IR 05000387/1989007
| ML17156B125 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/14/1989 |
| From: | Conicella N, Conte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17156B124 | List: |
| References | |
| 50-387-89-07OL, 50-387-89-7OL, 50-388-89-07OL, 50-388-89-7OL, NUDOCS 8904260340 | |
| Download: ML17156B125 (94) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO.
89-07 (OL)
FACILITY DOCKET NOS.
50-387 50"388 FACILITY LICENSE NOS.
LICENSEE:
FACILITY:
EXAMINATION DATES:
EXAMINERS:
NPF" 14 NPF-22 Pennsylvania Power and Light Company 2 North Ninth Street Al 1 entown, Penn syl vani a 18101 Susquehanna Steam Electric Station Units 1 and
February 28 to March 3, 1989 T.
S.
J.
M.
K.
J.
Walker, Senior Operations Engineer Pullani, Senior Operations Engineer Hanek,
.EGEG Bi e 1 by, Operati on s Engineer (Observer)
Mikkelsen, PNL (Observer)
'uth, PNL (Observer)
CHIEF EXAMINER:
APPROVED BY:
id'icola F. Conicella, Operations Engineer Richard J.
Conte, ief, BWR Section Operations Branch, Division of Reactor Safety Date
/cg//I Jjo Date SUMMARY:
Written examinations and/or operating tests were administered to
~five 5) senior reactor operators (SRO)
and four (4) reactor operators (RO)
candidates.
All candidates passed these examinations.
890A260340 85000g87 8q0PJS pOR AQOC)4 0 pgU V
DETAILS 1.0 INTRODUCTION AND OVERVIEW The NRC examiners administered complete initial replacement examinations for one (1)
SRO instant, four (4)
SRO upgrade and three (3)
RO candidates.
A partial retake examination (written examination only) was administered to one (1)
RO candidate.
The examinations were administered in accordance with NUREG 1021, Rev.
5, dated January 1, 1989.
The results are summarized below.
RO Pass/Fail SRO Pass/Fail Written 4/0 5/0 Operating 3/0 5/0 Overall 4/0 5/0 2. 0 EXAMINATION RELATED FINDINGS/CONCLUSIONS 2.1 The following is a
summary of the generic strengths or deficiencies noted on the operating tests.
This information is provided to aid the licensee in upgrading license and requalification programs.
No licensee response is required.
STRENGTHS a. General knowledge of the facility's technical specifications b. General knowledge of the facility's emergency plan c. General knowledge of the facility's administrative procedures d.
Crew communications and teamwork during the simulator scenarios DEFICIENCIES No general deficiencies were found 2.2 The following is a
summary of generic strengths or deficiencies noted from the grading of written examinations.
This information is being provided to aid the licensee in upgrading license and requal-ification training programs.
No licensee response is require "3" STRENGTHS All questions on the written examination where answered at an average proficiency level of 80% or better (except as noted below).
This indicated a good general knowledge of those areas.
DEFICIENCIES Question 3.01:
Knowledge of the bases for the TCV fast closure SCRAM 3.13b:
Knowledge of the requirements that must be met for a reactor operator assuming the control room command function 3. 13c:
Knowledge of the definition of 'operational condition 5'.
15:
Knowledge of the different modes of operation of the MSIV leakage control system 6.05:
Knowledge of the technical specification bases for the ADS limiting condition for operation 6.07:
Knowledge of the technical specification bases for water level above.the RPV flange during refueling
)
6. 10:
Knowledge of the purpose of the head spray capability of the shutdown cooling mode of RHR 6. 16:
Knowledge of access requirements for controlled access areas during fuel receipt or inspections 6. 17b:
Knowledge of emergency radiation exposure levels that require approval of the emergency director 6.20:
Knowledge of the requirements for maintaining an operator license active and the requirements for reactivating an inactive license 2.3 TRAINING PROGRAM COMMENTS Overall, the applicants performed well on all portions of the examinations.
There were very few generic weaknesses noted indicating that the training department prepared the applicants well for the licensing examination. 0 PRE-EXAMINATION REVIEW 3.1 ATTENDEES NRC Personnel N. Conicella, Chief Examiner K. Mikkelsen, PNL J. Muth, PNL Facilit Personnel A. Fitch, Operations Training Supervisor D. Steffenauer,'Shift Supervisor 3.2 SUMMARY A pre-examination review was conducted with licensee representatives on February 27, 1989 to assure questions were written concisely, avoided ambiguities, and were specific to the licensee's facility.
Specific comments changes were incorporated into the examinations (Attachments 1 and 2).
4.0 EXIT MEETING 4.1 ATTENDEES NRC Personnel N. Conicella, Chief Examiner Facilit Personnel G. Stanley, Assistant Superintendent Outages W. Lowthert, Manager, Nuclear Training H. Palmer, Jr.,
Supervisor of Operations R. Peal, Operations Training Supervisor A. Fitch, Operations Training Supervisor K. Roush, Supervisor of Nuclear Instruction B. Stitt, Simulator Instructor 4.2 SUMMARY COMMENTS The chief examiner thanked the -training and operations staffs for their cooperation during the examinations.
The chief examiner stated that the training department did a good job ensuring site access went smoothly on the days of the plant walk-throughs. Initially there was confusion over the training requirements for NRC visitor access, however, the training department expeditiously rectified the proble The examiners observed that plant housekeeping was excellent.
The examiners stated that security for the written and operating examinations was adequate'he generic strengths and deficiencies noted on the operating examinations were discussed.
The written examination pre-examination review was discussed.
The chief examiner felt the review was extremely beneficial.
The examiners stated that simulator fidelity was satisfactory for examination purposes.
The minor problems that were found shall be identified in the simulator fidelity report.
The chief examiner stated that every effort would be made to send the candidates'esults in approximately 30 working days.
The facility staff expressed their appreciation and stated that the NRC conducted the examinations in an extremely professiohal manner.
The chief examiner was presented the facility's formal comments on the written examination.
Attachments:
1. Written examination.and answer key (RO)
2. Written examination and.answer
.key...{SRO)
3. Facility formal comments on the written examinations 4.
NRC response to the facility formal comments 5. Simulation facility fidelity report
U. S.
NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION I
FACILITY:
Sus uehanna I
& 2 REACTOR TYPE:
BWR-GE4 DATE ADMINSTERED:
89/02/27 INSTRUCTIONS TO CANDIDATE:
Use separate paper for 'the answers.
Write answers on one side only.
Staple question sheet on top of the answer sheets.
Points for each question are indicated in parentheses after the question.
The passing grade requires at least 70~ in each category and a final grade of at least 80~.
Examination papers will be picked up 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after
'the examination starts.
~ OF CATEGORY
~ OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE 27.00 48.00 48.00 CATEGORY 2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27~o)
PLANT SYSTEMS (38~o)
AND PLANT-HIDE GENERIC RESPONSIBILITIES (10~)
75.00 FINAL GRADE
"
>o TOTALS "
All work done on this examination is my own.
I have neither given nor received aid.
Can idate's Signature
2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 27<o Page
QUESTION 2.01 (1.50)
Step S-12 of E0-100-101,
"Scram," requires
"Reset Main Generator Lockout if Conditions Permit."
STATE the basis for this step.
A copy of the flow chart is attached for reference.
ANSWER 2.01 (1.50)
This signal when combined with a LOCA [+0.75] signal will cause a load shed
[+0.75] (of loads such as:
condensate pumps, service water pumps, cir'culating water pumps, auxiliary boiler and turbine building heating load centers).
REFERENCE 1.
Susquehanna:
E0-100-101.
295006G007
..(KA's)
QUESTION 2.02 (2.50)
LIST the entry conditions (parameters AND setpoints)
for EO-100-103 Primary Containment Control.
ANSWER 2.02 (2.50)
Suppression pool water temperature above 105 deg.
F Drywell temperature above 150 deg.
F Drywell pressure above 1.72 psig Suppression pool water level above 24 feet Suppression pool water level below 22 feet
[+0.25] each parameter f+0.25] each setpoint (*****CATEGORY 2 CONTINUED ON NEXT PAGE *****)
2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 27~o Page
REFERENCE 1.
Susquehanna:
E0-100.
295026G011
..(KA's)
QUESTION 2.03 (1.00)
IDENTIFY which one (1) of the following conditions will NOT cause a "half scram" or a
"SCRAM" signal to be generated by the RPS circuitry.
(a.)
Closure of the outboard Main Steam Isolation Valve (MSIV)
in steam line "A" and
"C" with reactor power at 50%.
(b.)
Mode switch in "Refuel" and spurious signal causes High Drywell Pressure Switch "A" to activate.
(c.)
IRM C and D fail to inoperable with reactor power at 20%.
(d.)
Mode switch in Shutdown with Scram Discharge Volume (SDV)
high water level scram signal on Channel
"C" of RPS bus.
ANSWER 2.03 (1.00)
(c.)
[+1.0]
REFERENCE 1.
Susquehanna:
SY017, L-5.
295006K201
..(KA's)
QUESTION 2.04 (3.00)
The purpose of the RC/L leg of E0-100-102,
"PRV Control," is to restore level to assure adequate core cooling.
STATE three (3)
conditions in the basis of EO-100-102 that assure adequate core
~iiii>'"9 A copy aP fm f'(o~ chan iseW ck'~ol Po~
("*"**CATEGORY 2 CONTINUED ON NEXT PAGE *****)
2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 27~o Page
ANSWER 2.04 (3.00)
Active fuel is covered with liquid or two phase mixture.
[+1.0]
ECCS flow is cooling each fuel assembly in sufficient quantity to remove all heat generated in assembly.
[+1.0]
Steam flow is cooling each fuel assembly in sufficient quantity to remove all heat generated in assembly.
[+1.0]
REFERENCE 1.
2.
Susquehanna:
E0-100-100.
Susquehanna:
E0-100-102.
295031K101
.. (KA')
QUESTION 2. 05.
(2. 50)
In accordance with ON-134-001,
"Loss of Reactor Building Chilled Water," if a complete loss of chilled water occurs and cannot be restored, STATE the valves that automatically rep'osition to "
provide cooling water to the drywell.
PLID copies are attached for reference.
(2.5)
(*****CATEGORY 2 CONTINUED ON NEXT PAGE *****)
s 2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 27<m Page
ANSHER 2.05
{2.50)
RHCU non-regen heat exchanger RBCCH inlet valve auto isolates (HV-11315)
RBCCH supply valve (FV-187710)
opens RBCCH return valve (FV-18771C)
opens Chilled water supply valve to drywell cooler (FV-18771B)
closes Chilled water return valve from drywell coolers
{FV-18771A)
closes
[+0.5] each REFERENCE Susquehanna:
ON-134-001, Loss of RBCCH, Rev.
1, pp. 3,5,7.
295018K101
.. (KA')
QUESTION 2.06 (2.50)
SSES Unit 1 is operating at 100% core power.
A failure of the master recircuiation flow contro'lier causes oth recirculation pumps to run back to minimum speed (
No reactor protection trip occurs and ali attempts to return the recirculation system to normal are ineffective.
ae b.
Hith respect to ON-178-002,
"Core Flux Oscillation," STATE two (2) conditions which would require the operator to scram the plant IMMEDIATELY.
(1.5)
.
HHY is the (APRM) Average Power Range Monitor flow biased scram ineffective in mitigating certain core flux oscillations.
(1.0)
("****CATEGORY 2 CONTINUED ON NEXT PAGE *****)
2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 27<o Page
ANSWER 2.06
{2.50)
APRM Oscillation f+0.5] of 10% of rated flux when measured peak to peak f+0.25].
Two (2) or more LPRM UPSCALE [+0.5] alarms flashing and clearing on a one to five second period [+0.25]
b.
The time delay in the APRM flow biased scram setpoint has a 6 second time delay to account for the fuel time constant.
If the flux oscillations are less than 6 seconds the flow biased APRM trips would not see them.
[+1.0]
. REFERENCE 1.
2 ~
3 ~
Susquehanna:
ON-178-002.
Susquehanna:
G0-100-003.
Susquehanna:
G0-100-009.
295014A201
..(KA's)
QUESTION 2.07 (2.00)
SSES Unit 1 is at 100% power when condenser air in-leakage causes main condenser vacuum to decrease.
LIST four (4) automatic actions that occur as a direct result from degraded vacuum.
ASSUME no operator action and INCLUDE setpoints.
ANSWER 2.07
{2.00)
2.
3 ~
main turbine trip 21.7 inches Hg vacuum (8.2" absolute)
feed pump turbine trip 17.4 inches Hg vacuum (12.5" absolute)
MSIV closure 9 inches Hg vacuum (20.9" absolute)
bypass valve closure 7 inches Hg vacuum (22.9" absolute)
Action [+0.25] each; Setpoint
[+0.25] each (*****CATEGORY 2 CONTINUED ON NEXT PAGE *****)
2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 27~o Page
REFERENCE 1.
Susquehanna:
ON-143-001.
295002K203
..(KA's)
QUESTION 2.08 (2.00)
The Bleeder Trip Valves (extraction non-return valves)
on the Extraction Steam Supply lines are designed to close automatically under two (2) conditions.
STATE BOTH conditions and EXPLAIN WHY closure is required for each condition.
ANSWER 2.08 (2.00)
main turbine trip [+0.5] - close to prevent overspeed of turbine [+0.5]
high level in the feedwater heater~tk
[+0.5] - close to prevent moisture carryover to the turbine [+0.5]
REFERENCE l.
Susquehanna:
SY017, H-l.
295005K305 24500K105 245000K405
.. (KA's)
(*****CATEGORY 2 CONTINUED ON NEXT PAGE *****)
2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 27~o Page
QUESTION 2.09 (3.00)
SSES is operating at 1008 when a tube leak develops inside heater lA and causes a high-high level in heater 1A.
'a ~
b.
For EACH of the following STATE the response over the next few minutes (INCREASE, DECREASE, REMAIN THE SAME) if a high-high level occurs in heater 1A and EXPLAIN you answer.
ASSUME no operator action.
1.
reactor power 2.
feedwater temperature 3.
feedwater flow WHAT AUTOMATIC actions would occur if the high-high signal in feedwater heater 1A was concurrent with a level 4 in reactor vessels ANSWER '.09 (3.00)
a ~
b.
1.
reactor power increases"[+0.5]
2.
feedwater temperature decreases
[+0.5]
3.
feedwater flow decreases
[+0.5]
The high-high signal causes the heater 1A isolation and bypass valves to shut [+0.5] which causes the FW temperature to decrease and FW flow to decrease which causes power level t'o increase
[+0.5].
Recirculation runback to 45~ speed.
[+0.5]
REFERENCE 1.
Susquehanna:
SY017, H-1, p. 24 of 28.
2.
Susquehanna:
ON-147-002.
295001A202
.. (KA')
(**+**CATEGORY 2 CONTINUED ON NEXT PAGE *****)
2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 27~
Page
QUESTION 2.10
. (2.00)
The RCIC system has automatically initiated and has been operating for several minutes when you notice that the turbine speed is 2000 rpm.
A caution in OP-150-001,
"Reactor Core Isolation Cooling (RCIC) System," states that the RCIC turbine should not be operated for extended periods of time at less than 2200 rpm.
a.
b.
c ~
STATE all signal(s) that could have caused RCIC to automatically initiate.
WHAT potential problem(s)
could arise and WHY do you want to limit operation of the RCIC turbine below 2200 rpm?
If you were controlling the RCIC system from the Remote Shutdown Panel 1C201 and the RCIC turbine had tripped due to an electrically sensed overspeed condition, HOW could you reset the trip throttle valve from the Remote Shutdown Panel?
ANSWER 2. 10 (2.00)
a.
b.
C ~
level 2 (-30")
[+0.5]
Operation below 2200 rpm does not ensure adequate oil pressure is maintained
[+0.5].
(also accept prevents water, hammer in the exhaust line due to erratic valve operation)
By fully shutting the trip throttle valve [+1.0].
REFERENCE 1.
Susquehanna:
SY017 C-5, RCIC, pp. 3-24.
.
2950096007 217000A402
.. (KA')
(*****CATEGORY 2 CONTINUED ON NEXT PAGE *****)
2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 27~o Page
QUESTION 2.11 (1.00)
Manual initiation is required to reestablish depressurization.
(b.)
Depressurization will be automatically reestablished when the core spray or RHR pumps are restored.
(c.)
Both timer reset pushbuttons must be depressed and held for continued depressurization.
(d.)
Automatic depressurization continues without pumps running.
ASSUME all the required conditions have been met for the Automatic Depressurization System (ADS) initiation AND depressurization is in progress.
If ALL Residual Heat Removal (RHR)
pumps and Core Spray pumps trip off, WHICH one (1) of the following describes the effect that this will have on the automatic depressurization system?
(a.)
(1.0)
ANSWER 2. 11 (1.00)
(d )
r+1.03 REFERENCE 1.
Susquehanna:
SY017 C-4, Specific Objective 89, Table Four.
295025K205 218000K501
.. (KA')
QUESTION 2.12 (3.00)
SSES Unit 1 is in Operational Condition 4 and both loops of the*
shutdown cooling mode of RHR have failed.
In accordance with ON-149-001,
"Loss of RHR Shutdown Cooling Mode,
"LIST the acceptable methods of:
a ~
b.
Adding water to the reactor vessel (FOUR (4) ways).
Rejecting water from the Vessel (TWO (2) ways).
(2.0)
(1.0)
(*****CATEGORY 2 CONTINUED ON NEXT PAGE *****)
2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 27~o Page ll ANSWER 2. 12 (3.00)
CRD Condensate Transfer (keep fill/SDC flush)
Condensate Core Spray RHR in LPCI mode Any four (4) [+0.5j each b.
RWCU suction from vessel RWCU letdown SRV blowdown Any two (2) [+0.5] each REFERENCE 1.
Susquehanna:
Technical Specification 3.4.9.2.
2.
Susquehanna:
ON-149-001.
295021K305
..(KA's)
QUESTION 2-13 (1.00)
SSES Unit 1 is operating at 100~ power when safety relief valve H opens.
In accordance with ON-183-001,
"Stuck Open Safety/Relief Valve," STATE three (3) conditions when you are required to SCRAM.
ANSWER 2. 13 (1.00)
1.
When it is evident that the SRV will not close.
2.
If the SRV has not closed after two (2) minutes have elapsed.
3.
If suppression pool temperature has reached 105 degrees F.
[+0.33] each (*~***CATEGORY 2 CONTINUED ON NEXT PAGE *****)
2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 27~o Page
REFERENCE 1.
Susquehanna:
ON-183-001, Rev. 7, p. 3.
295026K305
..(KA's)
(*****END OF CATEGORY 2 *+***)
3.
PLANT SYSTEMS 38~a AND PLANT-WIDE GENERIC RESPONS I B It ITI ES10'age
QUESTION 3.01 (1.50)
a 0 b.
STATE the basis for a reactor scram from a Turbine Control Valve fast closure.
EXPLAIN WHY the turbine control valve reactor scram is not required below 24~ power.
ANSWER 3.01 (1. 50)
a ~
b.
Anticipate the pressure/neutron flux/heat flux increase that would result from a fast closure of turbine control valves.
[+1.0]
Due to the bypass valve capacity of 25~ no damage would occur.
[+0.5]
REFERENCE 1.
. Susquehanna:
SY017, L-5, p. 26 of 52.
LO $4 245000K307
..(KA's)
(*****CATEGORY 3 CONTINUED ON NEXT PAGE **~**)
3.
PLANT SYSTEMS 38<
AND PLANT-HIDE GENERIC RESPONSIBILITIES10'age
QUESTION 3.02 (1.00)
WHICH one (1) of the following is TRUE concerning the Control Rod Drive Hydraulic System response during a
(a.)
The Scram pilot valve energizes to vent the air off the Scram inlet and outlet valves.
(b.)
The Scram Discharge Volume (SDV) vent and drain air pilot.
valves energize to vent the air off the Scram discharge volume vent and drain valves.
(c.)
If one of the Scram Discharge Volume (SDV) vent and drain air pilot valves fails to reposition, the Scram Discharge Volume will remain vented and drained.
(d.)
If any scram pilot valve fails, the action of the backup scram valves will cause the rod associated with the failed scram pilot valve to scram.
ANSWER 3.02 (1.00)
REFERENCE 1.
Susquehanna:
SY017 L-5, Specific Objectives 12 and 14.
212000K106
..(KA's)
QUESTION 3.03 (2.50)
STATE four (4) rod blocks associated with the IRMs.
INCLUDE setpionts and AUTOMATIC bypasses for each, as applicable.
(*****CATEGORY 3 CONTINUED ON NEXT PAGE *****)
3.
PLANT SYSTEMS 38>
AND PLANT-WIDE GENERIC RESPONS IBI LITI ES 10%
Page
ANSWER 3.03 (2.50)
Block Upscale Downscale INOP Detector not full in Setpoint 108/125 5/125 N/A N/A BYPASS mode switch in RUN (APRM > DNSC)
range switch on range
or mode switch in RUH (APRH < DNSC)
mode switch in RUH mode switch in RUN block [+0.25] each; setpoint
[+0.25] each; bypass
[+0.25] each REFERENCE 1.
Susquehanna:
SY017 I-2, Learning Objective 3.
212000K106
..(KA's)
QUESTION 3.04 (2.00)
For the Core Spray System, EXPLAIN HOW a leak is detected in the piping between the inside of the RPV penetration and the core shroud.
INCLUDE a description of HOW and WHY the monitored parameter will change if a break occurs in this piping.
ANSWER 3.04 (2.00)
A differential pressure switch measures the dP between the bottom of the core (SLC above core plate tap)
[+0.5] and inside of the Core Spray Sparger pipe just inside the RPV shroud [+0.5]. If a break occurs, the dP will increase
[+0.5] because the pressure drop across the steam separator will be included [+0.5]
(*****CATEGORY 3 CONTINUED OH NEXT PAGE *****)
3.
PLANT SYSTEMS 38<
AND PLANT-WIDE GENERIC RESPONSIBILITIES 10'age
REFERENCE Susquehanna:
SY017 C-2, Learning Objective 7, pp. 15-16.
209001K404
..(KA's)
QUESTION 3.05 (2.50)
SSES Unit 1 is in operational condition 3 with one RHR subsystem, in the Shutdown Cooling mode.
You are maintaining a cooldown rate of 50 degrees F per hour using RHR.
'a ~
b.
If the cooldown rate started to increase, DESCRIBE three (3)
options available to return the cooldown rate to 50 degrees F
per hour.
In the shutdown cooling mode, if the operator were to inadvertently close the 'RHR injection valve (F015),
EXPLAIN HOW and WHY reactor level would respond.
(ASSUME negligible decay heat).
(1. 5)
ANSWER 3.05 (2.50)
'0 b.
Throttle open the heat exchanger bypass valve (F04B)
Throttle closed the RHRSW inlet valve Throttle closed the heat exchanger outlet valve (F003)
Throttle closed the injection valve (F017)
gyff:~poA(< o~w t~cM~$'~ p(o~
anarch 1 ~A~< <kl'++
Any three (3) [+6.5] each ([+0.25] valve,
[+0.25]
direction)
Reactor water level would decrease because the minimum flow line would open which would open a drain path from the vessel to the suppression pool. [+1.0]
REFERENCE 1..
Susquehanna:
SY017 C-l, Learning Objective 5.d, Attachment D.
205000K102
..(KA's)
(*****CATEGORY 3 CONTINUED ON NEXT PAGE *****)
3.
PLANT SYSTEMS 38<
AND PLANT-HIDE GENERIC RESPONSIBILITIES 10&
Page
QUESTION 3.06 (2.00)
Concerning the main condenser air removal system.
STATE the initiation signals required for automatic actuation and STATE the basis for EACH of the following trips.
a 0 Air removal steam jet air ejection shutdown signal (ARESD).
(1.0)
b.
Low dilution steam trip of the off gas recombiner.
ANSHER 3.06 (2.00)
a 0 b.
HY-10721, Condenser Air Removal System discharge valve not 100~ open [+0.5] (valve name or number okay).
This prevents a buildup of pressure caused by operation of the condenser air removal system with the system discharge isolated
[~.5].
"Isolate off gas" signal (two (2) flow signals)
[+0.5].
Hydrogen concentrations kept ( 4% [+0.5 (hydrogen concept)]
REfERENCE 1.
Susquehanna:
SY017-D-2, Learning Objectives 9 and 10.
256000K411
..(KA's)
QUESTION 3.07 (3.00)
Concerning the DC Distribution System:
a ~
b.
LIST three (3) major loads of the 24VDC system.
l25v H STATE three (3) available sources of~DC power to ~~g Di~se! W~~o P<clo( gas'h pe~~ <~pal~.
(1.5)
(*****CATEGORY 3 CONTINUED ON NEXT PAGE *****)
C 3.
PLANT SYSTEMS 38~
AND PLANT-WIDE GENERIC RESPONSIBILITIES10'age
ANSWER 3.07 (3.00)
a ~
Process Rad. Monitor (include OG pretreatment, RB, CCW, Service Water, RHR SW Rad Monitors)
b.
SRM IRM Trip Auxiliary Units Any three (3) [+0.5] each 1.
batteries 2.
charger
& Acc/p'-
u-I hHfgig.
u -/ I2 > UDC Sy~k 4-/~ ~~
(>Sun< S~~S~ o
+
~~~ y 4.
common transfer from Unit 2 125VDC Any three (3) [+0.5] each REFERENCE 1.
Susquehanna:
SY017 G-3,. and G-4, Learning Objectives 5 and 6.
263000K101
.. (KA')
QUESTION 3.08 (2.50)
Concerning the Standby Gas Treatment System.
'a ~
b.
LIST three (3) signals that will automat" ically start the SGTS fan selected for "AUTO LEAD."
STATE which components are used to maintain Reactor Building pressure at approximately 0.25 inches H20 vacuum.
(1.5)
(1.0)
{*****CATEGORY 3 CONTINUED ON NEXT PAGE *****)
PLANT SYSTEMS 38~o AND PLANT-WIDE GENERIC RESPONSIBILITIES 10~
Page
ANSWER 3.08 (2.50)
a ~
b.
1.
reactor level 2 (-38 inches)
5.
(> 1.5 inches)
WG delta-P on inlet header Any three (3) [+0.5] each (The fan has a set of motor driven variable) inlet vanes (FD-07551A1,) (that operates in conjection with the)
makeup air damper(FD-07551A2')and a differential pressure damper (PP0-07554A4 I+1.0]
IS~>
~X('Y 2.
DW pressure (+1.72 psig)
yI g ~y qy~ ~<@ QhaV,4 4;i ~4 3.
Zone III high radiation o~
Q.ar,
<3 Viomhiqk en&~4 <I md 9 ~i~vi<b, ~c-~<di g s h~(% e<~~q 4.
(> 230 degrees F) charcoal bed temperature h~ +<4 REFERENCE-Susquehanna:
SY017 L-3, pp.
14 5 15, Learning Objectives 5 and 6.
261000K401
.. (KA's)
QUESTION 3.09 (2.00)
Concerning the LPCI mode of RHR.
'a ~
b.
All RHR pumps have initiated on a valid LOCA signal (a double ended shear of the recirculation loop A suction piping).
EXPLAIN HOW pump runout is prevented for those pumps injecting into the A recirculation loop.
STATE two (2) initiation signals that will automatically close the recirculation loop discharge valves and bypass valves.
(*****CATEGORY
CONTINUED ON NEXT PAGE *****)
3.
PLANT SYSTEMS 38~o AND PLANT-WIDE GENERIC RESPONS IBI L IT I ES 10~
Page
ANSWER 3.09 (2.00)
a ~
b.
Each RHR pump discharge is routed through an orifice [+1.0]
(pump flow is limited to 14,500 gpm).
(-'(a~ )
level 1"and low reactor pressure
[+0.5] (236 psig)
high drywell pressure and low reactor pressure
[+0.5]
(236 psig)
REFERENCE 1.
Susquehanna:
SY017 C-1, Learning Objectives 4 and 9, Attachment A.
203000K415 203000K410
.. (KA')
QUESTION 3.10 (2.50)
Concerning the HPCI, High Pressure Coolant Injection System:
STATE the turbine and valve response to an automatic isolation signal from both Logic Divisions.
INCLUDE all valves that receive a signal from the. isolation logic.-
(A drawing is attached for reference).
ANSWER 3.10 (2.50)
P Shuts F002 [
Shuts F100 [
Shuts F003 [
Shuts F042 [
+0.5]
+0.5
+0.5
+0.5 or HPCI or HPCI or HPCI or HPCI Tri s HPCI Turbine [i0.5]
STM Supply IB ISO Warmup Line ISO Steam Supply OB ISO Pump Suction from Supply Pool REFERENCE 1.
2.
3.
Susquehanna:
SY017 C-6, p. 18, Objective 5.
Susquehanna:
SY017 C-6, p. 26.
Susquehanna:
OP-152-001, p.
17, Terminal Objective.
206000K402
..(KA's)
(*****CATEGORY
CONTINUED ON NEXT PAGE *****)
PLANT SYSTEMS 38~a AND PLANT WIDE GEHERIC RESPONSIBILITIES 10~
Page
QUESTION 3.11 (2.00)
Concerning the Reactor Water Cleanup System:
a ~
b.
STATE two (2) signals that will cause the F004, Outboard Isolation Valve, to automatically close while the F001, Inboard Isolation Valve, remains open.
EXPLAIN WHY the heat load on the non-regenerative heat exchanger is at a maximum load when in the blowdown mode.'1.O)
(1.0)
AHSWER 3. 11 (2.00)
a 0 b.
SLCS Actuation
[+0.5]
Non-regen Hx outlet temperature high (140 degrees F) [+0.5]
In the normal mode of operation the regenerative heat exchanger reduces the fluid temperature prior to entering the non-regenerative heat exchanger.
In the blowdown.mode the entire heat load is on the non-regenerative heat exchanger.
[+1.01 REFERENCE Susquehanna:
SY017L-1, Rev. 0, pp.
8 14, Learning Objectives 4 and 5.
204000K108 204000K504 223002K102
..(KA's)
QUESTION 3.12 (2.50)
CONCERNING the reactor recirculation system, a ~
b.
Technical Specifications requires recirculation pump speed shall be maintained; within (1)
% of each other with core flow greater than or ~eqoa to (g)
of rated flow; within (3)
% of each other with core flow less than ~q
% of rated flow.
DO NOT allow a recirculation pump to remain in operation if stator windings reaches (g)
degrees F.
(2-0)
'I (0.5)
(*****CATEGORY 3 CONTINUED ON NEXT PAGE *****)
PLANT SYSTEMS 38+o AND PLANT WIDE GENERIC RESPONSIBILITIES10'age
ANSWER 3.12 (2.50)
(1)
(2)
(3)
(4)
(5)
240
"-
1 ~ P
[+0.5] each REFERENCE 1.
2 ~
Susquehanna:
SY017 L-8, Learning Objective
Susquehanna:
SY017 L-9 202001K411 202001K503
.. (KA')
QUESTION 3. 13 (3.00)
Concerning SSES Technical Specifications.
a ~
b.
c ~
STATE the definition of LIMITING CONTROL ROD PATTERN-WHEH may an RO assume the control room command function?
STATE the definition of OPERATIONAL CONDITION 5.
(1.0)
(1.0)
(1.0)
(*****CATEGORY 3 CONTINUED OH NEXT PAGE *****)
3.
PLANT SYSTEMS 38>
AND PLANT-HIDE GENERIC RESPONSIBILITIES 10~
Page
ANSWER 3.13 (3.00)
b.
C ~
A LIMITING CONTROL ROD PATTERN shall be a pattern which results in the core being on a thermal hydraulic limit, i.e., operating on a limiting value for APLHGR, LHGR, or MCPR.
[+1.0]
During any absence of the Shift Supervisor from the control room when the unit is in OPERATIONAL CONDITION 4 or 5.
[+1.0]
Fuel in the reactor vessel
[+0.33] with the vessel head closure bolts less than fully tensioned or the head removed
[+0.33] average reactor coolant temperature less than 140 degrees F [+0.33].
REFERENCE Susquehanna:
Technical Specifications, pp. 1-3, 1-10, 5 6-6.
201002G001
..(KA's)
QUESTION 3. 14 (2.00)
The "A" diesel generator has automatically started due to a valid bus undervoltage condition.
a.
WHICH one (1) of the following conditions will cause the diesel to automatically trip off?
(1.)
2.)
3.)
4 ~
high jacket water temperature high vibration.
main bearing high temperature low lube oil pressure b.
STATE the action(s)
required to manually trip the diesel.
(*****CATEGORY 3 CONTINUED ON NEXT PAGE *****)
3.
PLANT SYSTEMS 38~
ANO PLANT-WIOE GENERIC RESPONS IBILITIES 10~
Page
ANSWER 3. 14 (2.00)
(4.)
[+1.0]
b.
Take mode selector switch to local [+0.5] and depress the emergency stop button [+0.5].
REFERENCE Susquehanna:
SY017 G-1, Learning Objective 5.
264000K402
..(KA's)
QUESTION 3.15 (2.50)
Concerning LOCA Load Sequencing:
A LOCA initiation signal is present and diesel generators are supplying bus power.
ASSUMING equipment was previously running or ready to start, STATE the ESS bus loads which are sequentially loaded during the first 60 seconds.
(2.5)
ANSWER 3.15 (2.50)
RHR pump A,B,C,O core spray pump A,B,C,5 ESW pump OP504 A,B,C,O Control Room Emergency Outside Air Supply System (CREOASS) train emergency switch-load center coolers and ESSW pump house RHR SW pump fan
[+0.5] each (*****CATEGORY
CONTINUEO ON NEXT PAGE *****)
3.
PLANT SYSTEMS 38<
AND PLANT-WIDE GENERIC RESPONSIBILITIES 10~a Page
REFERENCE Susquehanna:
SY017 G-1, Learning Objective 4, p. 23.
264000K303
..(KA's)
QUESTION 3.16 (2.00)
HPCI has automatically initiated due to a valid low level. signal.
STATE all requirements that must be met prior to securing or placing HPCI in the manual mode AN ANSWER 3. 16 (2.00)
Misoperations in automatic is confirmed [+0.5] or adequate core cooling is assured
[+0.5] or when directed to do so by EOP s:[+0.5]
and verified by two.(2) independent indications
[+0.5].
REFERENCE 1.
Susquehanna:
OP-152-001.
206000G001
..(KA's)
QUESTION 3.17 (2.50)
190 degrees F.
Drywell temperature is
'a ~
b.
HOW would increased drywell temperature affect the upset range level indication (INCREASE, DECREASE, OR REMAIN THE SAME)?
EXPLAIN your answer.
STATE two (2) additional level instruments that will be adversely affected by high drywell temperature.
(*****CATEGORY 3 CONTINUED ON NEXT PAGE *****)
~
t 3.
PLANT SYSTEMS 38<
AND PLANT-WIDE GENERIC RESPONSIBILITIES10'age
ANSWER 3.17 (2.50)
a ~
b.
increase
[+0.5 due to the change in density of the reference leg [+1.0]
shutdown, extended wide range
[+0.5] each REFERENCE 1.
2.
3.
Susquehanna:
E0-100-100, Caution 1.
Susquehanna:
'C006-4, Learning Objective 4.b.
Susquehanna:
SY017 J-2, learning Objective 6.
216000K507
.. (KA')
QUESTION 3.18 (3.00)
'a ~
FILL in the chart according to the exposure limits of AD-00-735, "External Dosimetry Program":
ASSUME a completed and signed form NRC-4 is on file and no exposure extensions have been"authorized for Quarterly exposure.
(2.5)
Whole Body Quarterly mrem Emergency-Rem (Life Saving)
(2)
Emergency-Rem (Protect Facility)
(3)
Extremity Skin (4)
(5)
300 N/A 100 N/A b.
Emergency exposure greater than mR/qtr.
111 qi h pi pp lushyy after recommendation by the Radiation Protection Coordinator.
(0.5)
(*****CATEGORY 3 CONTINUED ON NEXT PAGE *****)
3.
PLANT SYSTEMS 38~
AND PLANT-HIDE GENERIC RESPONS IBI LITI ES lotto Page
ANSWER 3. 18 (3. 00)
a ~
b.
l.
500
[+0.5]
2.
7S
[+O.S]
3.
[+0.5]
4.
10,000 [+0.5]
s. ~
[+o.s]
QQOQ lsoo
[~.s]
REFERENCE l.
Susquehanna:
A0-00-735.
294001K103
..(KA's)
QUESTION 3.19 (2.00)
A feedwater heater has been taken out of service and Protective Blocking tags have been applied.
Conditions require a change to the Protective Blocking.
STATE all personnel that are required to consent to the change in accordance with AD-gA-103,
"Protective Permit and Tag System".-
I'2.o)
ANSWER 3.19 (2.00)
Permit Holder
[+0.5]
Shift Supervisor
[+0.5]
System Operating Representative
[+0.5]
All individuals signed on permit
[+0.5]
REFERENCE 1.
Susquehanna:
AD-gA-103, p. 20.
294001K102
..(KA's)
(*****CATEGORY
CONTINUED ON NEXT PAGE *****)
3.
PLANT SYSTEMS 38~
AND PLANT-WIDE GENERIC RESPONSI BI L IT I ES 10~
Page
QUESTION 3.20 (3.00)
You are sent out to verify a valve lineup.
All of the valves on your list are manual valves that do not have open/close position indication/markings directly on the valve.
DESCRIBE the correct verification process for the following valves in accordance with AD-QA-300, "Conduct of Operations".
a ~
b.
c ~
A six.inch gate valve required to be closed but not required to be locked.
A ten inch globe valve required to be open but not required to be locked.
A four inch gate valve required to be open and lockwired.
ANSWER 3.20 (3.00)
a ~
b.
c ~
The valve shall be manually confirmed/verified closed by attempting to further close the valve.
{The valve SHOULD NOT be opened (lifted off its seat)
and then closed to determine position).
[+1.0]
The valve shall be manually'closed slightly and then restored to its required open position.
[+1.0]
The confirmer shall check the valve position and then the independent verifier shall recheck the valve position and lockwire the valve in position.
[+1.0]
REFERENCE 1.
Susquehanna:
AD-QA-300, p. 43.
294001K101
.. (KA')
(***"*CATEGORY 3 CONTINUED ON NEXT PAGE ***~*)
3.
PLANT SYSTEMS 38~o AND PLANT-WIDE GENERIC RESPONSIBILITIES10'age
QUESTION 3.21
{2.00)
Technical Specifications have limits on chlorides in the reactor cool ant system.
a ~
b.
Briefly EXPLAIN basis of a limit on chlorides.
Briefly EXPLAIN WY the limit changes from shutdown to power operation.
ANSWER 3.21 (2.00)
Chloride limits are specified to prevent stress corrosion cracking of the stainless steel.
)+1.0]
b.
During shutdown and refueling operations, the temperature. necessary for stress corrosion to occur is not present (so a higher concentration of chlorides is allowed during these periods).
f+1.0]
REFERENCE 1.
Susquehanna:
Technical Specification 3.4.4 and B.3.4.4.
294001A114
.. (KA')
(*****END OF CATEGORY 3 *****)
(**********
END OF EXAMINATION*****~****)
DRAFT COPY U. S.
NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION
FACILITY:
Sus uemanna
3
REACTOR TYPE:
BWR-GE4 DATE ADMINSTERED:
89/02/27 INSTRUCTIONS TO CANDIDATE:
Use separate paper for the answers.
Write answers on one side only.
Staple question sheet on top of the answer sheets.
Points for each question are indicated in parentheses after the question.
The passing grade requires at least 70~ in each category and a final grade of at least 80~.
Examination papers will be picked up hours after the examination starts.
~ OF CATEGORY
~o OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE 33.00 43.00 76.00 FINAL GRADE CATEGORY 5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (33~)
6 ~
PLANT SYSTEMS (30~o)
AND PLANi-WIDE GENERIC RESPONSI BILITIES (13~a)
TOTALS All work done on this examination is my own.
I have neither given nor received aid.
Can i ate's S>gnature DRAFT COPY
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 33~o Page
QUESTION 5.01 (3.00)
The purpose of the RC/L leg of E0-100-102,
"RPV Control" is to restore level to assure adequate core cooling.
STATE three (3)
conditions in the basis of EO-100-102 that assure adequate core cooling.
ANSWER 5.01 (3.00)
Active fuel is covered with liquid or two phase mixture.
[+1.03 2.
ECCS flow is cooling each fuel assembly in sufficient quantity to remove all heat generated in assembly.
[+1.0j Steam flow is cooling each fuel assembly in sufficient quantity to remove all heat generated in assembly.
[+1.0]
REFERENCE 1.
2.
Susquehanna:
E0-100-100.
Susquehanna:
E0-100-102.
295031K101
.. (KA')
QUESTION 5.02 (2.50)
The Plant is at 100~ power when a fire in the control complex forces the abandonment of the Control Room.
You order the Control Room evacuated immediately and, after leaving, the Reactor Operator reports to you he was unable to scram the reactor.
In accordance, with EO-100-009 "Plant Shutdown from outside Control Room,"
STATE actions required to SCRH rn TH G
/BAN.rog AND WHAT GrHae ARFc> tkummRric. Bc7adnOaS c~~~
AS A RESQaT OF 7nESEc7iduS, (*****CATEGORY 5 CONTINUED ON NEXT PAGE *****)
~'.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 33~o Page
ANSNER 5.02 (2.50)
Open breakers CB2A [+0.5] and CBBB [+0.5].
This step scrams reactor [+0.5] and isolates inboard and outboard MSIVs [+0.5] and MSL drains [+0.5]
REFERENCE 1.
Susquehanna:
E0-100-009.
295016K301
..(KA's)
QUESTION 5.03 (2.50)
CLASSIFY the following events in accordance with EP-IP-001,
"Classification of Emergency Conditions."
a ~
b.
C ~
Reactor coolant activity determined by sample analysis to be equal to 2.2 uCi/cc of I-131 equivalent.
1.
Rx mode switch in Shutdown, AND 2.
RX coolant temperature 210 degrees F
and rising, AND 3.
suppression pool temperature 295 degrees F
Loss of power to Startup Transformers 10 and 20 AND 2.
All diesel generators start but output br'eakers fail to shut.
d.
e.
Initiation of Control Room evacuation procedures and.
Shutdown systems control at local stations not established within 15 minutes.
You order the transport of an externally contaminated injured individual from site to offsite medical facility.
(*****CATEGORY 5 CONTINUED ON NEXT PAGE *****)
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 33~o Page
ANSWER 5.03 (2.50)
ao b.
c d.
e.
Unusual Event General Emergency Alert Site Emergency Unusual Event
[+0.5] each REFERENCE 1.
Susquehanna:
EP-IP-001, Rev. 6.
295034G011
..(KA's)
QUESTION 5.04 (1.50)
~
~
Step S-12 of E0-100-101,
"Scram" requires
"Reset Main Generator Lockout if Conditions Permit".
STATE the basis for this step.
ANSWER 5.04 (1. 50)
This signal when combined with a LOCA [+0.75] signal will cause a load shed
[0.75] (of loads such as:
condensate pumps, service water pumps, circulating water pumps, auxiliary boiler and turbine building heating load centers).
REFERENCE 1.
Susquehanna:
E0-100-101.
295006G007
..(KA's)
(*****CATEGORY 5 CONTINUED ON NEXT PAGE *****)
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 33~
Page
QUESTION 5.05 (3.00)
For each of the conditions/situations from Column A, SELECT ALL EO Procedure(s)
from Column B that should be entered.
(CONSIDER the initial conditions to be the plant at 90~
power operations).
If none is applicable, state NONE.
Note - Not all of the procedures in Column B need be used, and some may be used more than once.
'a ~
b.
c ~
d.
e.
go h.
Column A
RPV Level
= -40" Reactor Scram from improper ranging by operator in Inter-mediate Range Drywell Temp. of 155 deg.
F Suppression Pool Temp. of 98 degrees Drywell Pressure of 1.75 psig MSIVs closed on a valid isolation signal HPCI equipment area rad level 10 times alarm setpoint Suppression Pool level of 22.5 feet Column B
1.
EO-101 Scram 2.
EO-102 RPV Control 3.
EO-103 Primary Control 4.
EO-104 Secondary Control 5.
EO-105 Rad.
Release 6.
EO-111 Level Control 7.
EO-112 Rapid Depressurization 8.
EO-113 Level/Power Control 9.
EO-114 RPV Flooding (*****CATEGORY 5 CONTINUED ON NEXT PAGE *****)
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 33~o Page
ANSWER 5.05 (3.00)
a ~
b.
c ~
d.
e.f.
go h.
EO-102 EO-101 EO-103 NONE EO-102 EO-102 EO-104 NONE RPV Control 80-i>>
Scram Primary Containment Control, ~~ ~~~
and EO-103 RPV Control 8 Primary Containment Control, 8 0 ->><
RPV Control, E>->>~
Secondary Containment Control
[+0.33] each REFERENCE 1.
Susquehanna:
Procedures E0-101, 102, 103, and 104.
295036GOll 295010G011 2950032G01
..(KA's)
OUESTION 5.06 (2.00)
In accordance with ON-164-.002,
".Loss of Reactor Recirculation":
a ~
b.
If one recirculation pump trips off, its discharge valve is closed by the operator as a subsequent step.
STATE the reason for closing the valve.
Within 5 minutes the recirculation pump discharge valves are then reopened.
WHAT is the reason for reopening the valves?
ANSWER 5.06 (2.00)
a.
When a recirculation pump is is closed to ensure the pump and reverse flow through the
[+1 0]
tripped, the discharge valve has seated on its thrust bearing pump is no longer of consequence.
b.
To reduce the probability of 1 ocking.. [+1.0]
thermal binding and/or pressure (*****CATEGORY 5 CONTINUED ON NEXT PAGE *****)
'
P 5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 33~o Page
REFERENCE 1.
Susquehanna:
ON-164-002 Loss of Recirc Flow, Rev. 8, p. 3-4.
295018K302 295018K101
..(KA's)
QUESTION 5.07 (2.00)
The Bleeder Trip Valves (extraction non-return valves)
on the Extraction Steam Supply lines are designed to close auto-matically under two (2) conditions.
STATE BOTH conditions and EXPLAIN WHY closure is required for each condition.
ANSWER 5.07 (2.00)
main turbine trip [+0.5] - close to prevent overspeed of turbine [+0.5]
high level in the feedwater heater
[+0.5] - close to prevent moisture carryover to the turbine [+0.5]
REFERENCE 1.
Susquehanna:
SY017, H-l.
295005K305 24500K105 245000K405
..(KA's)
(*****CATEGORY 5 CONTINUED ON NEXT PAGE *****)
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 33+0 Page
QUESTION 5.08 (2.50)
.
SSES Unit 1 is operating at 100% core power.
A failure of the master recirculation flow controller causes both recirculation pumps to run back to minimum speed (less than 45 BuT 4R<@6R THnW 90 MILLIE~ Ibpg)
No reactor protection trip occurs and all attempts to return the recirculation system to normal are ineffective.
a ~
b.
With respect to ON-178-002,
"Core Flux Oscillation,"
STATE two (2) conditions which would require the operator to scram the plant IMMEDIATELY?
WHY is the (APRM) Average Power Range Monitor flow biased scram ineffective in mitigating certain core flux oscillations?
ANSWER
'a ~
b.
5.08 (2.50)
1.
APRM Oscillation [+0.5 of 10~ of rated flux when measured peak to peak f+0.25].
2.
Two (2) or mor'e LPRM UPSCALE [+0.5] ala'rms flashing'nd clearing on a one to five second period [+0.25].
The time delay in the APRM flow biased scram setpoint has a
6 second time delay to account for the fuel time constant.
If the flux oscillation are less than 6 seconds the flow biased APRM trips would not see them.
[+1.0]
REFERENCE 1.
2.
3.
Susquehanna:
ON-178-002.
Susquehanna:
G0-100-003.
Susquehanna:
G0-100-009.
295014K201
.. (KA's)
(*****CATEGORY 5 CONTINUED ON NEXT PAGE *****)
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 33~o Page
QUESTION 5.09 (2.00)
SSES Unit 1 is at 100~ power when condenser air in-leakage causes main condenser vacuum to decrease.
LIST four (4)
automatic actions that occur as a direct result from degraded vacuum.
ASSUME no operator action and INCLUDE setpoints.
ANSHER 5.09 (2.00)
main turbine trip 21.7 inches Hg vacuum (8.2" absolute)
2.
3.
4 ~
feed pump turbine trip 17.4 inches Hg vacuum (12.5" absol ute)
MSIV closure 9 inches Hg vacuum (20.9" absolute)
bypass valve closure 7 inches Hg vacuum (22.9" absolute)
Action [+0.25] each; Setpoint
[+0.25] each REFERENCE 1.
Susquehanna:
ON-143-001.
295002K203
.. (KA's)
(*****CATEGORY 5 CONTINUED ON NEXT PAGE *****)
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 33~o Page
QUESTION 5.10 (1.00)
IDENTIFY which one (1) of the following conditions will NOT cause a "half scram" or a
"SCRAM" to be generated by the RPS ciruitry.
(a.)
Closure of the outboard Main Steam Isolation Valve (MSIV)
in steam line "A" and
"C" with reactor power at 50~.
(b.)
Mode switch in "Refuel" and spurious signal causes. High Drywell Pressure Switch "A" to activate.
(c.)
(4-)
IRM C and D fail to inoperable with reactor power at 20~.
Mode switch in Shutdown with Scram Discharge Volume (SDV)
high water level scram signal on Channel
"C" of RPS bus.
ANSWER 5.10 (1.00)
(c.)
[+1.0]
REFERENCE 1.
Susquehanna:
SY017, L-5.
295006K201
.. (KA's)
(*****CATEGORY 5 CONTINUED ON NEXT PAGE *****)
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 33~o Page
QUESTION 5. 11 (3.00)
SSES 'is operating at 100~ power when a tube leak develops inside heater lA and causes a high-high level in heater lA.
a ~
For EACH of the following STATE the response over the next few minutes (INCREASE, DECREASE, REMAIN THE SAME) if a high-high level occurs in heater 1A and EXPLAIN you answer.
ASSUME no operator action.
(2.5)
2.
reactor power feedwater temperature b.
3.
feedwater flow WHAT AUTOMATIC actions would occur if&E Hu.H-Hl~a signal was concurrent with a level 4 in reactor vessel?
(0.5)
ANSWER 5. 11 (3.00)
a ~
1.
2.
3.
Reactor power increases
[+0.5]
Feedwater temperature decreases
[+0.5]
Feedwater flow decreases
[0.5]
b.
The high-high signal causes the heater 1A isolation and bypass values to shut [+0.5] which causes
.the feedwater temperature to decrease and feedwater flow to decrease which causes power level to increase
[+0.5]
Recirculation System runback to 458 speed.
[+0.5]
REFERENCE l.
2.
Susquehanna:
SY017, H-l, p. 24 of 28.
Susquehanna:
ON-147-002 295001A202
..(KA's)
(*****CATEGORY 5 CONTINUED ON NEXT PAGE *****)
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 33~o Page
QUESTION 5. 12 (2.00)
DESCRIBE the effect (INCREASE, DECREASE, REMAIN THE SAME) that a
loss of both reactor building chilled water chillers would have on:
a ~
b.
c ~
d.
drywell temperature drywell pressure RWCU RgTVRIO FROM NDQ RE6E'NI-'-<&vE HE4r c/CHIRR recirculation pump motor winding temperature ANSWER 5. 12 (2.00)
a. increase b. increase c. increase d. increase
[+0.5] each REFERENCE Susquehanna:
ON-134-001,
"Loss of RBCCW," Rev.
pp. 3, 5, and 7.
295018K101
..(KA's)
(*****CATEGORY 5 CONTINUED ON NEXT PAGE *****)
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 33~o Page
QUESTION 5.13 (2.00)
During plant operations, the reactor operator reports to you that he has indications of a stuck control rod for rod 30-31.
ON-155-001,
"Stuck Rod Control," directs you to increase drive header pressure.
a ~
b.
WHAT should the reactor operator do to INCREASE drive header pressure'?
EXPLAIN how increasing drive header pressure would
. affect (INCREASE, DECREASE, REMAIN THE SAME)
EACH of the following:
1.
HCU Accu mulator charging flow 2.
CRD total system flow (0.5)
(0.5)
ANSWER 5. 13 (2.00)
a ~
b.
close the drive water.pressure control valve
[+1.0]
1.
Remain the same
[+0.5]
2.
Remain the same
[+0.5 REFERENCE 1.
2.
Susquehanna:
ON-155-001.
Susquehanna:
SY017.
295015K201
..(KA's)
(*****CATEGORY 5 CONTINUED ON NEXT PAGE *****)
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 33~o Page
QUESTION 5. 14 (1.00)
ASSUME all the required conditions have been met for the Automatic Depressurization System (ADS) initiation AND depressurization is in progress.
If ALL Residual Heat Removal (RHR)
pumps and Core Spray pumps trip off, WHICH one (1) of the following describes the effect that this will have on the automatic depressurization system?
(a.)
Manual initiation is required to reestablish depressurization.
(b.)
Depressurization will be automatically reestablished when the core spray or RHR pumps are restored.
(c.)
Both timer reset pushbuttons must be depressed and held for continued depressurization.
(d.)
Automatic depressurization continues without pumps running.
ANSWER 5.14 (1.00)
(d )
I+I 03 REFERENCE 1.
Susquehanna:
SY017 C-4, Specific Objective f9, Table Four.
295025K205
..(KA's)
QUESTION 5.15 (2.00)
The Main Steam Isolation Valve Leakage Control System (MSIV-LCS)
is manually initiated after a Loss of Coolant Accident (LOCA).
a 0 b.
After 20 minutes, when Reactor Vessel Pressure (PRV) and Main Steam Line (MSL) pressure is below psig, the mode of the MSIV-LCS initiates.
When Main Steam Line (MSL) pressure decreases even further to
'sig, the mode of the MSIV-LCS initiates.
(1.0)
(*****CATEGORY 5 CONTINUED ON NEXT PAGE *****)
5.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS 33~o Page
ANSWER 5.15 (2.00)
a.
35 psig [+0.5], depressurization
[+0.5]
b.
1 psig [+0.5], bleed [+0.5]
REFERENCE 1.
Susquehanna:
SY017, H-3, Chapter 26.
295028K202
.:(KA's)
QUESTION 5. 16 (1.00)
During normal 80~ power operations, a safety relief valve opens and will not shut from the control room.
The reactor mode switch must be placed in shutdown if suppression pool temperature reaches
, or the safety relief valve cannot be closed within minute(s).
(1.0)
ANSWER 5.16 (1.00)
105 degrees F [+0.5], two (2) minutes [+0.5]
REFERENCE 1.
Susquehanna:
Technical Specification 3.4.2.b.
295026K305
..(KA's)
(*****END OF CATEGORY 5 *****)
6.
PLANT SYSTEMS 30>
AND PLANT-WIDE GENERIC RESPONSIBILITIES13'age
QUESTION 6.01 (2.50)
STATE four (4) rod blocks associated with the IRMs.
INCLUDE setpionts and AUTOMATIC bypasses for each, as applicable.
ANSWER 6.01 (2.50)
Block Upscale Downscale INOP Setpoint 108/125
. 5/125 N/A BYPASS mode switch in RUN (APRM ) DNSC)
range switch on range
or mode switch in RUN (APRM < DNSC)
mode switch in RUN Detector not full in N/A
.
.
.....
mode switch. in RUN block [+0.25] each; setpoint
[+0.25] each; bypass
[+0.25] each REFERENCE 1.
Susquehanna:
SY017 I-2, Learning Objective 3.
215003K401
.. (KA')
(*****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
6.
PLANT SYSTEMS 30%
AND PLANT-WIDE GENERIC RESPONSIBILITIES 13~a Page
QUESTION 6.02 (2.00)
"A" diesel generator has automatically started due to a valid bus undervoltage condition.
a 0 WHICH one (I) of. the following conditions will cause the diesel to automatically trip off?
2.)
4 ~
high jacket water temperature high vibration main bearing high temperature low lube oil pressure b.
STATE the action(s)
required to manually trip the diesel.
(I.O)
ANSWER 6.02 (2.00)
(4 )
!+I 03 b.
Take mode selector switch to local [+0.5] and depress the emergency stop button [+0.5].-
REFERENCE 1.
Susquehanna:
SY017 G-l, Learning Objective 5.
264000K402
..(KA's)
QUESTION 6.03 (2.50)
190 degrees F.
Drywell temperature is a 0 b.
HOW would increased drywell temperature affect the upset range Tevel indication (INCREASE, DECREASE, OR REMAIN THE SAME)?
EXPLAIN your answer.
STATE two (2) additional level instruments that will be adversely affected by high drywell temperature.
(I.O)
(*****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
6.
PLANT SYSTEMS 30>
AND PLANT-HIDE GENERIC RESPONSIBILITIES13'age
ANSWER 6.03 (2.50)
a ~
b.
increase
[+0.5 due to the change in density of the reference leg [+1.0]
shutdown, extended.wide range
[+0.5] each REFERENCE 1.
2.
3.
Susquehanna:
E0-100-100, Caution 1.
Susquehanna:
SC006-4, Learning Objective 4.b.
Susquehanna:
SY017 J-2, learning Objective 6.
216000K507
.. (KA')
QUESTION 6.04 (1.00)
During a startup the Rod Worth Minimizer (RWM) becomes inoperable at 18~ power.
STATE the action required by Technical Specifications to continue power ascension.
(1.0)
ANSHER 6.04 (1.00)
With the RWM inoperable, verify CR movement and compliance with prescribed CR pattern by a second licensed operator or other technically qualified member of unit staff who is at the reactor control console.
[+1.0]
REFERENCE 1.
Susquehanna:
Technical Specification 3/4.1.4.
201006G005
.. (KA')
(*****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
~
~
6.
PLANT SYSTEMS 30%
AND PLANT-WIDE GENERIC RESPONS I BILIT I ES 13~
Page
QUESTION 6.05 (1.00)
Technical Specifications for Emergency Core Cooling System (ECCS)
allow one (1) Automatic Depressurization System (ADS) valve to be inoperable for up to fourteen (14) days provided High Pressure Core Injection (HPCI), Core Spray System (CSS)
and Low Pressure Coolant Injection (LPCI) are operable.
Concerning the basis for this Technical Specification, WHICH one (1) of the following is true?
(a.)
Safety analysis only takes credit for five valves, so one valve out of service for up to fourteen (14) days does not reduce system reliability.
(b.)
Risk assessment for these valves indicates a negligible chance for a second valve failure in fourteen (14) days.
(c.)
HPCI, together with CSS and LPCI provides for adequate decay heat removal from 100~ power for up to fourteen (14)
days with five operable ADS valves.
(d.)
The heat capacity of the suppression pool is conservatively analyzed to allow continuous operation with one (1) fully opened Automatic Depressurization System (ADS) valve.
ANSWER 6.05 (1.00)
(a )
I+1 03 REFERENCE Susquehanna:
Technical Specifications 3/4, 5-2, Basis Section.
218000G006
.. (KA's)
(*****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
6.
PLANT SYSTEMS 30~
AND PLANT-WIDE GENERIC RESPONSIBILITIES13'age
QUESTION 6.06 (3.00)
a.
WHAT is the CONTROL ROD PATTERN?
definition of LIMITING b.
In accordance with Technical Specification interpretation, STATE the difference between OPERABLE and FUNCTIONAL.
ANSWER 6.06 (3.00)
a.
b.
A LIMITING CONTROL ROD PATTERN shall be a pattern which results in the core being on a thermal hydraulic limit, (i.e., operating on a limiting value for APLHGR, LHGR, or MCPR).
[+1.0]
An OPERABLE system per Technical Specification is one which is capable of performing its specified Technical Specification function(s). '+1.0]
A FUNCTIONAL system is one which, while perhaps not OPERABLE for a Technical Specification, is nonetheless capable of performing a desired function.
This function may consist of surveillance testing, post maintenance testing, administrative
"alternate" or "backup" to required Technical Specification systems or some other special evolution.
[+1.0]
REFERENCE 1.
2.
Susquehanna:
Technical Specifications, Section 1.29 and 3.4.
Susquehanna:
Technical Specifications, Interpretations TSI 1-88-003, p. 1-2.
201002G001
.. (KA')
QUESTION 6.07 (1.50)
STATE the basis for Refueling Operation Technical Specification 3.9.8, which reads:
"At least 22 feet of water shall be maintained over the top of the reactor pressure vessel flange."
(1 5)
(*****CATEGORY
CONTINUED ON NEXT PAGE *****)
6.
PLANT SYSTEMS 30~
AND PLANT-HIDE GENERIC RESPONSIBILITIES 13~m Page
ANSHER 6.07 (1.50)
The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10m iodine gap activity released from the rupture of an irradiated fuel assembly
[+0.5]..
P4'm begs At0T gEppK EO REFERENCE 1.
Susquehanna:
Technical Specification, p.
8 3/4, 9-2.
234000G006
..(KA's)
QUESTION 6.08 (2.00)
Concerning the Reactor Hater Cleanup System:
a ~
b.
STATE two (2) signals that will cause the F004, Outboard Isolation Valve, to automatically close while the F001, Inboard Isolation Valve, remains open.
EXPLAIN WHY the heat load on. the non-regenerative heat.
exchanger is at a maximum when in the blowdown mode.
ANSHER 6.08 (2.00)
a ~
b.
SLCS Actuation
[+0.5]
Non-regen Hx outlet temperature high (140 degrees F) [+0.5]
In the normal mode of operation the regenerative heat exchanger reduces the fluid temperature prior to entering the non-regenerative heat exchanger.
In the blowdown mode the entire heat load is on the non-regenerative heat exchanger.
[+1.0]
(*****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
6.
PLANT SYSTEMS 30M AND PLANT-WIDE GENERIC RESPONSIBILITIES 13'age
REFERENCE Susquehanna:
SY017L-l, Rev. 0, pp.
3 5 14, Learning Objectives 4 and 5.
223002K102 204000K104 204000K504
..(KA's)
(}UESTION 6.09 (3.00)
While performing a Surveillance Test on High Pressure Coot.eev Injection (HPCI)
for HV-155 F002, DTGRm ROrl<ss~y< ygmg(ggggggg)
- (IRC) Technician reports the. isolation function is inoperable (i.e., will not auto isolate).
In accordance with'echnical Specifications, STATE all actions required, INCLUDE all LCOs that apply to present status.
(*****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
PLANT SYSTEMS 30~o AND PLANT WIDE GENERIC RESPONS IBI L IT I ES 13~
Page
ANSWER 6.09 (3.00)
Technical Specification 3.5.1.c.1
[+1.0]
With the HPCI system inoperable, restore the HPCI system to OPERABLE status within 14 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce reactor steam dome pressure to < 150 psig within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Technical Specification 3.6.3.a
[+1.0]
ACTION:
With one or more of the primary containment isolation valves shown in Table 3.6.2-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
Restore the inoperable valve(s) to OPERABLE status, or 2.
3.
Isolate each affected penetration by use of at least one deactivated automatic valve secured in the isolated position, or Isolate each affected penetration by use of at least one closed manual valve or blind flange.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
echnical Specification 3.3.3.(a)
[+1.0]
a.
With an ECCS actuation instrumentation channel trip setpoint t +
less conservative than the value shown in the Allowable Values column of Table 3.3.3-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip
P'etpoint adjusted consistent with the Trip Setpoint value.
b.
With one or more ECCS actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.3-1.
REFERENCE Susquehanna:
Technical Specifications, Sections 3.3.3.(a),
3.5.l.c.l, and 3.6.3.a..
206000A409 206000G001
.. (KA's)
(*****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
PLANT SYSTEMS 30~o AND PLANT WIDE GENERIC RESPONSIBILITIES13'age
QUESTION 6.10 (2.50)
a.
b.
A prerequisite to procedure OP-149-002,
"RHR Operation in Shutdown Cooling Mode," requires minimum water level in the reactor vessel.
STATE the level and the basis for a minimum level?
While in the gwoaw/usual goyt op RHR system a portion of the flow maybe diverted to the spray nozzle in the reactor vessel head.
LIST three (3) reasons for spraying the vessel head.
(1.0)
(1.5)
ANSWER 6. 10 (2. 50)
a ~
b.
+55 inches
[+0.5] and ensure natural recirculation for core cooling [+0.5].
Keep system pressure down to facilitate vessel flooding
[W.5].
Decrease thermal stratification in RPV coolant [+0.5]
Limits thermal stress in the'vessel during cooldown
[~.5]
REFERENCE 1.
2.
3.
Susquehanna:
OP-149-002.
Susquehanna:
SY017 C-1 Attachment D, p.
7 L.O.
1 and 5.
Susquehanna:
SY017 C-l, p. 5, L.O.
1 and 5.
205000K102 205000K101
..(KA's)
(*****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
PLANT SYSTEMS 30 o AND PLANT WIDE GENERIC RESPONSIBILITIES 13~m Page
QUESTION 6. 11 (2.50)
Concerning the Standby Gas Treatment System.
a e b.
LIST three (3) signals that will automatically start the SGTS fan selected for "AUTO LEAD."
STATE which components are used to maintain Reactor Building pressure at approximately 0.25 inches H20 vacuum.
ANSWER 6.11 (2.50)
a
~
1.
reactor level 2 (-38 inches)
2.
DW pressure (+1.72 psig)
3.
Zone III high radiation Po~
n iso~~~e>>
('0.5)
b.
4.
(> 230 degrees F) charcoal bed temperature 5.
(> 1.5 inches)
WG delta-P on inlet header Any three (3) [+0.5] each The fan has a set of motor driven variable inlet vanes (FD-07551A1 that operates in conjunction with the makeup air damper FD-0755IA2jand a differential pressure damper PDD-07554A.
,[+1.0]
REFERENCE Susquehanna:
SY017 L-3, pp.
8 15, Learning Objectives 5 and 6.
261000K401
.. (KA's)
(*****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
PLANT SYSTEMS 30~o AND PLANT WIDE GENERIC RES PONS IBILITI ES 13M Page
QUESTION 6. 12 (2. 50)
Concerning LOCA Load Sequencing:
A LOCA initiation signal is present and diesel generators are supplying bus power.
ASSUMING equipment was previously running or ready to start, STATE the ESS bus loads which are sequentially loaded during the first 60 seconds.
(2.5)
ANSWER 6.12 (2.50)
RHR pump A,B,C,D core spray pump A,B,C,D ESW pump OP504 A,B,C,D Control Room Emergency Outside Air Supply System (CREOASS) train emergency switch-load center coolers and ESSW pump house RHR SW pump fan
[+0.5] each REFERENCE 1.
Susquehanna:
SY017 G-l, Learning Objective 4, p. 23.
264000K303
..(KA's)
(*****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
6.
PLANT SYSTEMS 30~
AND PLANT-.WIDE GENERIC RESPONSIBILITIES13'age
(}VESTION 6. 13 (3.00)
The reactor is at 100~ power when the electrical supervisor reports that the specific gravity for the load group channel
"C" 125VDC battery pilot cell is 1.195.
a ~
b.
STATE all actions required by Technical Specifications and INCLUDE all LCOs.
STATE all actions required if the electrical supervisor reported additionally that the load group channel
"C" 125VDC battery had a terminal voltage of 128VDC while on a float charge; INCLUDE all applicable LCOs.
(1.5)
(1.5)
ANSWER 6.13 (3.00)
'a ~
b.
Technical Specification 3/4, 8.2.1, Table 4.8.2.1-1.
For any Category A parameter(s)
outside the limit(s)
shown, the battery may be considered OPERABLE provided that within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> all the Category B measurements are taken and found to be within.their. allowable values, and provided all Category A and B parameter(s)
are restored to within limits within the next 6 days.
[+1.5]
Technical Specification 3/4, Surveillance 4.8.2.l.a.2.
4.8.2.1 Each of the above required plus or minus 24-volt, 125-volt, and 250-volt batteries and charges shall be demonstrated OPERABLE:
At least once per 7 days by verifying that:
1.
The parameters in Table '4.8.2.2-1 meet the Category A limits, and 2.
There is correct breaker alignment to the battery chargers, and total battery terminal voltage is greater than or equal to 26, 129, 258-volts on float charge.
I+1.5]
( 1.5)
(*****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
6.
PLANT SYSTEMS 30~
AND PLANT-WIDE GENERIC RESPONSIBILITIES13'age
REFERENCE Susquehanna:
Technical Specifications, 3/4, 4.8.2. 1.a.2, 8.2. 1, and Table 4.8.2.1-1.
263000G005
..(KA's)
QUESTION 6. 14 (1.00)
WHICH one (1) of the following is TRUE concerning the Control Rod Drive Hydraulic System response during a SCRAM?
(a.)
The Scram pilot valve energizes to vent the air off the Scram inlet and outlet valves.
(b.)
The Scram Discharge Volume (SDV) vent and drain air pilot valves energize to vent the air off the Scram discharge volume vent and drain valves.
(c.)
If one of the Scram Discharge Volume (SDV) vent and drain air pilot valves fails to reposition, the Scram Discharge Volume will remain vented and drained.
(d.)
If any scram pilot valve fails, the action of the backup scram valves will cause the rod associated with the fai.led scram pilot valve to sera~.
ANSWER 6.14 (1.00)
(d )
r+I 0]
REFERENCE 1.
Susquehanna:
SY017 L-5, Specific Objectives 12 and 14.
212000K106
..(KA's)
(*****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
6.
PLANT SYSTEMS 30~
AND PLANT-WIDE GENERIC RESPONSIBILITIES 13M Page
QUESTION 6.15 (1.50)
a ~
b.
STATE the basis for a reactor scram from a Turbine Control Valve fast closure.
EXPLAIN WHY the turbine control valve reactor scram is not required below 24~ power.
ANSWER 6. 15 (1. 50)
a ~
b.
Anticipate the pressure/neutron flux/heat flux increase that would result from a fast closure of turbine control valves.
[+1.0]
Due to the bypass valve capacity of 25~ no damage would occur.
[+0.5]
REFERENCE 1.
Susquehanna:
SY017; L-5,.p. -26 of 52.
2.
.
Susquehanna:
SY017, L-5, Learning Objective
245000K307
..(KA's)
QUESTION 6.16 (1.50)
WHO, by title, has the authority to authorize personnel into a controlled access area during fuel receipt/inspection activities?
(NAME three (3)).
(~****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
PLANT SYSTEMS 30~o AND PLANT WIDE GENERIC RESPONSIBILITIES 13~
Page
ANSWER 6.16 (1.50)
Superintendent of Plant - Susquehanna Assistant Superintendent of Plant - Susquehanna Fuel Receipt Inspection Supervisor On-Duty Operations Shift Supervisor Any three [+0.5] each REFERENCE 1.
Susquehanna:
AD-00-815.
294001K105
..(KA's)
QUESTION 6.17 (2.50)
'a ~
b.
An Area Contamination Report has been presented to you, the shift supervisor, by a Health Physics Technician, in accordance with AD-00-720, "Contamination Control."
WHAT responsibilities. do you have with regards to the Area Contamination Report?
Emergency exposure greater than mR/qtr.
F11 qi h pi pp l~gyW after recommendation by the Radiation Protection Coordinator.
(0.5)
(*****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
PLANT SYSTEMS 30~o AND PLANT-HIDE GENERIC RESPONSIBILITIES13'age
ANSWER 6.17 (2.50)
a.
The Shift Supervisor is responsible for:
Initiating immediate corrective action for ACR's generated as a result of Station activities.
[+1.0]
Evaluating ACR's and determining need for generating Significant Operating Occurrence Report (SOOR)
or implementing the Emergency Plan.
[+1.0]
b.
1500
[+0.5]
- REFERERNCE 1.
Susquehanna:
AD-00-720, Rev. 6, p. 6.
REFERENCE 294001K103
..(KA's).
QUESTION 6.18 (3.00)
You direct a plant operator to verify..a valve lineup.
All of the valves on the list are manual valves that do not have open/close position indication/markings directly on the valve.
In accordance with AD-QA-300, "Conduct of Operations,"
DESCRIBE the correct verification process for the following valves.
a ~
b.
C ~
A six inch gate valve required to be closed but not required to be locked.
A ten inch globe valve required to be open but not required to be locked.
A four inch gate valve required to be open and lockwired.
(*****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
PLANT SYSTEMS 30~o AND PLANT WIDE GENERIC RESPONSIBILITIES13'age
ANSWER 6.18 (3.00)
a 0 b.
c ~
The valve shall be manually confirmed/verified closed by attempting to further close the valve.
(The valve SHOULD NOT be opened (lifted off its seat)
and then closed to determine position.)
f+1.0]
The valve shall be manually closed slightly and then restored to its required open position.
[+1.0]
The confirmer shall check the valve position, by removing the lockwire and then the independent verifier shall recheck
,the valve position and lockwire the valve in position.
[+1.0]
REFERENCE 1.
Susquehanna:
AD-QA-300, p. 43.
.294001K101
..(KA's)
QUESTION 6. 19 (2.00)
Technical Specifications have limits on chlorides in the reactor coolant system.
a ~
b.
Briefly EXPLAIN the basis of a limit on. chlorides.
Briefly EXPLAIN WHY the limit changes from shutdown to power operation.
(1 0)
ANSWER 6.19 (2.00)
a 0 b.
Chloride limits are specified to prevent stress corrosion cracking of the stainless steel.
[+1.0]
During shutdown and refueling operations, the temperature necessary for stress corrosion to occur is not present (so higher concentration of chlorides is allowed during these periods).
[+1.0]
(*****CATEGORY 6 CONTINUED ON NEXT PAGE *****)
6.
PLANT SYSTEMS 30~
AND PLANT-WIDE GENERIC RESPONSIBILITIES 13~a Page
REFERENCE 1.
Susquehanna:
Technical Specification 3.4.4 and B.3.4.4.
294001A114
..(KA's)
Pl QUESTION 6.20 (2.50)
a ~
b.
WHAT is required to maintain a Senior Reactor Operator (SRO) license in an ACTIVE status in accordance with lOCFR55?
(1.0)
If an SRO license is in an INACTIVE status, WHAT is required before the person. can resume the duties that require an active SRO license7 (Negeqg 0g g~,F7 Qg]-]eg gf Q+ /$0)
ANSWER 6.20 (2.50)
a ~
b.
The license holder must perform the functions of an SRO
[+0.25] on a minimum of 7 eight hour shifts [+0.5]
per calendar quarter
[+0.25].
The license must be current and valid [+0.5] and the license holder must perform a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of. gpggA<
0ht s,gFr 0pEgnT)gg/5
[+0.25] under the direction of a SRO ~].
These functions must include a tour of the plant and all shift turnover procedures
[+0.5].
c go)
REFERENCE 1.
2.
Susquehanna:
AD-QA-300, "Conduct of Operation," Section 6.4.
3.
LFR 0> ~iM Z~ Rdf'd~u~
294001A103
..(KA's)
(*****END OF CATEGORY 6 *****)
(**********
END OF EXAMINATION**********)
Pennsylvania Power 8 Light Company P.O. Box 467
~ Berwick, PA 18603-0467
~ 717/542-3350 Susquehanna Training Center c:
NRC File SRMS - DCC: Site March 2, 1989 Mr. R. Conti U. S. Nuclear Regulatory Commission Region
475 Allendale Road King of Prussia, PA 19406 SUSQUEHANNATRAININGCENTER NRC EXAM REVIEW PLA 3163 File A14-12F Attached please find the facilityreview comments forthe Reactor Operator and Senior Reactor Operator wiitten exa'minations administered at Susquehanna on February 27, 1989.
R..
m Supt of Plant - SSES Response:
No MP/Ltc00li RGB/RPM/llc
NRC EXAM REVIEW REACTOR OPERATOR (RO)
'ESTION 2.06 a (1.50)
SSES Unit 1 is operating at 100% core power. A failure of the master recirculation flowcontroller causes both recirculation pumps to run back to minimum speed (less than 45 but greater than 40 million Ib/hr). No reactor protection trip occurs and all attempts to return the recirculation system to normal are ineffective.
a.
With respect to ON-178-002, "Core Flux Oscillation," STATE two (2)
conditions which would require the operator to scram the plant IMMEDIATELY?
(1.5)
ANSWER a.
1.
APRM Oscillation [+0.5] of 10% of rated fluxwhen measured peak to peak [+0.25].
2.
Two (2) or more LPRM UPSCALE [+0.5] alarms flashing and clearing on a one to five second period [+0.25].
COMMENT The answer key is correct. Our procedures also require the operator the scram if"LPRMs in the vicinityofthe selected rod are oscillating ~ 5 watts/cm~".
RESOLUTION The answer key should be amended to add this and accept any 2 ofthe 3 conditions.
REFERENCE AD-QA-300 Attachment D SRO Question 5.08 Page 1 of 1
NRC EXAM REVIEW REACTOR OPERATOR (RO)
9 U E S T 0 N 2tl 7 (2.00)
SSES Unit 1 is at 100/0 power when condenser air in-leakage causes main condenser vacuum to decrease.
LISTfour (4) automatic actions that occur as a direct result from degraded vacuum. ASSUME no operator action and INCLUDE setpoints.
ANSWER 1.
main turbine trip 21.7 inches Hg vacuum (8.2" absolute)
2.
feed pump turbine trip 17.4 inches Hg vacuum (12.5" absolute)
3.
MSIVclosure 9 inches Hg'acuum (20.9" absolute)
4.
bypass valve closure 7 inches Hg vacuum (22.9" absolute)
Action t+ 0.25] each; Setpoint [+ 0.251 each COMMENT The NUREG 1123 referenced, 295002K203 is "Knowledge ofthe interrelations between LOSS OF MAINCONDENSER VACUUMand PCIS/NSSSS".
Neither this nor the plant off-normal procedure referenced, nor the Plant Administrative Procedures (AD-QA-300, section 6.2) require memorization of setpoints.
RESOLUTION Full credit should be given for stating the actions that occur,.without the setpoints.
REFERENCE SRO Exam Question 5.09 AD-QA-300 Section 6.2 Page 1 of 1,
NRC EXAM REVIEW REACTOR OPERATOR (RO)
UESTION 3.05 a (1.50)
SSES Unit 1 is in operational condition 3 with one RHR subsystem in the Shutdown Cooling mode. You are maintaining a cooldown rate of 50'
per hour using RHR.
a.
Ifthe cooldown rate started to increase, DESCRIBE three (3) options available to return the cooldown rate of 50'
per hour.
(1.5)
ANSWER a.
Throttle open the heat exchanger bypass valve (F048)
Throttle closed the RHRSW inlet valve Throttle closed the heat exchanger outlet valve (F003)
Throttle closed the injection valve (F017)
Anythree (3) [+ 0.5J each ([+0.25) valve, [+ 0.25) direction)
COMMENT a.
The question asks "Describe 3 options available to change cooldown rate".
The answer key as given is correct and should be accepted.
The candidate may have replied with:
a)
"Decrease RHRSW flowthrough the heat exchanger" b)
"Decrease RHR system flow" c)
"Secrease RHR flowthrough the heat exchanger" d)
"Increase RHR system bypass flow" and this reply would fullysatisfy the question as stated.
RESOLUTION Accept either a)
The answer key as stated or b)
a, b, c, and d above.
only one of c) and d) should be accepted.
Page 1 of 1
NRC EXAM REVIEW REACTOR OPE RATOR (RO)
UESTION 3.06 a.
Airremoval steam jet air ejection shutdown signal (ARESD).
(1.0)
b.
Lowdilutionsteamtripoftheoffgasrecombiner.
(1.0)
ANSWER g
12.0tl)
Concerning the main condenser air removal system.
STATE the initiation signals required for automatic actuation and STATE the basis for EACH ofthe followingtrips.
a.
HV-10721, Condenser AirRemoval System discharge valve not 100'/o open
[+0.5] (valve name or number okay). This prevents a buildup of pressure caused by operation ofthe condenser air removal system with the system discharge isolated [+ 0.5].
b.
"Isolate offgas" signal (two (2) flowsignals) [0.5].
Hydrogen concentrations kept <4/0 [+ 0.5 (hydrogen concept)].
COMMENT Part (b) is confusing. The candidates may have interpreted this as "What causes an offgas Isolate" signal. Ifso they would listthe signals, which willinclude lowdilution steam flow.
RESOLUTION Full credit should be given ifthey list:
Lowdilution steam flow-keep H2 concentrate within limits.
The candidate should not be penalized for listing the other signals or actions.
Page 1 of 1
NRC EXAM REVIENl REACTOR OPERATOR (RO)
UESTION 3.07 b (1.50)
Concerning the DC Distribution System:
b.
STATE three (3) available sources of 125 volt DC power to any Diesel Generator field flash power supply.
(1.5)
ANSWER b.
1.
batteries 2.
charger 3.
common transfer from Unit 2 125VDC Anythree(3) [+0.5] each COMMENT b.
The answer key is correct, but confusing. Itshould read:
U-1 battery U-1 charger U-2 battery U-2 charger
~ RESOLUTION Full credit should be given-for U-1 125 VDC system U-2 125 VDC system OI U-1 battery U-1 charger.
U-2 battery U-2 charger Page 1 of 1
NRC EXAM REVlEW REACTOR OPERATOR (RO)
'UESTID 3.08 (2.50)
Concerning the Standby Gas Treatment System.
a.
LlSTthree (3) signals that willautomatically start the SGTS fan selected for
"AUTOLEAD."
(1.5)
b.
STATE which components are used to maintain Reactor Building pressure at approximately 0.25 inches HzO vacuum.
(1.0)
ANSWER a.
1.
Reactor level 2 (-38 inches)
~
2.
DW pressure (+ 1.72 psig)
3.
Zone III high radiation
'4.
(>230'F) charcoal bed temperature 5.
(>1.5 inches) WG b,P on inlet header Anythree (3) [+ O.S] each b.
The fan has a set of motor driven variable inlet vanes (FD-07551A1) that operates in conjunction with the makeup air damper (FD-07551A2) and a differential pressure damper (PDD-075S4A).
[+ 1.0]
I COMMENT The answer key.as written is correct, but other terms commonly used at Susquehanna should also be accepted.
High Drywell Press~re Reactor Level 2 Refuel floorwall exhaust hi rad Refuel floor high exhaust hi rad Railroad access shaft access exhaust hi rad Charcoal bed high temperature WG d,P on inlet header Zone 1 isolation Zone 3 isolation Page 1 of 2
NRC EXAM REVIEW REACTOR OPERATOR (RO)
RESOLUT(ON The answer key should accept:
Zone 1 isolation or the signals that cause it, but not both.
Zone 3 isolation or the signals that cause it, but not both.
Charcoal bed high temperature WG hP on inlet header Page 2 of 2
NRC EXAM REVIEW REACTOR OPERATOR (RO)
g U 6 S TID M 3. Il9 (2.oo)
Concerning the LPCI mode of RHR.
a.
AllRHR pumps have initiated on a valid LOCAsignal (a double ended shear of the recirculation loop A suction piping). EXPLAINHOW pump runout is prevented forthose pumps injecting into the A recirculation loop.
(1.0)
b.
STATE two (2) initiation signals that willautomatically close the recirculation loop discharge valves and bypass valves.
'(1.0)
ANSWER a.
Each RHR pump discharge is routed through an orifice [+ 1.0] (pump flow is limited to 14,500 g pm).
b.
Level 1 and low reactor pressure [+0.5] (236 psig)
High drywell pressure and low reactor pressure [+0.5] (236 psig)
COMMENT a.
The question implies an answer specific to the A loop (the loop with the suction break). The answer given is not specific to the A loop, and in fact is not specific to the conditions given in this question at all. The information given leads the candidate into thinking specifically about the
'A'oop in this situation. "-.
b.
The question asks for 2 signals that willautomatically close the Recirculation valves.
Reactor level 1 and low reactor pressure are "2 signals which will automatically close the Recirc valves".
High DW pressure and low reactor pressure are "2 signals which will automatically close the Recirc valves" ~
LOCAsignal and low reactor pressure are "2 signals which will automatically close the Recirc valves".
RESOLUTION a.
Grant fullcredit for a)
The answer as written in the key or b)
The A Recirc loop Discharge valve and discharge Bypass valve will shut and stop RHR flowout the break.
b.
Any of these 3 combinations should be accepted for full credit.
Page 1 of 1
NRC EXAM REVIENI REACTOR OPERATOR (RO)
UESTION 3.12 a (1.00)
a.
WHATis the definition of LIMITINGCONTROL ROD PATTERN?
(1.0)
ANSWER a.
A LIMITINGCONTROL ROD PATTERN shall be a pattern which results in the core being on a thermal hydraulic limit,(i.e., operating on a limiting value for APLHGR, LHGR, or MCPR).
[+ 1.0]
COMMENT The referenced item from NUREG 1123, 2010026001, Knowledge of Operator Responsibilities during all modes of Plant Operation, does not implythe need to memorize the definition for LimitingControl Rod Pattern.
RESOLUTION Strike part (a) ofthe question and apply the point value to part (b).
REFERENCE SRO Question 6.06 NUREG 1123, 201002G001 Page 1 of 1
NRC EXAM REVIEW REACTOR OP E RATOR (RO)
QUESTIONS.IE (2.00)
HPCI has automatically initiated due to a valid low level signal. STATE all requirements that must be met prior to securing or placing HPCI in the manual mode.
(2.0)
ANSWER Misoperations in automatic is confirmed [+ 0.5] or adequate core cooling is assured [+0.5] or when directed to do so by EOP's [+0.5] and verified by two (2) independent indications [+0.5].
COMMENT The answer key is correct but confusing. It should read Misoperation in automatic or Adequate core cooling assured or Directed to do so by EOPs.
verified by 2 independent indications Further, the question specifically states that HPCI started due to a valid initiation signal, so a candidate who leaves out "Misoperation in automatic" should not be penalized.
RESOLUTION Accept changes to answer key for clarification.
REFERENCE AD-QA-300 Conduct of Operations RO Question 3.16 Page 1 of 1
NRC EXAM REVlEW SENIOR REACTOR OPERATOR (SRO)
QUES D
5.05 (3.00)
For each ofthe conditions/situations from Column A, SELECT ALLEO Procedure(s) from Column B that should be entered.
(CONSIDER the initial conditions to be the plant at 90% power operations). Ifnone is applicable, state NONE. Note - Not all ofthe procedures in Column B need be used, and some may be used more than once. (3.0)
Column A a.
RPV Level = -40" b.
Reactor Scram from improper ranging by operator in Inter-mediate Range c.
DrywellTemp. of 155'
d.
Suppression Pool Temp. of 98 e..
Drywall Pressure of 1.75 psig Column B 1.
EO-101 Scram 2.
EO-102 RPV Control 3.
EO-103 Primary Control 4.
EO-104 Secondary Control 5.
EO-105 Rad. Release 6.
EO'-111 Level Control g.
MSIVs closed on a valid isolation signal HPCI equipment area rad level 10 times alarm setpoint 7.
EO-112 Rapid Depressurization 8.
EO-113 Level/Power Control h.
Suppression Pool level of 22.5 feet 9.
EO-114 RPV Flooding ANSWER a.
b.
C.
d.
e.
f.
EO-102 RPV Control EO-101 Scram EO-103 Primary Containment Control NONE EO-102 And EO-103 RPV Control & Primary Containment Control EO-102 RPV Control EO-104 Secondary Containment Control NONE
[+0.33] each Page 1 of 2
NRC EXAM REVIEW SENIOR REACTOR OPERATOR (SRO)
COMMENT Items A, C, E, F.
The answer key is correct and the questions should elicitthe answer as stated, however these 4 items also imply a scram condition. The examinee should not be penalized for including EO-101, Scram, in his answer for A, C, E, or F.
'ESOLUTlON Do not subtract credit ifthe candidate includes EO-101 in the answer for A, C, E,orF.
REFERENCE EO-100-101 AD-QA-300, Attachment D Page 2 of 2
NRC EXAM REVIEW SENIOR REACTOR OPERATOR (SRO)
UESTION 5.08 a (1.50)
SSES Unit 1 is operating at 100% core power. A failure ofthe master recirculation flowcontroller causes both recirculation pumps to run back to minimum speed (less than 45 but greater than 40 million lb/hr). No reactor protection trip occurs and all attempts to return the recirculation system to normal are ineffective.
a.
With respect to ON-178-002, "Core Flux Oscillation," STATE two (2)
conditions which would require the operator to scram the plant IMMEDIATELY?
(1.5)
ANSWER a.
1 ~
APRM Oscillation [+0.5] of 10% of rated fluxwhen measured peak to peak [+0.25].,
2.
Two (2) or more LPRM UPSCALE [+0.5] alarms flashing and clearing on a one to five second period [+0.25].
COMMENT The answer key is correct. Our procedures also require the operator the scram if"LPRMs in the vicinityofthe selected rod are oscillating ~ 5 watts/cm'".
RESOLUTION The answer key should be amended to add this a'nd accept an'y 2 ofthe 3 conditions.
REFERENCE AD-QA-300 Attachment D Page 1 of 1
NRC EXAM REVIEW SENIOR REACTOR OPERATOR (SRO)
QUESTO 5.09 (2.00)
SSES Unit 1 is at 100 /0 power when condenser air in-leakage causes main condenser vacuum to decrease.
LISTfour (4) automatic actions that occur as a direct result from degraded vacuum. ASSUME no operator action and INCLUDE setpoints.
ANSWER 1.
main turbine trip 21.7 inches Hg vacuum (8.2" absolute)
2.
feed pump turbine trip 17.4 inches Hg vacuum (12.5" absolute)
3.
MSIVclosure 9 inches Hg vacuum (20.9" absolute)
4.
bypass valve closure 7 inches Hg vacuum (22.9" absolute)
Action [+0.25] each; Setpoint [+0.25] each COMMENT The NUREG 1123 referenced, 295002K203 is "Knowledge of the interrelations between LOSS OF MAINCONDENSER VACUUMandPCIS/NSSSS".
Neither this nor the plant off-normal procedure referenced, nor the Plant Administrative Procedures (AD-QA-300, section 6.2) require memorization of setpoints.
RESOLUTION Full credit should be given forstating the actions that occur, without the setpoints.
REFERENCE AD-QA-300 Section 6.2 Page 1 of 1
NRC EXAM REVIEW SENIOR REACTOR OPERATOR (SRO)
QUES ID S. I (2.oo)
The Main Steam Isolation Valve Leakage Control System (MSIV-LCS) is manually initiated after a Loss of Coolant Accident (LOCA).
a.
After 20 minutes, when Reactor Vessel Pressure (PRV) and Main Steam Line (MSL) pressure is below psig, the mode ofthe MSIV-LCS initiates.
(1.0)
b.
When Main Steam Line (MSL) pressure decreases even further to psig, the mode ofthe MSIV-LCSinitiates.
(1.0)
ANSWER a.
35 psig [+0.5], depressurization [+0.5]
b.
1 psig [+0.5], bleed [+0.5]
COMMENT The question is ambiguous as written, and no single answer stands out. We see the following problems:
a.
The system is manually initiated (stated in the question stem). Both (a)
a6d (b) then say "the mode initiates". This implies an auto initiation or mode change.
b.
Neither (a) or (b)"specifies th'e outboard or inboard MSIV-LCS system. The answer differs or based on the choice.
c.
The blanks ask for automatic actions and interlocks that da not exist in the implied condition.
RESOLUTION a.
The answer given is correct ifthe candidate was thinking "when reactor vessel pressure drops below psig, I can manually start the system and itwillstart in the mode.
Ifhe thought "Itwas initiated 20 minutes ago and RPV and MSL pressure have dropped to 1 psig, itwillautomatically switch to the bleed mode.
For (a) accept either 35 psig, depressurization or 1 psig, bleed REFERENCE OP-184-001 Page 1 of 1
NRC EXAM REVlEW SENIOR REACTOR OPERATOR (SRO)
S OM606 (3.00)
a.
WHATis the definition of LIMITINGCONTROL ROD PATI ERN?
(1.0)
b.
In accordance with Technical Specification interpretation, STATE the difference between OPERABLE and FUNCTIONAL.
(2.0)
ANSWER a.
A LIMITINGCONTROL ROD PATTERN shall be a pattern which results in the core being on a thermal hydraulic limit,(i.e., operating on a limiting value for APLHGR, LHGR, or MCPR).
[+1.0]
b.
An OPERABLE system per Technical Specification is one which is capable of performing its specified Technical Specification function(s).
[+ 1.0]
A FUNCTIONALsystem is one which, while perhaps not OPERABLE for a Technical Specification, is nonetheless capable of performing a desired function. This function may consist ofsurveillance testing, post maintenance testing, administrative "alternate" or "backup" to required Technical Specification systems or some other special evolution.
[+ 1.0]
COMMENT The referenced item from NUREG 1123, 2010026001, Knowledge of.Operator Responsibilities during all modes of Plant Operation, does not implythe need to memorize the definition for LimitingControl Rod Pattern.-
RESOLUTION Strike part (a) ofthe question and apply the point value to part (b).
REFERENCE NUREG 1123, 201002G001 Page1of
NRC EXAM REVIEW SENIOR REACTOR OPERATOR (SRO)
gUEST 0 U E ll9 (3.00)
While performing a Surveillance Test on High Pressure Coolant Injection (HPCI)
for HV-15S F002, Steam Admission Valve (Inboard) (IKC)Technician reports the isolation function is inoperable (i.e., willnot auto isolate).
In accordance with Technical Specifications, STATE all actions required, INCLUDEall LCOs that apply to present status.
ANSWER Technical Specification 3.5.1.c.l [+ 1.0]
With the HPCI system inoperable, restore the HPCI system to OPERABLE status within 14 days or be in at least HOT SHUTDOWN withinthe next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce reactor steam dome pressure to (150 psig withinthe following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Technical Specification 3.6.3.a [+ 1.0]
ACTION:
With one or more ofthe primary containment isolation valves shown in Table 3.6.2-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
1.
Restore. the inoperable valve(s) to OPERABLE status, o'
2.
Isolate each affected penetration by use of at least one deactivated automatic valve secured in the isolated position, or 3.
Isolate each affected penetration by use of at least one closed manual valve or blind flange.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWNwithin the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Technical Specification 3.3.3.(a) [+ 1.0]
a.
With an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With one or more ECCS actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.3-1.
COMMENT The question does not state why the valve willnot auto isolate.
In reality, at this point the report would have included why the valve willnot auto isolate.
The candidate may have assumed that the problem was-the valve or the motor operator, in which case he would not enter the instrumentation LCO.
Page 1 of 2
NRC EXAM REVlENl SENIOR REACTOR OPERATOR (SRO)
RESOLUTION Full credit should be given forthe answer as itexists or forTechnical Specifications 3.5.1.c.1 and 3.6.3.a, without 3.3.3.a.
Page2of2
NRC EXAIVIREVIENI SENIOR REACTOR OPERATOR (SRO)
gUEST U 6.1 (2.50)
Concerning the Standby Gas Treatment System.
a.
LISTthree (3) signals that willautomatically start the SGTS fan selected for
"AUTO LEAD."
(1.5)
b.
STATE which components are used to maintain Reactor Building pressure at approximately 0.25 inches HzO vacuum.
(1.0)
ANSWER a.
1.
Reactor level 2 (-38 inches)
2.
DW pressure (+ 1.72 psig)
3.
Zone IIIhigh radiation 4.
(>230') charcoal bed temperature S.
()1.5 inches) WG b,P on inlet header Anythree (3) [+0.5] each b.
The fan has a set of motor driven variable inlet vanes (FD-07551A1) that operates in conjunction with the makeup'air damper (FD-07551A2) and a differential pressure damper (PDD-07S54A).
[+ 1.0]
COMMENT The answer key as written is correct, but other terms commonly used at Susquehanna should also be accepted.
High Drywell Pressure Reactor Level 2 Refuel floorwall exhaust hi rad Refuel floorhigh exhaust hi rad Railroad access shaft access exhaust hi rad Charcoal,bed high temperature WG b,P on inlet header Zone 1 isolation Zone 3 isolation Page 1 of 2
NRC EXAM REVIEW SENIOR REACTOR OPERATOR (SRO)
RESOLUTION The answer key should accept:
Zone 1 isolation or the signals that cause it, but not both.
Zone 3 isolation or the signals that cause it, but not both.
Charcoal bed hig h temperature WG hP on inlet header Page 2 of 2
NRC EXAM REVlEW SENlOR REACTOR OPERATOR (SRO)
gUEST UN ET 6 (1.50)
WHO, by title has the authority to authorize personnel into a controlled access area during fuel receipt/inspection activities? (NAMEthree (3)).
(1.5)
ANSWER Superintendent of Plant - Susquehanna Assistant Superintendent of Plant - Susquehanna Fuel Receipt Inspection Supervisor On-Duty Operations Shift Supervisor Anythree [+0.5) each COMMENT The NUREG 'l123 Reference, 294001K105, "Knowledge offacilityrequirements for controlling access to vital/control areas," does not justify requiring the candidate to commit to memory all ofthe administrative controls for access to all ofthe job areas in the plant.
The question requires memorization of controls for a job that is not normally controlled by operations, is not time critical, and would not be attempted without reference to the controlling document.
RESOLUTION Delete the question.
Page 1 of '
NRC EXAM REViEW SENIOR REACTOR OPERATOR (SRO)
QUES OM6 (2.50)
a.
An Area Contamination Report has been presented to you, the shift supervisor, by a Health Physics Technician, in accordance with AD-00-720,
"Contamination Control.'HAT responsibilities do you have with regards to the Area Contamination Report?
(2.0)
b.
Emergency exposure greater than mR/qtr. shall require the prior approval ofthe Emergency ire or a er recommendation by the Radiation Protection Coordinator.
(0.5)
ANSWER a.
The Shift Supervisor is responsible for:
Initiating immediate corrective action for ACR's generated as a result of Station activities.
[+ 1.0]
Evaluating ACR's and determining need for generating Significant Operating Occurrence Report (SOOR) or implementing the Emergency Plan.
[+ 1.0]
b.
1500
[+0.5]
CQMMENT The question requires'memorization of administrative actions.- What we really want the operator to do is exercise sound judgement and be sensitive to contamination control. He should 1.
Refer to the procedure.
2.
Take action to clean-up and/or contain the contamination as appropriate.
3.
Make notifications as appropriate.
Nothing in the question leads one to believe that the problem is on the same order of magnitude as an Emergency Plan requirement so the question doesn'
elicitthis as part ofthe answer.
RESOLUTION Grant fullcredit for a general statement which includes reference to 1, 2, and 3 above.
Page 1 of 1
NRC EXAM REVIENI SENIOR REACTOR OPERATOR (SRO)
g STDN6.20 (2.50)
a.
WHATis required to maintain a Senior Reactor Operator (SRO) license in an ACTIVEstatus in accordance with 10CFR55?
(1.0)
b.
Ifan SRO license is in an INACTIVEstatus, WHATis required before the person can resume the duties that require an active SRO license?
(NORMALON SHIFT DUTIES OF AN SRO)
(1.5)
ANSWER a.
The license holder must perform the functions of an SRO [+0.25] on a minimum of 7 eight hour shifts [+0.5] per calendar quarter [+0.25].
b.
The license rust be current and valid [+0.5] and the license holder must erform a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of NORMALON SHIFT OPERATIONS
+ 0.25] under the direction of a SRO [+0.5]. These functions must include a tour ofthe plant and all shift turnover procedures [+0.5].
COMMENT The reference in NUREG 1123, 294001A103 states "Abilityto locate and use procedures and station directives related to shift staffing and activities".
It implies access to the document but the question required the candidates to
~ answer from memory.
RESOLUTION Grant fullcredit for a reference to performance of licensed duties without regard to specific numbers or time frames.
OI Eliminate the question.
REFERENCE NUREG 1123, 294001A103 Page 1 of 1
ATTACHMENT 4 NRC RESPONSE TO FACILITY FORMAL COMMENTS Question 2.06:
Comment NOT ACCEPTED.
The reference provided by the facility does not justify the facility resolution.
No change required.
Question 2.07:
Comment NOT ACCEPTED.
The operator should know the order in which plant systems will fail upon a degrading vacuum condition. Additionally, the operator should know the speed at which he should respond in an effort to counteract a degrading vacuum condition.
No change required.
Question 3.05:
Comment ACCEPTED.
The answer key was changed to accept either
'throttle open'r
'increase flow'nd 'throttle closed'r
'decrease flow'.
Question 3.06:
Comment NOT ACCEPTED.
The wording of the question is consistent with the terminology of the training material provided.
No change required.
Question 3.07:
Comment ACCEPTED.
The answer key was changed to accept either a '25 Vdc system'r
'a battery and a charger'.
Question 3.08:
Comment ACCEPTED.
The answer key was changed to accept Zone I isolation for Hi D/W Press and RPV Level 2 and Zone III isolation for Refuel Floor Mall Exhaust Hi Rad and Refuel Floor High Exhaust Hi. Rad and Railroad Access Shaft Exhaust Hi Rad.
Question 3.09a:
Comment NOT ACCEPTED.
The orifice in the discharge of the pump prevents pump runout while closing the discharge and bypass valves directs flow to the core.
No change required.
Question 3.09b:
Comment NOT ACCEPTED.
The answer key is consistent with the terminology of the training material provided.
No change required.
Question 3. 12:
Comment NOT ACCEPTED.
A licensed operator must be able to recognize if he is operating on a limiting control rod pattern.
In order to do so he must understand what a limiting control rod pattern is.
No change required.
Question 3. 16:
Comment NOT ACCEPTED. Misoperation in automatic is not limited to a spurious actuation signal.
No change required.
Question 5.05:
Comment ACCEPTED.
The answer key was changed so that no credit would be lost if the candidate stated EO-100-101 for A,C,E or F
ATTACHMENT 4 Question 5.08:
see question 2.06 Question 5.09:
see question 2.07 Question 5. 15:
Co~ment NOT ACCEPTED.
The question is clearly written to solicit the answers as stated in the answer key.
No change required.
Question 6.06:
see question 3. 12 Question 6.09:
Comment ACCEPTED.
The answer key was changed to accept technical specification section 3.5. l.c. 1 and 3.6.3.a for full credit.
Question 6. 11:
see question 3.08 Question 6.16:
Comment NOT ACCEPTED.
The question does not require the candidate to memorize all administrative controls for access to all job areas of the plant.
Rather, the question attempts to discern whether the candidate knows some of the administrative requirements for'access during special activities at the plant.
No change required.
Question 6.17:
Comment NOTED.
The facility resolution is the same as the response required for full credit.
No change required.
Question 6.20:
Comment NOT. ACCEPTED...Each licensed operator must fully understand the conditions and limitations of the license.
No change require ATTACHMENT 5 SIMULATION FACILITY FIDELITY REPORT Facility Licensee:
Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Facility Licensee Docket Nos.
50"387 50-388 Facility Licensee Nos.
NPF" 14 NPF-22 Operating Tests Administered At:
Susquehanna Unit 1 Simulator Operating Tests Given On:
March 1 to March 3, 1989 Scenario Validation Performed On:
February 28, 1989 During the conduct of the simulator portion of the operating tests and/or scenario validation identified above, the following apparent performance discrepancies were observed:
The chart recorder pen for 'B'PRM sticks at 100,o power regardless of actual reactor power.
Quarterly RCIC pump flow.verificati.an surveillance test SO-150-002 cannot be performed on the simulator without excessive overrides by the simulator operator.
Therefore, this surveillance cannot be used for examination purposes.
Malfunction REC-9 (recirculation pump 'B'ower seal fai lute) in combination with REC-10 (recirculation pump 'B'pper seal failure) should indicate a dual recirculation pump seal failure. Individually, both malfunctions performed satisfactorily.
However, when inserted simultaneously, seal cavity pressures were normal. (i.e.
lower seal pressure was equal to recirculation loop pressure and upper seal pressure was equal to 50Fo of lower seal pressure)
The correct indication should be both seal cavity pressures decreasing for a dual recirculation pump seal failure.
Overall, the simulator fidelity was acceptable.