control Bank "A" A RBLs clear at 20 steps. D: Incorrect 0: Incorrect - Control Bank A does NOT have Rod Bottom Bypass Bistable. 35 steps is the
-
<__ Rod Bottom Bypass Bistable setpoint. Exam Question Number: 57
Reference:
SD-009, IRPI, Pages 16, 16, 17 17 and Figure 2; APP-005-F2. KA Statement: Knowledge of the physical connections and/or cause-effect relationships between the RPIS and the following systems: CRDS. History: History: New - Written for HLC-08
- HLC-08 NRC NRC exam.
exam. 64 64
SD-009 SD-009 INDIVIDUALROD INDIVIDUAL RODPOSTION POSTIONINDICATION INDICATIONSYSTEM SYSTEM 4.4. Rod Rod Bottom Bottom Lamp Lamp 24 VAC 24 VAC (Nominal) (Nominal) Outputs Outputs 1.1. Rod Rod Bottom Bottom Relay Relay Capable of Capable ofdriving driving aa 12 12 VAC VAC coil coil (Struthers Dunn (Struthers Dunn PN#A314XCX48P-12A) PN#A3 14XCX48P-12A)
- 2. Meter
- 2. Meter Capable of Capable ofdriving driving aa panel panel meter meter with with impedance >1.5K impedance >1.5K ohms ohms +0.075
+0.075 to -3.67 to 3.67 VDC Input VDC Input
- 3. Computer
- 3. Computer Capable of Capable of driving driving aa computer computer input input module with module with impedance>
impedance> lOOK lOOK ohms ohms
+0.075 to
+0.075 to -3.67
-3.67 VDCVDC
- 4. Annunciator
- 4. Annunciator Contact closure Contact closure Switch rating:
Switch rating:
** LowLow level/dry level/dry circuit circuit or or power power 0.4 VA 0.4 VA Max Max @ @ 20 20 vac vac or or DC DC Max Max oror 55 amps amps @ 120 120 V AC or VAC or 28 VDC
** Recommended Recommended loading:loading: 0.4 0.4 VA VA 3.2.2.3 Environment 3.2.2.3 Environment Ambient Temperature Normal operating temperature 85°F +/- 20°F Abnormal operating temperature 50°F to 140° Ambient Humidity Normal operating range 60% (Nominal)
Abnormal operating range <12 0oto 95%95 % non-condens non-condensing ing Hrs. Accuracy +/-3
+/-3 Steps Steps or +/-O. 045 .VDC or +/-0.045 VDC 3.2.3 3.2.3 P-A P-A Bypass, Bypass, Micro Micro Sentry Sentry Modules Modules (Control (Control BankBank Bypass Bypass Bistable)
Bistable) (Refer (Refer to to RPI RPI-Figure-2 Figure-2 & 19)19) The The three three modules modules forfor the the Control Control Bank Bank Bypass Bypass Bistables Bistables are are located located inin Rack Rack 22 above above the P-A converter. There is a bypass the P-A converter. There is a bypass bistable bistable associated associated with with Control Control Bank Bank B,B, C, C, and and D. D. The The Shutdown Shutdown Banks Banks and and Control Control Bank Bank A A does does notnot have have bypass bypass bistables. bistables. The The .~ bypass bypass bistable bistable obtains obtains itsits signal signal from from the the analog analog signal signal outout of of the the P-A P-A Converter Converter correspondin corresponding to the g to the demand demand position position for for the the banks. banks. The The bypass bypass bistable bistable was was originally originally designed designed to to provide provide aa blocking blocking action action on on the the turbine turbine IRPI IRPI Page 16of Page 16 of27 27 Revision22 Revision INFORMA INFORMATION TION USE USE ONL ONLY Y
SD-009 SD-009 rNDIVIDUALROD INDIVIDUAL RODPOSTION POSTIONINDICATION INDICATIONSYSTEM SYSTEM runbacksignal, runback signal,rod rodbottom/rod bottom/roddrop dropannunciator, annunciator,and andthetheinhibiting inhibitingofofthe theautomatic automatic rod withdr awal rod withdrawal when the when therodsrodsofofthetheassociated associatedbank bankare aretotobe beoperated operatednear nearororbelow below theRod the RodBottomBottomBistableBistablesetpoints. setpoints. BypassBypassofofthese thesefunctions functionswere wereconsidered considered necessaryininthe necessary theoriginal originaldesigndesignofofthe theplant planttotoallow allowautomatic automaticwithdrawal withdrawalof ofthe therodsrods duringplant during plantstartup startupand andtotoprevent preventundesired undesiredrunbacks runbackswhen whenoperating operatingnear nearororbelow below theRod the RodBottomBottomBistableBistablesetpoints. setpoints. IfIfthe theRod RodBottom BottomBistables Bistables were werenot notbypassed, bypassed, the the roddrop rod dropcontact contactininthe the in-out in-outrelayrelay circuits circuits of ofthe theRodRodControl Control System System would wouldprevent prevent automaticrod automatic rodwithdrawal withdrawal since since any any banks banks not notyet yetmoved moved wouldwould indicate indicate aa rodrod bottom. bottom. A bypass was not consid A bypass was not considered necessary ered necess ary for for the the Shutdown Shutdown Banks Banks or or Control Control Bank Bank AA since these since these banks banks was was determined determined toto always always be be withdrawn withdrawn prior prior toto placing placing the the control control system in autom atic. Autom system in automatic. Automatic Rod withdrawal atic Rod withdr awal hashas been beenpermanently permanently disable disable and and the the turbine runback turbine runback has has been been eliminated. eliminated. This This blocking blocking feature feature still still exists exists in the RPI in the RPI System but System but it's its ONLY ONLY function function now now isis to to block block thethe rod rod bottom/ bottom! ifif conditions conditions are are met. met. Note: If Note: If control control rods rods areare being being withdrawn withdrawn in in Control Control Bank Bank B,C,B,C, or or DD andand the the deman demanded ded position position of of the the bank bank :::;; 35 35 steps steps and and aa rod rod drops drops in in the the bank, bank, The RTGB The RTGB rod rod drop annunc iator would drop annunciator would NOT alert the NOT alert the Operator. Operator. However, However, the the rod rod bottom bottom LED LED wouldwould still illuminate. still illuminate. The bypass The bypass bistable bistable is set to operate at 35 steps from the bottom of the core. The The blocki ng action blocking action is is automatically automatically removed removed when the control control bank demand position is demand position is above 35 above 35 steps steps (+ (+ 33 steps steps for reset). These bypass bistables bistables would also operate if if the the Pulse to Pulse to Analog Analog Converter Converter lost power or had an input < 35 steps demanded
<35 demanded rod rod positio n.(example: rod position.(example: rod contro controll startup pushbutton pushbutton inadve inadvertently rtently pushed at power) 3.2.4 3.2.4 Pulse Pulse to to Analog Analog (P-A) Conve Converter rter Drawe Drawerr (RPI-F igure-20 &
(RPI-Figure-20 & 21) The The P-AP-A Conve Converter rter Drawe Drawerr is is located located on on aa single single chassis chassis in in RPI RPI Cabine Cabinett #2. #2. This This single drawer actuall y contain single drawer actually contain four (4) (4) P-A P-A Conve rters, one Converters, one for eacheach Contro Controll Rod Rod Bank. Bank. The The P-AP-A Conve Converterrter receive receives s upup oror down down pulses pulses fromfrom thethe slave slave cycler cycler in in the the Rod Rod Contro l System . P-A Control System. P-A Converter conver Conve rter converts ts these these pulses pulses to DC analog to aa DC analog signal. signal. This This signal signal isis sent sent to to Rod Rod Bottom Bottom Bypas Bypass s Bistab Bistable,le, to to rod rod inserti insertion limit circuit (alarms), on limit circuit (alarms), and and to the local indicat to the local indicator. or. InIn additio addition n toto detecti detecting ng thethe actual actual vertica vertical l positio position n ofofeach each CRDM CRDM drive drive rodrod with with thethe IRPI System IRPI System, , the the desired desired positio position n of ofthethe contro control l rods rods based based on on comma command signals nd signals from from the the Rod Rod Contro Control l System System isis require required.d. The The deman demand d signals signals from from thethe Rod Rod Contro Control System l System drive drive mecha mechanicalnical step stepcounte counters rs ononthe themain maincontrocontrol l board boardand andprovid provide inputs e inputs to theto the plant plantcompu computer ter and andthe theP-A P-AConve rter. The Converter. Thefunctio function n ofofthe theP-AP-AConve Converterrter isistotocount count Contro Control l Bank BankA, A, B, B, CCandandDD step steppulses pulsesfor forthetheRod RodContro Control System and convert l System and convert these these step counts into an equiva step counts into an equivalent analogDC lent analog DCvoltage voltage. . TheTheDC DCvoltage voltageisisthenthensentsenttotothe the rod rodinsertio insertion n limit limit(RIL) (RIL)compucomputer ter ininthe theproces process s instrum instrumentation, entation, totothe thebankbankDD IRPI IRPI Page Page1717ofof2727 Revision2 2 Revision INFO INFORMATION RMA TION USE USEONL ONLY Y
RPI CHANNEL RPICHANNEL RPI-FIGURE-2 RPI-FIGURE-2 SIGNAL CONJ)mOHlNC IroDUU: SIGNAL TEST SIGNAL TUT ) RTGB INDICATOR
'osmON SICHAL ... _'l'O PLAJI'f Ip - COMPUTIR
'i<IU.--II UrI:I"AU::/-'i<AI..-" ... "RJ".t. IN TES1'
-----.. - ... coJrraOLROOIi MEDIAN &' FROM ERFIS Vsec 1-PO$ITlON SIG:NA1. SHon IN ROD BOTfO)(
COHJ)moN IP.A on Control Banks ONLY
...----...
JU.HUAL SE'I1'ER. 1'0 R.r.L CU. ROD CONTROL PULSE TO (ALARKS) sTAlttUP SIlTCH ANALOe COtNATER toc.V. INDICATION IUSTIR CYClJ:R TO COMPUTIR SLAVE CYCLER -S1'CP COUM'tIR INFOR INFORMATION MATION USE USE ONLY ONLY
APP-005-F2 APP-005-F2 ALARM ALARM ROD BOTTOM ROD BOTTOM ROD DROP ROD DROP AUTOMATIC ACTIONS AUTOMATIC ACTIONS 1.
- 1. None None CAUSE CAUSE 1.
- 1. Control Rod Control dropped (IRPI)
Rod dropped (IRPI) 2.
- 2. IRPI Failure IRPI Failure OBSERVATIONS OBSERVATIONS 11.. Rod Bottom Rod Light on Bottom Light on Dropped Dropped Rod Rod
- 2. APP-005-A3, PR DROPPED ROD annunciator
- 3. Power Range meters and Recorder ACTIONS
- 1. IF a dropped rod OR an IRPI failure has occurred, THEN refer To AOP-001.
AOP-00i. DEVICE/SETPOINTS .-...::::;;:.- 1. Individual RPI Rod Bottom Switches /20 steps from fully inserted POSSIBLE PLANT EFFECTS
- 1. Power Reduction
- 2. Flux Tilt
- 3. Entry into TECH SPEC LCO Action REFERENCES 1.
- 1. ITS LCO 3.1.7 and ITS LCO 3.1.4 2.
- 2. AQP-OO1, AOP-001, Malfunction of Reactor Control System 3.
- 3. CWD CWO B-i 90628, Sheet 80 Cable B-190628, Cable AS IAPP-005 APP-005 I Rev. 29 Rev. 29 Page 35 Page 35 of of 40 40 I
HLC-08 NRC HLC-08 NRC Written Written ExamExam
- 58. Given
- 58. Given the the following:
following:
- AA Reactor
- Reactor Startup Startup isis inin progress.
progress.
- IIR
- Channel N-35 R Channel N-35 indicates indicates 3E-13E-10 amps.
0 amps. IR Channel
- IR
- Channel N-36N-36 indicates indicates 9E-11 9E-1 1 amps.
amps. No manual
- No
- manual blocks blocks have have beenbeen inserted.
inserted. SR Channel
- SR
- Channel N-32 N-32 indicates indicates 81008100 cps.
cps. SR Channel
- SR
- Channel N-31 N-31 fails fails HIGH.
HIGH. Which ONE Which ONE (1)(1) ofof the the following following describes describes the the plant plant response response toto the the SR SR Channel Channel N-31 N-31 failing failing HIGH? HIGH? A. A reactor reactor trip trip signal signal isis generated, generated, resulting resulting in reactor trip. in aa reactor trip. B. A reactor trip signal is generated, but no trip occurs since ONE (1) (1) IR JR channel is is above P-6. P-6. No reactor C. No reactor trip signal is generated since ONE (1) IR JR channel is above P-6. D. No reactor trip signal is generated, but the N-31 Level Trip Switch must be taken to D. BYPASS. BYPASS. 58 58
HLC-08 NRC HLC-08 Written Exam NRC Written Exam
- 58. K4.01 001lNUCLEAR 015 K4.01
- 58. 015 INSTRUMENT/2/2/3. 1/3 .31R0/HIGH/N/AIFARLEY - 2001INIS-01O 001/NUCLEAR INSTRUMENT/2/2/3.1I3.3IROIHIGHINIA/FARLEY - 200 1INIS-0 10 the following:
Given the Given following:
-A
- A Reactor in progress.
Startup isis in Reactor Startup progress. IR Channel
- IR
- Channel N-35 N-35 indicates amps.
3E-10 amps. indicates 3E-10 IR Channel
- IR
- Channel N-36 N-36 indicates 9E-1 1 amps.
indicates 9E-11 No manual
- No
- blocks have manual blocks have beenbeen inserted.
SR Channel
- SR
- N-32 indicates Channel N-32 indicates 8100 cps.
8100 cps.
- SR Channel N-31 fails HIGH.
-
Which ONE (1) of the following describes the plant response to the SR Channel N-31 failing HIGH? A A reactor trip signal is generated, resulting in a reactor trip. A'I B. A reactor trip signal is generated, but no trip occurs since ONE (1) IR lR channel is above P-6. C. No reactor trip signal is generated since ONE (1) IR channel is above P-6. D. No reactor trip signal is generated, but the N-31 Level Trip Switch must be taken to BYPASS. The correct answer is A. A: Correct - - Since no blocks are in for the SR, a Reactor Trip will occur. B: Incorrect - The trip must be manually blocked when above P-6.
-
c: Incorrect - Although above P-6, the SR trip signals have NOT been manually blocked. C: - 0: Incorrect - The trip must be manually blocked when above P-6, taking N-31 Level Trip D: - Switch to BYPASS is the correct action per the OWP, but the Reactor will trip. Exam Question Number: 58
Reference:
SD-Oil, SD-011, RPS, Figure 18. 18. KA Statement: Knowledge of NIS design design feature(s) and/or interlock(s) provide for the following: Source-Range Source-Range detector detector power shutoff at power shutoff at high high powers. powers. History: Direct from Bank. History: Direct Bank. 65 65
SOU SOURCE RCE RANRANGE GE HIGH FLU FLUX REACTOR X REA CTO R TRIP RPS-FIGUR RPS-F IGURE 18 E--18 SOU SOURCE RCE RANRANGE GE HIGH FLUX REA REACTORCTO R TRIP CHANNELLlI CHANNE CHANNEL CHANNE II L II MANUAL BLOCK (MOMENTARY) l TRIP BYPASS (NIS RACK) (NISRAC K) TRIP BYPASS (NIS RACK) (NISRAC K) NOT NOT DEENERGIZE DEENER GIZESOUSOURCE RCE H.?. (80TH RANGE H.V. (BOTH A&B LOGIC TRAIN REQUIRE REQUIRED) D) NOT ENERGIZE ENERGIZ E SOURCE RANGE H.V. (EITltER (EITHER LOGIC TRAIN) REACTOR TRIP Ij rpsfl8 rpsf18 I
B. 79%. C. 73%. C.73%. D. 70% D.70% For every 11% % above QPTR of 1.00, reduce power by 3%, when QPTR exceeds 1.02. A - Incorrect, QPTR UPPER: 1.0176; 1.0176-1.00=1.76% (rounded to 2%); 100% RTP-
- RTP (3%*2%)94%
(3%*2% )=94%. 100%RTP-(3 %*7%)=79%. B - Incorrect, 1.07-1.00=7%; 100%RTP-(3%*7%)=79%.
-
C - Correct, QPTR LOWER: Average of lower excore detectors is 0.98.
-
100%RTP(3%*9%)=73%. 1.07/0.98=1.0918; 1.0918-1.00=9%; 100%RTP-(3%*9%)=73%. 97%RTP(3%*9%)=70% D - Incorrect, 1.09-1.00=9%; 97%RTP-(3%*9%)=70%
-
2000-30 1 Source: Farley NRC Exam 2000-301 Answer: C 015A2.01 1
- 33. 015A2.011 l-tLY'Le,y tytey 2 00
':;2. O1I Given the following conditions:
- Reactor startup is in progress.
-
- All NI switches are in their normal lineup.
-
- Intermediate Range (IR) Channel N-35 indicates 3E-1O.
- 3E-10.
- IR Channel N-36 indicates 9E-11.
- 9E- 11.
- No manual blocks have been inserted.
-
- Source Range (SR) Channel N-31 has failed high.
-
- SR channel N-32 is functioning normally.
-
Which ONE of the following describes the plant response to the SR Channel N-3 N-311 failing high? A. A reactor trip signal is generated resulting in a reactor trip. B. A reactor trip signal is generated, but no trip occurs since one IR channel is above P-6. c. C. No reactor trip signal is generated since one IR channel is above P-6. D. No reactor trip signal is generated but, the level trip switch must be taken to bypass as soon as N-36 indicates above 1E-1O. 1E-lO. A - Correct, Since no blocks are in for the SR a reactor trip occurs.
-
B - Incorrect, The trip must be manually blocked when above P-6.
-
C - Incorrect, Although above P-6 the SR trip signals have not been blocked.
-
D - Incorrect, The trip must be manually blocked when above P-6.
-
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 59. Given the
- 59. Given following:
the following: Tl-579, Inadequate
- TI-579,
- Inadequate Core Core Cooling Cooling Monitor Monitor (ICCM)
(ICCM) Train Train AA Plasma Plasma Display, Display, isis deenergized. deenergized.
- AA Loss
- Loss of of Offsite Offsite Power Power andand Reactor Reactor Trip Trip occur.
occur. Natural Circulation
- Natural
- Circulation conditions conditions are are being being verified verified in in Supplement Supplement E, E, NATURAL NATURAL CIRCULATION VERIFICATION.
CIRCULATION VERIFICATION. How will How Subcooling and will Subcooling and Core Exit Thermocouple Core Exit Thermocouple Temperatures Temperatures (CETC) (CETC) be be determined? determined? Subcooling from the A. Subcooling Train A the Train A Subcooling Subcooling Monitor. Monitor. CETC temperatures by CETC local readings by local readings on on the the junction boxes. boxes. B. Subcooling by by comparing highest highest Hot Hot Leg Leg temperature to highest highest RCS RCS wide rangerange pressure. thermocouple readings. CETC temperatures by thermocouple C. Subcooling by ICCM Train B. CETC temperatures by BOTH Train A and Train B CETCs. D. Subcooling by comparing Hot Leg temperatures to Cold Leg temperatures. temperatures. CETC temperatures by Train B CETCs ONLY. 59 59
HLC-08 NRC HLC-08 NRC Written Written ExamExam
- 59. 017K3.01 59.017 K3.01 001/IN-CORE 001/IN-CORETEMP MONITORJ2/2/3.5/3.7IROIHIOHIN/A/NEW- 20081ICCM-005 TEMPMONITORl2/2/3.5/3.7IROIHIGH/NINNEW - 2008/ICCM-005 Given the Given following:
thefollowing: Tl-579, Inadequate
- TI-579,
- Inadequate CoreCore Cooling Cooling Monitor Monitor (ICCM)
(ICCM) Train Train AA Plasma Plasma Display, Display, isis deenergized. deenergized.
- AA Loss
- Loss of of Offsite Offsite Power Power andand Reactor Reactor Trip Trip occur.
occur. Natural Circulation
- Natural
- Circulation conditions conditions are being verified are being verified inin Supplement Supplement E, E, NATURAL NATURAL CIRCULATION VERIFICATION.
CIRCULATION VERIFICATION. How will How Subcooling and will Subcooling and Core Core Exit Exit Thermocouple Thermocouple Temperatures Temperatures (CETC)(CETC) be be determined? determined? A. Subcooling A. Subcooling from from the the Train Train AA Subcooling Subcooling Monitor. Monitor. CETC temperatures CETC temperatures by by local local readings readings on the junction on the junction boxes. boxes. B. Subcoo(ing by B. Subcooling comparing highest by comparing highest Hot Hot Leg Leg temperature temperature to to highest highest RCS RCS wide wide range range pressure. pressure. CETC temperatures CETC temperatures by thermocouple thermocouple readings. C~ Subcooling by ICCM C Subcooling ICCM Train B. CETC temperatures CETC temperatures by BOTH Train A and Train B CETCs. D. Subcooling by D. Subcooling comparing Hot Leg temperatures to Cold Leg temperatures. by comparing temperatures. CETC temperatures CETC temperatures by Train B CETCs ONLY. The correct answer is C. The correct A: A: Incorrect Incorrect - CETCs do NOT have any local indication at the junction boxes.
-
B: B: Incorrect Incorrect - Subcooling
-
Subcooling should be determined from the highest THOT T HOT and lowest lowest pressure. pressure. C: C: Correct Correct - - CETC CETC can be displayed can be displayed onon CET CET Recorder Recorder and and ERFIS ERFIS ifif Plasma Display Display panel panel is is inoperable. inoperable. D: D: Incorrect Incorrect - Hot
-
Hot leg leg temperature temperature to to cold cold leg leg temperature temperature equals equals Delta Delta T. T. Exam Exam Question Question Number: Number: 59 59
Reference:
Reference:
Supplement Supplement E, E, Page Page 29;29; ICCM ICCM Figure Figure 1,1, 27. 27. KA KA Statement: Statement: Knowledge Knowledge of of the the effect effect that that aa loss loss or or malfunction malfunction of of the the ITM ITM system system willwill have have on the following: on the following: Natural Natural circulation circulation indications. indications. History: History: New New - Written
-
Written for for HLC-08 HLC-08 NRCNRC Exam. Exam. 66 66
Rev. Rev. 35 35 EPP-Supplements EPP-Supplements SUPPLEMENTS SUPPLEMENTS Page 29 of Page 29 of 89 89 f__STEP H INSTRUCTIONS INSTRUCTIONS I f RESPONSE RESPONSE NOT NOT OBTAINED OBTAINED CONTINUOUS CONTINUOUS USE USE Supplement Supplement EE Natural Circulation Natural Circulation Verification Verification (Page (Page 11 of of 1)1) 1.
- 1. Check Natural Check Natural Circulation Circulation Status Status Increase Increase dumping dumping steam.
steam. As Follows: As Follows:
** Steam pressure Steam pressure - STABLE
- STABLE OR OR DECREASIN DECREASINGG AND
** RCS subcooling RCS subcooling - GREATER
- GREATER THAN 35°F THAN 35°F [55°F]
[55°F] AND
** Core exit Core exit TiCs T/Cs - STABLE OR
-
DECREASIN DECREASING G AND
** RCS hot RCS hot leg leg temperatures - -
STABLE OR DECREASIN DECREASING G AND
** RCS RCS cold cold leg leg temperatures temperatures - -
TRENDING TRENDING TO SATURATIO SATURATION N TEMPERAT TEMPERATUREURE FOR STEAMSTEAM PRES SURE PRESSURE 2.
- 2. Return Return To To Procedure Procedure And And Step Step In In Effect Effect
-- END END --
ICCM SIMPLIFIED TRAINS ICCM-FIGURE-1 (Rev. 1) ICCM-FIGURE-l
------
RVLIS ICCM r---tI TRAIN A TRAIN AI TRAIN B ICCM PLASMA I ELECTRONICS ELECTRON ICS DISPLAY CABINET
*
- CETM CETM r----~-w TRAIN A Control Room
~ BAY ~
TRAIN AI TRAIN B 1 -II TRAIN B SMM BAY SMM --- r-l' control Contro Room l Room TRAIN A TRAIN B Auxilary Auxilary Building Building Rod Rod Drive Drive Control Control Room Room I ICCM ICCM TRAIN BB TRAIN L.I PLASMA PLASMA DISPLAY DISPLAY INFOR MATION USE INFORMATION USE ONLY ONLY
ICCM-86 SIGNAL PROCESSOR INPUTS/OUTPUTS ICCM-FIGURE-27(Rev .2) ICCM-FIGURE-27(Rev.2) INPUTS OUTPUTS TE-41 3-2 TE-413-2 2 WIDE RANGE TEMP. (HOTS) TE-423 .p WIDE RANGE PRESS. PT-51 1AA PT-511AA ... po PLASMA DISPLAY TE-51 1AA TE-511AA 2 TOP OF VESSEL RTD TE-511AB TE-51 lAB ... PANEL ..
...
-
HOT LEG RTD TE-511AC ..... po TE-51 1AF TE-511AF ICCM-86 BO1TOM .OF VESSEL RTD 2 BOTTOM TE-51 lAG TE-511AG ... CHANNEL I CEI RECOR2,.ER 8 CET RECORDER
...
.....
po TOP OF VESSEL HYDRAULIC 115-51 lAB LlS-511AB ISOLATOR HOT LEG HYDRAULIC ISOLATOR LIS-511AA LlS-511AA .. p BOTTOM OF VESSEL LIS-511AC LlS-511AC .. DATA LINK TO ERFIS ... h
....
p HYDRAULIC ISOLATOR p UPPER RANGE D/PDIP TRANS. LT-511AA _ po FULL RANGE D/PDIP TRANS. LT-511AB LT-51 lAB
...
DYNAMIC HEAD D/P TRANSMI1TER TRANSMITTER DIP LT-51 1AC LT-511AC .. TE-433 1 WIDE RANGE TEMP. 1 ...1 (HOT) po WIDE RANGE PRESS. PT-51 1BA PT-511BA ... PLASMA DISPLAY
.....
po TE-511BA 2 TOP OF VESSEL RTD TE-511BB ... po PAN EL PANEL I CCM-86 ICCM-86 CHANNEL II BO1TOM .OF BOTTOM OF VESSEL RTD TE-511BF TE-511 BF .. CE1 RECORD,R 8 CET RECORDR TOP OF VESSEL HYDRAULIC ISOLATOR LlS-511BB LIS-511BB .p
...
HOT LEG HYDRAULIC ISOLATOR LIS-511BA LlS-511BA ... p DATA LINK TO ERFIS ... BOTTOM BO1TOM OF VESSEL HYDRAULIC ISOLATOR LlS-511 LIS-511BCBC ... UPPER RANGE D/P FULL RANGE D/P DIP TRANS. DIP TRANS. LT-511 LT-5118A LT-511BB BA LT-511 BB
.....
DYNAMIC HEAD D/P TRANSMITTER TRANSMI1TER DIP LT-511BC ..... po IIICCMF27I ICCMF27 I INFORMATION USE ONLY
HLC-08 HLC-08 NRC NRC Written Written Exam Exam
- 60. Given the
- 60. Given the following:
following: An RCS
- An
- LOCA has RCS LOCA has occurred occurred which which resulted resulted in Containment Spray in aa Containment Spray Actuation.
Actuation. ALL ESF
- ALL
- ESF equipment equipment has has functioned functioned as designed.
as designed. NO ESF
- NO
- ESF signals signals have have been been reset.
reset. pressure is 88 PSIG.
- Containment pressure
- PSIG.
The REQUIRED action(s) the crew must perform in order to allow valve SI-845A, SAT DISCH CLOSED, is(are) to reset the VLV, to be CLOSED, the...
...
A. SI Signal, and then reset the Containment Spray Actuation Signal. B. Containment Spray Actuation Signal. C. Containment Isolation Phase B Signal. D. SI Signal, and then reset the Containment Isolation Phase B Signal. 60 60
HLC-08NRC HLC-08 NRCWritten WrittenExamExam 60.027
- 60. 027Kl.Ol K1.01OOl/CTMT 001/CTMTIODINEIODINEREMOVREMOVAL/ 2/2/3.4/3.7/ROIFflGHIN/AIBRAIDWOOD- 20041ESF-004 AL/2/2/3.4/3.7IROIHIGH/NINBRAIDWOOD - 2004IESF-004 Giventhe Given thefollowing:
following:
- An
- AnRCS RCSLOCA LOCAhas hasoccurred occurredwhich which resulted resultedininaaContainment ContainmentSpray SprayActuation.
Actuation. ALLESF
- ALL
- ESFequipment equipmenthas hasfunctioned functionedas asdesigned.
designed.
- NO
- NO ESFESFsignals signals have have been been reset.
reset. Containmentpressure
- Containment
- pressure isis88 PSIG.
PSIG. The REQUIRED The REQUIRED action(s)action(s) thethe crew crew must must perform perform inin order ordertoto allow allow valve valve SI-845A, Sl-845A, SATSAT DISCH DISCH VLV, to be CLOSED, VLV, to be CLOSED, is(are) is(are) to reset the to reset the...
...
A. SI A. SI Signal, Signal, andand then then reset reset the the Containment Containment Spray Spray Actuation Actuation Signal. Signal. B Containment B:I Containment Spray Spray Actuation Actuation Signal. Signal. C. Containment C. Containment Isolation Isolation Phase Phase BB Signal. Signal. D. SI D. Signal, and SI Signal, and then then reset reset the Containment Containment Isolation Isolation Phase Phase BB Signal. Signal. The correct The correct answer answer is is B. B. A: Incorrect A: Incorrect - SI - SI reset reset is unnecessary, unnecessary, therefore therefore it is NOT a required required action. B: Correct B: Correct - - CV Spray CV Spray Actuation can be reset since CV pressure pressure is less than 10 PSIG. PSIG. C: Incorrect - Resett C: Incorrect - Resettinging Phase BB would have NO effect on CV Spray. D: D: Incorrect Incorrect - Resett
- ing SI Resetting SI and Phase B B would would have NO NO effect on CV CV Spray.
Exam Exam Question Question Number: Number: 60 60 Refere
Reference:
nce: SD-006, SD-006, ESFAS, ESFAS, PagesPages 13,13,17 17 and and Figure Figure 3.3. KA KA Statem Statement:ent: Knowledge Knowledge of of the the physical physical connec tions and/or connections and/or cause-cause-effect relationships effect relatio nships betwee n the CIRS between the CIRS and the and the following following system systems: CSS. s: CSS. History: History: Direct Direct from from Bank. Bank. 6767
SD-024 SD-024 CONTAINMENT SPRAY CONTAINMENT SPRAY SYSTEM SYSTEM 3.3 3.3 Eductors Eductors Number Number (1 for 22 (1 for each each pump) pump) Volume Volume Provide enough Provide enough NaOH NaOH to to keep keep pH.2:.. pH > 9.3 9.3 Design Pressure Design Pressure 200 psig 200 psig Design Temperature Design Temperature Ambient Ambient Flow (max) Flow (max) 80 gpm 80gpm The purpose The purpose of of the eductors isis to the eductors provide aa low to provide low pressure pressure areaarea for for injection injection of of the the NaOH NaOH solution stored solution stored inin the the SAT. SAT. The The eductors eductors use the the venturi venturi principle for for injecting injecting NaOH NaOH into the suction suction of the spray spray pumps. As As the velocity increases the pressure decreases decreases at at the constricted the constricted section. section. TheThe SAT SAT is connected at is connected at this this low low pressure area. area. 3.4 Major Valves 3.4.1 Suction Relief Valve, SI SI-871
-871 The purpose of the SI-871 is to protect the suction piping from overpressurization. overpressurization. The relief valve is set at 200 psig. It relieves to "B" B Spray Header downstream of SI-880C and SI-880D.
3.4.2 CV Spray Pump Suction Valves, SI-844A and SI-844B The purpose of the suction valves is to allow pump isolation for maintenance maintenance.. They are motor operated and controlled with a close/open switch from the RTGB. At power, these valves are normally open. SI-844A and SI-844B are powered from MCC-5 and MCC-6, respectively. 3.4.3 '~.4.3 Spray Additive Tank Discharge Valves, SI-845A and SI-845B The purpose of the SAT discharge valves is to isolate the SAT from the eductors. These parallel valves are motor operated and are normally closed, but will open automatically on spray signal (P-signal). They They are controlled from the RTGB with a Close/Auto/O Close/Auto/Open pen switch (spring return to Auto from open) and are powered from MCC-5 for SI-845A and MCC-6 for SI-845B. SI-845B. 3.4.4 3.4.4 Spray Spray Additive Additive Tank Tank Throttling Valve,Valve, SI-845C SI-845C The Spray The Spray Additive Additive Tank Tank throttling throttling valve valve isis used used toto adjust adjust the the flowrate flowrate ofof NaOH NaOH to to the the eductor eductor thereby thereby controlling controlling the the concentration concentration of of NaOH NaOH in in the the spray spray being being delivered delivered to to the CV. It is a normally open, motor operated the CV. It is a normally open, motor operated valve powered valve powered fromfrom MCC-5 MCC-5 and and isis controlled controlled with with aa close/open close/open switch switch (spring (spring return return to to center) center) located located onon the the RTGB. RTGB. css CSS Page Page 1313 of 26 of26 Revision 99 Revision INFORMAT INFORMATION ION USE ONLY ONLY
SD-024 SD-024 CONT~NTSPRAYSYSTEM CONTAINMENT SPRAY SYSTEM Reset of Reset of Containment Containment Spray Spray A Containment Spray A Containment Spray signal signal can can be be reset (key switch) reset (key switch) after after actuation actuation ifif itit becomes becomes necessary to stop or realign equipment necessary to stop or realign equipment actuated by actuated by the the Containment Containment Spray Spray signal. signal. Resetting Containment Resetting Containment Spray Spray will not "terminate" will not terminate Containment Containment Spray. Spray. The The coppnents actuated components actuated byby Containment ContainmenL Spray Sprayo not change do not change statestate when when Containment Cptainment Sprais
~pray iss reseL-J'hey reset. They mustmust be be manually manually aligned aligped after after Containment Containment Spray Spray isis reset.
reset During thlS"Condition, During this condition, if if another another Containment Containment Spray Spray signal signal isis generated, generated, aa manual manual Containment Spray Containment Spray must must be initiated by be initiated by the operator for the operator for Containment Containment Spray Spray to to occur. occur. Until the the Containment Containment Spray signal isis manually Spray signal manually reset, reset, any any safeguards safeguards equipment equipment stopped from stopped from the the RTGB RTGB cannot cannot be restarted without be restarted without removing removing the the control control power power fuses fuses at at the breaker and reinstalling them. This due to the anti-pump feature is due feature in in the breakers. The Phase "B" breakers. B Containment Containment Isolation Isolation mustmust bebe reset reset individually individually afterafter the the Containment Spray Containment Spray signal signal isis reset or cleared. Phase Phase "B"B Containment Containment Isolation is reset from pushbuttons on the RTGB. Manual spray actuation will cause the following:
- 1) Spray actuation
- 2) Containment Phase "B" B 3)
-3) Containment Ventilation Isolation - The following valves will close:
-
** Purge Purge Valves Valves
*
- Pressure Relief Valves
*
- Vacuum Relief Valves 5.2 Auto-actions on Spray Actuation 1)
- 1) Both Spray Pumps start
- 2) Spray Pump Discharge Valves (880 A/B/C/D) Open
* *~3) 3) Spray Spray Additive Tank Outlets Additive Tank Outlets (845 (845 A/B)
AlB) Open Open 6.0 6.0 SYSTEM SYSTEM OPERATION OPERATION 6.1 6.1 Normal Normal Operation Operation The The Spray Spray system in standby system isis in standby whenever whenever plantplant isis above above cold cold shutdown shutdown conditions. conditions. The The pump pump discharge discharge and spray tank and spray tank outlet outlet valves valves areare shut. shut. The The Spray Spray pumps pumps are are aligned aligned for for auto start with the suction valves auto start with the suction valves opened to opened to the the RWST. RWST. There There isis aa note note inin PLP-1 PLP-111, 11, Leakage Leakage Reduction Reduction Program, Program, for for plant plant personnel personnel to to notify notify the Control the Control Room Room for for eight eight different different systems systems whenwhen leaks leaks are are identified identified onon components components css CSS Page 17 of Page 17 of26 26 Revision99 Revision INFORMAT INFORMATION ION USE USE ONLY ONLY
LOGICDIAGRAM LOGIC DIAGRAMON ONSPRAY SPRAYACTUATIO ACTUATION N CSS-FIGURE-3 CSS-FIGUR E-3 TwoPush Two PushButton Button Manuel Manuaf Spray Actucation Spray Actucation Isol. Cont.lsol, Cone. Lege.nd: Legend: Phase Phcise B8 1AX5A Cont. Vent Cont. Veniiso!. Isol.
@
I Pressure Pressure PC Channel Channel
~stable 951A Bistable 951A U
I
.ORGate 2/3 IHi.Hi 2/3 Hi-Hi 2/3 Hi-Hi 2/3 IHi-Hi ti
_..w,..
~
Coincidence Coincidence VI I V.4+. outofof3)3) (2(2out V TI Li ANDGate AND Gate
- I I.
W CD Retentive Retentive Memory Memory SteamLIne/Si Steam tine /slSIGNAl. Isolation /
- SIGNAL4
- M.R.
- I 1 L_______ .1 ML I
.Containment Containment Ventilation V"ntilatiori Isolation Isolation CSSFO3 CSSF03 I i°v Actuation Cent. iso!. Phae]
INFORMATION INFOR MATION USE USE ONLY ONLY
QuestNo: Quest No: RO SRO: ROSRO: TIER: TIER: GROUP: GROUP: Topic No: TopicNo: KA No: KANo: RO: RO: SRO: SRO: Cog CogLevel: Level: 59 59 RO RO 22 22 027000 027000 027000K1.01 0270ooK1.01 3.4 3.4 3.7 3.7 !,.ow Low System/EvolutionName: System/Evolution Name: Statement: CategoryStatement: Category ContainmentIodine Containment RemovalSystem iodineRemoval System(CIRS) (CIRS) Knowledgeof Kuowledge ofthe physicalcounections thephysical connections and/or andlorcause-effect cause-effectrelationships relationshipsbetween between theCIRS the andthe CIRS and thefollowiug systems: followingsystems: KA Statemeut: KA Statement: CSS CSS UseriD: BW04NRC-059 UserID: BWO4NRC-059 Topic Liue: Topic Line: Question Stem: Question Stem: Given: Given:
- AA Unit - Unit 11 RCSRCS LOCALOCA and and Containment Containment Spray Actuation have Spray Actuation have occurred.
occurred. ALL U1
- ALL - Ui ESF equipment has ESF equipment has functioned functioned as designed.
as designed. NO U1
- NO - Ui ESFESF signals signals havehave been reset.
been reset. The MINIMUM The MINIMUM action(s)action(s) the crew must the crew must perform perform in in order order to to allow allow 11 CS019A, CSO1 9A, EDUC EDUC 11 AA SPRAY SPRAY ADD ADD VLV VLV to CLOSE to CLOSE and and remain remain CLOSED, CLOSED, is/are is/are to reset the to reset the U1 Train A: Ui Train A: AA SI Signal, SI Signal, andand thenthen reset reset the the U1 Train AA Containment Ui Train Containment Spray Spray Actuation Actuation Signal. Signal. BB Containment Spray Actuation Signal, only. only. cC Containment Isolation Isolation Phase B Signal, only. oD SI Signal, and then the U1 Ui Train A Containment Isolation Phase B Signal. Answer: Auswer: Task No: R-EP-009 Question Source: Questiou Question Difficulty B B Obj No: S.CS1-08-D S.CSI-08-D NEW. Added unit references and the word minimum "minimum" to the stem make sure only one correct answer. Got 33 Time: Time: Cross Ref: BWLI-CSI BWLI-CSI-040 .040 rid of Phase A as a choice, added SI signal. 1
Reference:
Reference:
Big Big Note Note CS-i CS-I Rev 7 Explanation: Explanation: Containment Containment sprayspray actuation actuation signal signal must be reset (nothing else). Phase B, and SI status have no uo effect, though both are plausible since they they both both should have occurred. A: A: SISI reset reset is is unnecessary. B: B: Correct Correct C: C: Phase Phase BB would would have have no effect. effect. D: D: SISI and and Phase Phase B B resets would have have no no effect effect Date Date Written: Written: 3/22/2004 3/2212004 Author: Author: Unknown Unknown App. App. Ref: Ref: None. None.
HLC-08 NRC Written Exam
- 61. Given the following:
MODE 6.
- The plant is in MODE
-
- Refueling activities are in progress.
-
- APP-005-C1, SR HI FLUX AT SHUTDOWN is illuminated.
-
Which ONE (1) of the following describes SR counts when the alarm was received and the automatic action expected? than... SR counts are greater than ... A. 3 times AII-Rods-In All-Rods-In background and the CV Evacuation horn will sound. All-Rods-In background and the LOCAL Evacuation alarm will sound. B. 3 times AII-Rods-In All-Rods-In background and the CV Evacuation horn will sound. C. 2 times AII-Rods-In All-Rods-In background and the LOCAL Evacuation alarm will sound. D. 2 times AII-Rods-In 61
NRC Written HLC-08 NRC HLC-08 Exam Written Exam 61.
- 61. 034 A4.02 OOllFUEL 034 A4.02 001/FUEL HANDLING - 20081N1S-008 EQUIP/2/2/3.5/3.9/ROILOWIN/A/NEW - 200SINIS-00S HANDLING EQUIP/2/2/3.5/3.9fROILOWINIAfNEW Given the Given following:
the following: The plant
- The
- plant isis in MODE 6.
in MODE 6.
- Refueling
- are in activities are Refueling activities in progress.
progress.
- APP-005-C1, SR HI
- FLUX AT SHUTDOWN is HI FLUX is illuminated.
Which ONE ONE (1) of the (1) of following describes the following describes SRSR counts when the counts when the alarm alarm was received and was received and the the automatic action expected? SR counts are greater than than...
...
All-Rods-In background and the CV Evacuation horn will sound. A 3 times AII-Rods-In A'I All-Rods-In background and the LOCAL Evacuation alarm will sound. B. 3 times AII-Rods-In All-Rods-In background and the CV Evacuation horn will sound. C. 2 times AII-Rods-In D. 2 times AII-Rods-In All-Rods-In background and the LOCAL Evacuation alarm will sound. The correct answer is A. A: Correct - - High Flux at Shutdown alarm setpoint is set at 3 times the ALL-Rods-In background count rate to ensure early warning of changing counts. counts, IF the setpoint is exceeded, an automatic initiation of the CV Evacuation Horn will occur. B: Incorrect - High Flux at Shutdown alarm setpoint is set at 3 times the ALL-Rods-In
-
background count rate to ensure early warning of changing counts. There is NO automatic initiation of LOCAL evacuation. C: Incorrect - If SR counts double during any reactivity addition, dilution or rod movement is
-
stopped to ensure positive control over the core. This is an incorrect application of this setpoint. D: Incorrect Incorrect - IfIf SR
- SR counts double during any reactivity addition, dilution double during dilution or or rod movement is is ensure positive control over stopped to ensure over the core. This is is an an incorrect incorrect application of this setpoint.
Exam Question Number: Number: 61
Reference:
GP-002, G P-002, PagePage 118; OP-002, Pages 118; OP-002, 15 and Pages 15 and 16; 16; APP-005-C1. KA Statement: Statement: Ability to to manually manually operate monitor in and/or monitor operate and/or in the the control room: Neutron Neutron levels. levels. History: History: New Written for New - Written
- for HLC-08 HLC-08 NRCNRC Exam.
Exam. 68 68
APP-005-C1 APP-005-C1 ALARM ALARM SR HI SR HI FLUX FLUX ATAT SHUTDOWN SHUTDOWN ACTIONS AUTOMATIC ACTIONS AUTOMATIC 11.. Evacuation Alarm CV Evacuation CV Alarm CAUSE CAUSE 1.
- 1. Addition of Addition positive reactivity of positive reactivity while shutdown while shutdown 2.
- 2. Failure to Failure block prior to block prior to to startup startup 3.
- 3. Electrically induced Electrically induced "noise" noise in SR Channel in SR Channel 4.
- 4. Failure Source Failure Range Channel Source Range Channel OBSERVATIONS OBSERVATIONS 1.
- 1. Source Range Range NI NI ACTIONS 1.
- 1. IF a valid High IF High Flux Flux level is indicated, indicated, THEN perform the following:
- a. Evacuate Containment.
- b. Insert any Control Rods withdrawn.
- c. IF fuel movement is in progress, THEN discontinue fuel movement.
- d. IF Source Range count rate is increasing, THEN borate the RCS lAW OP-301 until SUR becomes negative.
- 2. IF due to failure to block the alarm during startup, THEN block alarm.
- 3. IF due to electrical spikes AND personnel are in the CV, THEN make PA announcement to disregard alarm.
- 4. IF NOT due to known core reactivity change, THEN notify Reactor Engineering to evaluate the potential need to perform EST-001. (ACR 93-00198)
DEVICE/SETPOINTS 1.
- 1. N-31, or N-32 /I 3 times Countrate with all rods inserted. (CR 95-00294)
POSSIBLE PLANT EFFECTS EFFECTS 1.
- 1. Inadvertent Criticality Criticality 2.
- 2. Loss Loss ofof required Technical Specification Shutdown Margin Specification Shutdown Margin REFERENCES 1.
- 1. ITSLCO3.1.1 ITS LCO 3.1.1 2.
- 2. EST-001, EST-001, Source Source Range Range Statistical Statistical Reliability Reliability Test Test 3.
- 3. ACR 93-00198, N-32 ACR 93-00198, N-32 failed to to indicate indicate proper proper change change in in countrate countrate 4.
- 4. CWD CWD B-190628, B-190628, Sh Sh 441, 441, Cable Cable AMAM 5.
- 5. CR 95-00294, IN CR 95-00294, IN 93-32:
93-32: Nonconservative Inputs For Nonconservative Inputs For Boron Boron Dilution Dilution Event Event 6.
- 6. OP-3d, OP-301, Chemical Chemical and and Volume Volume Control Control System System (CVCS)
(CVCS) !APP-005 APP-005 Rev. Rev. 29 29 Page 16 Page 16 of of 40 40 I
Section 8.4.1 Section 8.4.1 Page Page 2 of 2 of 55 8.4.1.2 (Continued) 8.4.1.2 (Continued) INIT INIT INIT INIT N-31 N-31 N-32 N-32 NOTE: NOTE: Unless otherwise stated, the switches, potentiometers, Unless potentiometers, AND indicators addressed by by the procedure steps in in this section are located on the drawer front panel panel for the channel being adjusted.
- d. PLACE the LEVEL TRIP switch in the BYPASS position.
- e. VERIFY the LEVEL TRIP BYPASS indicator is ILLUMINATED.
- f. VERIFY the SOURCE RANGE TRIP BYPASS status light on the RTGB is ILLUMINATED for the channel being adjusted.
- g. VERIFY the NIS TRIP/DROP ROD BYPASS annunciator on the RTGB is ILLUMINATED (APP-005-D4)..
(APP-005-D4)
- h. RECORD the neutron level meter indication (Background). N-31 CPS _ __
N-32CPS N-32 CPS _ __
- i. PLACE the HIGH FLUX AT SHUTDOWN switch in the BLOCK position.
- j. VERIFY the HI FLUX AT SHUTDOWN ALARM BLOCK annunciator is ILLUMINATED ILLUMINATED on the RTGB (APP-005-B1).
OP-002 IOP-002 Rev. Rev. 19 19 Page Page 1515 of of 221
Section Section 8.4.1 8.4.1 Page Page 3 of 3 of 55 (Continued) 8.4.1.2 (Continued) 8.4.1.2 INIT INIT INIT INIT N-31 N-31 N-32 N-32
~- k. CALCULATE the CPS neutron level setpoint 8.4.1 .2.h OR per
[3 times the reading in Step 8.4.1.2.h EST-049, OR LP-551]. EST-048, EST-049, (ACR 95-00294) N-31 CPS _ _ N-32CPS N-32 CPS _ _ I. PLACE the OPERATION SELECTOR Switch in the LEVEL ADJ position.
- m. CHECK APP-005-D3, NIS CHANNEL TEST annunciator on the RTGB, is ILLUMINATED. __
~
- n. ADJUST LEVEL ADJ Pot until the CPS Neutron Level Meter indication is at the 8.4.1 .2.k.
desired trip point in Step 8.4.1.2.k.
- o. SLOWLY ADJUST TRIP ADJ on NC-103 ADJUSTTRIPADJ NC-i 03 until the Bistable just trips as indicated by the HIGH FLUX AT SHUTDOWN Lamp.
(Adjustment inside drawer)
- p. IF the alignment can NOT be satisfactorily completed, THEN NOTIFY the SSO.
- q. TURN the LEVEL ADJUST to the full counter-clockwise (CCW) position.
!OP-002 OP-002 Rev. Rev. 19 19 Page Page 1616 of of 22 221
ATTACHMENT 10.5 ATTACHMENT 10.5 of 33 Page 22 of Page RESETTING SR RESETTING SR HI FLUX AT HI FLUX AT SHUTDOWN SHUTDOWN ALARM ALARM lNlT 3.
- 3. Approval from Approval from the the Manager Manager - Operations,
- Operations, or or designee, designee, to insert to insert both Shutdown both Shutdown Banks Banks hashas been received.
been received. 4.
- 4. IF Rods IF Rods are withdrawn, THEN are withdrawn, THEN insert all Rods insert all Rods as as follows follows 173910-11]:
[CAPR 173910-11]: 1)
- 1) Select SBA on the Rod Select Rod Bank Bank Selector Selector switch.
- 2) Insert the Shutdown Bank "A" A to 005 steps.
- 3) Depress the REACTOR TRIP pushbutton.
,~ 5. Adjust the HI FLUX AT SHUTDOWN alarm to 3 times the All-Rods-In count rate lAW AII-Rods-In JAW OP-002. (ACR 95-00294)
- 6. IF desired to withdraw the Shutdown Bank and Control Bank Rods, THEN perform the following [CAPR 173910-11]:
- 1) Perform the following while maintaining RCS temperature constant:
- a. Verify closed the Reactor Trip Breakers.
- b. Depress the ROD CONTROL STARTUP pushbutton.
c. C. Verify the Group Step Counters indicate 000. 000.
- d. Check Individual Individual Rod Position Indicators Indicators are within 7.5 inches of the Bank Bank average rod height. height.
e.
- e. Select SBA on the Rod Rod Bank Bank Selector switch.
switch. NOTE: NOTE: Criticality Criticality shall be anticipated shall be anticipated at any time, when the Shutdown at any Shutdown BankBank OR OR Control Control Bank Bank Rods Rods are are being being withdrawn. withdrawn. f.f. Withdraw Withdraw Shutdown Shutdown Bank Bank A "A" to to 225 225 steps. steps. 2)
- 2) Select Select SBBSBB on on the the Rod Rod Bank Bank Selector Selector switch.
switch. 3)
- 3) Withdraw Withdraw Shutdown Shutdown BankBank B "B" to to 005 005 steps.
steps. G P-002 Rev. Rev. 103 103 Page Page 118118 of of 124 1241
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 62. Given
- 62. Given the the following:
following: The plant
- The
- plant was was operating operating atat 100%
100% RTP RTP when when aa Small Small Break Break LOCA LOCA occurred. occurred. Safety Injection
- Safety
- Injection has has been been actuated.
actuated. RCPs were
- RCPs
- were tripped tripped due to loss due to loss of subcooling.
of subcooling. Which ONE Which ONE (1)(1) of of the the following following describes describes how how the the S/Gs S/Gs areare controlled controlled to to ensure ensure core cooling isis core cooling maintained during this maintained during this event? event? A. SIG levels A. S/G levels are are NOT NOT required required toto be maintained at be maintained at aa minimum minimum level level due due to to SI SI injection injection flow. flow. B. SIG levels B. S/G levels are are maintained maintained at at> 8% [18%]
> 8% [18%] toto provide provide additional additional heat heat removal removal capacity.
capacity. C. S/G C. S/G levels levels are are NOT NOT required required asas long long asas core core exit exit thermocouples thermocouples areare maintained maintained less less than than 700 OF. 700 °F. D. S/G D. S/G AFW AFW flowflow rates rates are are maintained maintained at 80-90 GPM to provide provide additional heat heat removal capacity. capacity. 62 62
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 62. 035
- 62. 035 A2.06 A2.06 OOllSTEAM GENERATORJ2/2/4.5/4.6IROJLOWJN/AINEW- 200S/PATH-I-005 001/STEAM GENERATORJ2/2/4.5/4.6IROILOWININNEW - 2008IPATH-1-005 Given the following:
Given the following:
- The
- plant was The plant was operating operating at at 100%
100% RTP RTP when when aa Small Small Sreak Break LOCA LOCA occurred. occurred. Safety Injection
- Safety
- Injection has been actuated.
has been actuated. RCPs were
- RCPs
- were tripped tripped duedue toto loss of subcooling.
loss of subcooling. Which ONE Which ONE (1) of the (1) of the following following describes describes how how thethe S/Gs S/Gs are are controlled controlled toto ensure ensure core cooling isis core cooling maintained during maintained during this this event? event? A. SIG levels A. S/G levels areare NOT NOT required required to to be maintained at be maintained at aa minimum minimum level level due due to to SI SI injection injection flow. flow. B B~ S/G levels are S/G levels are maintained maintained at at> 8% [18%]
> 8% [18%] to provide additional to provide additional heat heat removal removal capacity.
capacity. C. S/G C. levels are S/G levels are NOT NOT required required as long as as long as core exit thermocouples core exit thermocouples are are maintained maintained less less than than
°F.
700 of. D. S/G AFW AFW flow rates are maintained at 80-90 GPM to provide provide additional heat removal capacity. capacity. The correct answer is S. The B. A: Incorrect - Secondary Heat Sink is required as long as RCS pressure is greater than S/G A: - pressure and RCS temperature is > 350 of. °F. B: Correct - - Maintaining S/G levels> 8% ensures Secondary Heat Sink is maintained as long as RCS pressure is greater than S/G pressure. C: Incorrect - Secondary Heat Sink is required as long as RCS pressure is greater than S/G
-
pressure and RCS temperature is >> 350 °F. of. D: 0: Incorrect Incorrect - AFW
-
AFW flow rates of 80-90 GPM GPM maintains maintains the S/G S/G internals wet when ALL S/Gs are faulted and does NOT NOT provide 300 300 GPM minimum minimum flow. Exam Exam Question Question Number: Number: 62 62
Reference:
Reference:
PATH-i PATH-1 BD, SO, Page 37; FRP-H.1 Page 37; FRP-H.1 BD, SO, Page Page 45.45. KA KA Statement: Statement: Ability Ability to (a) predict to (a) the impacts predict the impacts of of the the following following malfunctions malfunctions oror operations operations on on the SG; and the SG; (b) based and (b) based on on those those predictions, predictions, useuse procedures procedures to to correct, correct, control, control, or or mitigate mitigate thethe consequence consequences s of of those those malfunctions malfunctions or or operations: operations: Small Small break break LOCA. LOCA. History: History: New New - Written
-
Written forfor HLC-08 HLC-08 NRC NRC Exam.Exam. 69 69
GRID WOG BASIS/DIFFERENCES STEP SSD DETERMINATION This is an SSD per criterion 10. E8) 28 RNP STEP
,., . . CONTROL AFW FLOW TO MAINTAIN S/G LEVELS BETWEEN 8% AND 50%
RNP STEP ANY S/G WITH UNCONTROLLED LEVEL INCREASE (with transition to Path-2) WOG BASIS
. PURPOSE: To ensure adequate feed flow or SC SG inventory for secondary heat sink requirements
,
BASIS: The minimum feed flow requirement satisfies the feed flow requirement of the Heat Sink Status Tree until level in at least one SG is restored into the narrow range. Narrow range level is reestablished in all SGs to maintain symmetric cooling of the RCS. The control range ensures adequate inventory with level readings on span. The transition to E-3, STEAM GENERATOR TUBE RUPTURE, responds to an increasing level which would be observed following a a SGTR. KNOWLEDGE:
* "Level manner means that the operator cannot control Level increase in an uncontrolled manner" level using available equipment, i.e., level continues to rise even when all feed flow valves to that SG are fully closed.
- This step is a continuous action step.
RNP DIFFERENCES/REASONS There are no significant differences. SSD DETERMINATION This is not an SSD. E-9 29 RNP STEP R-19'S, R-1 9S, R-31'S, R-31 S, AND R-15 R-1 5 RAD LEVELS NORMAL (with transition to Path-2) WOG BASIS PURPOSE: To identify any ruptured (failure in primary to secondary pressure boundary) SGs BASIS: Abnormal radiation in a steam generator indicates primary to secondary leakage. Since the air ejector and blowdown lines may have been isolated at the initiation of the transient, it may be necessary to check each steam generator at this time. Optimal recovery in dealing with a steam generator tube rupture is provided in E-3, STEAM GENERATOR TUBE RUPTURE. KNOWLEDGE:
- How to obtain secondary radiation level readings including signals that may need to be reset.
- Normal means the value of a process parameter experienced during routine plant "Normal" operations.
IPATH-1-BD PATH-1-BD I Rev 18 951 Page 37 of 95
RNP WOG waG BASIS/DIFFERENCES BASISIDIFFERENCES STEP STEP RNP DIFFERENCES/REASONS The RNP procedure places the caution or note in an action step to prevent actions within cautions and noted as required by the writers writer's guide. SSD DETERMINATION This is an SSD per criterion 11. 3 1 1 WOG BASIS WOGBASIS BASIS: Before implementing actions to restore flow to the steam generators, the operator should check if secondary heat sink is required. For larger LOCA break sizes, the RCS will depressurize below the intact steam generator pressures. The steam generators no longer function as a heat sink and the core decay heat is removed by the RCS break flow. For this range of LOCA break sizes, the secondary heat sink is not required and actions to restore secondary heat sink are not necessary. For these cases, the operator returns to the guideline and step in effect. Since Step 8 directs the operator to return to Step 11 if the loss of secondary heat sink parameters are not exceeded, break sizes that take longer to depressurize the RCS will be detected on subsequent passes through Step 1. If RCS temperature is low enough to place the RHR System in service, then the RHR System is an alternate heat sink to the secondary system. Therefore, an attempt is made, to place the RHR System in service in parallel to the attempts to reestablish feedwater flow. RCS pressure must be below normal RHR System pressure limits. KNOWLEDGE: The operator must be able to place the RHR System in service before the pressure and temperature limits are exceeded to make this alternate heat sink a valid option. Efforts to restore feedwater flow to the SGs should not be delayed if the RHR System is not a valid option. RNP DIFFERENCES/REASONS There are essentially no differences. SSD DETERMINATION This is not an SSD. IFRP-H.1-BD Rev 22 Page 45 af of 70 I
HLC-08 NRC Written Exam
- 63. Given the following:
- A Steam Generator Tube Rupture has occurred.
-
°F lAW PATH-2.
- The crew is preparing to cooldown to a target temperature of 480 of
-
- A Loss of Off-Site Power occurs.
-
- All equipment functions as required.
-
Which ONE (1) of the following describes how the cooldown to target temperature will be accomplished? A. Intact S/G PORVs controllers set to 1005 PSIG. B. Steam Dumps in Pressure Control mode set to 3.95 (553 PSIG). C. Intact S/G PORVs controllers set to obtain full OPEN valve position. D. Steam Dumps in Pressure Control mode set to maximum rate. 63 63
HLC-08NRC HLC-08 WrittenExam NRCWritten Exam
- 63. 041A4.06 63.041 A4.06OOllSTM 001/STMDUMPffURB DUMP1TURBBYPASS/2/2/2.9/3.1IROIHIGWNINSALEM BYPASS/21212.913. 1IROIHIGHIN/AJSALEM- 2001IPATH-2-005- 2001IPATH-2-005 Giventhe Given thefollowing:
following:
- AASteam
- GeneratorTube Steam Generator Tube Rupture Rupture has occurred.
has occurred. The crew
- The
- preparing toto cooldown crew isis preparing cooldown to targettemperature to aatarget temperature of of 480 480 of lAW PATH-2.
°F lAW PATH-2.
- Loss ofof Off-Site
- AA Loss Off-Site Power Power occurs.
occurs. All equipment
- All
- equipmentfunctions functions as required.
as required. Which ONE Which ONE (1) (1) of the following of the following describes describes how how the the cooldown cooldown to to target target temperature will be temperature will be accomplished accomplished? ? A. Intact SIG A. Intact S/G PORVs PORVs controllers controllers set set to 1005 PSIG. to 1005 PSIG. B. Steam Dumps B. Steam Dumps in in Pressure Pressure Control Control mode mode set set to 3.95 3.95 (553 (553 PSIG). PSIG). Cy Intact C:I Intact SIG PORVs controllers set to obtain full OPEN valve position. S/G PORVs D. Steam D. Steam DumpsDumps in Pressure Control mode set to maximum rate. The correct answer The correct answer is is C. C. A: Incorrect - Setting A: Incorrect - Setting PORVs to 1005 PSIG will NOT cooldown the plant, but will maintain maintain RCS temperature at 547 °F. of. B: B: Incorrect Incorrect - Condenser
-
Condenser Steam Dumps are unavailable due due to loss of Condenser from from LOOP. LOOP. Set Set at target target temperature saturation pressure. C: C: Correct Correct - - Steam Steam Line Line PORVs PORVs on on intact intact S/Gs S/Gs setset to to max max rate. rate. Condenser Condenser Steam Steam Dumps Dumps are are unavailable unavailable due due toto LOOP. LOOP. D: 0: Incorrect Incorrect - Steam
-
Steam Dumps Dumps unavailable unavailable due due toto loss loss of of Condenser Condenser from from LOOP. LOOP. Exam Exam Question Question Number: Number: 63 63
Reference:
Reference:
PATH-2PATH-2 BD, BD, Page Page 7.7. KA KA Statement: Statement: Ability Ability toto manually manually operate operate and/or monitor inin the and/or monitor the control control room: room: Atmospheric Atmospheric relief relief valve valve controllers. controllers. History: History: Direct Directfrom from Bank. Bank. 70 70
----.-..------.-.---...-.--.--- ...~::::""'~~
2.2 .::2S!.!:::G~T=R=T:r=a=ns=i=en=t=:ePowerUflav (TraentOffsit =O=ff=s=it:e:p:o:w=e:r~u=n=av=a::=i:::la=b=le Nab __) principal systems/components affected by station blackout blackout are the steam are the steam dump dump system, coolant pumps reactor coolant system, reactor pumps (RCPs), and (RCPs), and RCS RCS pressure pressure control. control. The The effect effect of of each each of of these these on on the the system system response response and and recovery recovery is is discussed. discussed. The The steam steam dump dump system system is is designed designed to to actuate loss of following loss actuate following of load load or or reactor trip to reactor trip to limit limit the the increase increase in in secondary secondary side side pressure. pressure. Without Without offsite offsite power power available, available, the the steam dump valves, steam dump which bypass valves, which bypass the the turbine turbine to to the condenser, will the condenser, will remain remain closed. closed. Hence, Hence, energy energy transferred transferred from from the the primary primary will rapidly increase will rapidly increase steam steam generator pressures after generator pressures after reactor reactor trip trip until until the the atmospheric atmospheric relief relief valves valves lift lift to to dissipate this energy, dissipate this energy, as as shown shown in in Figure Figure 16. 16. Since Since the secondary the secondary side side temperature temperature increase increase is is greater, greater, sensible sensible energy energy transfer the primary from the transfer from primary side side following following reactor reactor trip trip is is reduced. reduced. Consequently, Consequently, RCS pressure decreases RCS pressure decreases more more slowly, slowly, as demonstrated in as demonstrated in Figure Figure 17, 17, so that SI so that actuation and SI actuation and allall attendant attendant automatic automatic actions, actions, are delayed. A are delayed. typical sequence A typical sequence of events without of events without offsite offsite power power available available is is also also presented in in Table 1. 1. RCPs trip on a loss of offsite power and aa gradual transition to to natural circulation flow ensues. The cold cold leg temperature temperature trends trends toward the steam steam generator generator temperature as as the fluid residence residence time time in in the tube tube region region increases. Initially, Initially, the core delta-T delta-T decreases decreases as as core power decays core power decays following reactorreactor trip and, and, subsequently, subsequently, increases increases as as natural natural circulation flow develops (Figures circulation (Figures 18 18 and 19). Without RCPs and 19). running the upper RCPs running upper head head region region becomes becomes inactive inactive and and the fluid temperature in that region will Significantly significantly lag the temperature in the active RCS regions. This creates a situation more prone to voiding during the subsequent cooldown and depressurization. Sufficient instrumentation and controls are provided to ensure that necessary recovery actions can be completed without offsite power power available. Although the recovery method is the same with or without offsite power available, the equipment used may be different. Since automatic steam dump to the condenser is unavailable, reactor coolant temperatures may remain significantly greater than no-load temperature following reactor trip, as shown in Figure 20. Voiding may occur in the RCS as primary-to-secondary leakage depletes coolant inventory until manual actions to cool the RCS are initiated. In most cases, AFW flow will cool the RCS sufficiently to prevent voiding. This depends on the capacity of the AFW system and the actuation logic. For the results presented, AFW is assumed to actuate on the SI signal. ~ J,!:le - The RCS is cooled using siiapower the power operatedopjelief reli~f valyes vl (PORVs) on the intact PORVs) .pntbJnI ct steam generators since ~ither nier the
~am dump valves nor the condenser would be availab~ available without offsite power. Even with one steam generator out of service, these valves provide sufficient capacity to complete the initial RCS cooldown rapidly. Note that the hot leg temperature does not respond as quickly as the cold leg and steam generator temperatures since RCPs are not running. RCS pressure decreases rapidly during this cool cooldown down (Figure 21). The reactor coolant may saturate temporarily during the cooldown after the pressurizer empties (Figure 22).
Under natural circulation conditions subsequent actions to isolate the affected steam generators and cool down the intact RCS loops may stagnate the affected loop. Consequently, the hot leg fluid in that loop may remain warmer than in the unaffected loops. Similarly, SI flow into the stagnant loop cold leg may rapidly decrease the fluid temperature in the cold leg, downcomer, and pump suction regions significantly below the rest of the RCS, as observed during the tube failure event at R.E. Ginna (Figure 23). With RCPs stopped, normal pressurizer spray would not be available. Consequently, RCS pressure must be controlled using pressurizer PORVs or auxiliary spray. Although aa PORV enables more rapid RCS depressurization, it also results in an additional loss of reactor coolant which may rupture the pressurizer relief tank (PRT) and contaminate the containment. Auxiliary spray conserves reactor coolant but may create excessive thermal stresses in the spray nozzle nozzle which could result in nozzle failure. Consequently, it is recommended only if normal spray and pressurizer PORVs are not available. Since the upper upper head region is is inactive, voiding may occur in this region during during RCS depressurization. This will result in aa rapidly increasing pressurizer pressurizer level level indication as water displaced from the upper head replaces steam released or condensed from the pressurizer. This behavior was observed during during the GinnaGinna tube failure event, event, as shown in in Figure Figure 24, 24, when the the pressurizer pressurizer PORV PORV failed to close. The extent extent of of voiding voiding is is limited to the inactive inactive regions of of the the RCS RCS provided subcooling is is maintained maintained at the core exit. However, flashing in in the inactive inactive regions may may slow slow further RCS depressurization to cold shutdown conditions. Even Even without offsite offsite power, the E-3 recovery scheme establishes the E-3 establishes sufficient sufficient RCS subcooling, secondary side side heat heat sink, sink, and and reactor coolant inventory inventory to to ensure ensure SI SI flow is is no longer required. The plant no longer plant response is is similar similar with or or without offsite power available. offsite power available. Once Once SI SI flow flow is is stopped, stopped, no no additional additional primary-tosecondary primary-tosecondary leakage leakage or or uncontrolled uncontrolled radiological radiological releases releases from from the the affected affected steam generators should steam generators should occur. occur. IPATH-2-BD PATH-2-BD Rev. Rev. 1717 Page Page 77 of of 110 110 I
SALEM FOXTROT SALEM FOXTROT NRC WRITTEN 2001 NRC 2001 WRITTEN EXAMINATION EXAMINATION WORKSHEET Question Question Common 42 Common 42 Number: Number: Question: Question: Unit 22 has sustained cooldown to a preparing to cooldown sustained a Steam Generator Tube Rupture. The crew is preparing target temperature ofof 497°F. A loss of Off-Site Power occurs. All equipment functions as required. of OffSite Which one of the following describes how the cooldown to target temperature will be accomplished? A. MS10s set to 25% Intact SG MS1Os B. Main Steam Dumps in Pressure Control mode set to 25%25 % C. Intact MS 1Os set to maximum rate Illtact SG MS1Os D. Main Steam Dumps in Pressure Control mode set to maximum rate Answer: C Justification: MS lOs on intact SGs set to max rate will not cause MSLI. Main steam dumps unavailable due MS10s to LOOP. C-9 unavailable with no CWPs. 25% put in there because that'sthats the setpoint for normal steam dump cooldown for SGTR Tier/Group 1/2 112 10CFR55.41 41.10 10CFR55.43 Bank/New/ BankfNew/ New Modified KJA#: K/A #: 038EA2.08 determine action to place unit in safe condition, no steam dumps available KJA K/A Values: RO 3.8 SRO 4.4 Cognitive Analysis Level:
References:
EOP-SGTR-l, EOP-SGTR-1, Step 15 LP SGTR-l, SGTR-1, objective 3
HLC-O8 NRC HLC-08 Written Exam NRC Written Exam
- 64. Which
- 64. Which ONEONE (1)(1) ofofthe thefollowing following describes describeshow howthe the Reactor Reactor Protection Protection System System provides provides Runback signals toto the Runback signals the Turbine Turbine Generator?
Generator? The RPS The RPS initiates initiates aa Turbine Turbine (1)(1) runback when runback when 2/3 2/3 OT Delta TT (2) OT Delta (2) 2/3 2/3 OP OP Delta Delta TT signals signals reach their runback setpoints. reach their runback setpoints. A. (1) Reference A. (1) Reference (2)OR (2) OR B. (1) Valve B. (1) Valve Limiter Limiter (2)OR (2) OR (1) Reference C. (1) C. Reference (2) AND (2) AND D. (1) Valve D. (1) Valve Limiter Limiter (2) AND (2) AND 64 64
HLC-08 NRC Written Exam
- 64. 045 K1.18 OOllMAIN 64.045 GEN/2/2/3.6/3.7/RO/LOW[N/A/NEW - 2008/RPS-006 001/MAIN TURBINE GEN/2/2/3.6/3.7fROfLOWfNINNEW -
Which ONE (1) of the following describes how the Reactor Protection System provides Runback signals to the Turbine Generator? The RPS initiates a Turbine (1) runback when 2/3 OT Delta T (2) 2/3 OP Delta T signals reach their runback setpoints. A'I (1) Reference As (2) OR B. (1) Valve Limiter (2) OR C. (1) Reference (2) AND D. (1) Valve Limiter (2)AND (2) AND The correct answer is A. A: Correct -- Turbine Reference runbacks operate from 2/3 OT Delta T OR 2/3 OP Delta T on a 30 second timer. Runback signal is ON for 1.5 seconds and OFF for 28.5 seconds until runback signal clears. B: Incorrect - No valve limiter runback exists.
-
C: Incorrect - Reference runback from 2/3 OT Delta T OR 2/3 OP Delta T, does NOT require
-
BOTH. D: Incorrect - No valve limiter runback exists.
-
Exam Question Number: 64 SD-Oil, RPS, Page 23, Figure 15.
Reference:
SD-011, KA Statement: Knowledge of the physical connections and/or cause-effect relationships between the MT/G system and the following systems: RPS. History: New - Written for HLC-08 NRC exam.
-
71
SD-Oil SD-011 REACTOR PROTECTION SYSTEM
- b. lout 1 out of 2 Intermediate Range Channels above 20 %, this block can be bypassed.
20%,
- c. OTLLT s above calculated setpoint, this calculated setpoint is less 2 out of 3 OTAT's OTIXT Trip by ~ 2%.
than the OTAT Provided by the same bistable as the Turbine Runback. (See Figure 14)
- d. OPAT s above calculated setpoint, this calculated setpoint is less 2 out of 3 OPAT's OP~T Trip by ~ 2%.
than the OP1T Provided by the same bistable as the Turbine Runback (See Figure 14) 4.4 Turbine Runbacks The Turbine Runback is designed to reduce Turbine Load and thus avoid an unnecessary trip. The Turbine Runback is caused by High ~T zT Signals and are initiated by a Load Reference Reduction. 4.4.1 Load Reference Reduction (Figure 15) ~ The Load Reference Reduction is caused when any of the following occur:
- a. OTZT OT ~ T - when 2 out of 3 Reactor Coolant Loop ~
- T' s (Th - Tc)
ATs - Te) exceeds the calculated setpoint. This causes a cyclic reduction in Turbine Load at the rate of 200%/minute. The cyclic duration is that of a 1.5 second runback (which equates to 5% Load Reduction) and a 28.5 second wait, if OTAT OT~T condition still exists, the 1.5 second runback and the 28.5 second wait repeats. This cyclic reduction continues until the OT OTAT~ T condition is corrected. The setpoint is identical to the Reactor Trip Setpoint except the Kl K term becomes 065 ~ 22% 1.1065 1.1 % < the trip setpoint (Refer to 4.1.5.5).
- b. OP~T - when 2 out of 3 Reactor Coolant Loop ATs OPAT - ~T's (Th - Tc) exceeds the
-
calculated setpoint. stpoint. This causes a cyclic reduction in Turbine Load at the rate of 200%/minute. The cyclic duration is that of a 1.5 second runback (which equates to 5% Load Reduction) and a 28.5 second wait, if the OP~T OPAT condition still exists, the 1.5 second runback and the 28.5 second wait repeats. This cyclic OP~T condition is corrected. reduction continues until the OPAT RPS of 30 Page 23 of30 Revision 8 INFORMATION USE ONLY
TURBINE LOAD REFERENCE REDUCTIONS RPS-FIGURE-1 RPS-FIGURE-15 5 HIGH HIGH .HIGH HIGH OVER-OVER- OVER; OVER TEMPERATURE POWER POWER I D A
. RELAY LOGIC
.(CYCLIC)
ON ~ f4- 28.5 SEC OFF~
...... t+- I.5SEC REDUCE LOAD REFERENCE AT 200% MIN RPSFI5 RPSF15
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 65. Given
- 65. Given the the following:
following: EPP-1, LOSS
- EPP-1,
- LOSS OF ALL AC OF ALL AC POWER, POWER, isis being being performed.
performed. The RCS
- The
- RCS has has been isolated.
been isolated. The Inside
- The
- Inside AO AO and maintenance technicians and maintenance technicians are are working working onon starting starting an an EOG.
EDG. There isis NO
- There
- NO SI SI signal signal present present or or required.
required. EDG "A"
- EOG
- A isis finally finally started.
started. Which ONE Which ONE (1) (1) ofof the the following following actions actions isis necessary necessary following following the the energization energization of of 480V 480V Bus Bus E-1? E-1? Verify Service Verify Service Water Water Pumps Pumps ... A. "A" A. A and and "B" B are are running. running. B. "A" A and "C" C areare running. running. B and "0" C. "B" D are running. D. "C" D. C and "0" D are running. 65 65
HLC-08 NRC HLC-08 NRC Written Exam Written Exam
- 65. 075 K2.03 65.075 K2.03 OOl/CIRCULATING 001/CIRCULATING WATER/2/2/2.6/2.7IROIHIGH/NIAIRNP WATERJ2/2/2.6/2.7IROIHIGHJN/AJRNP AUDIT AUDIT - 200l/SW-009
- 2001/SW-009 Given the Given the following:
following: \'--...-., EPP-1, LOSS
- EPP-1,
- LOSS OF OF ALL ALL AC AC POWER, POWER, is is being performed.
being performed. The RCS
- The
- RCS has has been been isolated.
isolated. The Inside
- The
- Inside AO and and maintenance technicians are maintenance technicians are working working on on starting starting an an EDG.
EDG. There is
- There
- is NO NO SISI signal signal present or required.
present or required. EDG "A"
- EOG
- A is finally started.
Which ONE (1) (1) of the following actions is necessary necessary following the energization of 480V Bus E-1?? E-1 Verify Service Water Pumps ... A'I A and "B" A "A" B are running. A and "C" B. "A" C are running. C. "8" B and "0"D are running. C and "0" D. "C" D are running. The correct answer is A. A: Correct - - A and "B" "A" B now have power available and should have started. B: Incorrect - A
- "A" now has power available and should have started. C "c" does NOT have power.
C: Incorrect - "8"
- B now has power available and should have started. D "0" does NOT have power.
D: 0: Incorrect - C
- "c" and D "0" do NOT have power.
Exam Exam Question Number: 65
Reference:
EDP-002, EOP-002, Page 11; 11; SD-004, SO-004, SW, Page 21. KA Statement: Knowledge of bus power supplies to the following: Emergency/essential SWS pumps. History: History: Direct from Bank. 72 72
Section 8.0 Section 8.0 Page Page 11 ofof 11 8.0 8.0 480V-E1{ TC 480V-E1{ 480VE1 \f TC "480V-E1" \f C C \l 1 })
\1 "1" 480V-El 480V*E1 POWER SUPPLY:
POWER NORMAL - 4160V SUPPLY: NORMAL - 4160V BUS BUS 22 (52/13)LOCATION: (52/13)LOCATION: E-1/E-2 E-1IE-2 ROOM ROOM CMPT CMPT LOAD TITLE LOAD TITLE CWD CWD BKR BKR NO. NO. EDBS LOAD EDBS LOAD TAG TAG NO. NO. NO. NO. EDBSNO. EDBS NO. 17A 17A PTS && METERING PT'S METERING EQUIPMENT EQUIPMENT (*) (*) N/A N/A N/A N/A N/A N/A 17B 17B EMERGENCY DIESEL EMERGENCY GENERATOR AA TO 480V BUS DIESEL GENERATOR BUS E*1 E-l 890 890 52117B 52/17B 480V.El 480V-E1 18A 18A PT'S METERING EQUIPMENT PTS && METERING EQUIPMENT (**)() N/A N/A N/A N/A N/A N/A 1 8B 18B STATION SERVICE TRANSFORMER 2F TO 480V BUS E*1 E-l 892 52/18B 5211 8B 480V-El 480V-E1 19A CVSPRAYPUMPA CV SPRAY PUMP A 287 52119A 52/19A CV-SPRAY-PMP-A CV-SPRAY-PMP-A 19B 19B CV RECIRC FAN, HVH-1HVH-l 511 52119B 52/19B HVH-l HVH-1 190 19C SERVICE WATER PUMP B 832 52119C 52/190
~
SW-PMP-B 20A AUX FEEDWATER PUMP A 651 52120A 52/20A AFW-PMP-A
~ 20B SERVICE WATER PUMP A 831 52/20B 52/208 SW-PMP-A 20C CV RECIRC FAN, HVH-2 512 52120C 52/20C HVH-2 21A FEED TO MCC*5 POWER)&
MCC-5 (NORM POWER) & MCC-16 1187 52121 52/21A A MCC-5,_MCC-16 MCC-5, MCC-16 21B CHARGING PUMP B 162B 52/21 52/21B B
- CHG-PMP-B 210 21C SAFETY INJECTION PUMP A 237 52/21C SI-PMP-A 22A RESIDUAL HEAT REMOVAL PUMP A 214 52/22A RHR-PMP-A 228 22B 480V BUS E-l E*1 SUPPLY TO SI PUMP B 891 52122B 52/22B 480V-E1,_E2 480V-E1, E2 220 22C COMPONENT COOLING WATER PUMP B 205 52122C 52/22C CCW-PMP-B 17A also contains two amp meters, two amp meter switches,
*
- Compartment 17A switches, oneone volt meter, one volt meter switch, two undervoltage relays, four overcurrent relays, and two auxiliary relays.
** ** Compartment 118A 8A also contains eight run time meters,meters, three degraded degraded grid grid relays, relays, one one degraded grid trip degraded grid trip signal, signal, three three test switches, and test switches, and one one degraded degraded grid grid voltage voltage switch.
switch. jIEDP-002 EDP-002 Rev. Rev. 1010 Page Page 11 11 ofof 13 13\
SD-004 SERVICE WATER SYSTEM Pump D power from its normal supply (E-2) to its emergency supply (DS Bus) by use of a Kirk-key operated breaker (located in the CCW Pump Room). 5.5 Power Supplies
~i'SUPPIY Component Power Supply ~a.
- a. SW Pump A SWPumpA -1 ,
~b.
-b. SWPimpB SW Pump B -iI
-1
- c. SWPumpC SWPump C E E-
- d. SW Pump D SWPumpD E-21 E-2/ DS Bus
- e. SW Booster Pump A MCC-16
- f. SW Booster Pump B MCC-18
- g. V6-12A (South Header Isolation) MCC-5
- h. V6-12B (Header Cross-Connect) MCC-5
- i. V6-12C (Header Cross-Connect) MCC-6
- j. V6-12D (North Header Isolation) MCC-6/5
- k. V6-16A (North Header Turbine Bldg Isolation) MCC-9
- 1. V6-16B (South Header Turbine Bldg Isolation) MCC-10 MCC-lO
- m. V6-16C (Turbine Bldg header Isolation) MCC-10/9 MCC-1O/9 5.6 Electrical Manhole Sump Pumps The Service Water Pump Power cables are routed between the Intake Structure and the Reactor Auxiliary Building (RAB) through two (2) underground trenches. The cables enter the trenches though 2 Manholes between the RAB and the Radioactive Waste Building and the cables exit the trenches though 2 Manholes at the intake structure. Due to the high water table at the H.B. Robinson Plant the manholes are constantly being filled with water. Permanent sump pumps in Manholes M35 and M36 have been installed in order to improve the life span and reliability of the cables installed in these 98-003 19). The sump pumps have level switches installed in the manholes (ESR 98-00319).
manholes to provide automatic start of the pumps when water accumulates in the manhole sump. A sump pump control panel has been installed in the area of the manholes and has a manual pump switch installed to provide for manual operation of the pump. The control panel also has a pump run light for each pump that will be illuminated when the pumps are in operation. A level switch has been installed in the manholes to energize an alarm light and horn on the control panel if the water level in either of the manholes rises above 18 inches. The discharge piping of the sump pumps has been installed with freeze protection cable and insulation to ensure that the piping does not freeze during cold weather. The control panel includes a freeze protection test switch for each of the discharge lines freeze protection circuits and an ammeter to circuits current draw. This modification also installed three provide indication of the circuits' (3) spare cables from PP-61 to the new sump pump control panel. A storage box has sw SW of 35 Page 21 of35 Revision 11 INFORMATION USE ONLY
QUESTIONS REPORT QUESTIONS for AUDIT AUDIT
- 1. 055
- 1. 001/////1/1 G2.4.30 0011/11111/
055 G2.4.30 Given the following conditions: Given the conditions: EPP-001, Loss
- EPP-0O1, Loss of Power, is of All AC Power, being performed.
is being performed.
- The RCS has been isolated.
Inside AC
- The Inside AO and maintenance are working on starting an EDG. EOG.
- There is no SI signal present or required.
The A "A" EDG EOG is is finally started. Which ONE (1) of the following is the first action to be taken following the energization of Bus E-1? A'I Start A A: "A" and B "BII SW Pumps as necessary to obtain SW pressure of at least 40 psig B. Start A IIAII and B IIBII SW Pumps as necessary to obtain SW pressure of at least 50 psig C. Start IICII C and D 110 11 SW Pumps as necessary to obtain SW pressure of at least 40 psig O. C and 110" D. Start IICII D SW Pumps as necessary to obtain SW pressure of at least 50 psig A is correct. Need SW to support EOG. EDG. IIA" B now have power available. A and IIBII Common Question 050 Tier 11 Group 11 K/A Importance Rating - RO 3.2/ KIA - 3.2 / SRO 3.2 Emergency Procedures /I Plan Knowledge of which events related to system operations/status should be reported to outside agencies. Reference(s) - EPP Proposed References to be provided to applicants during examination - None - Learning Objective - - Question Source - Bank - Question History - 2004 Harris #12
-
Question Cognitive Level - Comprehension - 10 CFR Part 55 Content - 41 - Comments - Needs KA Change
-
Category 1: 1: Category 2: Category 3: Category 4: Category 5: Category 6: Category 7: Category 8:
- Tuesday, Tuesday, June June 17, 17, 2008 2008 6:49:52 6:49:52 PM PM 1
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 66. Given
- 66. Given the the following:
following: Operators are
- Operators
- are performing performing valve valve lineups lineups to to support support BOPBOP Flush.
Flush. Several valves
- Several
- valves above above Heater Drain Tank Heater Drain Tank "B" B are are to to be be repositioned.
repositioned. The valves
- The
- valves are are approximately approximately 15 15 feet feet above above the floor level.
the floor level. What fall What fall protection protection or or safety safety measures measures is is required required toto perform perform the the valve valve manipulations manipulations safely? safely? A. Tie or secure a ladder to structural components at BOTH the top and and bottom, use 3-point contact while on the ladder. contact B. B. Don aa full body Don body harness harness and and attach itit to the Extraction Extraction Steam line line support or snubber rods. rods. C. Don a Bosun's Bosuns Belt with a 6 foot lanyard attached to an approved anchorage point. D. Don a full body harness attached to an approved anchorage point. 66 66
HLC-08 NRC HLC-08 NRC Written Written Exam Exam
- 66. G2.1.26
- 66. 02.1.26 OOllEQUIPMENT 001/EQUIPMENT CONTROLl3/3.4/ROILOW/N/A/NEW CONTROL/3/3.4/ROILOWIN/A/NEW - 200S/GET-FALLPROT
- 2008/GET-FALL PROT Given the following:
Given the following: Operators are
- Operators
- are performing performing valve valve lineups lineups to to support support BOPBOP Flush.
Flush. Several valves
- Several
- valves above above Heater Heater Drain Drain Tank Tank "B"B are are to to be be repositioned.
repositioned. The valves
- The
- valves are are approximately approximately 15 15 feet feet above above the the floor floor level.
level. What fall What fall protection protection or or safety safety measures measures isis required required toto perform perform the the valve valve manipulations manipulations safely? safely? A. Tie A. Tie or or secure secure aa ladder ladder toto structural structural components components at at BOTH BOTH the the top top and and bottom, bottom, use use 3-point 3-point contact while contact while onon the the ladder. ladder. B. B. Don aa full Don full body body harness harness and and attach attach itit to the Extraction to the Extraction SteamSteam line line support support or or snubber snubber rods. rods. C. Don a Bosun's Don Bosuns Belt Belt with a 6 foot lanyard lanyard attached attached to an approved anchorage pOint. point. D Don a full body harness attached to an approved anchorage point. D~ The correct answer is D. The Incorrect - Procedure requires that extension ladder be attached to structural components A: Incorrect - at the top of the ladder while the ladder is secured at the bottom by an individual. B: Incorrect - Fall protection is to be attached to engineered anchorage points. B: - pOints. Line or snubber supports are NOT approved anchorage pOints. points. C: Incorrect - Bosuns
-
Bosun's Belts are NOT approved fall protection at Robinson. D: Correct - - Full body body harness properly used and attached to approved anchorage points is required to safely perform work. Exam Exam Question Question Number: 66 66
Reference:
Reference:
SAF-NGGC SAF-NGGC-2172, -21 72, Sect. Sect. 9.17. 9.17. KA KA Statement: Statement: KnowledgeKnowledge of of industrial industrial safety safety procedures p}}