ML20197B369
| ML20197B369 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 10/29/1997 |
| From: | Chitwood G HOUSTON LIGHTING & POWER CO. |
| To: | Bundy H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML20197B061 | List: |
| References | |
| 50-498-97-301, 50-499-97-301, NUDOCS 9803110065 | |
| Download: ML20197B369 (27) | |
Text
__
Mr.Iloward Bundy, Chief Examiner U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington,TX 76011-8064
)
Dear Mr. Bundy
Subject:
Initial Examination (NRC Inspection Report 50-498/97 301;50-499/97 301)
'Ihis letter is accompanying the examination materials for the South Texas Pmject Initial Examination scheduled for December 01,1997.
None of these materials are to go to the public reconis until aAer the examination has been completed.
Please call me at (512)972-7241 if you have any questions.
Sincerely, hM/
Y Greg6:7 Chitwood ExamImd
^
SouthTexas Pmject Nuclear Training Department c:cc
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JPM NUMBER:
NRC-002 CANDIDATES:
Upgrade JPM TITLE:
Misaligned Rod QUESTION NUMBER:
1 Open Reference At 1500 Unit #1 performed a QPTR in response to a bank D rod m'salignment.
Carrent power level is 95% Results of QPTR were 1.03. As the Unit Supervisor what action (s) must be completed by 17007 ANSWER Reduce power to 591% (.5 pts) by 1500 (.5 pts)
Must reduce power > 3% for each percent >1.0,1.03 would require 9%
j v 'ch would require power to be reduced to 91% or less. Tech Spec time is2 hrs.
REFERENCES:
STP: Tech Specs 3.2.4
]
KA:
GEN 2.1.12 [2.9](4.0) Ablilty to apply Tech Specs for a system.
t OBJ: CRO 92102 Ability to apply Tech Specs for a given condition 1
Comments: Must interpret Tech Specs and apply to a given con 6 tion.
7 e
JPM NUMBER:
NRC-004 CANDIDATES:
Upgrade JPM TITLE:
Locally Operate SG PORVs QUESTION NUMBER:
2 Open Reference While operating at 100% RTP as the Unit 1 Supervisor, the maintenance supervisor informs you that surveillance records indicate that one steam generator sofaty valve on 1B S/G and one Safety Valve on 1C S/G are inoperable and cannot be repaired until the next outage, in addition,1B has developed a leaking PORV that can not be repaired. What is the first action which must be taken?
ANSWER Power Range Trip Setpoint must be reduced to 63% within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (inoperable 4
PORV is 7 day TS)
REFERENCES:
STP: TS 3.7.2 KA:
Generic 2.1.12 [2.9/4.0] Ability to tipply Tech Specs for a system OBJ: CRO 92102 Ability to apply Tech Specs for a given condition Jf
s JPM NUMBER:
NRC-005 CANDIDATES:
Ugjrade JPM TITLE:
Control Room Evac / Perform TGB Operator's Addendum for a Control Room QUESTION NUMBER:
1 s
Closed Reference z-What actions are to be taken prior to evacuating the control room?
ANSWER 3
(5/6 required for credit) 1)
Trip the reactor 2)
Initiate main steam isolation 3)
Trip all RCPs
)
4)
Isolate letdown l
5)
Plam CCPs in Pull To Lock 0)
Close pressurizer PORV isolations
=
REFERENCES:
STP: OPOP04-ZO-0001, Control Room Evacuation KA:
000068AK312 [4.1/4.5] K/O rcquired sequence of actions during CR evac OBJ: CRO 92108 Given a plant condition STATE the simulator action to be performed per the applicable off-normal procedure.
L m
?
i JPM NUMBER:
NRC-006 CANDIDATES:
Upgradeilnstant JPM TITLE:
Isolate Accumulators QUESTION NUMBER:
2 Open Reference l
A small break loss of coolant accident has occurred and all ECCS equipment has actuated as expected.
All ESF load sequencers have been reset in the Control Room aiid locally. After the ESF Load Sequencers have been reset the supply breaker to ESF Bus E1C is inadvertently opened.
The Diesel Generator breaker automatically recloses energizing ESF Bus E1C.
What will be the finL1 staus of HHSI pump 1C and Component Cooling Water Pump 1C?
ANSWER:
. Both HHSI pump 1C and CCW Pump 1C will be running.
REFERENCES:
STP: Logic Diagram 9-Z-42115 and 42117 KA:
006000K411[3.9/4.2] K/O reset of SIS OBJ: CRO 80107 DESCRIBE the ESF Sequencing Logic i
e 1
JPM NUMBER:
NRC-009 CANDIDATES:
Upgrade JPM TITLE:
Establish Attemate Charging Flow QUESTION NUMBER:
1 Open Reference Unit 1 is in a refueling outage and is in the process of placing a new fuel assembly into the core. Maintenance has just completed repairs on FCV-110B and requests that the Control Room stroke the valve for post-maintenance testing.
a) is this action permissible?
b)
If it is permissible, what compensatory artic7s must be taken?
If it is not permissible, why can't it be performed?
ANSWER a)
Not permissible b)
Refueling TS requires that this valve be maintained closed and secured in position during core alterations
REFERENCES:
STP: TS 3.9.1 and Bases KA: Generic 2.1.12 [2.9/4.0] Ability to apply Tech Specs for a system OBJ: CRO 92102 Ability to apply Tech Specs for a given condition.
i
JPM NUMBER:
NRC-009 CANDIDATES:
Upgrade JPM TITLE:
Establ:sh Altemate Charging Row QUESTION NUMBER:
1 Open Referere,e Unit 1 is in a refueling outage and is in the process of placing a new fuel assembly into the core. Maintenance has just completed repairs on FCV-110B
- and requests that the Control Room stroke the valve for post-mairitenance
- testing, a) is this action permissible?
b)
If it is permissible, what compensatory actions must be taken?
If it is not permissible, why can't it be performed?
I h
a
JPM NUMBER:
NRC-010 CANDIDATES:
Upgrade l
JPM TITLE:
Loca.:y Stop EDG l
QUESTION NUMBER:
1 Open Roference The Yard Ltch calls the Control Room and reports the following conditions exist on 11 EDG:
Jacket water teinperature is 85 F Both Diesel Starting Air Receivers are at 225 psig Oil level for the Overspeed Govemor is high in the sightglass The AFOST is aligned to fill the DGFOST What action must be taken to restore the 11 DG to an operable condition?
ANSWER Jacket water temperature must be raised to >90 F
REFERENCES:
STP: LOT 201.39 OPOP02-DG-0001, Emergency Diesel Generator 11(21)
KA: 064000K101 [4.1/4.4] K/O the EDG relationship with AC distribution OBJ: CRO 92102 Ability to app;f Tech Specs for a given condition.
o t
JPM NUMBER: -
NRC-011 -
CANDIDATES:
!nstant JPM TITLE:
Perform Rod Operability Test QUESTION NUMBER:
2
- Open Reference The plant is at 30% power and is proceeding to 100% power using manual rod control.
A " ROD CONT URGENT ALARM"annunciater (5M03-BS)is received. Rod M-12 in Control Bank D stopped moving at 140 steps and the remainder of the -
- benk D rods are at 162 steps by the time rod motion is halted, l&C determines that rod M-12 should still insert into the core upon a reactor trip.
The lift coil on rod M-12 is detrermined to not be responding and it will take 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> to reatore normal rod motion to rod M-12. --
i The crew takes actions to restore the remainder of the Bank D rods to the current rod M-1?. position of 140 steps.
The power increase is recommenced. Are there any limits on reactor power.
during the powerincrease?
e
+
JPM NUMBER:
NRC-012 CANDIDATES:
Inutant JPM TITLE:
Perform CCW Inservice Test QUESTION NUMBER:
1 Open Reference Given the following:
Unit 1 is at 100% power.
All systems are in their normal alignment.
CCW Train 1 A is in service.
CCW le/el decreases to 63% and stabila:es.
All automatic actions have occurred as designed.
CCW Surge Tank level cannot be increased above 63% and :equired procedural actions have been taken.
How will pressurizer level be affected?
ANSWER Pressurizer level will increase due to letdown and excess letdown isolation.
REFERENCES:
STP: OPOP04-CC-0001, Addendum i KA:
008000A301 [3.2/3.0] Ability to monitor CCW indications OBJ: CRO 57126 DESCRIBE the operation of the CCW System and it's major components. Include automatic actions intedocks and trips.
i JPM NUMBER:
NRC-012 CANDIDATES:
Instant JPM TITLE:
Perform CCW Inservice Test QUESTION NUMBER:
2
- Closed Reference
- a. TWhat are two (2) indications or symptoms which will be observed if a tube leak occurs in a RCP Thermal Barrier heat exchanger. (Assume NO -
alarm setpoints are reached.)
- b. If the tube leak continues to increase in severity, what AUTOMATIC action will occur?
ANSWER a.
- (0.25 points each)
- 1. Rising CCW surge tank level /high level a%rm
- 2. Increasing CCW system radioactivity
(.25 pointe each) b.
REFERENCES:
STP: - LOT 201.12, Component Cooling Water System -
KA:
008000K102 [3.3/3.3] K/O loads cooled by CCW OBJ: CRO 4291 DISCUSS the basis for the RCP thermal barrier isolation on high temperature and/or high flow.
O
JPM NUMBER:
NRC-014 CANDIDATES:
Instant JPM TITLE:
Restore Off-Site Power QUESTION NUMBER:
2 Open Reference The plant is at 100% power with Centrifugal Charging Pump 1 A in service and 1B secured. A LOCA occurs and Safety injection actuates resulting in a reactor trip. While in step 6 of EOOO the normal feeder breaker to 4.16 KV ESF Bus 3
E1C opens and cannot be reclosed. Standby DG#13 comes up and ties on to bus E1C.
What would the status of the Centrifugal Pumps be with no operator actions.
ANSWER:
CCP 1A and 1B wili be secured.
REFERENCES:
STP: Logic Diagram 9-Z-42115 and 42117 KA: 064000A307 [3.6/3.7] Ability to monitor load sequencing OBJ: CRO 80107 DESCRIBE the ESF sequencing logic.
1
JPM NUMBER:
NRC-016 CANDIDATES:
Instant /RO JPM TITLE:
Startup of Gaseous Waste System QUESTION NUMBER:
1 Closed Reference What is the function of the Guard Bed in the Gaseous Waste Processing System?
q ANSWER 1.
Protects downstream charcoal tanks from moisture contamination ( 5 pts).
2.
Easily isolated vessel for large percentage of radioactivity (.5 pts)
REFERENCES:
STP: LOT 203.14 KA:
Generic 2.1.28 KIO pu; pose and function of major system ccmpcnents OBJ: CRO 91634 State the functions of the GWPS System
4 JPM NUMBER:
WC-016 g
CANDIDATES:
- w. int /RO JPM TITLE:
Startup of Gaseous Waste System QUESTION NUMBER:
2 Closed !!eforence What is the largest source of radioactive gas sent to the Gaseous Waste Processing System (LWPS), during normal full load operations?
ANSWER Volume Control Tank
REFERENCES:
STP: LOT 203.14 KA:
071000A405 [2.6/2.6) Ability to manually operate / monitor Gas Decay Tanks OBJ: CRO 91648 IDENTIFY Interface / Support systems and describe the effects on GWPS.
n a
tc JPM NUMBER:
- CANDIDATES:.
NRC-018-Instant /RO JPM TITLE:
RPSNerify AMSAC is in Service QUESTION NUMBER:
2 Open Reference Unit #1 is at 25% power. The Startup Feed Pump is in service with #1'1 MFP
- being prepared to place !n service. MFP #12 and #13 are secured. The Startup
- Feed Pump trips and #11 MFP cannot be placed in service prior to a reactor trip on low S/G level.
How would AMSAC respond to this event?
ANSWER No actuation, system is bypassed due to low power level.
REFERENCES:
STP: Logic Diagram 9-Z-40143, and STP Precautions Limitations and Setpoints
- Document 5ZO10ZS1101.
KA:
GEN 2.1.32 3.4/3.8 Ability to explain and apply all system limits and
. precautions OBJ: CRO 91842 Given a set of parameters, ANALYZE the situation and PP. EDICT the results of the condition.
Comment:
AMSAC is blocked below 40% power as sensed by tubine impulse pressure.
The setpoint is shown in the Precatutions Limitations and Setpoints document The affect of being less than the setpoint can be seen on the logic diagram since the' impulse pressure input and the AMSAC blocked annunciator are shown.
Plant power level is 25% power which is well below the 40% power level at which AMSAC is normally unblocked based on increasing turbine impulse pressure, therefore AMSAC will not actuate, e
JPM NUMBER:-
NRC-019 CANDIDATES:
Instant /RO JPM TITLE:
Retrieve Dropped Control Rod
- QUESTION NUMBER:
-2 Closed Reference Power range channel N43 has failed high. Rods stepped in rapidly in response to the failure. The operators have stabilized the plant and are in the process of restoring Tavg to program. What different actions are available to allow restoration of Tavg to program?
ANSWER:
Dilution (0.33) or turbine load reduction (0.33) until the overpower rod stop (C2) is bypassed. Once the overpower rod stop is bypassed, then rods may be withdrawn to restore temperature (0.33).
REFERENCES:
. STP: OPOPO4-NI-0001, Nuclear Instrument Malfunction
- KA:
001000K403 [3.5/3.8) K/O rod control logic OBJ. CRO 92111 DESCREli the general sequence of operation for referenced procedure 1
4 JPM NUMBER:
NRC-022 CANDIDATES:
Instant /RO JPM TITLE:
Shift ECW Pumps QUESTION NUMBER:
2 Open Reference Essential Cooling Water (ECW) Pump 1 A was started for surveillance testing at 1100. The pump was run at full load, then secured at 1140 due to suspected vibration.
After a visual inspection the pump was restarted at 1145. A small oil leak developed and the pump was secured at 1150.
The oil leak is repaired. At what time is restart of the ECW pump allowed?
ANSWER:
1220
REFERENCES:
STP: POP 02-EW-0001 KA:
_076000A4012.9/2.9 Ability to monitor pumps OBJ: CRO91195 In regards to POP 02-EW-0001, dicuss precautions l
JPM NUMBER:
NRC-024 CANDIDATES:
Instant /RO JPM TITLE:
Load Emergency Bus QUESTION NUMBER:
2 Open Reference The plant is at 100% power A review of the Oontrol Room Logs indicates the following:
On Monday 10/6/97 at 1900 Battery Charger E1811-2 is declared inoperable.
The following Sunday 10/13/97 at 0815 Battery E1011 is declared inoperable. Later the same day (10/13/97) at 0845, Battery Charger E1D11-2 is declared inoperable.
When must Battery E1D11 be returned to service?
ANSWER 1015 on Sunday 10/13/97.
REFERENCES:
STP: Tech Sptc 3.8.2.1 KA:
GEN 2.1.2 2.9/4.0 Ability to apply Tech Specs OBJ: CRO 92102 Ability to apply Tech Specs Comments:
One battery charger is allowed to be out of service on B train or D train for an indefinite period of time since they are 100% capacity. Tech Specs require a battery to be operable on each DC bus and if not operable restored in two hours, thus the time from 0815 to 1015 on 10/13/97.
EVALUATOR ERRORS INSERTED - CONTROL ROOM LOGS (pkg W2)
(C) - Denotes Critical Step
- 1) The examinee should find the following errors:
A)
Cever Sheet (page 1 of 34)- There is no associted remark in th s remarks section for the out of specification reading on page 2 (page 2 of 34).
SAT UNSAT B)
Page 3 (Page 3 of 34) The incorrectly recorded (or.caRCB Average Temperature is lcula'ted) "'he average of the 4 highest RCFC Inlet Temperatures should be 92.8'F instead of 95'F. (C)
SAT UNSAT C)
Page 3 (page 3 of 34)- There are too many "N/A"s in the RCFC readings. Either the Unit is operating with 3 RCFCs at 100%
(which is not allowed by Technical Specifications), or the log taker incorrectly marked a running fan temperature as N/A. (C)
SAT UNSAT t
D)
Page 4 (page 4 of 34)- There are no initials for the lineout of ACC A Water level LI-0951 reading. The reading is lined out with a date only.
SAT UNSAT E)
Page 6 (Page 6 of 34)-The B ACC DISC Valve-MOV-0039B is recorded as being open with Power. The required condition of this valve is open without powcr.(Should Have Been " Red Circled" with an associated note) (C)
SAT UNSAT 1
}
s EVALUATOR ERRORS INSERTED - CONTROL ROOM LOGS (pkg #3)
~
3 (c) - Det.ates Critical Step
- 1) The examinee should find the following errors:
A)
Page 2 (page 28 of 3t)- The log taker did not record that he/she checked Flashing light A2 on the AMSAC operability g
sheet. (No check mark) (c)
SAT UNSAT B)
Page 2 (page 29 of 34)- Logreadings were taken on the Diesel Generator Levels on Monday, when they were not required to be recorded until Saturday-dayshift.
SAT UNSAT C)
Fage 4 (page 30 of 34)- The RCS Inventory blocks should not have oeen recorded as N/A". This su.rveillence is required to be performed every day on nightshift.
(c) i b
.I' 4
D)
Page 6 (page 32 of 34)- Choice "b" was not ciralad as method used to Calibrate Power Range NIs SAT UNSAT e
E)
Page 6 (Page 32 of 34)- The target time was missed by 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 41 minutes for performing N1 calibration. At bare minimum, a note should have been made documenting the late surveillence.
(c)
SAT UNSAT
e FA 301 Individual Walk.7hrcuth Test Outhne Form FS-301 2 Facility: South Texas Project Date of Famination: 124)l/97 fxam level (circle one): SRO(1)
Operating Test Noa 1112 System / JPM Title / T,9e Codes
- Safety Planned Follow up Questions:
Function K1A/O. Importance. Description
- 1. CRDS/ Perform Rod Operabliity Test I
- a. 001000K407 3.7/3.8 K/O CRDS design features and/or Of)(S)(NRC 011) interlocks for Rod Stops
- b. GEN 2.1.12 2.9/4 0 Ability to apply Tech Specs for a system
- 2. liCCS/ Isolat9 Accumulators (DXSXAXL) 11 e 006000K602 3 4/3 9 K/O loss oraccumulator (NRC406)
- b. 006000K4113 9/4 2 K/O reset of SIS
- 3. CCW/ Respond to loss of operating CCW pump VIII
- b. 008000K102 3.3/3.4 K/O loads coold by CCW 4.S/G/MSIV OperabQ Test (NXSXL)
IV a.035000K6013.2/3 6 K/O the malfunction of MSIV (NRC-007)
- b. 035000A2014.5/4 6 Ability to predict the impact of faulted or ruptured SK)
- 5. CSS / Monitor Containment Spray requirernents V
- a. 026000A3014.3/4.5 Ability to monitor pump starts and (DXCXL)(NRC 013) correct valve positioning
- b. 026000K404 3.4/3.6 K/O bus power supplies to Containment Spray Pumps
- 6. AC/ Restore Off Site Power to ESF bus VI
- a. 062000K2013.3/3.4 K/O bus power supplies to major (DXSXL) system loads (NKC 014)
- b. 064000A307 3.6/3.7 Abihty to momtor load sequencing
- 7. NIS/ Respond to SRNI channel fallute(DXS)
VII
- a. 015000K505 4.1/4 4 K/O indications of criticality (NRC 015)
- b. 015000A202 3.6/3.9 Ability to predict the impact of a loes of instrument power
- 8. WasteGas/Startup OWPS following a system IX
- a. 2.1.28 K/O purpose and function of major system breach (DXPXR)(NRC-016) components
- b. 071000A409 3.3/3.5 Abihty to manually operate / monitor Waste Gas Release Monite-s
- 9. CRDS/ Locally trip the Reactor (MXAXP)
I
- a. 012000A2.03 3.4/3.7 Ability ta predict impact on RPS of (NRC417) incorrect chamel bypassing.
- b. 012000A403 3.6/3 6 Ability to manually operate / monitor in the CR Channel Blocks and Dvpasses
- 10. RPS/ Verify AMSAC is in Servicc(D) P)
Vil
- a. 012000A20$ 4 4/4.7 Abihty to predict impact of failure of (NRC-018)
- b. 2.l.32 3 413.8 Abihty to explam and apply all system lir.nts and precinutions
' Type Codea: (D)irect from bank,(M)odified from bank,(N)ew,(A)ltemate path,(C)ontrol room,(S)imulator,(L)ow Power,(P)lant, (R)CA
(
Es-301 Indmdual Walk-Through Test Outhne Form ES-301-2 I
Facihty: Sou'h Texas Project Date of Exa:ninstion: 12/01/97 Exam l2 vel (circle one): RO / SRO(1)
Operating Test No.t 13-14 and ROl-R06 System / JPM Title / Type Codes
- Safety Planned Follow-up Questions:
Function K/A/O.importance Description I. CRDS/Retriew. Dropped Control Rod I
- a. 001000A106 4.1/4.4 Ability to monitor parameters to l
(NXS)(NRC 019) prevent enceedmr timits
- b. 001000K403 3.5/3.8 K/O rod control logic
- 5. RCS/ Start RCP (DXAXSXL) 11
- a. 003000K404 2.8/3.1 K/O adequate cooling of motor and (NRC-020) seals
- b. 2.1.12 2.9/44 Abihty to apply Tech Specs to a system
- 3. ECCS/Innsfer to llot leg Recire (DXCXL) til
- b. 006000K409 3.8/4.2 K/O design features / interlocks
- 4. ECW/ Shift running ECW pumps (DXS)
IV
- b. 076000A4012.9/2.9 Ability to monitor pumps
- 5. C./ Dreaker Functionahty Test (NXS) (L)
V
- a. 02600K401 [4.2/4 3] K/O source of water dwing (NRC-023) recirculation phase.
- b. 026000A30l[4.5/4.5) Ability to monitor automatic operation ofCSS
- 6. AC/ Load Emengency Dus (DXS)
VI
- a. 062000A4013.3/3.1 Ability to manually operate / monitor in (NRC 024)
CR. Allbreakers
- b. 2.1.1.2 2.9/4.0 Ability to apply Tech Specs
- 7. RMS/ Respond to a p AD nunitor alarm Vill
- a. 073000Kl013.6/3.9 K/O physical connections and cause (DXSXA)(NRC-025) effect relationships
- b. 029000A3013.8/4f Gility to monitor automatic operation ofCPS
- 8. WasteGas/Startup GWPS following a system IX
- a. 2.1.28 K/O purpose and function of major syst.a breach (DXPXR)(NRC 016) conwnents
- b. 071000A409 3.2/3.5 Ability to manually operate / monitor Waste Gas Release Monitors
- 9. CRDS/ Locally trip the Reactor (MXPXA)
I a 012000A2.03 3.4/3.7 Ability to predict impact on RPS of (NRC-017)
' wreet channel bvpassing,
- b. 012000A403 3.6/3.6 Ability to manually operate / monitor in the CR Channel Blocks and Dypasses
- 10. RPS/ Verify AMSAC is in Service (DXP)
Vil
- a. 012000A206 4.4/4.7 Ability to predict the irnpact of the (NRC-018) failure of the RPS sienal to trip the reactor
- b. 2.1.32 3.4/3 8 Abihty to explain and apply all system limits and precautions
- Type Codes:(D)irect from bank,(M)oditied from bank,(N)ew.(A)lternate path, W)ontrol room,(S)imulator,(L)ow-Power (P)lant, (RK'A 3
e*
F&301 Individual Waik Through Test Outline Form F&301-2 Facility: South Texas Project Date of Examination: 12/01/97 Examlevel(circleone): SRO(U)
Operating Test No.. UI-U2 System / JPM Title / Type Codes
- Safety Planned Follow-up Cuestions:
Function K/A/O. Importance. Description l
1.ECCSIisolate Accumuhtors (DX AKSXL) 11
- a. 006000K602 3.4/3 9 K/O loss of secumulators (NRC-006)
- b. 006000K4113.9/4.2 K/O reset of SIS 2.S/0/MSIV Operability Test (NXS)
IV a 035000K6013.2/3.6 K/O the malfunction ei MSiv (NRC-007)
- b. 035000A2014.5/4 6 Ability to predict the impact of fauhed or ruptured SKI
- 3. RAD. RELEASE / Establish Sec. System Vill
- a. 038000EA136 4.3/4.5 Cooldown of RCS to specific Contant Control (DXP)(NRC408) temperature
- b. 038000EA208 3.8/4 4 Ability to determine alternatives if cond. not available.
4.CVCS/ Establish Alternate chargmg flow
.I
- a. 2 8112.9/4.0 Ability to apply Tech Specs for a system control (DXPXR)(NRC-009)
~.
b.004000Al29 3.4/4.0 K/O the effects of and detection ofleaks on PZR and VCT level
- 5. EDG/tocally stop EDO (DXP)
VI
Jistribution
- b..,a000A1013.4/3.8 Ability to rnonitor DO load limits 6
a.
b.
7.
a.
b.
1 a.
b.
9.
a.
b.
10.
a.
b.
- Type Codes. (D)irect from bank,(M)odified from bank,(N)cw,(A)hernate path,(C)ontrol room,(S)inslator,(L)ow-Power (P)lant, (R)CA
f%301 Individual Walk-nrough Test Out!me Form ES-301 2 Facility; South Texas Project Date of Examination: 12/01/97 Exam Level (circle one): SRO(U)
Operatmg Test No.: U3-U4 System / JPM Title / Type Codes
- Safety Planned Follow-up Quettions:
Function K/AKI - Importance - Description
- 1. AC/ Align Equipment for less of AC VI
- a. 062000K410 3.1/3.5 K/O design and operation of un-(D)(S)(L)(NRC-001) interruptible power supplies
- b. OC0057A219 4.0/4.3 Ability to determine the plant automatic actions that occur from loss ofinstrument bus
- 2. CRDS/ Stuck / Misaligned Rod (N)(S)
I
- a. GEN 2.1.12 2.9/4 0 Abihty to apply Tech Specs for a given (NRC@2) system
- b. 000005A203 3.5/4.4 Ability to determine the required actions if more than one rod is stuck
- 3. ECCS/ Locally close Seal Retum and Excess 11
- s. 011000A102 3.3/3.5 Ability to predict changes in charging letdown Isolation (D(P)(R)(NRC@3) and letdown flows
- b. 004000A302 3.6/3.6 Abihty to monitor auto letdown isolation
- 4. S/0/ local PORV operation (D)(P)
IV a.040000AK106 '1.7/3.8) K/O the operational implications of (NRC 004) steam ime break
- b. 2.1.12 2.9/4.0 Abihty to apply Tech Specs for a system
- 5. Control Room Evac / Perform TOB Operator's Vill
- s. 000068AK312 [4.1/4.5] K/O required sequence of actions Addendum for a Control Room (D)(A)(P)(NRC.
during CR evac 005)
- b. 000068AK318 [4.214.5] K/O actions contained in procedures for CR es ac 6.
a.
b.
7.
a.
b.
C.
a.
l b.
9.
a.
b g
10.
a.
b
- Type Codes: (D)irect from bank,(M)udifled from bank,(N)ew,(A)ltemate path. (C)ontrol room,(S)imulator,(L)ow-Power, (P)lant, (R)CA
ES.301 Administrative Topics Outline Form ES.301 1 Facility: South Texas Project Date of Exanunation: 12/01/97 Examination Level: SRO Operating Test Number: U3,U4 Administrative Topic / Subject Describe method of evaluation:
Description
- 2. TWO Administrative Questions A.I Conduct of 2.1.3 [3.0/3.4] K/O shift turnover practices Operations (NRC-001A)
Review logs prior to accepting shift turnover (NRC-0010A) 2.1.19 [3.0/3.01 Ability to use computer to obtain data Perform a Reactor Coolant Inventory h$ A.2 Equipment Control 2.2.13i3.81 Knowledge of tagging and clearance procedures (NRC-015A)
Review a faulted tagout for AFW pump #11 A.3 Radiation Control 2.3.10 [3.21 Ability to control radiation releases (NRC-013A)
Review and approve gasecas release package A.4 Emergency Phn 2.4.44f4.01 Knowledge of emergency plan protective action reconunendation (NRC-014A)
Make the necessary recommendation for a given set of conditions
EXAMINER OPERATING TEST COMMENTS - STP 12/01/97 EXAM 3rd SUBMITTAL WALKTHROUGH JPMs Note: All comments apply to questions.
JPM 2, Q1: Direct lookup. Should be closed reference. Stem could mislead applicant with the 1700 time element. Fix stem. Resolution: Rewrote stem. Made closed referer.ce.
JPM 4, Q2: Reference should be 3.7.1.1 and 3.7.1.6. Also, borders on being direct lookup. Resolution: Rewrote question as open reference and changed outline.
JPM 5, Q1: Stem should tell applicant number of actions expected. Resolution:
Incorporated.
JPM 6,02: Should be closed reference Resolution: Incorporated.
JPM 9, Q1: Direct lookup. Make closed reference. Resolution: Incorporated.
JPM 10, Q1: K/A does not appear appropriate. Resolution: Changed K/A on question and outline.
JPM 11,01: K/A does not match outline. Resolution: Changed K/A on outline to match question.
JPM 11, Q2: Typo, "detrermined." Resolution: Corrected.
JPM 12, Q1: Should be closed reference Resolution: Rewrote question as open referer.ce.
JPM 12, Q2: Correct scoring. Part b is an "OR" response and would result in 0.75 points vice 0.5 points. Resolution: Corrected scoring.
JPM 13, Q2: K/A does not match outline. Resolution: Changed K/A on outline to match question.
JPM 14,02: Should be closed reference. Resolution: Wrote new open reference question and changed outline.
JPM 16, Q1: Need a higher percentage of open reference questions on outlines for 11/12 and 13/14/R1 R6. Resolution: Rewrote this question as open reference to increase open reference percentage.
JPM 16, Q2: K/A is not t.ppropriate. F.esolution: Changed KIA on question and outline.
JPM 17, Q2: K/A does not match outline. Resolution: Changed KIA on outline.
JPM 18, Q2: Should be closed reference. Resolution: Rewrote question as open reference.
JPM 19,02: Correct scoring for examiner Resolution: Corrected scoring.
JPM 22, Q2: Include note to examiner that this question rnust be asked prior to performance of JPM because the applicant will read answer in procedure.
Resolution: Note added.
JPM 24, Q1: K/A does not match outline. Resolution: Changed K/A on outline.
JPM 24, Q2: Should be closed reference. Resolution: Rewrote question as open reference.
ADMINIEIRATIVE JPMs JPM 1 A, D2: Step 1.B is not critical. Error discussed in Step 1D is actually on page 5 of attachment vice page 4. Resolution: Incorporated.
JPM 1 A, D3: In Step 1E, what is the requirement? "Should" does not make a step critical.
Resolution: Critical designation was removed.
JPM 10:
K/A is incorrect. Computer is not used in performing this JPM Resolution:
Changed K/A.
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