ML20207N077
| ML20207N077 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/06/1988 |
| From: | Burdick T, Reidinger T, Shepard D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20207M876 | List: |
| References | |
| 50-346-OL-88-02, 50-346-OL-88-2, NUDOCS 8810180486 | |
| Download: ML20207N077 (193) | |
Text
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k V. S. NUCLEAR REGULATORY COMMISSION REGION III t
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Report No. 50-346/0L-88-02 Docket No. 50-346 License ho. NPF-3 i
Licensee:
Toldeo Edison Company 300 Madiscn Avenue Toledo, OH 43652 Facility Name:
Davis-Besse Examination Administered At:
Davis-Besse Examination Conducted: Week of 29 August 1988
..D.feidingerV l0lQf dxaminers:
l Date D 5 p d
/0k/rf Date
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Approved By:
homas M. Burdick, Chief
[O [/
i Operator Licensing Date(
t Section 2 Examination Sumary Examination administered on week of 29 August 1988 (Report No. 50-346/0L-88-02) to nine senior reactor operator and one reactor operator candidates.
Results:
Five senior reactor ope;'ator and one reactor operator candidates passed the examination, hgg
((Mk 6
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REPORT DETAILS 1.
Examiners T. D. Reidinger, NRC, Chief Examiner B. Picker, EGG D. Shepard, NRC l
l 2.
Exit Meeting l
On September 2,1988, the Chief Examiner met with nr6ys cf tne plant staff to discuss generic findings made during the coarse of the examination.
The following persor.nel attended the exit reeting.
C. Blay, Nuclear Licensing G. A. Bradley, Nuclear Licensfog J. Syronski, Nuclear Training l
T. J. Myers, Nuclear Licensing l
T. Stallard, Nuclear Training l
R. A. Simpkins, Nuclear Training D. L. Miller, Quality Assurance L. Storz, Plant Manager R. Flood, Assistant Plant Manager, Operations J. Kasper, Operation 3vnerintendent i
P. Byron, NRC, SRI i
D. Kosloff NRC, R4 4
T. Reidinger, NRC, rdll l
D. Shepard, NRC, Rill i
NRC examiners presented the f0lbwing facility strength:
the candidates exhibited goud conceptual implementation of administrative procedures.
Some weaknesses were noted by the examiners, including observations of individuals wearing TLD's on their pockets below the waist and individuals act reading their SRD's upon exiting the RCA.
The latter weakness was also noted during the previous examination given in May 1988. Since that time, j
the licensee has revised their practices (procedure revisions are not yet i
finalized) to assign the responsibility for reading SRD's for dose l
tracking purposes to dosimetry clerks; however, individuals are still expected to read their SRDs for information upon exiting the RCA.
Both j
weaknesses appear contrary to current licensee pro:edures.
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A generic weakness was noted during review of the facility's Abnormal Procedures due to a lack of specificity in direction.
The examiners have f
raised a concern over the ability of inexperienced operators to mitigate off normal events based upon the Abnormal Procedures. Additionally, the examiners make decisions on candidate performance as judged against these procedures.
Without specific procedure guidance it is possible that the 5
candidate may not be evaluated properly leading to questionable examination l
results. This is compounded by the lack of a simulator.
The guidance (cperator actions and discussion) provided in the Abnormal i
Procedures does not address simple (or single) failures but rather the far more unlikely compo^und failures, e.g., AB 1203.08 "Loss of Neutron Flux Indication" covers the unlikely circumstance of a loss of all neutron instrumentation (NI) but not the far more credible scenario of a single N! failure. This leaves the operator to depend on his experience l
to combat these failures.
The plant does not presently have a comprehensive abnormal procedure or alarm procedure which addresses failures of the instrumentation relating to the Integrated Control System i
(ICS). The alarm procedures indirectly address some instrument failures in the supplementary actions but an operator would have to be intimately familiar with all the alarm procedures.
For example, the annunciator t
"Reactor Coolant Cold leg Loop 1 and 2 Temperature Differential High" and i
its alarm procedure will address the failure of a T cold instrument and i
actions that need to be taken for this failure. But the inexperienced l
operator will not readily have the presence of mind and the time required to positively address and control these types of ICS instrument failures.
I When addressing instrument failures through Technical Specifications, which require the candidates to trip an RPS channel, the candidates chose to trip the "High Reactor Building Pressure" bistable for temperature failures but there exists no documentation or procedure (abnormal or alarm) that the candidate would use to guide or direct this action.
There exists a very murky understanding of the reasons to trip the "High Reactor Building Pressure" bistable and this understandf rig has been passed by "word of mouth" from one training class to another. A concern exists that l
the lack of guidance for single failures could lead to more serious accidents.
For example, without procedure guidance, delays while responding to a high failure of a power range NI can lead to a i
high pressure reactor trip which might lead to a challenge of the pressure relief valves or the PORV.
Further operator licensing examinations will depend upon the NRC regaining j
confidence that the procedures provide sufficient guidance for inexperienced operators. Modification of the operating test format or i
delay of the exams may be necessary.
This issue will be subsequently l
addressed when the Region completes the review of the 42 procedures with the licensee in November 1988, A weakness was noted in that the normal operating procedures'(SP and ST) were difficult for the candidates to locate in the control room.
It appears that the lack of an effective cross reference and the plant's revision of numerous procedures including generic numbering changes is the root cause.
For example, one candidate had trouble locating the ST for heat balance since it was listed alphabetically under RPS since the title is "RPS Daily Heat Balance Check" (ST 5042.02.DB-SP-03357).
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3.
Examination Review l
A copy of the examination and answer key was given to the facility personnel for review at the conclusion of the written examination.
Facility personnel mailed their comments to the Chief Examiner after their review. Their comments and resolution of the coraents are Attachment I to this report.
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REACTOR OPERATOR EXAMINATION Question 1.01 (1.00)
With the reactor critical at 10 E-05% rod withdrawal is used to increase power i
to 10 E-04%.
Select the one statement that correctly describes the position l
of rods after the power has stabilized at 10 E-04%.
1 1
4.
The rod position will be higher than at 10 E-05*4 because more fuel must l
be exposed to the available neutrons to maintain the higher power level, r
I b.
The rod position will be higher than at 10 E-05% to overcome the power
- defect, l
c.
The red position will be the same.
The outward rod motion needed to achieve a given startup rate equalt, the inward motion needed to reduce t
the startup rate to zero.
d.
The rod position will be lower than at 10 E-05% due to the increased i
delayed neutron population associated with the higher power-level.
Answer 1.01 (1.00)
"c."
Facility Comments
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No installed instrumentation has readout of 10 E-05% to 10 E-04%.
Intermediate range channels have range of 10 E-11 to 10 E-03 amps.
If the power change was f rom 10 E-05 to 10 E-04 amps, the reactor would be above the point of adding heat.
Request accepting "b." for credit based on intermediate range respor.se.
See L
attached reference.
i ERC Resolution The answer key will be modified to accept either answer.
Question 1.09 (2,00)
The reactor is critical at 10 E-4% power when an atmospheric vent valve fails open. (Isolation valve is open, rods in manual, no operator action). Explain in general what happens to reactor power and Tave and w'iy, (Assume the reactor is undermoderated at BOL and no reactor trip occurs, continue explanation till primary power and Tave conditions are stable).
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Answer 1.09 (2.00)
The excess steam flow causes Tave to decrease and insert positive reactivity
(.50), the positive reactivity increase causes power to rise at, an increasing rate. When plant reaches POAH, the fuel temperature rise will add negative reactivity (.50) via doppler feedback and add Rx heat to step the temperature decrease.
Reactor power should equal steam demand (.50) with temperature less than original Tave (.5J).
(Dump vent valve - capacity of 5% rated steam flow.) (Similar wording acceptable.)
Facility Comments No installed instrumentation has readout of 10 E-4*. power.
Intermediate range channels have rance of 10 E-11 to 10 E-3.
If the valve failed open at 10 E-4 amps, response would be similar, but doppler feedback would be immediate because the resctor is already above the point of adding beat.
Recommend accepting for full credit the assumption that the plant is already above the point of adding heat.
See attached reference.
NRC Resolution The answer key will include that vne doppler feedback will be present.
Quertion 2.01 (2.80)
In 1987, a malfunction of an instrument air drytr isolation valve allowed instrument air pressure to dec"ease to 74 psig. The ICS responded in auto and caused a high flux reactor trip.
(The core being late in life - ECL) a.
DESCRICE wnat plant systems responded to this malfunction and how the ICS responded to this transient.
(1.6) b.
Describe why and how the rtactor trip was generated.
(1.2) l Answer 2.01 (2.80)
Low instrument air ceuses LP heater drains, HP feedwater heaters, MS
)
a.
drain tank, 1st/2nd stage tank reheat drains and feedwater heater bypass valves to open.
(or feed and
.t eam system valves open ta dump steam and condensate to condenser)
(9.4)
ICS respond?d by increasing feccwater flow (0.4) and pulled rods out.
(0.4) b.
Increased feedwater flow caused a decrease in reactor coolant Tave (0.4) moderator temperature coef ficient is most negative at EOL (0.4) and as a result caused reactor power to increase which caused a high flux trip.
(0.4) 2 i
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Facility to'mments Part A:
The question states, "DESCRIBE what plant systems responded to this,
malfunction". The answer key only addressed LP, HP feedwater' '
heaters and other feedwater associated concerns.
Recommended accepting any of the 17 actions for plant systems as alterna'te correct responses per reference TAP 88-02.
Also refer to SRO Question 6.14.
See attached reference.
NRC Resolution Com: ent noted. Answer key states... "feed and steam valves" open...
.The provided reference expands the list of steam and feed valves which function on this failure. The generic term feed / steam will be accepted in addition to any of the 17 actiens listed per additional supplement.
Question 2.05 (1 30)
Which one of the following parameters will NOT cause a trip of the main turbine if the setpoint is exceeded?
a.
High exhaust hood temperature b.
Low bearing oil pressure c.
Excessive thrust bearing wear d.
Low hydraulic fluid pressure Answer 2.05 (1.00) a.
High exhaust hood temperature (1.0)
Facility Comments Recommend this question b< deleted since all four parameters WILL trip the turbine.
See attached retorence.
NRC Resolution Disagree, high exhaust hood temperature is stiictly an alarm annunciator.
it does not trip the turbine.
Question 2.15 (1.50)
How is inadvertent draining of the spent fuel pool ;iping a.
prevented.
(0.5) b.
Which one of the following is the most correct reasons that spent fuel pool boron concentration must be maintained greater than 2000 ppm during fuel transfer operation?
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___ _- -- - -- --- - - - - - - - - - - - - - - - ^ - '
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1.
Technical Specification requirements t
2.
Assure safe storage of spent fuel l
3.
Prevent dilution of transfer canal water x '
Other than boron concentration, what one (1) hpent Fuel System design f
c.
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feature ensures that criticality will not occur 7 E
Answer 2.15 (1.50) a.
Suction and discharge lines have siphon breakers.
(0,5) b.
3 (0,5) c.
Rack spacing (0,5)
Facility Comments An alternate ~ answer for Part c may include the material the racks are made of 1
as identified in' USAR Chapter 9.
Recommend accepting rack material as an acceptable alternate response. See attached reference.
Part a answer may include that the pipes penetrate the pool 9' above the top of the fuel assemblies. Recommend accepting penetration level as an t
acceptable alternate response for Part a.
j NRC Resolution The additional answers of rack material of stainless steel and pipe suction penetration lengths are acceptable.
t Question 2.17 (2.50)
With respect to modifications of Makeup System:
LIST the advantage of relocating the new makeup pump suction lines to the a.
HP1 suction lines.
(1.0) b.
The new throttle valve (MU 6419) and new injection flow path could be used for two purposes.
List the two purposes.
(1.5)
Answer 2.17 (2.50)
Will allow piggyback operation of the Makeup System on the LPI pumps a.
(increases flow rate).
(1.0) b.
Bypass of MU 32 when it fails (0.75)
Allows emergency feed and bleed (0.75) a i
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a Facility Comments i
.Part b Recommend accepting additional responses per attached referance for full credit, concerning operating MU 6419.
Reference states open MU 6419 upon loss of subcooled margin and as an aid in pressurizer level control when flow through normal injection is not sufficient.
Comment also applies to SR0 Question 6.12.
See attached reference.
NRC Resolution Agree.
The reference noted was not supplied prior to the development of the examination. Answer key will be amended.
Question 3.02 (3.00)
Using the enclosed diagram of the' Integrated Control System, explain the actions that would occur in the following control sections if an asymmetric rod condition occurred at 90 percent of full power. (Include the actions that the control sections take with respect to components and other interactions).
a.
Feedwater co'ntrol (1.5) b.
Reactor control (1.5)
Answer 3.02 (3.00) a.
RI trol received a demand signal from the integrated master (steam gen.- tor / reactor demand) when an asymmetric rod condition occurs (reaccor at 90%, ASYMMETRIC rod Rx power limit is 60%, rod rate of change will be the percent per minutes [.375].
This will send a reduced demand signal to be compared with the actual flow rate [.375]., The output of I
which will send a signal to the feedwater regulating values to position the feed values to close [.375] until flow error is zero, Loop A and B feedwater demand, are summed, a total feedwater flow demand is developed and applied to expected pump speed demands to FW flow demands to ensure the lowest delta P error is sided [.375] to feedwater flow feed signal fine tuning the pump speed.
b.
The reactor control section receives the same decreasing signal [.375].
From the comparison between this signal and the neutron error and the reactor demand difference unit will send a, signal that will call for the insertion rods [.75]. The rod bite at 90 percent may be weak, and a reactor cross 11mits may occur limiting feedwater flow [.375).
Facility Comments Answer a. implies that an asymmetric rod runback is occurring.
This runback does not exist at Davis-Besse.
The Reactor Operator is directed to reduce power to < 60% RTP within one hour by AB 1203.23 (CR0 Malfunctions),
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4 Step 1.3.1.a.
This is done manually at the ULD panel.
Request that the first portion of Answer a. of 3.02 be deleted and the 375 pts, be spread throughout the remaining portion of the answer.
Answer b. required inclusion of potential cross limits to feedwater.
Step 1.2.1.c of AB 1203.23 directs a careful reduction of power while monitoring for imbalance and motion of other rods.
This by itself would preclude the event of cross limits.
Request that the portion of Answer b. of 3.02 be deleted and the.375 pts. be spread throughout the remaining portion of the answer. See attached reference.
NRC Resolution Comment noted. Answer key will not be modified, recognizing that the refer ence was modified af ter the examination developmer.t.
Per telephone conversation this modification reference material was not sent in time for examination development.
Question 3.03
( 1. '25)
List the five modifications made to the Reactor Protection System (either automatically or manually) when the shutdown bypass key switch is placed in bypass.
(Setpoints not required.)
1 Answer 3.03 (1.25) a.
Bypass power / imbalance / flow trip (0.25 pts, each) b.
Bypas3 power / pumps trip c.
Bypass pressure / temperature trip d.
Bypass low / pressure trip Adds shutdown bypass high RCS pressure trip e.
Facility Comments Question 3.03 asks for both automatic and manual modifications to the Rx Protection System. Table 2.2-1 of TechT Specs. includes reduction of the high flux trip setpoints to <5% RTP as a condition for shutdown bypass operation.
Request that Answer 3.03 be changed to five of six, with reduction of high flux trip setpoints to <5% RTP included as one of the six choices.
See attached reference.
NRC Resolution Disagree, reduction of the high flux trip setpoints although a condition for shutdown bypass operation is not a function manually or automatically of the shutdown bypass key switch operation.
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9 Question 3.11 (2.00)
Answer the following questions ragarding the Nuclear Instrument System:
Answer each part independently.
a.
You are conducting a plant shutdown from 30% power. What specific conditions will UN-bypass (remove) the high SUR rod withdrawal inhibit circuit? Specify channel or component numbers and i
setpoints.
(1.0) b.,
You are performing a plant startup from a source range level of 10 E-2 cps.
List all specific conditions throughout the startup will inhibit rod withdrawal?
(1.0)
Answer a.
NI-5 and NI-6 (C.5) both less than 10% power (0,5).
b.
Either SR (NI-1 or 2) greater than 2 dpm (0.5).0R IR (NI-3 or 4) greater than 3 dpm (0,5)
Facility Comments Question 3.11.a asks what specific conditions will remove the high SUR rod withdrawal inhibit circuit.
In actually, the circuit is inserted when either NIS and NI6 or NI7 and NI8 read <5% RTP.
Please accept for the correct response to 3.11.a:
NI5 and NI6 or NI7 and NI8 both less than 5% power.
See attached reference.
NRC Resolution Will accept NI-7 and NI-8 in addition to NI-5 and NI-6.
Either is acceptable.
Question 3.12 (1.00)
A reactor operator responding to a failed Loop 2 feedwater transmitter upset
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drove Group 8 rods (APSRs) in when the unit was at 100% power which resulted in a high flux trip. Why did his actions cause a high flux trip?
Answer 3.12 (1.00)
APSRs caused a power imbalance / increase which exceeded an RPS high flux trip
- setpoint, l
Facility Comments Answer 3.12 implies that the RPS high flux trip was caused by an imbalance / increase in Rx power due to APSR lnsertion.
Actually, the effect was a power increase, causing the RPS high flux trip setpoint to be exceeded.
l Recommend accepting the term "power increaso" vice "imbalance / increase" for full credit, See attached reference.
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NRC Resolution 4
Will accept power increase if the candidate states that driving the APSR's inward added positive reactivity which increased power above the high flux trip setpoint.
Question 4.03 (1.00)
' List the two parameters to identify the steam generator with the steam leak per Excessive Heat Transfer procedure.
Answer 4.03 (1.00)
S/G with the fastest level (0.5) AND pressure decrease (0.5).
Facility Comments Answer key identifies only two correct parameters, including rate and direction cf change, while question asked for parameters.
Recommend also accepting additional responses such as feedwater flow to SGs, Tcs and key valve positions for full credit.
See attached reference.
@RC_ Resolution l
Although the Excessive Heat Transfer procedure addresses specifically the stated answer, will accept feedwater flow, temperatures and audible indications of steam rupture if so stated by candidate.
Quertion 4.10 (1.00)
If the HPI System has actuated due to a low pressure condition and is providing core cooling, what is the criteria that must be considered to secure the HPI System?
Answer 4.10 (1.00)
LPI is in operation (.33) with a flow rate greater than/ equal to 1000 gpm in each line (.33) and stable for greater than/ equal to 20 minutes (.33).
Facility Comments Answer key identifies one criteria for HPI termination.
Per specific Rule 2 in EP 1202.01, an additional criteria for HPI termination is listed which allows for termination based on steam generators capable of removing heat, adequate subcooling margin restored and pressurizer level >100".
Recommend accepting above information as a correct response.
See attached reference.
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NRC Resolution Will accept additional response if the candidate specifically states that Steam Generators are available as a heat sink and core cooling is not being provided by MU/HPI. The question specifically states the converse of the assumptions to be used by the candidates.
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SENIOR REACTOR OPERATOR EXAMINATION Question 6.06 (1.50)
When tracking conditions cause the ICS to go to track, operator control at Unit Master Station is removed.
List three OTHER (non-tracking) conditions which remove operator control at this station.
Answer 6.06 (1.50) a.
Runback in progress b.
High load limit exceeded c.
Low load limit exceeded Allow I ciedit for individual runback events Facility Comments This question asks for three OTHER (non-track) conditions which remove operator controls at this station.
No indication is given in the question that three separate runbacks would not be an acceptable response while the key states "allow one credit for individual runback events".
Recommend accepting each runback as a separate response for the three required responses.
See attached reference.
NRC Resolution Agree, answer key modified.
Question 6.07 (1.50)
The OTSG pressure transmitters are used as inputs to control the Turbine Bypass Valves or atmospheric vent valves if any of five conditions occur.
List FOUR (4) of the conditions.
(Include applicable setpoints, if any.)
Answer 6.07 (1.50) a.
Turbine trip b.
Loss of vacuum 17 iri HGA c.
Loss of cire, water <100,000 gpm (currently being jumpered) d.
OTSG pressure greater than 1025 psig e.
Less than 90*4 open MSIV (any 4
.735 pts. each) r,
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Facility Coments
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Answerkeylists"turbinetrip"asansNra.
ICS digital. logic diagran describes the turbine trip as either stop valves 1 or 2 and 3 or 4 not open, i.e., 1 and 2 or 3 and 4 closed.
Recomend accepting this answer as alternate response for full credit.
NRC Resolution Agree, answer key amended to accept as an alternative to the turbine trip.
Original examination material did not include this referenced logic diagram.
Ques tion _6.09 (1.50)
With respect to the Fire Protection System:
a.
DESCRIBE the events which automatically occur on decreasing fire header pressure under fire ~ conditions.
(Include suction sources.)
( 1.25) b.
LIST an additional source of water which can aise supply the fire header.
(0.25)
Answer 6.09 (1.50) a.
Jockey pump attempts to maintain pressure (at 135 psi) (0.25 Electric pump starts (at 120 psi) next (0.25 Diesel fire pump starts last (at 100 psi)
(0.25 Jockey and electric pumps take suction from FWST (0.25)
Diesel fire pump takes suction from intake structure (0.25) b.
Fire department pumper connection (0.25)
Facility Coments Jockey fire pump does not automatically start.
The jockey pump normally is running to maintain header pressure. The question asked for automatic occurrences on decreasing fire header pressure. Recomend incorporating 0.25 i
points for jockey pump into remainder of responses fo.- 0.3 points each.
See attached reference.
NR-: ilesolution Disagree, answer key does not state jockey pump automatically starts but attempts to maintain pressure, if candidate states jockey pump is stopped will not subtract credit.
Question 6.10 (2.50)
If the Containment Purge Ventilation System is in operation:
a.
DESCRIBE the system response if an SFAS Level 1 signal is received.
(2.0) 4 2
-.._,.,-.gn,.
n v
m
_m-r,_,.,,,,-me,--,e,.~,,n~-e.
,-r.,.
b.
DESCRIBE the difference in response, if any, if a high radiation condition is detected in the containment.
-(0,5)
(BE-SPECIFIC on which fans and dampers will be. effected.)
Answer 6.10 (2.50) a.
CTMT purge exhaust fan (1-1) stops
(. 4)
CTNT exhaust' fan suction (0.2) and discharge (0.2) dampers close CTMT exhaust filter inlet damper closes (CV 5062)_
(0.4)
CTMT purge supply fan (1-1) stops (0.4)
CTMT supply fan suction (0.2) and discharge (0.2) dampers close b.
CTMT Purge System to EVS damper (CV 5062) will open (0.5)
Facility Comments Part A:
Answer key gives 0.2 points for exhaust'ftn suction and 0.4 points for CTMT exhaust filter inlet damper (CV 5052).
These are the same damper.
Recommend point value be redistributed.
Question also did not specify if containment purge ventilation was in containment purgs mode or penetration room purge mode.
Response of the system depends on initial lineup.
Recommend accepting either answer if correctly stated per attached reference.
Part B:
Damper number that cross-connects containment purge to station EVS is CV 5041 NOT CV 5062 as listed in answer key.
Recommend accepting full credit for CV 5061.
See attached references.
NRC Resolution Agree, answer key modified.
Question 6.12 (2.50)
With respect to modifications of Makeup System:
LIST the advantage of relocating the new makeup pump suction lines to the a.
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HDI suction lines.
(1.0) b.
The new throttle valve (MU 6419) and new injection flow path could be used for two purposes.
List the two purposes.
(1.5)
Answer 6.12 (2.50)
Will allow piggyback operation of the Makeup System on the LPI pumps a.
(increases flow rate).
(1.C) b.
Bypass of MV 32 when it fails (0.75) allows emergency feed and bleed (0.75) 3
Facility Comments Part B:
Recommend accepting responses per attached reference for full' credit, concerning operating MV 6419.
Reference states open HU 6419 upon loss of subcooled margin and as an aid in pressurizer level control when flow through normal injection is not sufficient.
Comment also applies to R0 Question 2.17.
See attached reference.
NRC Resolution Partially agree, will accept either pressurizer level control or bypass MU 32; in addition, will accept open MV 6419 upon loss of subcooling margin as separate response. Answer key modified.
Examination material provided did not ir.clude referenced DB-PF-02000 but previous EP !?02.01.
Que_stion6.13 (2.50)
In 1987, a malfunction of an instrument air dryer isolation valve allowed instrument air pressure to decrease to 74 psig.
The ICS responded in auto and caused a high flux reactor trip with the core being late life. DESCRIBE how the ICS responded to thir malfunction and how a reactor trip was generated.
Answer 6.13 (2.50)
Low instrument air cr.uses LP heater drains, HP feedwater heaters, MS drain tank,1st/2nd stage tank reheat drains and feedwater heater bypass valves to open.
(or feed and steam system valves open to dump steam and condensate to condenser)
(0.5)
ICS responded by increasing feedwater flow and pulled rods out.
(0.5)
Retetor pcwer increased and reiched ICS high demand limiter setpoir.t.
(0.5)
Increased feedwater flow caused a decrease in reactor coolant Tave.
(0.5)
Moderator temperature coef ficient is most negative et EOL and t.s a result causr.d reactor power to increase which caused a high flus trip.
(0.5)
Facility _ Comments The question statra., "DESCRIBE what plant systems responded to this malfunction". The answer key only addresses LP, HP feedwater heaters and other feedwater associated concerns.
Recommend accepting any of the 17 actions for plant systems as alternate correct respo,ves per reference TAP 83-02.
Also refer to R0 Question 2.01.
See attached reference.
NRC Resolution See re solution of Questien 2.01.
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k Question 6.17 (0.75)
DESCRIBE THREE methods of overpressure prote: tion for the OHR suction piping from RCS hotleg.2-2.
Answer 6.17 (0.75)
OH-11 not be open at greater than 301 psig DH-12 not be open at greater than 301 psig Par heaters not be er.ergized if DH-11 or 12 is open and RCS pressure greater than 301 psig Relief valve (any 3 at 0.25 pts, each)
Faci _lity Comments Recommend the following two additional response to this question be' considered' for full cred!'t:
1.
Administratively, both HPI pump breakers are racked out.
2.
Thermal expansion flowpath between DH11 and DH12.
j Recommend not requiring setpoints for full credit since the numbers vary depending on the location and sensing device used.
Recommend adding to answers No. I and 2 "or will close" at specified i
setpaint.
Recommend accepting, in lieu of response No. 3 "the pressurizer heater /0H11 and DH12 interlock".
NRC Resolution Partially agree, will accept (1) above as additional answer.
Setpoints not required for full credit.
Equivalent wording is acceptable.
Recommend facility Exam Bank Question be modified per comments above.
Question 7.05 (2.25)
EXPLAIN the reasons for the following precautions from Plant Procedures:
a.
PP 1102.02:
Upon an SFRCS actuation, 00 NOT under any i
conditions, push the MS1/ resets without first depressing the CLOSE pushbutton.
(0.75) b.
PP 1102.4:
The maximum rate of power increase between 0% RTP and 20% RTP is 10%/hr.
(0.75) c.
PP 1102.10:
OH Train 1-2 must be used in the OH mode for plant cooldown while >200 F RCS temperature.
(0.75) 5
Answer 7.05 (2.25) j 1
a.
MSIV could go wide open (.375) and damage the main steam lines
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(water-hammer) (.375) b.
Prevent expansion of any fuel defects.in "water-logged" fuel pins (.375),
the steam pressure inside fuei pin will be allowed to seep back into the RCS(3.75).
(Concept) c.
When RCS > 200F at least one train must be in LPI mcde (0.375) and to provide aux. spray for RCS depressurization.
(0.375)
Facility Comments Question 7.05.c specifically asks about the UH Train 1-2 portion of Limit and Precaution 2.36 of PP 1102.10 "Plant Shutdown".
The Answer 7.15.c, however, requires the mention of the other DHR train being lined for the LPI and gives equal point weight for both parts. ~
Recommend accepting "To' provide aux. spray for RCS depressurization" as the fully correct answer.
NRC Resolution Disagree, precaution in procedure states to meet these requirement (tech specs) and to provide aux spray for RCS depressurization, OH Train 1-2 must be used.
Question 7.07 (2.25)
A serious control room fire is occurring, STATE the actions which should be completed in the control room prior to evacuation.
(Do not include obtaining keys or where to report).
Answer 7.07 (2.25)
Trip the reactor Trip the turbine Isolate letdown (with MV 28)
Close PORV block valve (RC 11)
Open Pzr steam sample (RC 239A)
Start the second makeup pump Shift the second makeup pump i
Shift makeup pump suction (MU 3971) to BWST Manually actuate SFRCS on HIGH SG level i
Trip all source breakers to A and B buses (9 at 0.25 pts each)
Facility Comments Answer 7.07 lists as one action:
"Manually actuate SFRCS on High SG Level".
This capability was removed with the redesign of the SFRCS System.
In order to accomplish this now, two manual actuation switches must be depressed, labeled, "Initiate AFPT 1-1 (1-2) and Isolate SG 1-1 (1-2)".
6 i
,,,y---------,
r, -, - -,
,,,v,,.--
...-~--.---,,-y mm,--_nn-,._,.,
em,,,,-,--,-g e.---,,
r---
ee.,-
-,_.,_,---o.v,-
A Recommend accepting this response as an alternate acceptable response due to l
the candidates being trained on the new system. See attached reference.
3 NRC Resolution
~
Agree, answer Ley modified to accept the new reference material to initiate AFPT and Isoir.te SG.
Facility must change reference AE 1203.26 to require proper actions of the operators.
Question 7.g (0.75)
LIST the physical steps requires to remove and block the Low Steam Pressure Trip for Channel 1 at the cabinet only.
Artswer 7.09 (0.75) i For Channel 1:
l (0.25) f 1.
Press and hold INITIAL BYPASS (3-14) button 2.
Press BLOCK (S-7) push button (0.25) 3.
Release both (S-7 & S-14) buttons (0.25)
Facility Comments Question 7.09 refers to removal and block of the Low Steam Pressure Trip for Channel 1 SFRCS at the cabinet.
This capability has been removed by the SFRCS redesign. This was a major change identified and trained on early in the candidates' training program.
Recomtr.und deleting Question 7.09 because the equipment mentioned on longer, exists.
See attached reference.
NRC Resolution i
Agree, question deleted.
Reference SP 1105.16 must be changed to reflect actual plant conditions.
guestion 7.12 (3.00)
If control rods fail to de-energize in response to the RPS trip and manual trip, STATE the required action per Emergency Procedure EP 1202.01.
(Include all substeps 4f applicable).
Answer 7.12 (3.00)
T 1.
Attempt to maintain pri'to see heat transfer balance (0.2) a.
If MFW has run back below rea: tor power, manually control MFW to match reactor power.
(0.2) b.
If MFW is lost, ' initiate AN by tripping SFRCS on low SG 1evel using both SG 1evel low trip buttons.
(0.4) (logic 0.1) 7 1
4 I
i 8
2.
Attempt to manually de-energiza the CR0s in order below (0,1): _
a.
Momentarily de-energize 480V unit subs E2 and F2 simultaneously (0.3) (logic 0.1) b.
Manually trip three reactor trip breakers in low voltage switchgear room.
(0.3) c.
Manually de-energize the CR0 System by tripping BE211 on liq and BF211 on F2.
(0.3)(0.1 logic) 3.
Attempt to m'anually shutdown the rea'ctor:
a.
Manually drive. control rods in.
(0.2) b.
Begin emergency boration (0.1) by shifting MU pump suction to the i
BWST (0.1), initiate max. MU and letdown (0.?), shift letdown i
3-way valve to.CWRT (0.1).
facilityComments Answer 7.12.1.b requi,res the Reacitor Operator to manually initiate SFRCS on lo
~
SC Level. This capability no longer exists and is replaced by depressing two manual actuation pushbuttons labeled "Initiate AFPT 1-1 (1-2)".
Recommend accepting this action as an alternative response for full credit.
Answer 7.12.c requires the Reactor Operator to manua11y shift MU pump suction to the BWST.
The makeup System modifications resulting in enhanced feed and bleed provides separate suction three-way valves for each MU pump and 08-PF-02000, Revision 0 (EP 1202.01) reflects these changes.
Recommend accepting the wording from OB-PF-02000, Revision 0, Step 3.2, as an alternative response for full credit.
See attached reference.
NRC Resolution Agree, answer key modified to accept DB-PF-2000 as correct response.
Exam materials provided did not include facility reference DB-PF-02000 but previous EP 1202.01.
Questien 7.13 (2.25)
Per SPECIFIC RULE 2 of Emergency Procedure EP 1202.01. LIST the three times MU i
or HPI MUST throttled.
(List setpoints, if applicable.)
)
Answer 7.13 (2.25) 1.
M0/HPI must be throttled to prevent exceeding max. RCS pressure /tenperature for cooldown limit.
(0.75) 2.
HPI must be throttled, during piggyback operation, to limit HPI pump flow <950 gpm per pump.
(0.75) 3.
MU must be throttled to maintain pump discharge pressure >1500 psig and motor current <57 amps.
(0.75) 8
c
+
Facility Comments Makeup System modifications perfor: red during the 5th Refueling Outage provided new suction piping for the makeup pumps, allowing "piggyback, operation" from the discharge of the LPI pumps. As a result, the minimum dis; barge pressure for the makeup pumps is 1700 psig, as per DB-PF-2000, Revision 0 (EP 1202.01). Also maximum running current for the makeup psmp is 68 amps, as per OB-PF-02000, Revision 0.
Recommend accepting as an alternate correct response:
1700 psig and 68 amps as the MV pump throttling criteria in accordance with DB-PF-02000, Revision 0 (EP 1202.01).
See attached reference.-
NRC Resolution Agree, answer key modified to 1700 psig and 68 amps as correct response.
Exam materials provided did not include reference DB-PF-02000.
Question 8.02 (1.00) a.
WHAT is meant by the term "Verification"?
(0.5) b.
WHAT is meant by the term "Independent Verification"? (0.5)
Answer 8.02 (1.00)
When authorized personnel independently (0,1) perform the desired lineup a.
following the prescribed methods of positioning (0.1), checking (0.1) and then tagging (0.1) the device, component or system (.10).
b.
This means that each person (0.1) shall actually perform one of the methods and should not be in the area of the component (0.1) when the.
other individual is present to perform his portion of the inde. pendent verification (0.3).
(similar wording acceptable)
Facility Comments Answer key identifies 0.1 points for statement "when authorized personnel independently.
Identified reference rnaterial does not support this statement.
Recommend re-assigning this point value throughout emainder of the question.
See attached references.
NRC Resolution Disagree. Qualified or authorized operator (either is acceptable) is required to tag system per precedure ( ADM-SRO-005.02, P. 8).
9
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Questio'n 8.03 (1.50)
During emergene.y conditions, such as fire in the Control Room,
, !!0 CFR '50.54 x allows ' operators to deviate from license ::enditions or Technical Specifications.
a.
Two conditions must be satisfied before the deviation can be authorized.
BRIEFLY STATE these TWO conditions.
(1.0) b.
Such a deviation shall be approved, as a minimum, by what individual (s)
(no titles are required)?
(0,5)
Answer 8.03 (1.50) a.
1.
The deviation is needed to protect the health and safety of the public.
(0.5) 2.
No action, consistent with licensed requirements, that can provide
' adequate or equivalent protection is immediately apparent.
(similar wording acceptable)
(0.5) b.
A licensed SRO.
(one half credit liven for a titled position, such as i
Shift Engineer)
(0.5).
FacliityComments Answer key for Part b indicates half credit for title.
Recommend giving full 1
credit for the positions of Shift Supervisor and Assistant Shift Superd sor since they are.the itcansed Senior Reactor Operators responsible for directing shift operations.
See attached reference.
NRC Resolution Agree, answer key modified.
Question 8.05 (2.00)
LIST the actions required by the Shift Supervisor to clear a tag out in ths absence of the person listed on the clearance.
(Person holding clearance can not be contacted and the piece of equipment is needed to protect the safety of 1
the public.)
Answer 8.05 (2.00)
Shift Superv nor (SS) shall personally inspect the system or components (0.5) and verify tha'. the removal of the tags will not endanger personnel or damage equipment (0.5).
1 SS shall contact the person's immediate sapervisor or next level of supervision to deternine status of work (0.25) and get permission to remove the tags (0.25).
The supervisor so contacted will be noted un the RED TAG Clearance sheet (0.5).
10
a Facility Comments
~
Answer key indicates the Shift Supervisor must contact the individual's immediate supervisor or the next level of supervision.
The Safety Tagging Administrative Procedure contai.ns a caution step that states if the Shift Supervisor cannot contact the above listed individuals, he may assume responsibility for authorizing tag removal on his cognizance, t
Recommend accepting similar wording in addition tc c)ntacting 1ndividucl's' imrrediate supervisor or next level of supervision for permissiori to remove tags.
See attached reference.
NRC Resolution Partially agree, will accept response as additional answer if candidata l
specifies when this would be dorie.
Question 8.12 (4.50)
CLASSIFY the following per Emergency Plan (EP-1500) supplied:
a.
Containment Pressure 17.0 psia and increasing Makeup tank level decreasing at 3 in/ min RCS E-bar 2.5 MEV RCS samples:
0.3 uc/cc DE i-131 25.0 ue/cc gross activity RE 600/609:
500 cpm and incres. sing SFRCS initiated on 600 psi in steam lines b.
Report of chlorine leak to atmosphere onsite.
4 I
Report from security that an anti-nuclear group is picketing at the front gate.
Forebay level alarm with lake lovel at 562.0 feet.
Station computer is lost.
RCS inventory balance shows 10 gpm leakage.
c.
Containment temperatures:
TI1256=198F, TI2357=207F, TI1358=199F Containment pressures:
PI2000=0 PSIA, P!2001= 19. PSIA,PI2002= 18.9 PSIA,PI2003= 18.7 PSIA RE4597AB 10 uci/cc at time of shutdown RE4596A 50 R/hr at time of shutdown (Consider a, b, and c separately.
In answer give minimum classification which may be given and reference section of EP-1500.)
j Answer 8.12 (4.50) a.
Alert (1.0), 5 A.2 (0.5) b.
SAE (1.0), 8.D.2 (0.5) c.
SAE (1.0), 1.F.2 (0.5) 11
.--=w,-
y
.------ey,.,-,,-w.,w-.
-.--.a,w----=----,-me.-..,,,.,-.-,.,.,,,.wm.-_.,_--,-...._,--mm,.mwem,,,,r_.py-,m.-.,,,-.
y,.
w.,_c, r,m 4
+
~
[.
p Faciltity Comments
-..._~. -
The answer key for Part a classifies the event as an Alert based on Section 5 A.2 of EP-1500.
The event can also be classified as an Alert based on Section 2.A.2 of EP-1500.
Recommend considering either response for full credit.
See attached reference.
The answer key for Part b classifies the event as a Site Area Emargency based on Section 8.0.2 of EP-1500.
The applicable section of EP-1500 used to classify this event as a Site Area Emergency is 8.0.3, not 8.0.2.
Recommend accepting Site Area Emergency based on Section 8.0.3 as the correct response.
NRC Resolution Agree, answer key modified.
Question 8.13 (3.00)
An accident has occurred. The plant has been shutdown for 20 minuter with AFW feeding OTSGs and no MSSV or AVV stuck open.
Using attached EP 2240 (EP 2240-att.3) and the following data, CALCULATE the STABILITY CLASS and DOSE RATES (three required) at the site boundary (3.00).
(Show all work) 1.
Wind 6 mph from NE 2.
CTRM outside temperature gauge "35ft" 80.4F-3.
CTRM outside temperature gauge "250ft" 85.2F 4.
Flow Rate-Unit Vent 90000 cfm 5.
RE 600/609 (GROSS MODE) 4300 cpm.
6.
RE 4538 Channel 1 1x10-2 uti/cc 7.
RE 4598 Channel 3 8x10-4 uti/cc Answer _8.13 (3.00)
STABILITY CLASS 85.2-80.4=4.8F lower delta T or class G (0.5)
X/Q 4x10-4 (0.25)
AFW (4300-300)x10-5= 4.0x10-2 uc/cc (0.25) 8x10-3 ci/sec (0.25) 1 mr/hr (0.25)
Noble Gas 4.5x10-1 ci/sec (0.25) 80 mr/hr (0.25)
Child Thyroid (10 x 8x10-4= 8x10-3 to fit on scale) 10x gives 4x10-1 ci/ sac (0.25) 10x 60 mr/hr (0.25) actual 6 mr/hr 7000 x 6 mr/hr-42 rem /hr (0.50)
(Reasonable tolerances accepted.)
12
9 Facility Con. ents 4
Answer key giv6' dose rates at the site boundary in mr/hr. The nomagrams used in the CTRM have Neen revised and give dose rates in R/hr..The nomagram given on the exam was ve. < hard to read, which made it difficult to determine.if the dose rates at the si e boundary were in mr/hr or R/hr.
Based on this, recommend accepting fs-full credit the units of mr/hr or R/hr for dose rates -
at the site boundary.
'ee attached reference.
NRC Resolution P
Agree, will accept R/hr if c.,didate is consistent throughout answer.
Revised nomagraphs were not included il examination material provided.
9 l
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MASTER COPY tiUCLEAR REGULATORY COMMISSION U.
S.
SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY' D62.[hEESSE__._ _ ___
REACTOR TYPE:
6.8_Z03/29 EXAMINER:
SHE E6BIh_Dt___
CANDIDATE I?!5IBUCTIONS TO C6NDID6IEL Use separate paper for the answers.
Write answers on one side only.
.heet on top of the answer sheets.
Points for each Stap]e question quertion are indicated in parentheses af ter the question.
The passing crr.de requires et 1+ast 70%.in each category end a final grade of at least 801.
Exaninution papers will be picked up six (6) hourr. after the examination starts.
L OF CATEG0hY
% OF CANDIDATE'S CATEGORY
_ _Ye MIE _._TOI6 L
.. 0.C0E5_.__
._Y 6 LU E_.. _ _ ___ __._.._ _ C AIEG 0BL_ _.____.______
i 07.00 B. ll
___.____ 5.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS,AND THERMODYNAMICS
_f>l 04.._ _ab.17 6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSThUMEt;TATION N :^'
24.4A 7.
PROCEDURES - NORMAL, APNORt!A L,
EMEhGENCY AND RADIOLOGICAL CONTROL 37.00
_.E' E. ull
__________ 8.
ADMINISTRATIVE FROCEDUhES, CONDITIONS, AND LIMITATIONS
_1.0L.2 5.
Totals Final Grade All work done on this exaninstion is my own.
I have neither viven nor received aid.
Candicate'a Sienature i
. ws i a_. i \\.
ss
NRC RULES AND GUIDELINES FOR LICENSE EXAMI!1ATIONS Juring the administration of this examination the following rules apply:
Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
I Restroom trips are to be limited and only one candidate at a time may leave.
You must avoid all contacts with anyone cutside the examination room to avoid even the appearance or possibility of cheating.
4 Use blach ink or dark pencil only to facilitate legible reproductions.
)).
Print your name in the blank provided on the cover sheet of the exanination.
).
Fill in the date.on the cover sheet of the examination (if necessary).
3.
Use only the paper provided for an.wwers.
I Print your name in the upper right-hand corner of the first page of each section of the answer cheet.
3.
Consecutively number each answer sheet, write "End of Category _.." as appropriate, start each category on a new page, write cnly on one side of the paper, and write Last Page" on the last answer sheet.
).
Number each answer as to category and number, for example, 1.4, 6.3.
l
'. U. Skip at'least three lines between each answer.
- 11. Separate cnewer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. 1.'se abbreviations only if they are commonly used in facility literature.
L3. The point value for each quection is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
'l4.
Show all calculations, methods, or assumptions used to obtain an answer to mathemstical problems whether indicated in the question or not.
- 1 fi. Partial credit may be given.
Therefore, ANS'n'ER ALL PARTS OF THE QUESTI0t1 AND DO NOT LEAVE ANY ANS'n'ER E. LATE.
.16.
If parts of the examination are not clear as to intent, a.ek questione of the examiner only.
- 17. You must sign the statement on the cover sheet that indicates that the work ic your own and yvu have not received or been given assistance in completing the examination.
Thie must be done after the examination has
{
been completed, i
]
- 18. When you complete your examination, you shall:
a.
Auremble your examinat!.on as follows:
(1)
Exam questions on top.
(2)
Exam aids - figures, tables, etc.
(3)
Answer pages including figures which are part of the answer.
b.
Turn in your copy of the examination an) all pages used to answer the examination questions.
c.
Turn in all scrap paper and the balance-of the paper that you did not use for answering the questions, d.
Leave the examination area, as defined by the examiner.
If after leaving, you are found in this area while the exanination is still l
in progress, your license may be denied or revoked.
l 1
l h
l l
l 1,
j
Em__IHE081_DE_UUCLE68_ E0HEB_EL8BI_OEEBall0Nt Page 2
ELUIDS16BD_IBEEMODYUAdlGS l
l GUESTIOt1 5.01 (1.50)
TRUE or FALSE Answer'the following TRUE or FALSE with respect to Axial Power Shaping Rods (APGR) used to dampen Xenon oscillations.
a) If APSR are moved, it will take 6 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to determine if APSR are moved in wrong direction.
(0,5) b) APSR position of 40% withdrawal is allowed during all times in nore cycle 5.
(0,5) c) APS" move of 4% withdrawal usually takes care of a 1.5%
imbalance.
(0.5)
QUESTI0t1 5.02 (2.00)
STATE if water would be SUBC00 LED, SATURATED, or SUPERHEATED (by how many degrees,where applicable) for the conditions below:
a.
2150 psig and 604 F b.
28"Hg vacuum and 90 F c.
895 psig and b60 F d.
2165 psig and 646 F QUESTION 5.03 (1.50)
STATE how the following paraneters:
- 1. RCS pressure,
- 2. RCS average temperature,
- 3. P.CS powor; are affected by a group 5 rod drop from the following initial conditions:
a) Reactor startup with the reactor critical at 10-3 amps.(0.75) b) Reactor startup with the reactor critical at 3% power range centrolling on turbine bypass valves.(0.75)
(Cencider each situation independently,etate It1 CREASE, DECREASE, or REMAlti THE SAME for initial change only,no explanation required.)
(+'***
CATEGORY 5 CONTI11UED 0:1 NEXT PAGE * * * * * )
F __ISEQ8Y_QE_HURLEAE_EQWEB_ELAUT OPEE6110Nt Page 3
ELUlphot!P THEBdQDYH6 dig.3 QUESTION 5.04 (1.50)
After a run at 100% power for 55 days, the reactor trips. Twelve (12) hours after the trip with the reactor shutdown, the RO informs you that the source range indication is slowly increasing.
EXPLAIN WHY cr WHY NOT thic increase is expected.
(1.50)
QUESTION 5.05 (1.50)
Analysis of various accidents has been performed and presented in the USAR (Updated Safety Analysis Report).
Briefly EXFLAIN for each of the following accidents:
a) Control Rod Assembly Drop at power. (0.90) b) Loss of a last stage Feedwater Heater (steam supply) at power.
(0.60) the TIME OF LIFE (BOL.MOL,EOL) which causes the most severe consequences.
QUESTION 5.06 (2.50)
After a reactor trip from a 20 day run at 100% at BOL, STATE the effect of the following on SHUTDOWN MARGIN:
a) Borating 100 ppm.
(0,5) b) Driving APSR frnn 40%(WD) to 0%(WD).
(0.5) c) Cooling down from no load Tavg to 280 F.
(0,5) d) Withdrawing groupe 1-4 rods.
(0.5) e) Waiting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
(0.5)
(Consider each situation independently, limit answer to INCREASE, DECREASE, or SAME SHUTDOWN MARGIN.)
(+****
CATEGORY 5 CONTINUED ON NEXT PAGE *****)
2x__IBE0BY_9E_LUCLE68_EDEEB_ELANT OPE 88IlO61 Page 4
ELUIDSt88R_IBEBUQDYBAd1CS 1
QUESTION 5.07 (1.50)
STATE how the fu1]owing situations would effect the ACTUAL critical position vs. PREDICTED critical position of 50% on group 7:
a) Turbine bypass valve setpoint raised 20 psi above normal value.
(0.5) b) An inadverent dilution of 10 ppm occurs.
(0.5) t) Delay of 8 hourc prior to commence startup.
(0,5)
Assume ntartup after maintenance shutdown of 30 days from 100% power at middle of life.
(Consider each condition independently, limit answer to ACTUAL HIGHER,
& OWE 5 or SAME position as PREDICTED rod position,no explanation required. )
s CS: I JN t,98 (2.00)
Arlarst.o Nuclear Unit-1 a control rod was found to be 90 inches t reher int,6 the core than its rod group f >r la days.
The rod was w thdravn tv align it with the rest of the group within one hour while i
lb-plant operated at full power.
Fuel damage resulted from this incident.
Why is fuel dansge likely to occur in such a situation?
OUELTION 5 09 (2.00) ror each of the following conditions, STATE whether natural circulation can bi VERIFIED or NOT VERIFIED from the given indications:
a.
Unit Tavg DECREASING.
(0.6) b.
Thermocouples slightly INCREASING with time.
(0.5)
- c. OTSG startup level remaining CONSTANT with no feed.
(0.5) d.
OTSG rressure CONSTANT with loop T cold DECREAGING rapidly.
(0.5)
Anume react or 1 r. chutdown with no RCP's running.No explanation required.
Considar each condition separately.
(*****
CATEGORY 6 CON'lT.NnED ON NEXT PAGE *****)
e L.
THEQBY_9E_NUCLEAB_EDEER_ELSEI_DEEBAIION.
Page 5
ELUIDE; 6SD_IMEBMODYUbtilGS QUESTION 5.10 (1.50)
Some plants have to limit their power '.evel due to high OTSG levels.
a.
What causes the OTSG level to increase over core life for the same power level?
(0.9) b.
LIST the three heat transfer areas in OTSG tube area.
(0,0)
QUESTION 5.11 (1.50) 1he OTSGs operato in the bulk boiling heat transfer region and the reactor core must remain in the nucleate boiling heat transfer region.
EXFLAIN the DIFFERENCES between the OTSG and the Reactor Core which allow the OTSGu to operato in bulk boiling region and not allow the Reactor Core
]
to operate in the bulk boiling region.
(1.5)
QUESTION 5.12 (1.00)
TRUE OR FALSE The following are all indicationn that the reactor 4.s critical in the source rance after rod motion staps:
- a. Stortup r.ste is a po.d tive, constant value; b.
Log power remains constant at critical level; AND c.
No reactivity insertion.
(Only one answer desired).
QUED170N 5.13 (1.50)
Indicate which of the following are TRUE and which are FALSE INDICATIONS that the point of adding heat (FOAH) hos been reached.
[ Assume normal plant operation, appropriate systems in automatic.]
a.
SUR decreases (0,5) b.
Pressuriser level decreases (0.6) a Turbine bypara controller ntot4on output decrenees.
(6.5)
(*****
CATEGORY 5 CONTINUED ON NEXT PAGE *****)
L.__IBE0BLOE_.M!)RLE6B_EQHEB_EL6HLGEEBallQilt Page 6
EL!!11LotJILIBEMQDlt!6MLG5 QUESTI0t1 5.14 (2.00)
During power operation at 40% with three Reactor Coolant Pumps (RCP) in operation, the fourth RCP (loep 1) is started.
Assume ICS is in automatic.
Discuss how the below parameters will change during the transient:
a.
Feed flow OTSG 1-1 (0.40) b.
Feed flow OTSG 2-1 (0.40) c.
OTbG 1-1 level (0.40) d.
OTL'O 3-1 level (0.40) e.
RCS delta Tc (0.40)
' QUESTI0?1 5.15 (1.50)
Explain how insufficient flow through a centrifueal pump (e.g.,
isolation valve chuts with no recirculation flow) can cause damage to the pump componente. [i 5)
OtJESTIOli 5.16 (2.00)
Indicate whether each of the fo2]owing will cause the differential rod worth to ItiCHEASE, DECREASE or have tio EFFECT.
a)
An adaacent rod is withdrawn.
b)
Moderator temperature is DECREASED.
c)
Boron concentration is It1 CREASED, di A Burneblo Poison Rod depletes.
(Conc $ der each condition separatel/.)
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(*****
EtiD OF CATEGORY 5 *****)
E1__EL AB I_ SYSIE U E _ DE E10 b2_ RQHIB0ls _AU D_18EIBUd E N T AT I ON Page 7
QUES 110N 6.01 (1.00)
In January, 1987; Containment Air Cooler 1-2 Service Water Outlet Valve, SW 1357 was erroneoucly declared inor rable due to work on the portion of valve which modulates flow based on containment temperature. This portion
}
of the valve is non-safety related.
LIST the TWO safety related fetione performed by SW 1357.
l QUESTION 6.02 (1.00) l l
In January, 1987; the SFAS channel I containnent radiation trip m>dule was bypassed while performing post maintenance testing of Channe1 1 Containment Radiation Level Detector (RE 2004).
- a. What keys are required to bypass the radiation trip module?
(0.6)
- b. What would be the trip logic when channel 1 trip module wao bypassed?
(0.4)
QUESTION 6.03 (2.25)
In March. 1987; a maintenance contractor bunped the local control switch for SG #2 Me'.n Feedwater Stop Valve (FW 601) which went fully closed with reactor power at 92%.
A Main Steam Safecy Valve (MSSV) lifted.
DESCRIBE the transient which caused the MSSV to lift and final equilibrium ttatus.
(Include in description the status of Reactor, Turbine, OT3G and Feedwater no setpoints required).
QUEST 1UN 6.04 (1.00)
While 300% power with 4 RCF's operating, DESCRIEE the effect of the following on ICS: (Include in answer EFFECT or NO EFFECT and reason) a.
EC flew rate loop 1 input to ICS fails to O mlb/hr.
(u.61 b.
Selected operate level OTSG2 input to ICS fails t.o 01 (0,5)
(Concider each case sepa13tely )
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AL._ _P L o t!I_EYS T EMS _DE S10 th-.00HIB9L.i._6H D_IE SIB!J U E t!IAI1QB Page 8
QUESTION 6.05 (1.50)
If Loop 1 Feedwater Valve delta pressure input to ICS fails to O psid at 100% power.
DESCRIBE the feedwater transient including initial and final status of feodwater pumps and valves. (No setpoints required).
QUESTION 6.0G (1.50)
When tracking conditions cause the ICS to go to track, operator control at Unit Master Stat. ion is removed.
List three OTHER (non-tracking) conditionc which remove operator control at this station.
QUESTION 6.07 (1.50)
I The OTSG pressure transmitters are used as inputs to control the Turbine Pypass Valves or atmospheric vent valves if any of five conditions occur.
List FOUR (4) of the conditions. (Include applicable setpoints,1f any.)
QUESTION 6.08 (1.00)
As reactor pouer is increased source range volts turned off automatically. List all the circuit interlocks which will result in the automatic de-energi:ation of the Source Range detectors? (1,0) t QUESTION 6.09 (1.50)
With respect to the Fire Protection System:
a.
DESCRIBE the events which autoniatically occur on decreasing fire 3
header pressure under fire conditions. (Include suction sources).
i (1.25) b.
LIST an additional source of water which can also supply the 1
fire header.
(U.25) 4 l
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QUESTION 6.10 (2.50)
If the Containment Purge 7entilation System is in operation; a.
DESCRIBE the system response if a SiAS level 1 signal is received.
(2.0) b.
DESCRIBE the di:ference in response,1f any, if a high radiation condition is detect *d in the containment.
(0.5)
(BE SFECIFIC on which fans and dampers will be effected.)
1 QUESTION 6.11 (2.00)
DESCRIBE the response of the Component Cooling Water System for the following:
i
- a. High containment pressure of 16.4 psia.
(1.0) b.
High hich containment pressure of 38.4 psia.
(1.0)
(BE SPECIFIC with valve names or numbers).
QUESTION 6.12 (2.50)
With respect to modifications of Makeup System.
a.
LIST the advantage of reloca+ 1ns the new makeup pump suction lines to the HPI suction lines.
(1.0)
- b. The new throttle valve (MU 6419) and new injection flow path could be used for two purposes. LIST the two purposes.
(1.5)
QUESTION 6.13 (2,70)
LIST 6 process monitors which when receiving a high alarm, actuates to perform interlock or control functions.
(Function not required, list number of monitor or general name.one train only).
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.... ~. _ -._.__._ _ _.. _. _, _, _ _ _,. _ _. _ _ _, _,.. _..,...._ _....,_,,_
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SL_ELANLEYSIEdeE81GtLJAMIBOL,.. AND_lt!BIBUdEUI6ILOS Page 10
- QUESTION 6.14 (2.50)
In 1987,a malfunction of an instrument air dryer isolation valve allowed Instrument Air pressure to decrease to 74 psig.
The ICS responded in auto and caused a high flux reactor tr$p with the core being late in life.
DESCRIBE how the ICS rerponded to this malfunction and how a reactor trip was generated, l
iQUESTION 6.15 (1.00)
DESCRIBE in general the response of the primary system after a turbine high vibration trip to o FAILED OPEN Second Stage Reheat Steam Source Valve (MS 199) to the #1 Moisture Separator Reheater with its downstream pressure control valve open and in manual.
4 QUESTION 6.16 (0.80)
DESCRIBE the TWO means of establishinF long term boron dilution post-LOCA.
(Flowpaths only).
I lCUESTION 6.17 (0.75) i DESCRIBE THREE (3) methods of overpressure protection for the DHR suction piping from RCS hotleg 2-2 i
(*****
END OF CATEGORY E. *****)
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Zu__2B0gEDUES3_:_NDBU8Lt_6ENQBBAL1_EMEE9ENGX Page il AND_E6D19LQGIGAL_G9EIh0L
)
QUESTION 7.01 (1.00)
A precaution in CRD Operating Procedure (SP 1105.09) states any control rod not known to be free running,1.e., sucpacted of being mechanically bound, shall be operated only in run speed,except for latching.
STATE the purpose of this procaution (include component protected and why use run speed).
4
!GUESTION 7.02 (1.50)
STATE for each of tne following indications (required to be monitored shiftly), whether the Shift Supervisor should be NOTIFIED immediately or NOT NOTIFIED immediately since it is a normal condition:
a.
Victoreen CTRM module-green "FAIL" light is on.
(0,5) b.
"RI C' (Kaman Sciences)- white "FAIL" light is on.
(0.5) c.
PR-2C (General Atomics)- white "Operate" light is off.(0,5)
(Consider each si tuation independently, no explanation required).
J
! QUESTION 7.03 (1.50)
Certain primary valves (i.e.,MU-1A.MU-1B.MU-2B RC-10 and RC-11) have wedges that may stick in their seats if closed when they are hot l
and then cooled dcun. LESCRIBE the r; tern which must be perforned to prevent separStion of the wedge from the valve stem if valve is closed hot and cooled down and later opened. (Include all options.)
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7.
EBOCEDUBEE_:_UGEMAbi_68UQBUaL&_EMEBGENDY Page 12 AUD_ BAD 19k9GIGAL_RQUTBQL QUESTION 7.04 (2.00)
TRUE or FALSE STATE whether the following statements are TRUE or FALSE with respect. to Approach to Criticality (PP1103.08):
a.
If critica'ity is established after the lower rod index and before the upper rod index limits are reached, insert all regulating control rode and resolve the problem before continuing the startup.
(1.0)
- b. When criticality is establict*d, raise reactor power to 10-8 amps en IR NI and using control rods bring reactor to a stable
. condition such that power is constant. In RO log, enter the following information: time. control rod group positions, RCS boren concentration, IR NI power indication and EFPD.
(1,0)
(Consider each separately.)
QUESTION 7.05 (1.00)
When usAng a DH pump for decay heat removal.
DESCRIEE the effect of vortex formation at th~ RC3 Hot Le.t in the DH suction line on DH flow.
(1.0)
QUESTION 7.06 (2.25)
A serious control room fire is occuring. STATE the actions which should be comploted in the control room prior to evacuation. (Do Not include obtaining keys or where to report).
(2.25)
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I.
EBQCEDUEEE_ _HOBUAL2_A8t0BMALt_EMEBGENGY Page 23 l
AUD_ BAD 19LO91 GAL _CQUISQL QUESTION 7.07 (2.50)
Per Reactor Coolant Pump and Motor Abnormal Procedure (AB 1203.21) answer the following:
single seal stage is <100 psi or > 1400 psi, DESCRIBE how the pressure drop for each seal is calculated.
(0.75) b.
STATE the pres ore drops acroce the three RCP seals that would be expected if 2nd. stage seal fai)s.
(0.75) c.
The component cooling flow is loct to all RCPs, DESCRIBE all the actiono rc: quired if operating at 100% power (include naximum time lim'.ts,1f any).
(1.00)
CUESTION 7.06 (0.00)
QUESTION LELETED lOUESTION 7.09 (1.00)
At 56% power, the fourth RCP is started. The SS improperly orders an immediata increase of power to 100%, prior to reaching 100% power, a High Flux reactor trip occurs.
a.
EXFLAIN WHY the reactor tripred prior to 100%.
(0.6)
- b. What technical specification action (s) taken prior to increasing power past 564 would have prevented the reactor trip?
(0.5)
(Getroints not required.)
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' It RBQCEDUEES-HOEdakt_8buGBdAkt_EUEBEEUGY Page 14 ABD_B6D10LQ9196L_GRUIBQL
, QUESTION 7.10 (2.00)
According to Emergency Procedure EP 1202.01 RPS,SFAS,SFRCS Trip, or SG i
Tube Rupture SPECIFIC RULE 4,what are two (2) methods to reactivate SFAS equipment that has been blocked and overridden after an SFAS trip.(2.00) f QUESTION 7.11 (3.00)
T' ventrol rods fai) to de-energine in responce to the RPS trip and Manual I
trip, STATE the required action per F"ergency Procedure EP 1202.01. (3.00)
]
(Include all substeps if applicable.)
QUESTION 7.12 (2.25) a Per SPECIFIC EULE 2 of Emergency Procedure EP 1202.01, LIST the three (3) times MU or HPI MUST be throttled.(List setpoints, if applicable.)
(2.25)
OUEST10N 7.13 (2.25) l>uring refueling in the containment, a failrie of the seal ring around the reactor vessel flange necure.
STATE the immedista actions required to be performed.
(Assume no Fuel Assembly (FA) in refueling canni racks, in the I
mast using Fuel Storage Bridge, or in transfer mechanism;however, a spent FA is in the mast using the Main Fuel Handling Bridge)
(2.25) l l
QUESTION 7.14 (1.75)
While touring the Auxiliary Building, an Equipment operator spots a bottle marked RADIOACTIVE MATERIAL which has just tipped over and is spilling into the pssaageway. IiESCRIDE the actions he should take for this Radioactive Spill.
(1.76) i l
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Zu__EEOGEDUEES - 808 dol 1_AEHOBddLt_EMEBGENCY Page 15 ASD_BARIQLQG298L_G9BIBRL QUESTION 7.15 (2.25)
EXPLAIN the reasons for the following precautions from Plant Procedures:
- a. FP1102.02: Upon an GFRCS actuation,DO NOT under any conditions, push the MSIV resets without first depressing the CLOSE pushbutton.
(0.75)
- b. PP1100.04: The naximum rate of power increase between 0%RTP and 20%RTP is 10%/hr.
(0.75)
- c. PP1102.10: DH train 1-2 must be used in the DH mode for plant cooldown while >200 F RCS temperature.
(0.75) d i
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END OF CATEJORY 7 ****")
E.
6DUIUlGIB6IlYE_EBQ9EDLIBEEz_GOEDlIIONEA Page 16 6BD_LidlI&IIRES l
QUESTION 8.01 (1.50)
Mhat Tech Spec actions (including maximum time limits,1f any) should be taken by the.startup reactor operator if during a reactor startup NI-1 fails low?
Prior to the failure, channels had been increasing with the exception of NI-2 which had been holding constant at 3x E+3 cpm. At the time of the failure, the channels read:
NI-1 Ex E+5 cpm NI-2 3x E+3 cpm N1-3 6x E-10 amps s
N1-4 1x E-10 amps JUSTIFY YOUR ANSWER.
QUESTION 8.02 (1.00) a.
WHAT is meant by the term Verification?
(0.5) b.
WHAT is meant by the term Independent Verification?
(0.5)
QUESTION 8.03 (1.50)
During Emergency Conditions, such as a fire in the Control Room, 10CFR 50.t4 x allnws oporatore to deviate from license conditions or Technical Srecifications, s.
Two conditions must be satisfied before the deviation can be authoriced.
BRIEFLY STATE these TWO conditions.
(1.0) b.
Such a deviation shall be approved, as a minimur, by what individual (s)
(no titlet are required) 7 (0.h)
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6 __4DM1HIDIB3IlYE_EBOGEf9EES._GOND1IIONS.
Page 17 680_LIMLIAIl0Us QUESTION 6.04 (1.0U)
Davis Besse Emergency Plan provides guidance on worker radiation exposure during an Emergency :
- a. STATE the allowed dose limit for 31fesaving actions.
(0,5)
- b. A Shift Foreman volunteerc to enter a HIGH RADIATION area during an emergency to search for missing personnel. His reason is that five years aro he entered the sane area under similiar circumstances and feels cor.fident eibout what is needed. He recieved 90% of the Emergency Dose Limit during the previous event. Radiation Protection estimates a whole body enocure of 80% of the limit for the current planned entry.EXFLAIN whether this individual can be allowed to enter?
(0.5)
QUESTION 8.05 (2.00)
LIST the actions required by the Shift Supervisor to clear a tag out in the obsence of 2e person listed en the Clearance. (Person holding clearance can not be contacted and the piece of equipment is needed to protect the cafety of the public.)
(2.00)-
1
- QUE5 TION 8.06 (1.00) 1 TRUE or FALSE I
Fer Technical Specifications in the event any paraneter exceeds ite Liniting Safety Syclem Setting (LSSS) without a RPS trip, an immediate (within 3 minutes) Eeactor Trip is required, jQUESTION 6.07 (2.00)
Using attachment of a Gaseous Release Permit, REVIEW the form at Shift Supervisor and LIST the errore in the form.
(P 00)
QUESTION 8.08 (1.00)
At a Shift Supervisor during a plant tour, you see a locked closed valve with a red valve pedlock EXPLAIN why or why not this is a problem.
(1.00)
- CATEGORY 8 CONTINUED ON NEXT FAGE *****)
14 AD 1850.03.11 DAVil BESSE NUCLE AR POWER STATION
- "8'
"*8"N*
C AS.E..C.U,S CE LE ASE PCRMIT li3 $
O>
0=
to MtQUE 7 SY DATE TIME
'tCAY TANK M
g t/29 ht A%dto Pt m.pon mtLE Att O L D iO Pe+.toel DATL ilOLAf tD DOLATGO/TbAL. %
,n u
CONT AINMENT PUM68 U ESSVnt PStQ ESilMAT ED VOLUML P NOM ETEP gl e On C *P^c'T Y CURvt ' a
- T ' N s * ' 8 04 8 '
O Pf NttnAf TON MOOM PunSt 50 ri seso iY.ak u D rNeoMt INST. T ANK PURQt Pi ie33 it..= Si iso 102 //dI Psio mi Pi te3a if.am Si ANALYCEDBY@, o du/dl 3.5eNid S AMPLED sv itME TIME DAff f
8'A9/rf 000 Th737 07d0 GC.T E f
ER OR ESYlM TED (L)
FL E M AR KS hNUCLfDE UCdml OM 1.1 110*5 6, I l.ISilo-1 /.I5xfo**
ua ac.3u
=nsiu 1,11/0*G l0.1 3.ctD** 3.cx/o*V nu es an af
=n n
= a.,
xti3iM Mf133M 5.2vIo-2 11
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/, S r/b'2 x an x t 135M D8 535 28 131 xt.in 4.7t/o*3
//.4
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l 15 AD 1850.03.11
.W
- Jg0 se,Me MAxlMuM PU:ct TIMi MAxiuuM ntLE Ast m Att
_ MinvT,,
tre Cent.inm.at onivi
.g HloH OtBCH ARGE FLOW 8tTPolNT (Weste Oes Decoy Hhph Obscheepe Line Onivi le.0 SCPM TENTH VALUE OF M ANIMUM RELE ASE MATE MO se,M e
>n.e,that the ' tenth wolve of menWm teesee este' t E newee C AUTION :
u ee, Wo.to o. ee.ey Tonk,eiveet.
RELEASE
@OPER ABLE AND tr. 'URVEIL.
@ RELEASE AND DATA IN R ADI ATION V' NITOR IS APPROVED BY ITEM 15 COMPLETED.
R ECOMMENDED BY L ANCE TEST 15 UP T0 DATE frtt TURN TO C4 HP SECTIONI Smitt Swpe'v6ser/Date Shift Supeeviser/Dete Smitt Superviese/Dete CbHP Swpe-o5tv Pe'eennet/Date h%
nMitt 9/
RELEASE STARTED: DATE
. TIME Pmtssumt
.,Psto RELE ASE STOPPED: DATE TIME PRES $Umt PSIG TOT At. TIME OF RELE ASE MINUTt5 dP._..
Psts aP
..i. o A. Ao
,e.
n on e t.o,,eese.eie on e.e.
~
QATE TIME TESTER
)
Source check performed Channet check pe* formed Channel theth perf ormed GE 222 A and B WGDT Monitoe RE 1822 A and B WGDT Mninter F IC 1821 or 1821 A RE 5052C Conte. ament Purge Monitor RE 5052C Conteinment Puer Monitor (Circ 4 Monitor used)
(Cerck Monttor used!
9 O (Operetoel IOpereto')
(Detel (Ope'atoel (Detel (Det+1 REMARK 5 l
s he Masimum Reisese Rote: la e televiated we ve houd on the cueie eontent of att ist.arweites in the WGDT which nowld resilt in a release enust e
.estante6ecius tekene rete et statened 6m RET 5 The Tentti Voive of Memmvim sel*ese roie 6s e selviy tectee to ensure teet only a frution of tia Inste,teinous reiveis rete a ve*esed. Few Detey Tonk r*6eeses. ttne octual release rete nut be kit then ce equoi to the tenth venue of Mesimum N'****
i G:te oe 45 SCFM nhechever t less. if the tenth volve of Meilmum tele.e rate m item Il es yeeter then 45 SCFM. the lereast ectuni tion rete perme==h'+
l b455CFM-
~-
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1 eDUlulSIEAI1YF_fEOCEDUBE01_CDDD1710US2 Pace 18 4
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1 GUESTION 8.09 (1.00)
Using attached Tabic 3.7-1 of Technical Specification 3.7.1.1, STATE the required High Flux Trip Setpoint for the condition where one OTSG has three (3) inoperable and the other OTSG has one (1) safety inoperable.
duri,ng four FCP operation. (Calculation of W is not required.)
(1.0)
!WUESTION 8.10 (1.00) l During mode 1 operations, Decay Heat Cooler 1-2 was declared inoperable at 0000 aue tc tube replacement expected te take 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to complete.
At 0900 High Pressure Injection (HPI) pump 1-1 failed to pass its surveillance.
As Shift Superviror, DF3CRIEE the actions required per Technical Specifications.
(Assume HP1 pump 1-2 is operable.)
(1.00) i QUESTION 8.11 (1.60)
While in mode 1, HPI pump 1-1 is out of commission (000) repair. A surveillance is required which will take Emergency Diesel Generator (EDG) 1-1 000 for three hours.
i a.
Do Technical Specifications dire :tly FROHIBIT the Shif t Supervisor from allowing the EDG surveillance to be performed?
(0.75) b.
If EDG 1-1 ic 000, EXFLAIN the orerability of DH pump 1 $ per "echnical Specifications.
(0.75) i 1
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- 1 1
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TABLE 3.7-1 g
.c MKIMM ALLOM4KE HIGH FLUX TRIP SETPOINT WITH IMOPERARE STEAM LINE 5AFETY VALVE 5
=
G,
.u Mailuun Allowable l
~
High Flux Trip Setpoint*
i e5 Maxiaue Nisaber of Inoperable Safety (Percent of EATED THERML POWER)
Valves on Any Steam Generator j
-4
.I 0.95W i
1 1
i 0.82W
-L 0.69W t
3 w
N 0.56W
[
4 As 0.43W 5
k 6 ~
0.31W 3
I 0.18W l
3 7
.E 4
s
- Sased on High Flux Trip Setpoint for four pump operation. M. as per Table 2.2-1.
i 4
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H.
ADMINISIB6IlYE_EBQCEDUBSSu_CQUQlI1OUEt Page 29 6BD LldlIAIl9ES l
QUESTIOli 8.12 (4.50)
CLASSIFY the following per Emergency Plan (EP-1500) supplied:
a.
Containment Pransure 17.0 pslo and increasing Makeup tank level decronsing at 3 in/ min hCS E-bar.
2.5 MEV i
RCS samples:
25.0 uc/cc gross activity RE A00/609:
500 cpm and increasing SFhCG initiated on 600 psi in steam liress i
b.
Report of Chlorine leak to atomsphere onsite.
Report from security that an anti-nuclear group is picketing at the front gate Forebay level alarm with lake level at 562.0 feet.
Station computer is lost.
RCS inventory balance shows 10 gpm leakage, c.
Containment temperatures:
TI1356:198F,TI1357=207F,T11358:199F Containment nrecsures:
PT2000-0 P:IA PI2001: 19.0 PSIA,PI2002: 18.9 PSIA, P12003: 18.7 PSIA RE4597AB 10 uci/cc at time of shutdwon RE4596A 50 R/hr AT TIME OF shutdown (Consider a,b, and c ceparately. In answer give minimum classification which may be given and referer.ce section of EP-1500. )
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6 _'_6DMINIGIBoIIYE_EBOGEDUBESt_CQUDlIl0EE1 Page 20 6BD LIMLIAI1985 QUESTION 6.13 (3.00)
An accident has occurred. The plant has been shutdown for 20 minutes with AF% feeding OTSGs and no MSSV or AVV stuck open. Using attached EP 2240 1
(EP 2240-att.3) and the following data, CALCULATE the STABILITY CLASS l
and DOSE RATES (three required) at the site boundary (3.00):
1 (Show all work.)
- 1. Wind 6 mph from NE
- 2. CTRM outside ten perature guage ' 35 f t" 80.4 F
- 3. CTRM outside temperature guage '250ft" 86.2 F 4.
Flow Rate-Unit Vent 90000 cfm
- 5. RE 600/609(GROSS MODE) 4300 cpm
- 6. RE 4598 channel 1 1x10-2 uci/cc
- 7. RE 4596 channel 3 8x10-4 uci/cc QUESTION 8.14 (1.00)
According to Safe Work Procedure for Confin.3d Spaces (AD 1844.10), STATE what the Shift Supervie.or's signoture on a Confined Space Fermit indicates.
(1.00)
QUESTION 5.15 (2.00)
STATE for each of the following if notification to the NRC is REQUIhED or NOT RFQUIRED within ONE HOUR per adninistrative procedure Control of Conditions Adverse to Quality,ad 1807.00:
a.
Reactor shutdown due to refueling overhaul.
(0,5) l b.
Reactor transient at power which caused RCS preonure to peak l
at 2775 paia.
(0,5) c.
Reactor shutdown to perform radiography of MSR piping expected to l
take 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(0.5) l d.
Automatic SFAS actuation at power due to low RCS pressure.(0,5)
(C n. sider each independently. )
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t orts!TE DoSt AsstssMENT 16 Rs-EP-2240 (EP 2240)
~
Revision 1, INSTRUCT!0us FOR orFE!,T,E DOSE W0tt0 GRAM I'
1.
Tigure 1 shows an example of the offsite dose noeogram for use with station vent releases and secondary systes stone line releases. A copy of the actual moeogram can be foua6 in the Control Room, and in the dose assessment area of the Emergency Control Center.
I 2.
Use the Data Sheet on Page 3 of this attachment to record noeogras data.
l 3.
Determine monitor reading (3):
3.1 Tor whole' body dose rate free a station vent release use RE 4598 Channel 1 reading ta pCi/cc of noble gar,.
i 3.2 For child thyroid dose rate from a station vent release use RE 4598 Cher.nel 3 reading in pCi/cc of Iodine-131 and follow step 5.
3.3 Tot whole body dose rate from a release from MSSV, AW, or Auxiliary Teed Pump Turbine insert cpe reading from RE 600/609 in the tross mode into the blank below and calculate pCi/cc of noble gases.
(
cpe - 300 cpe) x IE-5 =
pCi/cc t
4.
Plot the monitor reading in pCi/cc on the right-hand side of scale (B).
f 5.
Determine whole body dose rates.
i
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l WOTE 5.1 l
l Flow rates gisan are conservative values for each l
l release pathway.
I 1 _ _ _ _
1 5.1 Draw a line from the appropriate monitor reading (5) to the appropriate flow rate (A). This line intersects (C) at the release rate value.
g 1
NOTE 5.2 I
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l Ensure that lower delta T, is used when entering l
I this sonogram.
l i_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _I l
5.2 Draw a line from the appropriate lower delta T or stability i
class (1) to the appropriate wind speed (2). This line inter-sects (3) at the I/q value.
4 Page 1 of 4
7 2
OTTSITE Dose A$$ES$NLNT 17 MS EP 2240 (EP-2240) l Revision 1 INSTRUCT!00is FOR OFTSITE DOSE WONOG%f (Cont.)
(*-
5.3 Draw a line from the release rate (C) to the I/Q value (3) determined in Step 5.1.
This line intersects (4) at the whole body dose at the site boundary or esclusion area beendary (EAB).
$.4 Obtain does rates at 2, 5, and 10 miles by dividing the site boundary (EAB) dose rate by 3,10, er 35 respectively.
6.
Detsruine child thyroid dose ratss, i
6.1 Use an todine pCi/cc value as though it were a noble gas con-centration and follow Steps 5.1 through 5.3 above to obtatu a dose rate at the site boundary (EAB).
6.1.1 If the iodine pCi/cr value is too small to plot on (B), multiply it by the power of 10 which will allow you to plot it.
Work through Steps 5.1 through 5.3 i
to obtain a dose rate at the site boundary, then divide that dose rate by the same powcr of 10 to produce a final mR/hr value for the site boundary.
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l CAUTION 6.2 l
1 I
1 If shutdown occurred > two (2) hours ago the nomo-l l
gram cannot be used.
Go to Attachment 4 or 5 for l
I hand calculation procedures.
l t
i I
6.2 Multiply the site boundary dose rate by the cocraction factor 7000 to obtain the child thyroid dose rate. This correction factor is only good for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> afte.r reactor shutdown.
6.3 obtain child thyroid Rose rates at 2, 5, and to miles by divid-ing the site boundary (EAC) dose by 3, lo, or 35 rexpectively.
l i
l 4
l Page 2 of 4
t.
OTT513 DOSE ASSESSMENT 18 Rs=Et.2240 (17 2240)
Revision 1 INSTRUCTIONS FOR 077517E DOSI Nm (Cent.)
Data Sheet for Noeograa Dats l
goggn a.
l pCi
- NG TIAW RATE er WINDSPF.ED
]
l TIME ce or i ECFM STAO. CLASS MFN 0
l f
)
Dose RATES IN MR/MR:
1 MIM 5 MIMS 5 MIES to MIus I
wwu a pCi WG TLOW RATE er WINDSPEED E
TIME ce or I ECTM
$ TAB. CI. ASS MPI 6
DOSE RATES IN MR/MR 1 M!u 5 MIIES 5 M112.5 10 M!us I
1 l
l l
Page 3 of 4
Offsite Dose Assessment Nomogram m_ -.
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6,.... add 1HISIB611YE_EBQcEDMBESt_QQHD1IIQllez Pcgo 21 AND_LidlIAI1QUE QUESTIOli 8.16 (1.00) 1 TRUE or FALSE The use of wood (e.g.. scaffolding) in the Auxiliary Building and the l
Containment is prohibited.
l QUESTIOli 8.17 (1.00)
LIST by title whose permission or approval is required to leave the PohV block valve (RC-11) shut during extended power operations in order s
to repair the PORY (RC-2A).
l 1
(*****
EllD OF CATEGORY 8
- )
(....,*,***
E N D O F E X A M I t1 A T I O !1 * * * " * * * * * )
h _IHE0BY_0E_UL!CLEAB_ED'dE8_ELoHI_QEEB6ILOS.
Page 22 ELMIDh6ED_IbEBU9DYSSMCS AhSWER 5.01 (1.50)
MASTR COPY e=
C) FALSE (0.5 pts each)
REFEREt1CE RTH-SRO-012,PF 10-13 Fl'1102.04.07,p.2 t
I
- tS 3.1.3.9 1920JCM114 192006K108 192000:;106
..(KA's) i ANAWER 5.02 (2.00) a.
subeccled, ~44 F i
b, cubcooled,
~9 F c.
surerheated, ~50 F d.
anturated,
'O F (or !;A)
( 5@ 0.25 ea.)
REFERE!;CE HTT-SEO-003,pp.3-4 19300SK115 193003K125
..(KA'si ANSWER 5.03 (1.50) i a) 1.
REMAlti THE SAME l
'.:. REMAlt; THE SAP.E I
3.
DECREASE B) 1.
DECREASE 2.
DECREASE j
3.
DECREASE i
(6 ANSWERS @ 0.25 FTS. EA"H) hEFEhENCE RTH-2RO-C11,AJ.3 RTH-SRO-012,ObJ.ic 192008K117 19J009K114 (KA'c)
I I
L C I Pi"""C U f "^""""
l
1 IBE0BY_0E_BUGLEAB_EQEEB_fLABI_02EBAIl0Hi Page 23 El.U1Ds2AUD_IHEBdQRYUad1CE-l'.
ANSWER 5.04 (1.50)
Expected (0,5), Xe peaks between 10-12 hours after a reactor trip and is decreasinc(0.4) which adds positive reactivity (0.3) which causes suberitical multiplication to increase neutron population (0.3)
REFERENCE RTH-SRO-008 192006K112 192006K107
..(KA's)
I ANSWER 5.05 (1.50) a) EOL (0.3), maximum worth of control rod (0.3), inost negative MTC(0.3 )
b) EOL (0.3),most negative MTC(0.3)
EEFERENCE USAR p.15.2-42,15.2-13,14 192005K107 192004K10C 192004K103
..(KA's) t ANSWER 5.06 (2.50) l a) INCREASE b) IECREAEE c) DECREASE d) SAME e) DECREASE I
(0.5 FTS EACH) l REFERENCE FF1101.02.8 figure 118,11b RTR-OLC:023,pp.6-6 19200JK114 190000K110 001010K517
..(KA's)
- ANSWER 5.07 (1.50) a.
ACTUAL HIGHER THAN FREDICTED b.
ACTUAL LOWER THAN FREDICTED c
ACICAL FAME AS FREDICTED (each 0.5 pts.)
i
(*****
CATEGORY 5 CCNTINUED ON NEXT FAGE *****)
4
_. _ _., _ _ _, _. ~ _ _ _ _ _, _ _ _ _ _ _, _ _. _ _,. _ _ - - -. -. _ -, _ _
e E.
IBE0BY_DE_EUCLE63_E0 WEB _ELABI_QEER6110H4 Page 24 ELUllL8t!D_IBEht19D1 Hat 11G FEFERENCE RTR-OLC-023,pp.9-11 001010K526 001010K524 001010A403 001010A201
..(KA's)
ANSWER 5.08 (2.00)
Fuel in the vicinity of the inserted rad experienced lower Xe and I concentrations due to flux depression (0,5). When the rod was ralled back out to the group position. flux in the region increases significantly (0.5).
Xenon burned out rapidly in the higher flux (0,5) adding ponitive reactivity resulting in severe power peaking in the region (0,5).
I REFERENCE i
RTR-0TC-023 l
i 192006K108 192005K116 001000K507 001000A203 000005K103
..(KA's) i l ANSWER 5.09 (2.00) e i
- a. NOT VERIFIED b.
NOT VERIFIED c.
NOT VERIFIED l
- d. NOT VERIFIED (0.5 pt. each)
! REFERENCE l
EOP Tech basee,pp.II.B-8,9,10 i
HTT-SRO-013,OBJ.8 193000K122 193006K121
..(KA's) a i
j i
I i
j 1
r I
i
(*****
CATE:10RY 5 CONTINUED ON NEXT FAGE *****)
1 1
1
. =,
5'.
IDE0BLQE_811CLE68 EQ' ER_ELAMI_0EEB&Il0lb Pap 25 d
ELUIDSJRLIBEBdQDX8AMLQS l
1
! ANSUER 5.10 (1.50)
- a. Corrosion products / impurities plating out on OTSG tubes (0.3) l reduce heat transfer coefficient (0.3) so need higher level to transfer some amount of heat (UA need larger A if U decreases)(0.3).
1 (SIMILAR CONCEPTS ACCEPTABLE).
f l
- b. Nuc1cate boiline region Film (bulk) boiling region Superheat region (0.2 pts, each) l t
iREFERENCE HTT-SRO-008 i
193008K101 193005K103
..(KA's) i i
r lANSWER 5.11 (1.50)
L The reactor core generates heat (0.375) and the temperature of the fuel is dependent on the heat transfer (HT) from fuel to RCS fluid, HT decreaces t
drastically in bulk boiling region leading to high temperatures (0.375)
The OTSG does not generate heat (0.375)and +.he steam temperature is limitett j
by RCS bulk temperature (0.375).
(SIMILAR CONCEPTS ACCEPTABLE).
NREFERENCE HTT-SRO- 0 0 6, OBJ. 3, 4, 5
- REFERENCE l
193003K105
..(KA's) s jANSWER 5.12 (1.00)
FALSE l
REFERENCE
[
1
- j RTH-ERO-009,PP.10-11,0PJ.2 192000K111
..iKA's)
}
1 I
i l
1 i
I
(*****
CATEGORY 5 CONTINUED ON NEXT FAGE *****)
h Tli.EQBLQE_t!UO LE 6B_EQi!EB_E L AERE B ail 0th Page 26 Eh010!hoti2_IBEBtiRDYl!6tilCd
)
'ANSUER 5.13 (1.50)
- a. True i
- b. Felte
- c. Falso
[3 W 0.5 ca)
(1.5) t r
REFERENCE 1
RTH-SRO-012 RTH-SRO-011 OLC-SUC-S012 192008K115 1900n8K114 190008K113
..(KA's) i I AN5WER 8>.14 (2.00)
J a.
1-1 OTSG feed flow will increase (0.40)
]
b.
2-1 OTSG feed flow will decrease (0.40) l c.
1-1 OTSG level will increare (0.40) d.
2-1 GT3G level will, decrease (0.40) 4 j
c.
RCS delta Te ui]1 return to zero (0.40) i REFERENCE ICS Lesson plans PP1101.01 PP1102.04.17.p.3 002000K515 0, N0OK! 11
..(KA'e) i
- ASSER 5.15 (1,50)
Heat is added to the fluid in the pump work (0,5) If the flow is
{
insufficier.t to remove this heet then cavitation may result j
f rom saturst ed condition.* and cause damage to the pump component s. (0. t )
Punp components (such as reals) may ba damaged by heat / temp (0.5)
(Similar concepts acceptable).
I l
(on* CATEGCRY 5 CONTINUED ON NEXT FAGE n*')
9
'F2__IHE0BY_0E_dUGLE8B EQUER_EL6BI_OFEBAI1982 Page 27 ELUIDhh!!ILIUEBMQDXUbMIGS 1
REFEhENCE 4
HTT-GRO-013,0bj.1,2 101004K104 191004K101
..(KA'a) i l
ANSUER b.16 (2.00) a)
Increase
(+.5 ea) 2 b)
Decreare c)
Decrease d)
Increaso
- REFERENCE RHT-SRO-005 13 000K107
..(KA's) 4 1
1 l
i i
I r
1 1
i j
i i
l
(*****
END OF CATEGor,Y 5
- )
~
di__EL8HI_SXEIESf_ DESIGN. CRNIBQL. AND_INSIBUMENIAIXQN Page 28 ANSWER 6.01 (1.00)
- 1. Serves as containment isolation valve.
2.
Performs fail open function with fan start due t a 'ty feature actuation.
(0.5 pts each) l REFERENCE l
l T/S 3.6.3.1 l
LER 87-003 022000K101 000069A202 000069A101
..(KA's) 4 I
ANSWER 6.02 (1.00) a.
SFAS cabinet door key (0.3)
Test Trip Bypass Switch (TTBS) key (0.3) b.
Logic would be 2 out of 3 (0.4)
REFERENCE LER 07-002 TM-SFAS p.5 SP 1105.03,p.6 072000G009 072000G007 072000A401 000061A206
..(KA's) j l ANSWER 6.03 (2.25) l l
FW 601 closing caused feed to #2 OTSG to stop (0.25)
Due to lack of RCS energy removal, the Reactor tripped (0.25) on high pressure (0.25)
Turbine tripped (0.25) due to the reactor trip (0.25)
Pressure in OTSGs increased due to turbine stop valves trip-no steam l
demard (0.25) which caused MSSVs to lift (0.25) l Due to low level in OTSO #2 (0.25),AFW flow started en SFRCS actuation (0.25)
REFERENCE LER 87-006 l
059000K304 000054K301 000064A203 000054A201
..(KA's)
(*****
CATEGORY 6 CONTINUED ON HEXT PAGE *****)
f.
PL88T SYSIEMS_DESIGU2_G9BIBOL, AND_XHEISUMENIAIIQB Page 29 ANSWER 6.04 (1.00)
- a. No effect (0.25) since RC flow measurement is blocked for 4 RCP ops.
(0.?.5)
- b. No effect (0.25) since operate level provided only a high level limit function to ICS.
(0.25)
REFERENCE TE ltr 1-817 enclosure p.12 ICS P&ID 016000K112 016000K101 016000A201
..(KA's)
' ANSWER 6.05 (1.50)
FW pumps increase speed to attempt to maintain d/p (44 psid) across FW valves (0,5). So FW flow to both OTSG's increases (0.26) FW control valves will partially close to bring FW flow to demand signal (0.25).
FW pumps will increase speed to the high speed stop (5150 RPM) (0.25)
FW control valves will be closed i'urther than initially. (0.25)
REFERENCE PWR-OLC-024,p.27 TE ltr 1-817 enclosure p.1 ICS P&ID 059000K107 059000A203
..(KA's)
ANSWER 6.06 (1.50) a.
Runback in progress (accept individual runback events) b.
High load limit exceeded i
c.
Low load limit exceeded l
REFERENCE ICS-OLC-001, pg. 7 045050K101 (KA'n)
(*****
CATEGORY 6 CONTINUED ON NEXT PAGE *****)
._=
~T~'
6.
EL8EI_El&IEMS DEB 10Hz CONIB0L1_AHD_lESIBENEEI&Il08 Page 30 ANSWER 6.07 (1.50) turbine trip or turbine stop valves 1 or 2 and 3 or 4 closed a.
b.
loss of vacuum 17 in HGA c.
loss of cire, water <100,000 gpm (currently being jumpered) d.
OTGG pressure greater than 1025 psig e,
less than 90% open MSIV (any 4 375 pts each)
REFERENCE PWR-OLC-027, pg. 19 041000G004 035010A302
..(KA's)
ANSWER 6.08 (1.00)
When both IR channels 3 and 6 = 10(-9) ampa (.50) or when NI-5 or 6 and 7 or 8 are GREATER than 10%
(0.50)
REFERENCE TM Nuclear Instrumentation FIG 28 015000K401
..(KA's)
ANSWER d.09 (1.50) a.
Jockey pump attempts to maintain pressure (at 135 psi)
(0.25) electric pump starts (at 120 psi) next (0.25) diesel fire pump starts last (at 100 psi)
(0.25) jockey and electric pumpe take suction from FWST (0.25) diesel fire pump takea auction frem intake structure (0.25) b.
fire department pumper connection (0.25)
REFERENCE PWR-OLC-003,0BJ.10 086000K402 086000K401 086000A202
..(KA's)
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CATEGORY 6 CONTINUED ON NEXT PAGF *****)
i,._._Eb88I_SlSIEUS_DESI90, CONIROL. AND_IUSIBHMEUIATTON Page 31 1
ANGWER 6.10 (2.50) a.
CTMT purge exhaust fan (1-1) stops (0.4)
CTMT exhaust fan discharge dampers close (0.4)
CTMT exhaust filter inlet damper closes (CV 5062)
(0.4)
CTMT purge supply fan (1-1) stops (0.4)
CTMT supply f an euction (0.2) & discharge (0.2) dampers close b.
CTMT purge system to EVS damper (CV 5061) will open (0.5)
REFERE!1CE FWR-OLC-04 6 OBJ. 2, pp.15-16 TM:CTMT PURGE SYST,pp.7-6 029000K403 029000K103 029000K102
..(KA's)
ANSWER 6.11 (2.00) a.
(SFAS 2&3)
CCW pumps 1-1, 1-2 start (0.25) aux. bldg. non-essential (0.25) and makeup header (0.25) isolation valves close (CC1495.1460)
DH cooler outlet valves open (CC-1467,1469) (0.25) b.
(SFAS 4)
CTMT inlet isc ation valves close(CC 1411A,B)
(0.25)
CTMT outlet leclation valves close (CC1407A,B.'
(0.251 CRDC booster pump suction valves close(CC 1326,1338)
(0.25)
CRD cooling containment isolation valves close(CC 1567A,B)
(0.25)
REFERENCE TM: Component Cooling Water,v.9,p.14 PWR-OLC-020, OBJ. 0 5, p. 7,8 P&ID M-036C 000026K302
..(KA's)
ANSWER 6.12 (2,50) a.
Will allow piggyback operation of the makeup system on the LPI pumps (increases flow rate).
(1.0)
- b. bypass of MU 32 when it falla or aid in per level control when normal flow insufficient allows emergency feed and bleed open MU 6419 upon loss of subcooled margin (any two at 0.75 pts each)
(*****
CATEGORY 6 CONTINUED ON 11 EXT PAGE *****)
~--
9 ELANT SYSIEds_DESIGU1_QQUIBQIu._AND_lNSTRUMEUIATTON Page 32 REFERENCE 5th. Outage mod-MU/Pur p.1, FCR 86-432 5th. Outage mod-MU/Pur p.3, FCR 86-432 004010K101 004000K115 000074K309 000074K304
..(KA's)
ANSWER 6.13 (2.70)
RE 8446,8447-Fuel Handling Area (Emergency Vent)
RE 5405 A/B/C-Radwaste Area Exhaust RE 4598 AA/AP/BA/BB-Station Vent RE 1412,1413-Component Cooling Water RE 1822A/B-Gaseous Rad Waste RE 1878A/B-Mise Liquid Rad Waste RE 1770A/B-Clean Liquid Radwaste RE 5052A/B/C-Containment / Penetration Room lany 6 at 0.45 pts each)
REFERENCE SP 1105.07.12 073000K401 073000K101 072000K402 072000K401
..(KA's)
ANSWER 6.14 (2.50)
Low instrument air causes LP heater drains,HP feedwater heaters,MS drain tank, 1st/2nd stage tank reheat drains and feedwater heater bypass valves 3
to open.(or feed and steam system valves open to dump steam and condensate to condenser)(0.5)
ICS responded by increasing feedwater flow and pulled rods out.(0.5)
Reactor power increased and reached ICS high demand limiter setpoint.(0,5)
Increased feedwater flow caused a decrease in reactor coolant Tavo(0,5)
Moderator temperature coefficient is most negative at EOL and as a result caused reactor power to increase which caused a high flux trip.(0.5)
REFERENCE LER 87-015 ICS P&ID 078000K300 000065A208
..(KA's)
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CATEGORY 6 CONTINUED ON NEXT PAGE *****)
S.,___ELoEI SYSIEliS_ DESIGN,..CQUIBL_b8D_lHSIBULiESIAIIQB Page 33 ANSWER 6.15 (1.00)
The large
'eom demand on OTSGs removes excessive RCS primary heat (0,5)
RCS temper, re and pressure decrease (0.5),
or excessive cooldown of RCS REFERENCE LER 87-010 MSR-OLC-28,p.6 P&ID M-003B 039000K305 039000K104
..(KA's)
ANSWER 6.16 (0.80)
DH-11,12 to DH-10 & 26 and around DH-1517 & 1518 (0.4)
Par Aux spray line (0.4)
REFERENCE PWR-OLC-043,0BJ If SP1104.04 DB EQB: 6-133 000011K313
.(KA's)
ANSWER 6.17 (0.75)
DH-11 not be open at greater than 301 psig DH-12 not be open at greater than 301 psig Par heaters not be energi:ed if DH-11 or 12 is open and RCS pressure greater than 301 psig Relief valve Administratively, both HPI pump breakers are racked out (any 3 at 0.25 pts each; REFERENCE PWE-OLC-043,OBJ.b SP1104.04 D14 EQB: 6-23 On5000K401
..(KA's)
(*****
END OF CATEGORY 6 *****)
1 ERQcEpuBEE_ _ERBd6L1_ABHQBd6Lt_EUEBGEHQX Page'34 AND_BoulRLOGIGAL CQUIBRL ANSWER 7.01 (1.00)
Prevent damaging the epider esssmbly (0.5) since less torque in run speed than in jog speed (0,5)
REFERENCE SP 1105.09,p.9 0010000005
..(KA's)
ANSWER 7.02 (1.60)
- a. NOT NOTIFY (0.5) b.
NOTIFY (0.5) c.
NOTIFY (0,5)
REFERENCE SP 1105.07,p.20 072000G015
.(KA's)
< ANSWER 7.03 (1.50)
- 1. Exercise the valve once for every 100 F cooldown (0.6) or 2.
If available, isolate line with manual valve and then reopen valve and continue cooldown (0,5) or 3.
If not 1 or 2, attempt to open valve manually after cooldown, do not attempt any excessive force (if not open, contact maintenance for assistence) (0.50 REFERENCE PP 1102.10,p.7 004000G010 000000G010
..(KA's)
ANAWER 7.04 (2.00) a.
FALCE b.
TRUE
(*****
CATEGORY 7 CONTINUED ON NEXT PAGE *****)
m.
Page 35 T&__EBOCEDUBEE_:_NOBOALt_8BHQBd6Lt_EMEB3ENg1 6HE_ bod 10LQGIR8L_G9 BIB 9h REFERENCE PP1103.08,p.5,6 001010A207 001000G015 001000G01) 001000G001
..(KA's)
AN3WER 7.06 (1.00)
Loss of flow or orratic flow from DH pump (due to air induction when at low RCS levels)
(1.0)
REFERENCE AB 1203.35,p.6 005000A102
..(KA's)
ANSMER 7.06 (2.2b)
Trip the reactor Trip the turbine Isolate letdc,wn (with MU 2B)
Close FORV block valve (RC 11)
Open Pr.r steam sample (RC 219A)
Start the second makeup pump Shift makeup pump suction (MU 3971) to BWST Manually actuate SFRCS on initiate AF:'T and isolate SG (both trains)
Trip all source breakers to A and B buses (9 at 0.26 pts each)
REFERENCE AB 1203.26,pp.1,2 000068M313 000068K312
..(KA's) 1
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Iu__EBOCEDUBBS - NOBd&Lt_8BHOBU6kx_EUEBGENGY Page 3G AUD_BADIRLOGIG6L_COEIBOL ANSWER 7.07 (2,50) a.
1st stage drop:RCS pressure minus 2nd. seal cavity pressure (0.25) 2nd stage drop:2nd. seal cavity minus 3rd seal cavity pressure (0.25) 3rd stage drop:3rd seal cavity pressure (0.25) b.
'Ist stage-1075psig (0.25) 2nd stage-Opsig (0.25) 3rd stage-in75psig (0.25)
(other values acceptable if same pressure on 1&S of approx.1/2 of RCS press and 0 on 2nd) c.
- 1. Attempt to reestablish CC flow (0.2) within 4.5 min (0.05)
- 2. Trip the reactor (0.25) 3.
Trip all RCPs (0.25) 4.
Carry out EP 1202.01 (0.25)
REFEhENCE AB 1203.21,p.3,5,10 003000K602 003000K407 003000A202 003000A201
..(KA's)
ANSWER 7.06 (0.00)
QUESTION DELETED REFERENCE QUESTION DELE' ED ANSWER 7.09 (1.00) a.
High Flux setpoint for 3 RCP operation was still in effect (0.5) b.
Have the High Flux trip setpoint increased to value for 4 RCP operacion (as per SP 1103.06,p.31)
(0,5)
REFERENCE SP 1103.00,p.31 TE 2.21,p.2-7 M':102.04.p.32 01duuGK400 012000K402
..(KA's)
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2 __EB00ERDEES_1_HQBUAL1_aE80BU6La_EMEBGENGX Page 37 SUD_B6DJ9Lfe01 col _G0HIBQL ANSWER 7.10 (2.00)
- 1. At equipment level, BLOCKED equipment will respond to the individual control switches for that piece of equipment.
(1.0)
- 2. At the system level, operation of the system level RESET pushbutton will clear any output logic blocks in the system. The equipment will then respond to the system level manual actuation TRIF pushbutton and to automatic actuation signals.
(1.0)
(Concepts.)
REFERENCE GOP-OLC-003,obj.5 EP 1201.01, SPECIFIC RULE 4 Db EBQ 7-10 013000K410 013000K118 013000A402
..(KA's)
ANSWER 7.11 (3.00) f 1.
Attempt to maintain pri to eec heat transfer balance (0.2) a.if MFW has run back below reactor power, manually control MFW to match reactor power.
(0.4) b.if MFW is lest, initiate AFW by t ripping SFRCS on using both initiate AFFT trip buttons.
(0.4)
(logic 0.1)
- 2. Attempt to manually de-energize the CRD's in order below(0.1):
- a. Momentarily de-energize 480V anit subs E2 & F2 simultaneously (0.3)
(logic 0.1)
- b. Manually trip three reactor trip breakers in low voltage switchgear rooms.(0.3)
- c. Manually de-energize the CRD system by tripping BE211 on E2 AND BF211 on F2. (0.3)
(0.1 logic)
- 3. Attempt to manually shutdown the reactor (0.2):
a.
Manually drive control rods in.(0.4) b.
Begin emergency boration (0,1) by shifting MU pump suction to the BWST (0.1), meximize MU flow to RCS & maximize letdown flow from RCS (0,1), divert letdown flow to CWRTs(0.1)
REFERENCE EP 1202.01 GOP-OLC-003,ATT.2,obj.5 GOP-OLC-003,ATT.2,p.7 000029K312 000029G910
..(KA's)
(****4 CATEGORY 7 CONTINUED GN NEXT PAGE *****)
lt__Eh0CEDUBE6_2_ HOED 8kt_6BE9806Lt_EMEBGEGGY Page 38 6UQ_B6D19L0GlG8L_GOUIB9k
)
At1SWER 7.12 (2.25)
- 1. MU/HPJ must be throttled to prevent exceeding max RCS Pressure /
Tomparature for cooldown limit (0.75)
- 2. HP1 must be throttled,during piggy back operation, to limit HFI pump flow < 950 gpm per pump (0.75)
- 3. MU must be throttled to maintain pump discharge pressure >1700 psig and motor current <68 amps.
(0.75)
REFEREt1CE EP 1202.01, SPECIFIC RULE 2 00P-OLC-003,ATT.1 013000K416 006020K601 006000A205 006000A204
..(KA's)
ANSWER 7.13 (2.25) 1.
Immediately start installation of gate between SFP e.nd transfer tubo pit (0.5)
- 2. Main FH Bridge-lower the fuel:
a.
back into the e, ore (0.26)
OR b.
into deep end of ref uelinc canal 4 f eet below normal tJansfer mechanism (ze tape reading)
(0.25)
- c. into transfor mechanism basket and lower basket (0.25) 3.
Transfer Mechanism:
a.
if time permits THEN disconnect most convenient cable from carriagee (0.25) and move carriage to oppoeito side (0.25) and close transfer tube valves (SF-1,2) when clears valves (0.25) b.
if time not permit (a),THEN elose the valves se tightly ac possible (0.25)
REFEREliCE PP 1502.04,ATT.7,P.1-2 034000G':114 00003CK303 000036G010
..('
's) i AN3WEh 7.14 (1.75) 1.Have the area claared of pers onnel( 0. 30 ) and restrict entry (0.30)
- 2. Notify tne Shift. Uopervisor(0.30) of locatien and nature of spill (0.30)
- 3. Initiate steps to stop or contain the e-pill (0.30)
- 4. Secure ventilation to area if there 1e potential for airborne rad 3cactivity(0.25)
(*****
CATEG0hY 7 C0t1TINUED ON 11 EXT PAGE *****)
1.s__E80GEDUEES - EQEU8L1_6BEQBM8L&_EMEBGEEGY Page 39 j
bt!D_B6D10LQGIG6L_CQBIERL REFERENCE AB 1203.39 194001K103
..(KA's) i ANSWER 7.15 (2.25)
- a. MSIV could go wide open (0.375) and damage the Main Steam Lines (. rater-hammer) (0.375)
- b. Prevent expansion of any fuel defects in "water-logged" fuel pins, (0.375) the stean pressure incide fuel pin will be allowed to seep back into t'he RCS. (0.375)
(Concept)
- c. When RCS >200F at leact one train must be in LPI mode (0.375) and to provide aux. spray for RCS depressarization.
(0.375)
REFERENCE PP 1102.02,p.34 PP 1102.04,p.6 FP 1102.10,p.10 19200SK119 192008K116 039000K408 005000G010
..(KA's)
(*****
END OF CATECORY 7 *****)
8.
ADMINISIB8IIVE_EE90EDUBES2_CRED1Il0N.;t Pase 40 AUD_L1dlIAIIONS ANSWER 8.01
().50)
- 1. Declare both source range channels inoperable (.75)
- 2. Action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (.50) to place the unit in at least hot standby (within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />) (0.25)
REFERENCE T/S 3/4.3.1, Table 3.3.1 N1, pg.2 T/S 3.0.3 AB 1203.08.1 000032K302 000032K301
..(KA's)
ANSWER 8.02 (1.00) a.
When authorized personnel i.ndependently (0.1) perform the desired lineup following the prescribed methods of positioning (0.2)or checking (0.2) and then tagging (0,1) the device, component or system.(0,1) b.
This means that cach person (0.1) shall actually perform one of the methods and should not be in the crea of the component (0,1) when the other individual is present to perform his portion of the independent verification. (0.3) (similiar wording acceptable)
REFERENCE SRO-ADM005.03, AD180?,p2 194001K103
..(KA's)
ANSW'Eh 8.03 (1.50)
- a. 1) The deviation s needed to protect the health and safety of the public.
(0.5)
- 2) No action, consistent with licensed requirements, that can provide eJequate or equivalent protection *s immediately apparent.
(similiar wording acceptabler)
(0.5) b.
A 14 censed GRO.
Shirt supervisor and assistant shift supervisor.
( either at 0.5 pts.)
l
(*****
CATEGORY 8 CONTINUED CH NEXT PAGE *****)
a 8.
ADMIMISIB8Il2E_EBQ9EQMBESu_QOUDlIlQUE1 Page 41 AMD_L1blIAIIQUE REFERENCE 10CFR50.54x 194001A116 194001A112 194001A110
..(KA's)
ANSWER 8.04 (1.00) a.
75 rem (0.5)
- b. This person cannot be allowed to enter due to the fact that emergency limits are " Once in a lifetime". This person will exceed the limit.
(similiar wording acceptable )
(0,5)
REFERENCE D/B EPIP P.6-14, para 6.5.1 194001K103
..(KA's)
ANSWER 8.05 (2.00)
Shift Supervisor (SS) shall personally inspect the e.ystem or components (0,5) and verify that the removal of the tags will not endanger personel or damage equipment (0.'5)
SS shall contact the person's immediate supervisor or next level of supervision to determine status of work (0.25) and get permission to remove the tags (0.25)
The supervisor so contacted will be noted on the RED TAG Clearance sheet (0,5)
-or-Shift supervisor may, in unusual circumstances, where the above can not be completed, assume responsibility for authorising tag removal on his cognisance.
However, he shall also assume the responsibility of notifying I
the requesting person of the tag renoval.
This responsibility shall not be delegated to another individual or another shift supervisor. (this answ.ar is acceptable if when it would be used is specified)
REFERENCE AD 1803.00,pp.14-15 194001K102 (KA's)
ANSWER 8.06 (1.00)
FALSE
(*****
CATEGORY 8 CONTINUED ON NEXT PAGE *****)
E___6DdlElEIB6TIVE_NBOCEDURES, _CQED2TIONSA Page 42 6ED_ LIM 1I6Il0ES REFERENCE T/S 2.2.1 032000G015
..(KA's)
ANSUER 8.07 (2.00) circle 4. RELEASE NO (none listed)
(0.5) circle 3.
is checked (either 1.
or 3. checked)
(0.5) circle 18. ACTUAL CURIES RELEASED-(only filled in after completion)
(three errors)
(0,5) circle 11. (should be 1/10 of item 8 or <45 sefm )
(0.5)
REFERENCE AD 1850.03 ADM-SRO-011,obj.8 ADM-SRO-011. add.#1 194001KiO3 071000A426
..(KA's)
At1SWER 8.09 (1.00)
A red valve padlock identifies a normally open valve (0.5).
Either valve is in wrong position or padlock is. wrong color (0.5)
REFERENCE ADM-SRO-007,obj.2 ADM-SRO-007,pp.3-4 AD 1839.02 194001K101
..(KA's)
A!;SWER 0.09 (1.00) 0.69W REFEREtiCE T/S 3.7.1.1 039000G005
..(KA's)
(*****
CATEGORY 8 CONTINUED ON 11 EXT PAGE *****)
B.
ADUIGISIB8IlVE_ERQQEDUBESt CONDlILONE;.
Page 43 ABR_L1611&I1985 i
1 ANSMER 8.10 -(1.00)
- 1. Action must be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit in a mode where T/S does not apply (0.5) place the unit in hot shutdown (<280F) (0.5)
(if candidate star,ee to cold shutdown -0.25 pts)
REFERENCE T/S 3.0.3 T/S 3.1.2.4 T/S 3.5.2 006000G005
..(KA's)
ANSWER 8.11 (1.50)
- a. No (not prchibit aurveillance from being performed)
(0.75) b.
DH pump 1-1 would be opereble (0.25) if normal power is operable (0.25) and all of its redundan c system (s. subsystems, trains. components, and devices) are operable (0.25) (Concept)
REFERENCE T/S 3.0.5 064000K303 064000G005 005000K201 005000G005
..(KA's)
ANSWER 8.12 (4.50) a.
ALERT (1. 0), S.A.2 or 2.A.2 (either at 0.5)
- b. SAE (1.0), 8.D.3 (0,5)
C.
SAE (1.01, 1.F.2 (0.5)
REFERENCE HS-EP-1500 (EP-1500)
EFT-SRO-001,obj.14 194001A116
.. ( K A '.s )
(* "** CATEGORY 8 CONTINUED ON NEXT PAGE *****)
j
- Em ADdidlSIB6IlY3_EEQQEDMBESt_GQUD111QMS1 Page 44 6ED_LIMII8IIQUE l
ANSWEF 8.13 (3.00)
I STABILITY OLASS 85.2-80.4u4.8F lower deltis T or class G (0.5)
X/Q 4x10-4 (0.25)
AFW (4300-300)x10-5: 4.0x10-2 uc/cc (0.25) 3x10-3 ci/sec (0.25) 1 mr/hr (0.25)
Noble Gas 4.5x10-1 ci/sec (0.25) 80 mr/hr s'0.25)
Child Thyriod (10 x 8x10-4: 8x10-3 to fit on scale) 10x gives 4x10-1 ci/sec (0.25) 10x 60 mr/hr (0.25) actual 6 mr/hr 7000 x 6 mr/hr: 42 rem /hr (0.50)
(Reasonable tolerances accepted.)
REFERENCE HS-EP-2240(EP-2240),att.3 EFT-OLC-001,obj.3 194001A116
..(KA's)
ANSWER 8.14 (1.00)
The enclosed volume is isolated (0.33) at atmospheric pressure (0.33) and tagged for safe entry (0.34)
(Concept)
REFERENCE AD 1844.10 ADM-SRO-010, add.1.P.9 ADM-SRO-010,obj.7 194001K114
..(KA's)
ANSWER 8.15 (2.00)
- a. NOT REQUIRED
- b. REQUIRED
- c. NOT REQUIRED d.
RECttIRED (0.5 ptt EACH)
(*****
CATEGORY 8 CONTINUED ON NEXT PAGE *++" )
c fL__ ADtEtU EIBiI1YE._ESQGEldlEES1_QQHDlIIQliS2 Page 45 AND_LiblI6IIQUE REFEREllCE AD 1807.00
'10CRF50.72 194001A116
..(KA's)
ANSWER 8.16 (1.00)
FALSE REFERENCE ISG-9 p.1 194001K116
..(KA's)
ANSWER 8.17 (1.00)
PLANT MANAGER REFEREt1CE SP 1103.05,p.8,25 010000G010
..(KA's)
(*****
END OF CATEGOhY 8 *****)
(**********
Et3D OF EXAMINATI0ti **********)
i
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L l&L Rl lL F t. AND 6tJ1 DEL INi.S F OR L ll:E NSE EXAMINul' IONS Dursmit the adoi t ni u t r ett 1 on of this in: am t n a t i on the fol1ow1nq rulen anoly:
1.
Ulies t i tio oli t iie e>:ano rio t i co s ineens an au t onia t i c denial of your application and could reuuit in inor e uovere pen a l t. i c G.
J.
lui r oose tript at e to t> e Jinoted and onl y olie (.asidi date at a time may le3ve.
Vou inu u t avoid all cont.octs wi lls anyono culuide the e r.avitrie t i o n r ouni t o o v oi ci even tho appearenc.e or porbitsality of theatino.
Une is t s c i i ni or derL p rin c 11 on 1 y 1. 0 t a t.: 1 1 1 t a t o 1 og ila l o r ep r odus.t. ) on n.
1.
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a.
hagamble your ex aini na t i on o *3 follou1 (1)
E n arn quee,t i oris on top.
(Z)
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e' t. c.
(3)
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I b.
l orsi in your-copy of the exaniination and all pages used to an <iuer t tir ex ofo l iiiil i t ir i q u e e.t i t>ti*s.
c.
line ti t re
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.!Uy Et10!!X UN1J % _ ME N. J F<0lmL!!B_.009.ll 9.19.l!-9L3 UUhblIUh 1.01 (1.00)
LJi Lli the t eattor ctitttal.i t 10 E - U M., rod en tiidr awal is ubeci to 1 r i t r c> c h e pownr to 10 l -O.6%.
Select ttie one s t a t.t+<nef it that correctly decct1bou tlie 6.(so) t. l oi t of rods eit<r t iie power liac s t ab i l i :' ed et 10 E - U O..
4 I l i e.- t ud pom tion will he l ii c4 h e r than a c.
14 E-UD% becauele inot u t' v e l init<.i Li tf s :0 05 ed t. c. tlie o vai 1 atil e ru utr ons t o nia ltit o)ri the li a d ici-powet 4o...I.
b.
Ilit-t o< i p os. i t i on will be h ) cihrer tisari at 10 E ~ O M. to a v er c. o m e the powet d u t ei_ I.
t.
liie-t Od
's o s.1 t 1 or e W) 1] Lee i tie t; a in e.
Ihe outwerci t oc) niot 2 oli t i P re d ted to
,+. h i e n a canvtin u t. o r l u p t ate equ,319 the i n w at ti inollon needed to remice t ii. startup eeto to : < r o.
d.
lin-t od lit m a l ) ar e wiil lie 1ower thori at 10 E - U S 'i. d u r.
tu the inte<oted di 1 e od neiii r on population aduottated with t he h i cht>r-pawor -l evel,
f t**
- L eill (- U h v 1 L DtJ1 1 h LIEI4 ( il l 1d 1i F at,1
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( u n,t ioit - rior nial p l siit oper ats ori aim rio oper ator a t c 2 01. No e >, p l s o c$t i o n tequired.)
n.
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- 1).
Frtissorizet level d ec r e a ts tm c.
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t QUESl]UN 1. U.'.
(1.SO) a putnp has t iie 4 al I c.wi rig p ar ainot er s :
Spered (hi.ali) :
U000 RPf1 D20r.herqe head:
2'200 PSI G (10 t e r-power:
800 hw.
' 1 ow:
600 bf il Wiial Wost1d be the <alue ut ench pareniet ee af the punip in blii f t ed to 4
t, l e w spuOd ( 400v liPI l)
( 1. O '>
re.
How cio e t-e out r ea u-in the teinper at ure of t ht-fluid (water ) b e i t na p t. iif. p O d stiUCl lleO CUFtChl
- OQUIFOd by (11 0 pump molOf nhunOO Speed 1 t, L osis t atit.
( O. ti) l l
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L i I t i,U U '-
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(Choose one) o.
Aq 1 w c-increases f r oni 130 degreen Februnheit to SOO degree s I alit orilun t.
b.
As a t: lal i1ue di s tr ibut 1 ( iri t2)ts t ci t he t;ot torn.
c.
Ad a resolt o+
f a sui aie product beiJdup.
d.
Wtit ri t 'io solishl e tior c re c oricelii t a t i oli i ric r 4 ocen.
gea
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r UllE E i lillJ 1.0G (1.00) itite en o r. t f.ur a rius e: r c> b l em with r e a c h arig thc-critstal tieat 41ux (L,fiF )
in ei 5' W H tea. tor 2 e. c ntsad by:
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(1.O)
Li.
the poor t h e r ni.s i c u educ t i vi t y of s t c etni.
l ts.
The blockc):r o+
f1ow t hr ouc3h the core when s t eain f orinat 1 oli j
liet oost t, u oria 4 i c arit.
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t OLIES f IUll 1.06 (1.SU)
Afttr tr s ticeli ty 1 *> ocis s eved, tiie oper ator wants to level power at 10-9 a ni;. s to record ct i ti cal d att a,
the operator driven rods to got a /ERU 19 t1 SUR. Ulie nii n u t cc l ai er, tive operator notices that power in increasing.
b'r pl al n Wi t y' l
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UUEGl' ION 1.07 (1.50)
A t. s u n se your p l orit lea s e><perienced e. desgraded electrical power c.oridi t i on erid tiiat you are nioni tor t tia t he pl ent 'u cooldown on natural circulation.
Str'te t UllE / F ni SF fo-the followirig s t a t enien t s.
o.
a slow downwi<rd trend in the indicated lave in a good i n d s c a t i c.. i of wel l -ec,t abl i t hed riatur al ci rcul at t ors fIow.
b.
A difference between wide range I hat and wide ranco 1 culd of 'J S l
doorees F arid L.l oul y a nce eat,i tig indacates d: vel opi no rectus el I
circulation
+10w.
l c.
IJat ur al c i r c.u l a t l a n f low r ete can
's e increat,ed by 1 sitr ereni no I
l the > t uaiti flow rate by turther openi s ig the turbine bypano v e e n d 14l i v.
t f i(v uine tiin r *.ia c t or i u undurinodoret ud at E<UL and no reactor trap ott ur<>,
tosit n sitio expl A net 2 oli ti11 primary power e #id Iova condat1ont se r ' i'_- k l Ji } } (1. #
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t UUES11014 1.10 (1.00)
NUL i li'l i LHLII G (Choobe the best entwern.)
Whicle of the following s t a t einen t t; are lhUE, with regard to centrifugal punp c c. < 1 i a t i ori a o.
Ast;unia riu pr oper val vo-lineup, cavitmtion cori be diaonoseo t r cini colett ol board i n d i c a t i on ;, et poinp discharge preocure, pump suctior care w ur u, a punip t1ow.
I b.
lhe par tit wlit t e cavatotion it nio t. t.
111ely to beann ib ttu-h i gh-on*L uun, discharoe cr ea of
- t. h e p oinp.
(:
It o voi l et.l e net posi t i ve tuc t i ori tieed (14P bH ) lb po01tivo, e t, v i t e t t ori U111 i'iO t occur.
d.
'the nytt.mo iluid v te l c it i t y tien f in e + f Etc t on the probabilit f 01 p u n
. int zero per cent c qui l i br i uni va l ue. How wall the 1'non concent. ration be trending in the followiny three e, x t u o t i on o 'r e. tine hour aftrr tiir ieip. [U.33) b.
- 1 houro a+ter tho tttp.
[U.33J c. 14 U haut b c41te t h t. trap. t he r ecc t or was t.d er e beck to
- _ r 1 t a c e t and power roturned to bu t.
at 17./ in t n. What would be the trend au power reccbec t.u ?. 'r [ o, ", l, j l I 1 e i i i l I ) l l t***** L n i E t.311R ( 1 COf t I liJUU) Ut1 (JL x1 EnGL......> l .m t l l I UUEfa l J Of4 1.12 (1.00) If t ia c.ondensate lcrvel a ri si Low pressure f eedwater heater 1.e .t l l ow ed to incet*oe, t-3PLf4111 What will noppen to the temperaturn of the f eedwot ur-e<1tifiq the heater arid why. (1.O) 4 (ao'aume power
- op er a t i on t. )
i t I t i k t ) t i i l P k t 6 i l I l l l l l l j r f t ? I I (*++++ Ca t E.bOh v 1 CUI41 J IJLfLI) Ull tE X I 19 hb E
- )
A t i I I i l + i utJESilull 1.13 (1.00i I Poe t t or power i t, i ncr uc sed + rom 50% to 100%. luipl +1 n Iww will DIFFEREtJ11 Al. rod worth change +or each of the following c und a i ) onc / Connader each tone separetely. i Hod pas.1 t 1 on.ind baron concontratson are hol d contatont, t ump er.. t u r o 4v.bu) as al3 owed t o dete r eaw. 2 b. Hod panstion i sa constent, bor un concentret1on as diluted to sna n n t.w i n ( u. C.u ) t en.peret or e conut ont. J t 7 L i 4 'I ) ( I 1 J .) i I i ) i 4 a a 1 I f l 4 ) I 4 f 1 1 l j I (***** CAlt tnJki 1 Luta l lt4UhD Oil (JE x l FnoE +++++, i I l l . _ = _ _. _... o, t t J DUE b l 1f 114 1.14 (2.00) 1 E plein i tie tieh o vi or of the D-itet.tse r esctor iollowing a riormel reactor tr1p + t om l ot s */, power. (i ncl ude i t) d i ticusci ori the offeet of both prompt and de? ayed titeut rons on tim stout < lown period.) (2.9) l i i i f L t I i I f f I L l c [ f [ r h I t '1 i l i l ) .Y t i l 1 ] (eoeea C(4] E(3()R y } t (j{ 3 { } {fijQ() [jN g,h y l g e fQ,y ,,,,ay o o l UUESIION 1.1D (1.00) Refer to fiqueo 14 on Why d o rn, the power doppler r eatti vi t y def i ci t curves change f r oin
- 07. power to 2 / *. p o w e r C'
(.UU) ti) Why d o * > t, t h er, te t arie power d op p l e;r react 2vtty c ur vers chanue f r ota 27% power to 10 0 ',. ~' (.LO) l l l (***** IJ)I F bt th 1 LUN I t hull) 014 16 41 i'inbE +++
- )
e t l i 1 ) ) UUESIluf1 1.16 (1.00) j f eer!wnt r r teroper etar e var s e.> wi th loed over a range of about.?B O to 46t> j d eyr ect Iahrenheit. tinplein how thermal nhocit is minimizrtd j to t he-U n bt3 t;he l 1 and 1 t F. 1ower t utste t>h oe t during plant st a r t u!) r' t 4 l 4 I i 1 a 4 a Y i f l ] l 3 ) i ,i 4 i l i l ] i I i 1 I (+>*** CATEuGNY l LUf 411tatllil; tirJ I4E A T I dibh
- =-)
,o 4 e 1 l 4 3 i utJEGIION 1.17 ( l. !>0 ) J + ~1 Rldi or FALGE l l Annwer ther f ol l cawing ikUE cir F AL.5E wi tte rekpect to Axi al Power Shopireg .i Roda (APbH) unod to dmopen Xenon os c i l l ei t i on s. t i a) 14 APSR arti trio v e d, it will take 6 to O tiours to detertnino l if APSR are inoved in wrono direction. (u.56 L) APSR pobation of 4 0*/. withdrawal i n all owtid dur i rso all t i nies l f l In core cycle b. (0.U) I
- c. ) iWSk move of 4*/. wi thdr awal usually t al es car e of a
- 1. ta.
1 :nb e l a n c o. 4 O. M i 1 1 i I ) I i i i l l l 1 l i 4 I l i (+++++ Cn ! L GUF6 1 t,OtJ i l NilED LIN ND. i Fwist *****) =, 1 c UUESI LOrt 1.'10 (1.SO) i Ane1yuie of v a r i (>u t, accidonts h a s u t..e n per f ornied and presented in thu ULak (Upda t ved S o f *2 L y Analvaaiu Report). briof1y EAPLAIN for nach of the iofIovnno a tt i derit r. : .I t;cirit r 0 1 Rod Abu nibi v 1)r op at power. ( 0. '!O ) { b) Louu of a 1,*ut w t. n a e F et d w.a l er Hoa t et * ( u t eevn supply) (0.00) at p t.w tet i ( ~l lf1E UF L i f 4: ( Ut JL t10L. EUL ) and all the factotu which csuboa tho most the j t ve ro pl. rit it anti et t or c on s.uq u en c t?. a L f .1 i 4 i 4 l ) i ,i i 4 1 l q j J i-1 i 1 1 4 4 i l i 4 1 (***6* CHILUURr i Cufil ll 4UE D bil (Jii x i P(.Ce.
- +4 I
f l 4 ._____m_ m s t 1 UULbIION 1 19 (2.bu) nf t er o reactor trip from a 20 duv ruri et 100?..it 14GL, STATE the effect. of the following on GHU1DOWtl MAHOIN: e) Lio r a t i sig 10v ppm. (O. D) b) Detvino APSR from C O *4 4 W D ) t o <>?. ( W U ). (O. S) l l c) Coolino dowri f r orii no loed l avt, t o 20i > F. ( 0, 5 ) [ d) Wt thdrewing at oups 1-4 rods. (O.S) i er ) Wet t i ne da hours. (O.D, (Lonntdor o.ic h ui tuat. t on independently, Itmal ianswer 1o INCREASE, I'l:t:.RE ASE, or GAMi SHUlDOWN MARbltJ. ) d 4 i I e 1 l i t i l [ [ c ? 4 i l, b l l l I I t i t i I i I t'**** Et40 UF C h t E-b Dh 'r 1.....> ,__ J i e 'r[s. LLdd.I. lS.ElOd lfdibl)91dl3JOEE11 6dl.L.EdEfidEUEE F*4P 2I EXU 1.E.05 I I O Uf.b i i UIJ . '. 01 ( 2. '30 ) in 190 /, a nie l 4 uric.t i on e of cri a rictr tuharit eir dryer i tsol est i on val va al1 owed I n u t r ueien t mr prezwure t o decr<=ouu to /4 pstg. 'l h o ICS responded 'n outo j etid c m.t.ed a h a rah + 1 u:t reactor trap,( the cor e bei tig late in life - EOi. ) j a. U E bl.' R I D E wh c. t. plont sivst oitis rouponded to tha s inal f unction and how the J(S respotated tn ihan t r ant,3 ent. L1.6) b. Describe why.and how the r o.* c t or trip was generated. ( 1. 2 's I l 6 r N i I l t t r t 6 I i l l i ...... au tuota e connuus,on ta n ena....., h b ,--..,_,c I q* I i 1 I i l l i f + i i UUliS 1 1 CN Z.02 (l.001 l 4 It the 1)/G output tir oo l1.ttr will Nul close due to a C1 (D1) bus l i oci:ou t, overheat a ny diumel desmago may occur when the diosol 1s 1of L running. I:xplain why the diesel would overheat under these conditicine. I i l I [ I i ii I t I l i e l ] I i j i i t I C i l i l 6 I t l t I l 1 L I (***** CnlE UU6 r 2 CON 1 ItatD UN ta x i F evs ++.*> ~ . y _,... -..... _. _ _ -. i ? e t i f i;tJh b I 1 DN .?, 0 3 ( 't. 0 0 ) If te d i r= t.e l gererator fails t.o out o t t ier t, do NOT re-energire e 416V volt bus wt th a snakuur puinp be uakot* clouod and K'J-19, Seel Injuction Controller. nn auto es. damage to the RCP t.ual c coul d occur. Depl ain how arid why the Fl;P so+1 n woul d be damaged 1i thasa cauttun wetn~t hueded. [ t + I I b r l h I t I i i i [ [ k I 1 i i t+++++ L d e l l L-O R Y J LO:41 ItJUE D OrJ NEx1 F,wt **,,,, o. .-i r ,o OUEG110(4 2.04 (u.73) nt 100% pc.uct an eri RO, lir>t what vote woul d expect for normal RN'seel pretsuure for tii+= thrette coa l s i n or den-to calcul ate t+ any RCP's abnormal seal leakage i t, pr escrit. 4 l I l l 1 I l l t+++++ CalEGORY 2 totJi It4tJL D UN NE G FNL +++.. I l i I i 000.5iiUN 2.OS (1.00) Wtisch orie of the f oll owa no paramuter s will NOl c ie ut.e a t r i p of the (nai re turbine ii the sotpoint in oncoeded') (1.0) l e. Hi oh enheunt hood t oroper a t ur e. ta. Low be.rtog on1 prout,ur e. [ i c. E n c e'a ta v e t h r u e,t b eer i ng ws r<r. I d. Low hyde.sulic tlutd pr onsur o, t ? [ f f I i f a f 5 l l l t (+++++. Cit l F CSis Y 4 CON I A fJUL L' Of 4 HE ) I 1-AL-E + + e k + ) . o ( l e i j OUES1IUr4 2.U6 (2.00) i j bru. r i tie tiow t t u n e. w nucleer ari trument power r arigen input looic 3 14-voed in the ICS t eact or dt?niand sec ti on. (i nc l ude coi ncidencte/ u if applicablo and l@Ji power ) mbbut th f 'UWEii t)PE Fm T I bNS ) (2.o, J 4 i l 4 i l } l i j 4 l l ) i 4 e i l l t+++++ CATEGuky 2 Cut i l I(Rih:> Ul1 tu A I Fsu;E.. +. + > i e (Mli b l litid . '. 'J / (l.00) l iie tor ts a t,o Li vp e t s volvcr> t>er ve in t her e v e:iit of a recctor trip tu proside a h i oli pr ou ;ur e eeiliof twatnning at 145 pst a t> o v e the 870 puig u o t.p oi n t. E vpl onn &.lty t hc-t> i.4 n of 1 % pt>1 as AI'DED t o the 870 peng reitet s o t p o ttat dortoo she i e...: t o r tesp. l l l l \\ t i l i....+ (.,u u.un i c tuin ar it t, t u a rn > i Wust:.**..> I ___.m. t i i I l l OllEb l IUf1 2.98 ( ?. 00). hegorditio en emeoyescy tat er t of the E mur <j enc y Gener ator c s 14 tho *2pimd governorm of tt'e hmorgency Diesel Gunerators wore failed to the droop mode of oper et t ore, what two potential problems may occur for l } equspment that traeu to st ar t or t u stat tod on thu 4160 volt saf+ety related i butbet 1 .k 1 t i i i 4 ) i 1 i b i l l { b 1 l 4 i 6 1 b i li j r I t I I I i i n h 4 i I I i i l i l I 5 L (***** CATEGORr 2 t OlJ iltJLiEle tii4 tJE > 1 F 4,L,L ....,3 s s Ol)E S i l utJ 2.09 (1.000 0,F AD c ont o t rimoret ke d 101 i ten L.ow fallure clarm is riormally ori whers ro. actor power is 1ow. Explann why this el aren tu on for this condition 1 \\ ) \\ l \\ \\ l I 1 1 1 l l l i+++++ C A t t uorn 2 Luul traito ou taEx1 hmE.***+> ,j o.. j i a t i i f OUFS) t ulJ 2.10 ( *. !. 0 0 ) t tie pri nian y mel.:trup crid puri f a cet101: Lyt t en. b.ir i riy lutn. power opt r ut i Otet., deel. v coi1 temper 4 Lore indtcator +atIr<1 hagh. (swunv no oper M or ettion, desc r i b t= how t f.e tual. crup syst em tr arit>i carit a f i ec t r, tlut pteasurirer emph:tst:nng the reuponue of tho automatic prouuur a zier level c on tr el t y t,t eni pr escitr 1 ; et-level. 1 l i i l l l l l 8 I i f i l I. <..... v.mmse
- comm, o om
,<e., m....., a _ ~ OUESTION 2.11 (1.00) Rapid Feedwetor Reduction system is activated. Low l evel limits have been reacheo on 9/G loop A for 75 seconds but S/G loop B has not reached low level limits. Describe ALL the possible resultant actions in regards to RFR to S/G LOOP B from the time S/G loop A reached low level limitu. (Include time limits - no setpointo required ) (l ) I i t. l t. (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) I _ - - - -..... ~. .,I. _... ~ t QUESTION 2.12 (1.25) Answer the f ollowing questions regarding the Fire Protect, ion System.
- i a.
List all the methods the Fire Protection Water System can be pressuri:ed when there IS system demand? [1 03, (include st;urces of water) b. What automatic fire suppression system prostects '.he Ee.tr genc y Diesel Generators (1 and 2) LO.253 A l'. 4 t i l 1 i l i iF I ' t I (***** CATEGORY 2 CONTINUED ON NEX1 F AGE + + + + + ) t. 1 a. ( r OUESTION 2.13 (2.00) Smart Analog Signal Selector (SASS) will automatically,' switch ICS input signals when it sennes a complete ICS signal failure between.a X-POWERED and Y-POWERED signal. List at least fave ICS input signals sensed by SASS. (DO NOT REPEAf SIGNAL TWICE) 4 8 ~ i. i d. 6 i 4 t (***** CATEGORY 2 CON 1INUED ON NEXT PAGE +++++) t ? ) i i e l i OUESTION 2.14 (2.00) The Component Cooling Water System supplies five separate components on each Reactor Coolant Pump and Motor. What are four (4) of those five coniponents? g 1 I 6 J i t l 't W
- p.
I 1 a ![ (+++** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
u .i." A_ ; _ n1 ; o e QUESTIOt4 2.15 (1.50) a. How is inadvertent draining of the Spent Fuel Poo! piping prevented. (0.5) b. Which one of the following is the rnost correct reason that Spent Fuel Pool boron concentration must be maintained greatter'than 2000 ppm 1 I during fuel transfer operation? (0.5) i 1. Technical Specification requirements. l 2. Assure safe storage of spent fuel. 3. Prevent dilution of transfer canal water. Other than boron concontration, what one (1) Spunt Fuel system design ) c. feature ensures that criticality will not occur? (0. 5) 4 3 l l n. t t l l I i (++**+ CATEGORY 2 CONTINUED Ot4 NEAT PAGE **+++) l .o r DUESTION 2.16 (2.00) Regarding the Reactor Coolant Pumps: What is the purpose of the following Reactor Coolant Pump start interlocks? ~ e. Reactor power must be less than 60 percent of full power. (1.0) b. Reactor Coolant Systems cold log temperature must be greater than 500 degrees Fahrenheit. (1,c) l l l l I l~ f 4 i l l t (***** CATEGORY 2 CONTINUED ON NEXT PAGE
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..........~.:.... r QUESTION 2.17 (2.50) With respect to modifications of Makeup Systems mr ^t ei 4. LIST the advantage of relocating the new makeup ~ pump suction (1.0) lines to the HP1 suction linus, e 6. The new throttle valva (MU 6419) and new injection flow path could be used for two purposes. LIST the two purposes. (1.5) l ~ I \\. [ I, d g 1 'd 't l (***** END OF CAlEGORY 2
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l l ) ~a i... ~ r 8 Es. lUhlRUt.ENTS AND,,QQUIRQLS Page 39 1 OUESTION 3.01 (1.50) Assume that the ICS is in autornatic with the reactor at a steady-state power of 757. with Group 7 roda 857. withdrawn. Describe the change in rod position (higher, lower, no change) that would occur due to each andependunt uituation.(No explanation required) a. The boric ecid concentration of the RCS is increased by 15 ppm. b. Tavo han increased to 592 degruos F. c. Following operation at 70% power for 7 days, power is to be reduced to 257. by rod motion only. What will be the change in the 257 rod pocition after 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> at 25% power. { 4 i i 4 i .I i A e I E ) 4 I 1 i 1 1 1 4 4 } \\ .l I ) 1, t (***** CATEGORY 3 CONTINUED ON NEXT PAGE
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j, i> ,.---n.-.--. --,=.-----.---n . 4i e DUESTION 3.02 (3.00) Using the enclosed diagram of the Integrated Control System explain the actions that would occur in the following control sections if an Asymmetric Rod condition occurred at 00 percent of full power.( Include the actions. that the control sections take wi t's respect to components and other interactions.) a. Ftedwater Control (1.5) b. Reactor Control (1.5) i I / 4 1 l I l, I, J s 1 i i l l l i l l 1 1 4 ' -j I-(***** CA1EGORY 3 CONTINUED ON NEXT FAGE
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'f ~ ~ -.. ~. - DUEG1 ION 3.03 (1.25) the five modifications made to the Reactor Protectior$ System (either List automatically or manually) when the shut down bypass key switch is placed in bypass. (Setpoints not required) e. d, - l b r l l l I l l I i i i I j-i 3 l 1 (***** CATF.GURY 3 CONTINUED ON NEXT PAGE
- s) 1
- - - _ _ ~ 3. ...._...._..-.a_...... . _ _ _. ~... - _ _. l i e i OUES1 ION 3.04 (1.00) Explain WHY each of the statements below is FALSE. }/
- a. A patch panel is used to ruassign specific APSRA drives, b.
Thu APSRA do not automatically insert on an RPS signal to open tiie CRD's i ~ breaker because their DC hold power supply in not fed from the affected l breakers. i t i i l l i i I b i s t i I 1 I i ( l i l i I .l l i e 1 l e 4 I I ( l (*+++* CATEGORY 3 CON 11NUED ON NEXT FAGE ***++) ,6 r 21 ,_-___-y_ .. -. _ _ _ ~. - _ _ _ - L.... -.. - - QUESTIUti 3.05 (1.50) 1AW S/G lovel setpoints! list ALL the S/G level setpoints for the following conditions (includo AFWP dischar ge lineup options if applicable) ,o a. SFRCS has actuated and SA2 has not actuated b. SFRCS has actuated and SA2 has actuated c. SFRCS has NOT actuated 4 3 4 j J 1 e L 1 i 4 ) l l D. I e i 1 i (***** CATEGORY 3 CONTINUED ON NEXT PAGE
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.6..'..,,........ .~. -n-- +- - - - l l s f 4 OUESTIGN 3.06 (2.00) Explain how a RPS channel 1 in manual bypass for testing would have its CRD bruaker trip from en Anticipatory Reactor Trip System (ARTS) signal (2/2) logic from two main focid pumps tripping. (assume power operations) k 4 e. 4 I I i i t l 6 4 f 1 1 (***** CATEGORY 3 CONTINUED ON NEXT PAGE
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I L...s.......................,.'..-;...;. e QUES 110N 3.07 (1.75) In the redesigned Control Rod Drive system, a rod stop button has been 4ad d ed to the diamond control panel. Describe SPECIFICALLY how this pushbutton functions when, actuated. (1.0) e. (include in discunnion what in energized)
- b. Does this button need to be reset like the direction error detector 7(.5)
- c. What CRD power sourcu/s is/are not affected by this rod stop?
(.25) I 1 i ) i i i (***** CATEGORY 3 CONTINUED ON NEAT FAGE
- +)
L ,_i...f...a__._-....~-..-.a~_-__-~--.-. o a OUEST10N 3.08 (2.00) The Reactor Protection System in designed with two types of bypasses; channel bypass and shutdown bypaus. 4 a. Define manual channel bypass in terms of its function. (1.0) b' I;efine shutdown bypass in terms of its function. (1 0) ? I 2: 4 (...** CATEGORY 3 CONTINUED ON NEXT PAGE
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e QUESI10N 3.09 (2.00) A limit and precaution in SP 1100.03 warns us not to reset SFAS level 2 trip until offwite power is restored when the EDG'o are supplying C1 and D1 buses. Explain the precatttion in resetting the SFAS trip? i I I t J i l + i 2 i (***** CATEGORY 3 cot 4T INUED ON NEX T PAGE
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'a. ....-..----.c,a .o ~........ o QUESTION 3.10 (2.00) A full EFRCS trip has occurred due to 01SG #1 low pressure'setpoint of 612 psig. List the actuated position for the following components (open or closud) for this SFRCS trip. -3 i a. ICS 11B, AVV #1 b. MS 101, MSIV #1 c. MS 100-1, t'S I V Bypass #2 d. MS 106,.#1 MS to AFPI #1 e. MS 1U64, #2 MS to AFPT #1 f. MS 107, #2 MS to AFPT #2 9 MS 107A, #1 MS to AFPT tt 2 k ? h. FW 601, MFW STOP VLV #2 (.25 pts ea.) 1 5 -2 1 1 J i i e t k i I I 1 i J (***** CATEGORY 3 COhTINUED ON NEXT PAGE
- )
g t I .__m. i ~.._..__._. e DUESTION 3.11 (2.00) Answer the followino questions regarding the Nuclear Instrument Systems Answer nach part independently. a. You ere ccnducting sa plant shutdown from 30% power. What specific conditions will UN-bypass (remove) the High SUR rod withdrawal inhibit circuit? Specify channel or component numbers and setpointu. (1.03 b. You are perf orrning a plant startup from a Source Range level of 10 E-2 cpp. Li st all specific c ond i t.1 on s throughout the startup rill inhabit rod withdrawal? Speci f y channel or component nutuber s and setpoi nt s. (1.0) e l l a i I l l 1 l l 1 6 } (++*** CAlEGORY 3 CONTINUED ON NEXT PAGE **+++) .? . - - - - - - - - - - - - - ~ ~ ~ ~ - - - - - - -. - - QUESTION 3.12 (1.00) A reactor operator responding to a failed loop 2 feedwater transmitter upset denve group 8 rodu (APSR'S) in when the unit was at 100*/. power which r eesul t ed in a high flux trip. Why did his actions cause a high flux trip? h k l I I t l l I I I (***** C AT E. GOR Y 3 CONTINUED ON NEXT PHGE
- )
i ~ - w o - - c. - - e,. i N i QUES 1 ION 3.13 (1.50) State the two types of Rod Position Indications and brie [1y describe how each of their indications are sensed? (1.5) i .,4 6 4 t l i f 4 e 4 i 4 f F l' I l I i i I 4 i .i i 1 I J 'I i i 4 (****+ CAlEGORY 3 CONTINUED ON NEX1 PAGE
- )
r t .i -,,-__----r,. 7, -.- m,. __.,. - - -., o....s..- ..~.. e QUESIION 3.14 (1.50) ' ~ Rogerding the Di amond Control panol State all the condit1ons will cautu on "Auto inhibit" to occur? .L I l' r i e u 9 i i t <i h 4 (+#++* CATEGORY 3 CONTINUED ON NEAT FAGE
- )
6 ..........--~-........,-..s.e-~~u.n... QUEST 10N 3.15 (1.50) SFRCS was redesigned during this OUTAGE. );,.
- a. What four (4) single solenoid components are now powered auctioneered to prevent single l' ass of power actuation.7 (1.0)
(.50) b. What is the GFRCS low level trip OTSG setpoint?. i I I J i 1 L I t 1 I i l a i i i l l 'l, i l I l i .a 1 i l 5 l 1 /' I i. 1 i (***** END OF CATEGORY 3 *****) l . s....r.... e
- 4. _EB9sEDi'36!i
_U9600ba OEU98dOb2 EUEO9009%
- 9" 3
OU9_B09196991986_GOUIB96 ,e QUESTION 4.01 (1.00) I AW Emergency Pr ocedure EP1202.01 RPS, SFAS S/G Tube Rupture Procedure if neither TSAT inoter is available, how can an oprirator verify adequato subcooltrig margin exists? I 4 / e i i i ) l l ?4 i i i l (***** CATEGORY 4 CONTINUED ON NEXT FAGE
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j l 1 ...-.-...-s.....~. QUES 1IOt1 4.02 (1.00) (Asv.ume 100% power, tee attached Tech Specu) (3/4.3.7.L Recently ILC personnel bypassed the Safety Features Actuation System (SFAS) Channel 1 Containment Radiation Trip Module while performing post maintenance testing on the failed level detector (RE 2004). Which one of thu following actions should have been accomplished in accordance with Tech 6 Spocs? e. Action 09 b. Act1on 10 c. Action 11 d. Action 12 e. Action 14 l I .I 4 4 i i 1 I l 4 L ) l i a l. .I 1 ) s 1 i 4 l l I (**++* CATEGORY 4 CONIINUED OtJ NEXT PAGE ++++*) L A _. 1.i.. _ _ 4 __.-.-.-.4-.__....___... i l GUESTION 4.03 (1.00) List the two parameters to identify the steam generator with the steam l ag + por Excessive Heat Transfer procedure. 4 i t e 6 i i t I i (++++e CATEGORY 4 CONTINUED ON NEXT PAGE ** *** ) 1......v......_....-.-....----w....-...... . ~ - -. = 0 ? OUESTION 4.04 (1.00) According to EP 1202.01, "Steam Generator Tubo Rupture," what in the backup method of dotormining which S/G has a tube rupture if RE609/RE600 are inoperable? 9 4i e P I 1 s l 1 1 l l l \\ t 4 4 i i l i I (***** CATEGORY 4 CONTINUFD ON NEXT F AGE
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.'li ...e... ~.T Z.. - - L. - a a - -. -. u - - J - - - - - ~ " - - 1 i QUESTION 4.05 (3.00) Per "Inadequate Core Cooling," section of EP 1202.01,, r a. Underr what all conditions can the RCP start inter 1ceks be Jumped (1.0) out? b. If component cooling water is not available, what is the maximum time limit the RCP's can be run? (O*U) c. Lint the threu methods evailable to the cperator for core cooling if a t Inadt quote Core Cooling condition exists. (1.5) l i i i L il [ l l r i I L I t I i t l l i (***** CA1EGORY 4 CONTINUED ON NEx1 PAGE *++++) 4 . ~.. a.. v v - u = DUESTION 4.06 (1.50) 3 In "RCS Sat S/G Removing Heat," per EP1201.01 several' containment poremotoru are monitored. List four of five parameters to be monitored. (no sutpoints required) i l i l l k i 1 i i l' l [ i l t f i i i l (+++++ CATEGORY 4 CONTINUED ON NEXT FAGE
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. o _ a. _ _. _. _ _ _ ) 1 t GUESTION 4.07 (1.00) According to EP1202.01 procedure "Solid Cooldown or Pressurizer Recovery," l you should anticipate what two effects on ther prirnary system when you restort RCP's on natural circulation or with pcosible steam voids in the RCS7 l i i i f e l i + 5-l f t t ( l I 1 r 1 e l ? I i 1 l 1 4 1 l ,1 j (***** CATEGORY 4 CON 11NUED ON NEX1 FAGE e*+++) ...... - - ~..... 4 OUEG110N 4.08 (1.00) Assume full power operations and re'2+ to the attached Tech Spec excetpts (3/4-8.1) to answer the following. In the event Emeroency Diesel Generat+sr (EDG) 1 is taken out of service f or i scheduled pruventive maintenance r$sair, which one of the following actions would be niost correct in accordance with Tech Specs? 4 I e. Demonatrate the operability of two diesel generators by performing SR 4.0.1.1.2.a.4 after EDG i s repca red after 1 day wi thin O hours and at leaut once por 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereaftwr. b. Demonstr ate the opt r abili ty of tho+ renian ning AC sourcen by performing 4.8.1.1.14 within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. I c. hentor e at least two diesel generators to operable status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> f r ein ttmo of initial loss. d. Restore at least one of the inoperable sourceb to operable status with + j in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or be in at leant Hot Standoy within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. i ] i
- I l
i i 1 8 I b t I + l J i l a b 1 1 O d l I J ) 1 1 1 4 l (***** CATEGORY 4 CONTINUED ON NEXT FAGE **+++) ) OUESTION 4.09 (1.00) On your shift, a monthly surveillance item is discovered overdue. Required date was 25th of the month, assume today is the 31nt, and the performance c. the SP hah begun. All previous surveillances were completed on tinie as scheduled. Which one of the statements below tu correct about the survuallance (SP)? a. The SP has been mi ssed and the syste:a munt be declared inoperable unti the SP 14 compluted satisfactory. I b. The system as operable as the lechnical Specific tavns ellow a monthly 1 to be waived 1 month out of 3. c. The system is inoperable because the 3.25x time interval for 3 consecutivo SPs was not met. l d. The s y s t <> m as operabtr because the T richni c al Spectf1 cations allow a time e>ttension which has not been exc'eeded. l l i 1 v 4 4 [ J I i l J \\ l l (***** CA1EGORi 4 CONTINUED ON NEXT PAGE
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{ l - -, _, _ _ ~ _ -, - -.. - - = _ - -. ^ - - ~ - - ~ ~ ~...-_.- _.-.. l \\ OUESTION 4.10 (1.00) If the HPI System has actuated due to a low pressure condition and i s providing core cooling, what is the criteria that must be' considered to secure the HPI system? (1.0) 's e p, I C, t M9 r. (***** CATEGORY 4 CONTINUED ON NEXT PAGE
- )
- G L-.s-.....
~ -,-o ~ --...-.--..=--.:..:. :...;.: 2 i OUESTION 4.11 (2.00) >z Answer each of the f ollowing questions TRUE or FALSE based on the requirdment of the emergency operating Procedures (EOP 's);.. Answer each part independently (0.5 points each) fiy,. 2 E 4 a.' You are executing the "Loss of Subcooling Margin" (SECT-5) procedure f when you determine that a steam generator tube rupture (SGTR) is l I. occurring.You must IMMEDIATELY EXIT (SEC-5) and TRANSFER to "Steam Generator Tube Rupture" (SECT-0). l b. You are executsng the "Inadequate Core Cooling" (SECT-9) procedure when you determine that a steam generator tube rupture (SGTR) is occurring You must IMMEDIATELY EXIT (SEC-9) and TRANSFER to SGTR (SECT-8). ] c. You are executing the SGTR (SECT-S) procedure when you determine that loss of subcooling margin (SCM) has decurred. You must IMMEDIATELY
- SCM" (SECT-5).
3 - EXIT SECT-8 and TRANSFER TO "Loss of d. You are executing the "Excessive Heat Transfer" (SECT-7) procedure and have just shut the Turbine Bypass valves from A-0TSG when you determine that the excessive heat transfer transient has terminated. You must COMPLETE the isolation of A OTSG and CONTINUE with (SECT-7) until the procedure transfers you to a different procedure. i 1 l i i l r f 1 i 1 l 4 m ). (***** CATEGORY 4 CONTINUED ON NEXT PAGE
- )
t........... ..~ ~ _~~~~.,~ - e OUESTION 4.12 (2.00) Which of the following are addressed by your Technical Specifications? Answer YES, if the item is addressed and NO, if it is'not addressed. (2.O) 'a a. Axial power shaping rod ineertion 1imits b. Core Flood tank level c. Fire hose stations d. Plant Computer e. Incore nuc. lear detectors f. RCP Seal Injection system g. 01SG criemistry h. Containment air temperature I r (***** CATEGORY 4 CONTINUED ON NEXT PAGE
- )
t(l ..a --* a -..--- ~ QUEST 10N 4.13 12.00) TRUE or FALSE STATE whether the following statements are TRUE or FALSE:with respect to Approach to Criticality (PP1103.08): ,,g4-a. If criticali ty i s established af ter the lower rod index and before the upper rod index limits are reached, insert all regulating control rods and resolve the problem before continuing the startup. (1.0) b. When criticality is established, raise reactor power to 10-8 amps on IR NI and using control rods bring reactor to a stable condition such that power is constant. In RO log, enter the following informations time, control rod group positions, RCS baron concentration, IR NI power indication and EFPD. (1.0) (Consider each separately.) t! 1 1e (. (***** CAlEGORY 4 CONTINUED ON NEXT PAGE
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A-,."_s._.__._____.:..- s GUEST IOfJ 4.14 (1.00) According to Emergency Procedure EP 1202.01 RPS,SFAS,SFRCS Trip, or SG Tube Rupture SPECIFIC RULE 4, what is one of the two-(2); methods to reactivate SFAS equipment that has been blocked and over' ridden after an SFAS trip. r { 3 i \\.. J 4 t (***** CATEGORY 4 CONTINUED ON NEXT PAGE
- )
t ,sr.._..-_ __..a__--_...-~~.......-___. QUESTION 4.15 (3.00) If control rods fall to de-energize inresponcetotheRkStrip and Manual trip, STATE the required action per Emergency Procedure EP 1202.01. (3.00) (Include all substeps if applicable.) ? ..',T : I J t s i (***** CATEGORY 4 CONTINUED ON NEXT PAGE
- )
. % u
..- --_.~.....--. -
QUESTION 4.16 (1.00)
What lech Spec actions (including maximum time l i mi t s, "i t, any) should be taken by the startup reactor operator if during a reactor startup N1-1 fails low?
Prior to the failure, channels had been increasing with the exception of NI-2 which had been holding conatant at 3x E+3 cpm. At the time of the f ailure, the channels read NI-1 5x E+5 cpm NI-2 3x E+3 cpm NI-3 Sx E-10 airips N1-4 1x E-10 amps JUSTIFY Y0. lR ANSWEf '.
I i
e i
1
. t.
)
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l
.e.".'..:............___..........._.....a.__..._..__.._._._._,__
c-QUESTION 4.17 (1.00)
Davis besse Emergency Plan provides guidance on worker radiation e><posure during an Emergency :
a.
STATE the allowed dose limit for lifesaving actions.
(O.D) l.
~
b.
A Shift Foreman volunteers to enter a HIGH RADIATION area during an emergency to seerch for missing personnel. His reason is that five years ago he entered the same area under similiar circumstances and feels confident about what is needed. He recieved 90% of the Emergency Dose Limit during the previous event. Radiation Protection untimates a whole body o>:posure of 80% of the limit for the current planned entry. EXPLAIN whether this i ndi vi dual can be al1 owed to enter?
(0.5) 4
?
k
(****a CATEGORY 4 CON 11NUED ON NEXT PAGE
- )
l",."--.-_....
QUESTTON 4.18 (1.00)
During Emergency Conditions, such as a fire in the Control Room, 10CFR 50.54 x allows operators to deviate from licer a conditions or Technical Specifications.
3 a.
Two conditions must be satisfied before the deviation can be authori;:ed.
BRIEFLY state one of these TWO conditions.
(0.5) b.
Such a deviation shall be approved, as a minimum, by what indi vi dual (s)
(no titles are required) ?
(0.5) l' l
(
(
3
- 1 l
(*****
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- )
)
(**********
END OF E X At11 N Al l ON o * * * * * * * * * )
I
z.L.-a.........-_.-------~.-----------
= ~ ----- -
It__E81NCIELES_QE_NUQ(E88_EQWEB_ELOUl_QEEB@llQU3 Page 71 IUEQUQQyU8dlQ@z_UE81_lEONSEEB_8BD_E(ylD_E(QW 1
ANSWER 1.01 (1.00)
}
[
" c. " 6/2. h REFERENCE RTR-OLC-025-OO - pg.
5, 7
192OOOK110 192OOSK103
..(KA'e)
ANSWER 1.02 (1.50) a.
True b.
False c.
True d.
False e
e.
False f.
True REFERENCE PP1102.02.25, pp. 66,RTR-OLC-026,SRO-RTHO10 GOP-OLCOO4, attachment TS 16.01, PP1102.02.25, pg. 63 ICS-OLCOO6 P14 5
192OOSK115 192OOOK112
..(KA's)
ANSWER 1.03 (1.50)
)
a.
1.
Discharge head:
550 PSIG ( 2200/ (OC)OO/ 4000) 2) 2.
Motor Power:
100 kw (G00/(8000/4000) 3) 3.
Flows 300 GFM (600/(0U00/4000))
(.33 pt)each b.
As the toinpurature of the water decreases, fluid denstty increasen Co.25J requiring pump motor power to inceeaseCO.253.
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+****)
w_s_________..._.._.o._________.._-
8 Page 72 tt__EBINGLELEg_QE_Nyg6E68_EQWEB_E(QUl_QEEB611QN 1 ISEGdQDYUed1GSi_UE0I_IBOUSEEB_000_EbulD_E69W REFERENCE U-HTR-OLC019, pg. 5;HTR-OLC-021,P5 LJ.
1910f4K107 191004K119
..(KA's) 4 ANSWER 1.04 (1.GO)
"a."
REFERENCE RTH-SROOOS, pg. 7 192OO5K107
..(KA's) k
?
ANSWER 1.05 (1.00)
"a."
(1.0)
REFERENCE HTR-OLC-OOS, pg.
6, paragraph 4,
obj.
3.d.,
4.
193OO8K106
..(KA'n)
ANSWER 1.06 (1.50)
When rods were inserted, only prompt neutrions were affected and reactor power was stabilized 0.75].
During the time that the operator was taking critical data, the delayed neutrons. contributed to the overall neutron population C.75); hence, power increases.(similiar wording acceptable)
REFERENCE RTR-OLC-025, pg.
5, pg. 6 192OO3K107
..(KA's)
ANSWER 1.0/
(1.50) a.
Falso
,3 b.
Felso I
c.
True i
l
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++***)
1
!.2.. - -..
--. ~..-..-
11__EBJUGIELES_9E_UUGLEGB_EgW63_E68NI_QEEBOI1991 Page 73 IUEBb9pyNGUIgg3_UEGl_lBOUSEEB_SUD_E691D_E6gW REFERENCE i
1 HTR-OLC-011,AB1203.04.11, OPS-ORQ-26 j.
193OOOK122
..(KA's)
{
ANSWER 1.08 (1.00)
Increasing the boron concentration will cause the coefficient to become LESS NEG or move in the POS. daraction.(.bO)
With higher boron concentration mor e boron is in the core as temperature increases more effect of baron leaving the core gives more positive value
(.5)
--or--
as boron concentration increases keff vs. moderator-to-fuel ratio curve shifts to lower left (lower moderator to f,uel ratio) (.25) and since moderator temperature coefficient is the slope at mod-fuel ratio boron curve the coefficient becomes more positive (.25)
( similiar words acceptable )
REFERENCE RTR-OLC-011, pg.
9, paragraph 2.c.
RXTH-TP11.7 192OO4K106
..(KA's)
ANSWER 1.09 (2.00)
The oncess steam flow causes lave to decrease and insert positive reactivity C.501, the positive reactivity increase causes power to rise at
~
an increasing rate.
When plant reaches POAH, the fuel temperature rise will add negattve reactivity C.50] via doppler feedback and add Rx heat to stop the temperature decrease.
Reactor power should equal steam demand C.503 with temperature loss than original Tave [.503.
(dump vent valve -
capacity of 5% rated steam flow.)
(similiar wording acceptable)
REFERENCE i
T.M.S/G pg.
15.4-31 Als 1203. 33. 03,OLC-SUC-SU11 OOOO40K105 039000A204 000040A114 OOOO40A112
..(KA's) t s
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l
m;..____.....__..--_--_.-.
1 Page 74 I t _ _EBINQ [ELEg _QE,,NUQ(E 68_EQWE G _ELOUI_QEE B811QN 1 ISE8dORYUGU1GS1_UEGl_166NSEE6_8NQ_E(ylD_E(QW 4
ANSWER 1.10 (1.00) f a.,c.,e.
are true (0.3 pts each for including) b.,d.
are falne (O.1 ptu each OFF if chosen)
REFERENCE HTT-SROO13-OO 191004U101
..(KA~s)
ANSWER 1.11 (1.00) k a.
(1) ( Increasing towards peak Xenon concentration).
(0.33) b.
(4) ( Decreasing toward ::ero percent power equilibrium value.)
(0.33) c.
(3) ( Decreasing toward a dip.)
(0.33)
REFERENCE RTR-OLC-021.01 192OO6K107 192OO6K106
..(KA's) t ANSWER 1.12 (1.OC The level increase Exposes less surface area in the heater tubes (O.D).
There is less latent heat r ernoved from the steam, and therefore less heat transferred to the feedwater resulting in a lower exit temperature for the fuedwater.
(d u c r o a'se )
(.5)
(similiar wording acceptable)
REFERENCE General Electric " T her mod yn a rni c s, Heat Iransfer and Fluid Flow".
193OO7K104 193OOSK103
..sKA*u) i e
3)
I 1
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- +**)
l 1
_., _ =. _ _ _ _ __ _
w>..-----...-=
--~_z-..
i l
it_ EBIUCIELES_gE_UUCLE68_EgWEB_ELOUI_9EEBBIJOU2 Page 75 IUE8dggyN801Cg3_SEGI_IBONSEEB_QNg_ELUlg_ELgW af e
ANSWER 1.13
( 1. N )
).
s a.
Decrease,(.25)
Lower temperature increases the density thus reducing the number of neutrons availat-le f or capture by the rods.(.25) b.
Increase,(.25) Decrease boron concentration increases the number of neutrons available for interaction with the rods.(.25)
(similiar wording acceptabic)
REFERENCE RTR-OLC-019 192005K107
..(KA's)
ANSWER 1.14 (2.00)
After a reactor trip the reactor power experiences a very sharp transient drop for few seconds).5), followed by a stablo shutdown period (0.5).
Prompt neutrons are responsible for the transient prompt drop within a few seconds, but are the basically removed from the process (0.5).
This stabic shutdown period is baceo on the half-life of the longest-lived delayed precursor (s),
(which is 83 seconds)
(0.5).
(similiar words acceptable)
REFERENCE Reactor Theory 192OO3K100 192003K107
..(KA's)
ANSWER 1.15 (1.00) a) From 0-less than 27%, deficit is combinetton of MTC (.25) t< F T C (.25) b) from 27% to 100%, MTC is constant (.25) due to FTC.
(.25) i
--or--
A) BELOW 27% POWER DOPPLER EFFECT 15 ADDED TO MODERA10R TEMPERATURE EFFECT 13 ) FROM 27% AND UP THE REACTIVITY CHANGE IS DOPPLER, MODERATOR TEMPERATURE IS CONSTANI, THE FUEL TEMPERATURE INCREASES WITH POWER LEVEL j
1 i
(
~f i
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n I
.c _ a _. _ _ _.
.... _ _ _... o. c o c c.m c _ _ __..._ _ _ _ _ _.
1s__P81NQlELE@_QE_UgGLE68_EQWEB_EL6MI_QEE86I1QUt Page 76 10ESdQD10ed1G5t_UE01_ISONSEEB_6MD_ELVID_ELQW REFERENCE T.
GOP-OLC-OO2-102 Fig 14 2) p.,
PP1101.02.9 Fig 14 192OO4K107
..(KA's)
ANSWER 1.16 (1.00)
Aspirating steam preheats the f eedwator (.5) to a near constant T-Sat (.5) for the OTSG minimi::ing the thermal gradient.
REFERENCE HTT-SRO-OOG.
059000K103
..(KA's)
(
l ANSWER 1.17 (1.50) a) FALSE b) FALSE C) FALSE (0.5 pts each)
REFERENCE RTH-SRO-012,PP.10-11 i
PP1102.04.07,p.2 TS 3.1.3.9 4
192OO6K114 192OO6K108 192OO6K106
..(KA's)
ANSWER 1.18 (1.50) a) EOL (0.3), maximum worth of control rod (0.3), most negative MTC(0.3) b) EOL (0.3),mont negative MTC(0.3)
REFERENCE i
USAR p.15.2-42,ib.2-13,14 192OOSK107 192OO4K106 192OO4K103
..(KA's) l I
J I
1
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u.-. m... o.. _ _ o............ % o. o. _ __ _.._._ -.-
e__._-___...
o 12__EBINc1ELES_QE_UUg(E0B_EgWEB_E68NI_gEEB911993 Page 77 IbEBd99YUBU1954_HE9I_IB60SEgB_8Ug_E691g_E69W i
gis l1 ANSWER 1.19 (2.50)
> 'll..
a) IfJCRE ASE b) DECREASE c) DECREASE d) 54ME e) DECREASE (0.5 PTS EACH)
REFEREtJCE PP1101,02.8 figure 11a,11b RTR-OLC-023,pp.6-8 192OO2K114 192OO2K110 OO1010K517 [
..(KA's) w-( ~
M t
i t
!i
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4
'f
_ _ ~ _.
i
- s I
Hu _E60NI_GEG10N_ING6YD100_H6EEIX_0ND_EdE6@Eggy Page 78 61EIEde 5
f
'i 7 g:Ligs -
h *,-
ANSWER 2.01 (2.80)
'.J t.
i m
- s. Low instrument air causes LP heater drains,HP feedwater heaters,MS drain
. tank, 1st/2nd stage tank reheat drains and feedwater heater bypasa valves
[
to open.(or feed and steam system valves open to dump steam and
~
condensate to condenser) (0.4)
ICS responded by increasing feodwater flow (0.4) and pulled rods out.(0.4)
Reactor power increased and reached ICS high demand limiter I
setpoi nt. (0. 4 )
- b. Increased feudwater flow caused a decrease in reactor coolant Tave(0.4)
Moderator temperature coefficient is most negative at EOL (.4) and as a result caused reactor power to increase which caused a high flux I'
trip.(0.4)
~
a l
REFERENCE
{
j t
i LER 87-015
- (,'
ICS P8<1D
.3 076000K302 OOOO65A208
..(KA's) l ANSWER 2.02 (1.00) t I
Since that side electrical bus is locked out, there is no power to the CCW pumo to cool the diesel damage will occur.
REFERENCE
{T C*4 EP 1202.01.03, pg. 10 064000K102
..(KA's) t 5'
4 ANSWER 2.03 (1.00)
MU-19 would be fully open C.503 energi:ing the bus would cause the make-up pump to start causing maximum flow C.25] to the seals, thermally shocking tte RCP seals [.253.
REFEREllCE EP1202.01.OO 4.1.2.,
pg. 7
- b n
062OOOK301 062OOOA201 OOOO22K302
...(KA's)'/,a i
i I
3-
'+
f k
?
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- )
l I
- -L......
= ~ = _ _
--_a---.-----------------...--~-.-
ft__PLOUI_Qggl@U_JUGLUDJU@_$6Egly_6UQ_gMEB9ENCY Page 79 sygIgMs J
ANSWER 2.04 (O.75) a.
2155 psig b'
1400 psig c.
700 psig
(.25 each)
REFERENCE PWR-OLCO33.01. pg. 4 OO3OOOA109 OO3OOOK103 OO3OOOA201
..(LA's)
ANSWER 2.05-(1.00) k a.
High enhaust hood temperature.
(1.0)
REFERENCE Systems Training Manual, "Main lurbine," pg. 27 0450SOkl01 045000 GOO 4
..(KA's)
ANSWER 2.06 (2.00) lhe N1 signals f rom N1-7 AND NI-8 ar e auctioneered(.40) i n urie NN1-Y (.40) cabinet and NI signals from NI-5 AND NI-6 are auctioneered (.40) in a NNI-X
(.40) cabinet with resultant signals auctioneered to reactor demand (. 40)
REFERENCE MOD-SF D/20/2 016000K301
..(kA's)
ANGWER 2.07 (1.00)
To limit the cooldown of reactor coolant 9,o ar. not to cooldown to 532 degreiev (.SO)
(Isat at 070psig) which aould causo pressurizer level to go off scale low L.L].
(similar wording acceptable)
'i
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i w
=;2--------.~.....--..-.--..
.-..==: -
=.=_
2i__ELBUI_Dgg199_IU969p1Ng_S8EEIy_899_EMgBggNgy Page 80 SYSIEL19 i
lf REFERENCE Y
e s
-1Y ICS-TM, pg. 30pFWR-OLC-027,P14
'/ k,, c 041020K417
..(KA*s) 1 ANSWER 2.08 (1.00)
The equipment breakers may trip from overcurrent or undervoltage (.50) and the equipment may not perform their safuty related functions / design objectives (r at ed flow, disch.<rge pressure, etc).
(.50)
(similiar words acceptable)
?
REFERENCE l
PWR-OLC-055, pg.
9, 10 I
SP1107.11.18, para. 1.2.15 4
OOOO56 GOO 7 000056G004 OOOOS6A214
..(KA's)
ANSWER 2.09 (1.00)
Containment radiation level signal is much smaller than is expected during power operations. (similiar wording acceptable)
REFERENCE SFAS-1M p52
(
000060A201
..(KA's)
}
ANSWER 2.10 (2.00)
When MU-2B (letdown valve) is shut (.2) from the delay coil high temperature indications, letdown flow stopu.(.2)
This will cause pressuriser level to increase L.,J.
As p:r level increases, the level control system will evnd signal to throttle down MU-32(.4)I however, without letdown flow, pressurizer level will continue to increase until the level c on t r ol system causes MU-r go completely shut when it reachen setpoint(.4). Pressue1;er level will continue to increase as a result of s e.41 injection C.43.Cif""
t:ouTruut 0, N/'t ??huk le s/s t-wi/
dec AMS C. % to twok, W N D Af/ tf t
S 1 sic. n w v+/ve wul S we to 14e-gwyr a wk par) wit /
(.4 tV 17Ns/&
V/A h!W
//GfeC.T*fo10 m j pf
//O Cf/4Cr?
ffc/hM) no up He-p%rnaa.
f e
j
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- )
I
+
&-s-.---.....---.---.-----.----------.-..-
2,.
.ELONI_QE@l@N,1GGLQQ10@_@@ Eely _6UQ_Et]EB@gGQY Page 81 SYSIEMS REFERENCE
's TM-PZR, pg. 13
,;' ;i.
TM-MU, pg. 3 MO31A B4 SP 1104.02.18, pg. !O, 39 SP 1103.OS.18 011000A207 OO4000K101 OOOO22K103
..(KA#s)
ANSWER 2.11 (1.00)
Loop B will remain on RFR (.50) until low level limits have been reached in loop B (.50) or additional 75 second has past since loop A reached low level limits (2.5 minutes total RFR time) (.50) at which time loop D will go on level control
(.50).
REFERENCE SP 1105.04.05, paragraph 2.14 p14 059000K110 059000K103
..(KA's) e ANSWER 2.12 (1.25)
(electric fire water pump)- FIRE WATER STORAGE TANK a.
Motor Driven (FWST)
Intake Structure i,
Diesel Driven 2-2.5 inch connections - Manual Fire Pumper Connection Jociny pump - FWST (8.125 pts each)
L.
Wut sprinkler
(.25)
REFERENCE OLC-PWROO3.03 Pt<1D-MU16A 086000l:406 OO6000F:402 086000k401
..(K4's) 1
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--.. L. - ~
e.
...L_
u...-
- -.~
'k2__EbeUI QEE100_luCLygiug seEEIY_eUD_EdEB@EUCy Page 82 EXEIEUS l
4
- ?,
-)
ANSWER 2.13 (2.00) i t
1)OTSG-S/U LVL 2)DTSG OP LVL 3)RCS-TAVG 4)RCS-DELTA T-C
- 3) LOOP-T-HOT
- 6) LOOP-T-COLD
- 7) MAIN FEED VLV DELTA PRESS
- 8) MAIN FEED FLOW 9 ) TURL4 HDR 10)MN FW-TTSPO1-1 11)OISG-SG OUT-PTSP1201 (any five
.4 pts each)
REFERENCE MOD 87-1092-ATT 3 016000K301
..(KA's)
ANSWER 2.14 (2.00) 1.
Lower motor journal or guide bearing cooler 2.
Thermal barrier (recirc impeller) 1 3.
Motor air cooler (heat e>< c h a n g er s )
4.
Upper Motor Boaring lube oil cooler 5.
RC pump noal cooler (f or s e a.'
injection)
(
4 G S pt.)
REFERLNCE FWh'- OLC 033. 01 1P-12 TM-RCP.
p.
O COOUUUK102
..O.A*s)
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4
- - - - - - -... - - ~...... - -.. - - _.. - - -.
$ s._ _ EL eUI _ DE S199_10CL yp1 gg_ s eE gIy_999_ E tjg B9 g B9Y Page G3 S1SIEMS ANSWER 2.15 (1.50) anddisch&erw up g ca%'er s& N (0.5) e lines have ciphon ASuct n
a.
aw (0.5) b.
3.
c.
Rack spacing j@
h8 Mu (0.5)
REFERENCE PWR-OLC-OO7.01, p.
7 paragr&ph C2, p.F, paragraph C3, P SFF'S TM-5FP. p.31, paragraph C.
033OOOK403 033OOOA203
..(KA's)
ANSWER 2.16 (2.00) a.
Reduces the potential of a positive reactivity insertion from cold water in a idle loop.
(1.0) b.
Precludes cor e lift phenofr.ena by insuring delta "P"
across core is not nufficient to cause 1ift of fuul elements to occur.
(1.0)
(Similar wording acceptable.)
REFERENCE TM-RCP
, pg. 27 i
b PWR-OLC-033.01 SP 1103.06.13, p ar agraph 2.1.4 OO3OOOV404 OO3OOOK402 OO3OOOK112 OO3OOOK110
..(KA's)
ANGWER 2.17 (2.50) a.
W111 al1ow piggyback oporStion of the mateup syt.t em on the LPI pumps (1nereanos f1ow rate).
( 1. O )
b.
b y p.i n s of MU 32 when it fai1h (O.75) p al e
guncy foud and lee
(
5)
REFE NCE M
a
,a y, s 5th. Outage mod-MU/Pur p.
FCR 86-432
./MG [dd/ [f/ F @ O # ~$F.0=D 5th. Out.iho mod-MU/ Fur p.3, FCR 06-432 OO4010K101 OO4000K115 OOOO74K30/
OOOO74K304
..(KA'c)
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- )
v.l......-..~....~,...-~........-......-....-......-..--
I bt__1.USI6YUE,UIg_QUQ_CQU16QLg Page 84 ANSWER 3.01 (1.50) a.
higher i
b.
lower c.
higher (0.5 pts eacia)
REFERENCE ICS-OLC-OO6-OO, pg. 14 BA1-OLC-334 OO1000A302 OO1000A106 OO1000A101
..(KA's)
ANSWER 3.02 (3.00) c.
FW Control received a demand signal from the Integrated Master (Steam Generator / Reactor Demand) when an asymmetric rod condition occurs (Reactor at 90%. ASSYMETRIC Rod Rx power limit is 60%, rod rate of change will be ti(apercent por minute /L.3753.
This will send a reduced demand signal to be compared with the actual flow rate C.3753.
The output of which will send a signal to the feedwater regulating values to position the feed values to close C.3753 until flow error is zero, Loop A end B f eedwater demandu, are summed a total feedwater flow demand is duveloped and applied to expected pump speed demands to FW flow demands to ensure the lowest delte P error is added L.3753 to Feedwater flow feed uignal ttne tuning the pump speed, b.
The Reactor Control section receives the same decreasing signal CO.3753.From the comparison between this signal and the Neutron Error and the Reactor Demand difference unit will send a signal that will call for the insertton rods C.753.
lhe rod bite at 90 percent may be weak, and a Reac tor Crosslimits may occur limiting Feedwater flow C0.3753.
REFERENCE "Integrated Cuntrol System bP13, BP-15 1CS-OLC-OO3-OO, pg 14 ICS-OLC-OOS-O pg.
7, 19, 23, FWS ICS-OLC-OO1-OO, pg. 20, pg. 6 0"nOOOV107
..(Vk'u)
't
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- e)
m
_ __._.. _ _ u s; --- - -
m..!..._..______.._
et__IUSIBUL1EUIS_8bLCONIB96g Page 85
- , 2
,c, ANSWER 3.03 (1.25)
+
Bypass power / imbalance / flow trip (0.25 pts each) a.
b.'
Bypass power / pumps trip c.
Bypass pr essure / temperature trip d.
Bypass l ow / p r et'.uur e trip e.
Adds shutdown bypass high RCS pressure trip REFERENCC.
PP 1102,10.9, t, t ep 5.2.14 SP 1105.02.08, step 0.2 SP 1105.02.06, pg. 11 012OOOK604
..(KA'c)
ANSWER 3.v4 (1.00) a.
Patch panel assigns only CRA not APSRA.
b.
APSRA do not scram due to buttons on the roller nuts.
(2 O O.50 ca.)
REFERENCE i.
PWR-OLC-036.091, p.
5, paragraph 8, p.
7, paragraph 4.B.4, p.
9, paragraph 1.c, p.
42, paragraph f,
p.
40, paragraph 4,p.32, para 2a OO1000K4vi OO1000K103
..(kA's)
ANSWER 3.05 (1.50) a.
49" if AFW f eedirig own S/G,(.3) GU" if oppostte S/G (0.3) b.
124" if AFW fendiog own S/G
(.3),
130" if oppostte S/G (O.3) c.
40" -A-S/G (.15) D-0TSG
(.15) l l
1
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a.4.x....--.......-----"-------.......---...----
l 1
l i>1. _ _ PJ E IBLJ dE N IS _ G U Q _C,001606 @
Page 86 REFERF.NCE SP 1105.16.13
,1M-SFRCS P10 GOP-OLC-OO3-SR-3 035010K401 035010en101
..(KA's)
ANSWER 3.06 (2.00)
The ARTS CRD breater trip contacts are in series (.5) with the CRD U-V contacts (1.0), manual bypass could not prevent a ARls utgnal from tripping the RPb channel 1 CRD BREAUERS t. 5) (the KA/B/C/D channel RELAYS AND COtJ1 ACIS are not affacted by the ARTS signal)
{l REFERENCE SP1105.02.06 p38 ANSWER 3.07 (1.75)
+ 9 di r ec t i ori urror relays (.50) on groups 1 to 8 (.50) to
. It en er g a ;: e u stop rod mot a
b.
no
(. 5)
{
c.The aux power suppy is not a f f ec.t ed, (. 25) or the normal power supply is affected
(.25)
( any one )
Of f$00f5 Sp*ip$ WC Af[CtTCO REFERENCE MOD 5-CRD CHANGES pl,2 004OOOh402
..(kA's) 1
- i
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CATEGORY 3 CONTINUED ON NEXT PAGE
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..wi....________._
=.~....m_._
=.-
31._10SISybENIS,@ND_CQUIBQLS Page 87 ANSWER 3.08 (2.00) iA a.
Manual channel bypass - method of placing one RPS channel in a cannot trip condition or allows testing of channel of the RPS with remaining 1cgic 2 of 3 channels.(1.0) b.
Shut down bypass - method of leaving safety rods withdrawn during cooldown and depressurization of the RCS, or allow rod withdrawal testing with t h s' unit in a shutdown condition (1.0)
REFERENCE SP 110E.02.03, paragraph 2.5,2.9 i '
012OOOK604
..(KA's)
\\
1
/
ANSWER 3.09 (2.00)
J a
If another SFAS tesp occurs ofter reset (.5), all previously secured SFAS equipment w i.',1 come en all at once.(.5), no automatic scouencing of loads will take place.'.5) This has the potential to cause damage to the diesel generators; complete loss of plant diesels. (.5)
REFERENCE SP 1105.03.12, paragraph 5.1 TM-SFAS, pg. 110, par agraph 4 064050A403 000056"302 OOOO56A247
..(KA's) i b
f 4
4
'O I
i
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- s, _.._ u.. _ _ m =
.... ~......
It__J.USI6uutuIg_eyD_CQUIBQLS Pa9e 88 ANSWER 3.10 (2.00)
, i.
a.
Closed b.
Closed c.
Cloned d.
Closed e.
Open f.
Open g.
Closed k.
h.
Closed REFERENCE GOP-OLC-OO3-2.02, table 1,p169 l
MOD 5 TP-5,SFRCS EP 1202.01 013OOOK404 013OOOK403 UOOOO7K301
..(LA's) l ANSWER 3.11 (2.00) t\\
a.
NI-5 AND NI-6 [0.53 both less than 10%' power CO.53 b.
Either SR (N1-1 or 2) greater than 2 dpm CO.53 OR 1R 441-3 or 4) greater than 3 dpm
[0.53 l
1 REFERENCE I M-N !.F'4 3.19,23 015000M604 015000K402 015000K103
.. W A 's )
ANSWER 3.12 (1.00) id'5k'S caut.ed e power ambulance /antrease whi.h exceeded a RFS high flux trip sutpoint t
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a..L.-
.s-..
= - -. - - - -. - - - - - -. - - -
. -. ~..
r 3t__IN}I690gNIg_8Np_CQNI6QLS Page 89 i
i
{
REFERENCE k
LER 87-011 SEPT'87 OO1000K501 012OOOK402
..(kA's)
.x t;g.,
ANSWER 3.13 (1.50)
Absolute (0.5), is sensed by reed switches (0.25). Relative (0.5), is sunsed by a stepping motor in parallel with the CRDM motor phases (0.25).
(similiar wording acceptable)
REFERENCE OLC-PWR-036.02,p32,20 OO1000K401
..(KA's) f ANSWER 3.14 (1.50)
- a. Neutron error gruater or equal to 1 percent. (v.5)
- b. Safety rods not on,out limit (0.5)
- c. Loss of power to the ICS. (0.5)
REFERENCE ICS-p45 PWR-OLC-36.P37.
OO1000K403 UO1000K100
..(kA's) i 4
ANGWER 3.15 (1.50) a.
1.
STEAM ADM VALVES 2.
ti31 V BYPASSESS 3.
AlHOS VENT VALVES 4.
SGWU VALVES
(.5 PTS - ea) b.
22.9 in
(.5) a I
l a
r 1
t
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-...a..s......__......,.....___....,__..._.
L.__INDIBLJL49IS_eUD_999IB969 Page 90 REFERENCE s
SFRCS SF C/10/1.2
'4-194001K103
..' O' A ' s )
l
.i 4
i I
(*
i i
.i
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a La.. _ _ _ _ _
= _ _
da _E899699855_ _NgBd86,_8pNQBd863_6dgBQgNQY Page 91 l
00D_60D196991986.99UIB96 i
(
t 7 '.3 ~
r 4
ANSWFR 4.01 (1.00)
' y; t.
Wtyen the RCS pressure and temperature combination
(.5)' on the P/T Display or on manual plot is above and to the left of the subcooled margin line(.5).
REFERENCE g
EP1202.01 p47 OOOO74K101
..(KA's)
' ANSWER 4.02' (1.00) f t
REFERENCE
[
LER 87-002 l
+
012OOOGOO5
..(kA's)
[
i I
l ANSWER 4.03 (1.00) t S/G with the fastest level [0.53 ND pressure decrease C
.53.
I fY W
h j ?YW5V REFERENCE gg p
EP 1202.01.00, paragraph 7.27,p.86 l
OOOO40A106 OOOO40A201 OOOO40A123 OOOO40A107
..(KA'u)
ANSWER 4.04 (1.00?
Local survey (.50) of Main Steam Lines (.50)
REFERENCE U
GOP-OLC-OO3-7.01 EP 1202.01 i
OOOO38A204 OOOO38A203
..(KA*s>
I l
1 I
\\
s
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)
~
...'..t._....................._.u._...............-....
$t__C69gEQQBgG__UQ6dQ63_OQUgBd@62_gdgBQgNgy Page 92 GUR_B09196991G06_G991696 ANSWER 4.05 (3.00) a.
Where T clad greater than 1800 dwgrees F C1.OJ or RCS presu L.333 and incore thermocouples temperaturas L.333 place you in Region IV t.
33.
b.
30 minutes.(.50) c.
1.
MU/HP1
(.5) 2.
Steam the S/G using MFW (.25)
Steam the S/G using AFW (.25) flow out the PORV (.25) and LOOP and P2R high point vents 3.
(.25) 4 (51mili&r Wording Acceptable)
REFERENCE I
1202.01, paragraph 9.13 p 127, pl30 L
OLCOO3-8.01 OOOO74L311 OOOO74K308 000074K305
..(KA's)
I ANSWER 4.06 (1.50) a.
Press
^
b.
Radiation c.
Hydrogen d.
CTMT vessel level e.
CTMT boron c oric en t r a t i on (ANY four G O.375 pts each) i REFERENCE 1
EP 1202.01.04, paragraph 11.9 table 3 GOP-OLC-OO3-10.01 022OOOG01O O22OOOGOO9 022OOOA405
..(KA*s)-
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u.. :-
4 __EB9GEQQ8E@_:_U9Bd86i_GBU98d86i_GUE6@EUgy Page 93 t
BUU_B00196901GOL_G991696 i
ANSWER 4.07 (1.00) k
'4 a.
drop in RCS pressure (.50) b.
drop in pressurizer level (.50)
REFERENCE GOP-OLC-Oo3-12.01 EP 1202.01.02, paragraph 13.7 OOOO17K101 011000K102 OO3OOOK110 (KA's)
ANSWER 4.08 (1.00)
.. b.
REFERENCE T/S 8/4.8.1, LER 87-007 064000G011
..(KA's)
ANSWEH 4.09 (1.00)
"d."
3 I.
1 REFERENCE T/S 4.02, pg. 3/4 0-2 194001 GOO 5
..(kA*s)
ANSWER 4.10 (1.00)
LF1 is in oper 4a t i on (. 33 ), with a flow rate greater than/ equal to 1000 gpm in each Inne(.33) and utable for gruater than/ equal to 20 minutes (.33).
REFERENCE EP 1202.ul.U4, Rule J OOOOO9A234
..(KA's)
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u.
.f t....
m...... -
a..
b__EB9GEQUBE$_ _NpSd b _8BUgBU L _EdgB9EN9y Page 94 00D_ BOD 196991966_G9UIB96 ANSWER 4.11 (2.00)
,l a.
Falsu (SCM is higher priority than SGTR) b.
F al se (Although listed after SGTR, ICC tu the more severe case of Loss of SCM and must be treated accordingly) c.
True d.
Felse (hold at that point, etabt11:e the plant, check f or other problems
[0.5 each3 I
REFEhENCE g
EP 1202 000074G012 000040K304 000040G012 00003BK306 000030G012 000009K321 000009G012
..(KA'n)
ANSWER 4.12 (2.00) a.
yes b.
yes C.
yes i
d.
no e.
yes f.
no g.
no h.
yes
(.25 pts each) 1 l
hEFERENCE
\\
Technical Spectfscations 3.3.3.2.3.3.1.1.3.5.1,3.6.1.5 064050G005 022000G007 015020G005 006050G005 "
006020A107
.. an's)
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e s.. i...e......
1 -
-===_
- - - - ~
$t__BB99E99 BEE _ _U98Ubb2_ODU9809b4_gdgBggbQy Page 95 00D_B9919699190L_9901896
.5 s
4 ANSWER 4.13 (2.00) a.
FALSE b.' 1 RUE REFERENCE
,PP1103.00,p.5,6 OO1010A207 OU100CG015 OO1000G010 OO1000 GOO 1
..(AA's)
AtGWER 4.14 (1.00)
- 1. At equipmen'. level,BLOCUED equipment wd;11 respond to the individual control switchen for that piece of equipment.
2.
At the system level, operation of the system level RESET pushbutton will clear any output logic blocks in the system. The equipment will then respond to the sys'am level manual actuation 1 RIP pushbutton and to automatic actuatton si gn al s.
(any one e.5 pt )
(Concepts.)
REFERENCE GOP-OLC-OO3,obj.5 EP 1201.01, SPECIFIC RULE 4 D E4 EDO 7-10 013OOOK410 013OOOK110 013OOOA402
.. WA's) t 4
e
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- +***)
c...-J............4....h...--..-~----.----.-&---.-.
6t..E6QCEQWBES_:_UQBd6Li_800QBd6Lx_EdEBQENQY Page 9a eUQ_B69106091G66_GQU1606 ANSWER 4.15 (3.00)
{
- 1. Attempt to maintain pri to see heat transf er Sal an'ce kO.2) d a.if MFW has run back below reactor power, manually control MFW to match reactor power.
(0.4) j b.if MFW is lost, initiate AFW by tripping SFRCS on le SG 1evel using both SG 1evel low trip buttons.
(0.4)
(l ogic O.1)
- 2. Attempt to manually de-energize the CRD's in order below(0.1):
- a. Momentaril y de-energi e 480V uni t subs E2 L F2 simultaneously (0.3)
(l ogi c O. ' )
b.
Manuelly crip three reactor trip breakers in low voltage switchgear rooms.(0.3)
Manually de-energi:e the CRD system by tripping DE211 on E2 AND c.
1 BF211 on F2. (0.3)
(0.1 logic) 3.
Attempt to manually shutdown the reactor (0.2):
a.
Manually drive control rodo in.(0'4)
- b. Begin emergency boration (0.1) by shifting MU pump suction to the BWST (0.1), initiate max MU & 1(tdown (0.1), shift letdown 3-way val ve to CWRT (0.1) 1 REFERENCE
[
(
EP 1202.01 l
GOP-OLC-CO3,ATT.2.obj.5 GOP-OLC-OO3,ATT.2.p.7 l
OOOO29K312 000029G010 W A 's) i J
t s
ANSWER 4.16 (1.00)
- 1. Declare both source range channels snuperable (.50) 1
- 2. Action shall be instaated within 1 hoe- (. 50 ) to place the unit in at t
i least hot standby (within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />) (or T/S 3.0.3 )
l REFERENCE t
- i T/S 3/4.3.1, lable 3.3.1
[
N1, pg.2 l
T/S 3.0.3 l
AB 1203.08.1 OOOO32U302 OOOO32K301
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CATEGORY 4 CONTINUED ON NEXT PAGE
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C69EEQ98EE.. _UQBU6bs.6Ed98U961 EdgBQgNQY Page 97 OUU_600196991G06_G9U1696
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el ANSWER 4.17 (1.00) a.
75 rum (0.5) b.
This person cannot be allowed to enter due to the fact that emergency limits are " Once in a lifetime". This person will exceed the limit.
(simt11er wording acceptable )
(0.5)
REFERENCE D/B EPIP P.6-14, para 6.5.1 194001K103
..(RA's) t f
ANSWE.R 4.10 (1.00) i a.
- 1) The deviation is needed to protect the health and safety of the publtc.
(0.5)
- 2) No action, consistent with licensed requirements, that can provide edequate or equivalent protection in immediately apparent.
(similiar (0.5) wording ecceptable) j b.
A licensud SRO. (one h41+ credit gaven for a titied posttion, such as Shift Engineer)
(0.5)
REFERENCE 10CFR50.54x 194001A116 194001A112 194001A110
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END OF CATEGORY 4
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(********** END OF EXAM 1NAT10N ******++++)
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3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM IN'TRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1.1 As a minimum, the Reactor Prote: tion System instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.
APPLICABILITY: As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
4 1
i I
SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each Reactor Protection System instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-1.
4.3'.1.1.2 The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CA1.!BRATION testing of each channel affected by bypass operation.
J
- 4. 3.1.1.'3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function shall be deconstr,ted to be within its limit at least once per 18 months. Each test shall include et least one channel per function such that all channels are tested at least once every N times 18 months l
where N is the total number of redundant channels in a specific reactor l
trip function as shown in the "Total No. of Channels" column of Table l
3.3-1.
I j
+
l DAVIS-BESSE, UNIT 1 3/4 3-1 c--,
i I'
TABLE 3.3-1 (Continued)
)
I TA8LE NOTATION l
' With the control rod drive trip breakers in the closed position and the control rod. drive system capable of rod withdrawal.
1
- When Shutdown Bypass is actuated.
fihe provisions of Specification 3.0.4 are not applicable.
HHigh voltage to detector may be de-energized above 10-10 amps on both i
Intennediate Range channels.
(a) Trip may be manually bypassed when RCS pressure i 1820 psig by l
actuating Shutdown Bypass provided that:
(1) The High Flux Trip 5etpoint is 1 55 of RATED THERMAL
- POWER, a
I i
(2) The Shutdown Bypass High Pressure Trip Setp,oint of < 1820 l
psig is imposed, and q
I (3) The Shutdown Bypass is removed when RCS pressure > 1820 psig.
(b) Trip may be manually bypasse'd when Specification 3.10.3 is in effect.
i l
(c) The minimum channels OPERA 8LE requirement asy be reduced to one when Specification 3.10.1 or 3.10.2 is in effect.
j ACTION STATEMENTS, With the number of channels UPERABLE one less than required i
l ACTION 1 by the Minimum Channels OPERABLE requirement, restore the 4
j inoperable channel to 0PERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or i
i open the control rod drive trip breakers.
\\
With the number of OPERA 8LE channels one less than the
)
l ACTION 2 Total Number of Channels STARTUP and/or POWER OPERATION l
may proceed provided all of the following conditions are satisfied:
1 i
a.
The inoperable channel is placed in the tripped l
condition within one hour.
i j
b.
The Minimum Channels OPERABLE requirement is met; i
however, one additional channel may be bypassed for l
up :o 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.1, e
DAVIS-8 ESSE, UNIT '
3/4 3-3 j
a TABLE 3.3 1 (Continued)
ACTION STATEMENTS (Continued)
With the number of channels 0PERA8LE one less than required ACTION 5 by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
< 1010 amps on the Intermediate Range (IR) in-strumentation, restore the inoperable channel to a.
OPERABLE 93atuspriortoincreasingTHERMALPOWER above 10*
amps on the IR instrumentation.
> 10-10 amps on the IR instrumentation, operation b.
may continue.
With the number of channels OPERABLE one less than re-ACTION 6 quired by the Minimum Channels OPERABLE requirement, verify compliance with the SMJTDOWN MARGIN requirements of Specification 3.1.1.1 within one hour and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
With the number of OPERABLE channels one less than the ACTION 7 Total Number of Channels STARTUP and/or POWER OPERATION may proceed provided all of the following conditions are satisfied:
a.
Within 1 hour:
1.
Place the inoperable channel in the tripped condition, or Remove power supplied to the control rod trip 2.
device associated with the inoperative channel.
One additional channel may be bypassed for up to 2 b.
hours for surveillance testing per Specification 4.3.1.1.1, and the inoperable channel above may be bypassed for to 30 minutes in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period when necessary to test the trip breaker associated with the logic of the channel being tested per Specification 4.3.1.1.1.
The inoperable channel above may net be bypassed to test the logic of a channel of the trip system associated with the inoperable channel.
With the number of channels OPERABLE less than required ACTION 8 by the Minimum Channels OPERABLE requirement, be in at lesst HOT STANDPv within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
DAVIS-BESSE, UNIT 1 3/4 3 5
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l INSTRUNNTATION 3/4.3.2 5ArtTT SYSTEM INSTRUMENTATION 7
5AFETY FEATUAtl ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OptRATION 3.3.2.1 The Safety Features Actuation System ($FA5) functional units shoe la Table 3.3-3 shall be OPERA 8LE with their trip setpoints set consistent with the values sho e in the Trip 5etpoint column of Table 3.3-4 and with RESPONSE TIPE5 as shown in Table 3.3-5.
APPLICA31LITY: As shown in Table 3.3-3.
4 ACTION:
3 i
a.
With a $FAS functional unit trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3 4, declare the functional unit inoperable and apply the applicable ACTION requirement of Table 3.3 3. untti the func.
tional unit is restored to OP[RAILE ttatus with the trip setpoint adjusted consistent with the Trip 5etpoint value.
i i
b.
With a 5FA5 functional unit inoperable, take the action shown in Table 3.3-3.
t l
5URyt!LLANCE REQUIREMENTS -
(
4.3.2.1.1 tach SFA5 functional unit shall be demonstrated OPERABLE by l
the performance of the CHANNEL CHECK. OWs EL CALIBRATION and CNustEL i
FUNCT10m4L TEST during the M00E5 and at the frecemcies sitswn in Table j
4.3-2.
l 4.3.2.1.2 The logic for the bypasses shall be. demonstrated OptRABLE f
l during the at powr CHANNEL FUNCTIONAL TEST of functional units affected by bypass operation. The total typass function shall be demonstrated i
UPERA8LE at loest once per 18 months during 04AletEL CALISRATION testing of each functional unit affected by bypass operation.
i.
4.3.1.1 J The SAFETT FEATURES Resp 0NSE TDE of esch 5FAS function shall be demonstrated to be within the Itait at least once per 18 months.
Each test shall include at least one functional unit per functies such that all functional units are tested at least once every N times 18 l.
months there R is the total number of redundant functional units in a j'
ipecific SFAS function as shown to the "Total No. of Units' Colum of if Table 3.b 3.
l BAY 15 SE15E. bu!T 1 3/4 3-9
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l TABIE 3.3-3 E
d SAFETT FEATURES ACTUATIOlt SYSTDf INATATICII i
en NINIMUlf
~
I e
l TOTAL NO.
UNITS int 1TS AFFLICA3EE I
FINICTf0K 1Nff?
0F UltITS TO TRIP
- OPERABIK,
, MODES ACT!W i
3 I'
, 3.
MANUAL ACTUATION 4
~
a.
SFAS (except Containment i'
3 prey med Beersency sump j
Recirculaties) 2 2
2 1,2,3,4,Geeee 13 I
2 2
2 1,2,3,4 11 j
b.
Caetainment Spray I
i 14.
SEQUENG IACIC CMANNELS Iw a.
Og x;er 4
2***
3 1,2,3,4 99 l
2 b.
Essential Bas Feeder l w l.'
Breaker Trip (901) 2 1
12 22 1,2,3,4 14#
i c.
Diesel Generator Start, Lead Shed on Esseettel
[
'~
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Bus.(591) 2 1
2 1,2,3,4 14#
i l
5.
IWfERISCK CRANNELS j
a.
Decey Neet Isolatlee Valve 1
1 1
1,2,3,4,5 12f I
i b.
Pressuriser Nesters 2
2 2
3,4,5
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TABI2 3.3-3 (Contiewed)
TABLE NC'ATICW
- f.,.
Trip function may be bypassed ta this NOCE with RCS pressure belev 1800 peig. typass shall be astematically removed ubea RCS pressure exceeds 1800 p613 I
i Trip function may I. bypassed in thir Noct with RCS pressure below 600 pois. Bypass shall be automatically removed when BCs pressure exceeds 600 pois, One must be in STAS Channels #1 or #3, the other must be la t
Chamaels #2 er #4.
This instrumentation must be OPERABLE during core alteratione or movement of irradiated fuel within the containment to meet i
the requirements of Tech. Spec 3.9.4.
All functional units may be bypassed for up to one minute when i
starting eacb Reactor Coolant pump or Circulating Water pump.
T f
The provisions of Specification 3.0.4 are not applicable.
ACTION STATEMENTS ACTION 9 -
With the number of OPERABLE functional units one less than the Total Number of Units, startup and/or power operation may proceed provided both of the following conditions are satisfied:
The inoperable functional unit is placed in the i
s.
tripped condition within one hour. For fea:tiemal unit 4a the sequencer channel shall be placed in the tripped condition by physical removal of the sequencer modul.
I i
I b.
The Minimum i OPERARIZ requirement is att; l
bewever, ese tiemal functiemal amit may be i
i bypassed ic to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing j
per Specif
.am 4.3.2.1.1.
ACTION 10 -
With tay cent et in the Output 1431c inoperable, trip i
the associatt cesponents, within ese hour er he in at Reast 307 STANDST within the mest 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and ta CCED I
EUTD0641 withis the fallowing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
i ACTION 11 -
With the number af OPERARIZ Unite one lesa than the Total Ember of Unita, restere the inoperable functiemal unit to WERARIA status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> er be is at least EFf STANDBf withis the mest 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in C01D 55U19048I within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
1 ACTION 12 -
a.
With less than the Minimua Units OPERARIA and reacter coolant pressure > 438 psis, both Decar Beat Isolaties l
Valves (Dell and Bet 12) shall ne verified cleoed.
I I
BAVIS-3 Esse, WIT 1 3/4 3-12 Ameatment No. #g 31, II.
1
.p e
l*
TA3LE 3.2 3 (Contiewd)
.ACTIWiTATDENTS l
b.
With Less than the Minimum Units OPERAttl med reacter I
coelaat pressure < 434 pois operaties may coattooe; i
bewever, the fonctional matt shall be crERAR11 prior to increasing reacter coolant pressure above 438 psig.
ACTION 13 -
With less than the Minious Units OPEAABIZ and reacter coolant pressure < 438 psis, operation may contiane however, the functieaal cast shall be OPERABLE prior to increasing reacter coolant pressure above 438 pois, or the inoperable functional unit shall be placed in the tripped state.
l ACTION 14 -
With the number of OPERABLE functional units one less than the Total Number of Units operation may proceed provided both af the following conditions are satisfied:
a.
The inoperable section of a functional unit is placed in the tripped condities within one hour.
b.
The Miniaun Units OPERABLE requirement is met; however, the inoperable section of a functieaal unit may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.
I i
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$1MPLIFIED INTEGRATED C f<h a,A P'IP'PIO 8Y 20YNIR ENG'"I' I
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3/4.8 ELECTRICAL POWEA ST875HS 3/4.8.1 A.C. 500RCE3 OPERATING LIMITING CONDIT10W FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sourced shall g
be OPERA 812:
Two independent circuits between the of fsite transmission.
I a.
metwork and the ensite Class 1E distribution systes, each consisting oft 1
1.
One OPERABLE 345 KV transmission line, 1
2.
One OPERABLE 345 13.8 KV startup transformer, and i
]
3.
One OPERABLE 13.8 KV bus, and I
i b.
Two separate and independent diesel generators each with:
l 1.
A separate day fuel tank containing a minimum volume l
of 4000 gallons of fuel, i
i 2.
A separate fuel storage system containing a minimum l
volume of 32,000 gallons of fuel, and 4
i 3.
A separate fuel transfer pump.
1 APPLICABILITY: HODES 1, 2, 3 and 4.
ACTION:
With either an offsite circuit er diesel generator of the above a.
required A.C. electrical power sources inoperable, demonstrate l
J the OPERABILITY of the remaining A.C. sources by performing J
Surveillance Requirement 4.8.1.1.1.a within one hour and at i
least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter and by performing Surveillance Requirement 4.8.1.1.2.a.4 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restore at least two l
ef fsite circuits and two diesel generators to OPERAS!I status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> er be in at least NOT STAl:DBY within the next 6 4
hours and in COLD SNUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
j i
b.
With one offsite circuit and one diesel generator of the above j
required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing l
Surveillance Requirement 4.5.1.1.1.a withis one hour and at... ;
i least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereaf ter and by performing Servet11ance i
Requirement 4.8.1.1.2.a.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Restore at least one ef the inoperable sources te OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> er l/
be in at least NOT STANDBY within the mest 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD h.
SEUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Restore at least two I
l davis-BEssE, UNIT 1 3/4 8-1 Amendment No. (,97
a
=
, 3 ELECTRICAL F0WER Sf87DtB ACTION (Contissed) offsite circuits and two diesel generators to OPERAllE status withia 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the time of initial less or be is at least l
507 STANDtY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and la COLD SHUfDOWN withia l
I I
the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
With two of the above required offsite A.C. circuits inoperable, i
c.
demonstrate the OPERAllLITY of two diesel generators by performing Surveillance Requirement 4.8.1.1.2.a.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at lcl l
least esce per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereaf ter, unless the diesel generators j
are already operatics; restore at least one of the isoperable
)
}
effsite sources to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least NOT STANDRY withis the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. With only one j
offsite source restored, restore at least two offsite circuits l
to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from time of initial loss or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOV' within the following ~30 hours.
j d.
With two of the above required dissel generatort inoperable, demonstrate the OPERABILITY of two of fsite A.C. circuits by performing Surveillance Requirement 4.8.1.1.1.a withis one hour and at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereaf ter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in et least NOT STANDBY within the sext 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Restore at least two diesel generators to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> l
from time of initial loss or be in at least NOT STANDBY within
}
the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SNUTDOWN within the following 30 f
i hours.
t i
SURVEILLANCE REQUIRENENTS j
i 4.8.1.1.1 Each of the above required independent circuits between the of fsite transmission network and the ensite Class 1E distributies systes shall be f
Determined OPERABLE at least once per 7 days by verityiss correct a.
breaker alignments and indica *:ed power availability, and l
i l
b.
Demonstrated OPERABLE at least esce per 18 seeths durlag shutdown by transferring (eanually and automatically) unit l
Power supply to each of the 345 KV tressaission lines.
4.8.1.1.2 Each diesel generator'shall be deemastrated OPERABLE:
At least once per 31 days en a STAGGERED TEST SASIS, if a.
Surveillance Requirement 4.8.1.1.2.c has not been performed l
within the previous 31 days, by l
i h
Davis-aEssE, UNIT 1 3/4 8-2 AmendmentNo.9;j u
a
n.:
(.
ELECTRICAL POWER STgTDtS SURVIILIJulCE RgQUIRDENTS (Continued) 1.
Verifying the fuel level in the day fuel tank.
2.
Verifying the fuel level in the fuel storage tank.
3.
Verifying the fuel transfer pump can be started and trans-i fers fuel from the storage system to the day tank.
4.
Verifying the diesel starts and accelerates up to 700 rpa, preceded by an engine prelube and/or appropriate other warmup procedures.
5.
Verifying the generator is synchronized, loaded to 11000 kw, and operates for 160 miputes.
l 6.
Verifyingthedieselgeneratbrisalignedtoprovide standby power to the associated essential busses.,
7.
Verifying that the automatic load sequence timer is OPERABLE with each load sequence time within i 10% of its required vaine.
b.
At least once per 92 days by verifying that a sample of diesel fuel froe the fuel storage tank is within the acceptable limits specified in Table 1 of ASTM D975-63 when checked for viscosity, water and sediment.
c.
At least once per 134 days on a STAGCERED TEST BASIS by:
1.
Verifying the fuel level in the day fuel tank.
2.
Verifying the fuel level in the fuel storage tant.
3.
Verifying the fuel transfer pump can be started and transfers fuel from the storage systes to the day task.
4.
Verifying the diesel starts from ambient cendition and acceleraies to at least 900 rpe in 3 10 seconds.
5.
Verifying the generator is synchronized, leaded to 11000 kw, and operates for f, 60 minutes.
l 6.
Verifying the diesel generator is aligned to provide standby power to the associated essential busses.
7.
Verifying that the automatic load sequence timer is OPERABLE with each load sequence time within i 10% of its required value.
l r
DAV!g-RESSE, INIT 1 3/4 8-3 Amendment No. 75. 77, 105
.a 4j u
f 812C11t! CAL POWER _STSTRIS
(
I StMtVE!!JMCE REQUIRDENTS (Continued) f i
4 d.
At least esce per 18 acaths durlag shutdown by:
i I
n 1
1.
Subjecting the diesel to en inspecties is accordance with I
precedures prepared in conjuncties with its manufacturer's recommendations for this class of standby service,*
l 2.
Verifytag the generator capability to reject a lead equal l
to the largest single emergency load supplied by the generator without tripping.
3.
Simulating a loss of offsite power la conjuncties with a safety features actuation system (SFAS) test signal, and:
l t
(a) Verifying de energitation of the essential busses and load shedding f rom the essential busses, i
(b) Verifying the diesel starts from ambient condition on the auto start signal, energises the essential busses with permanently connected loads, energines the auto-
, connected essential loads through the lead sequencer i
and operates for 15 minutes while its guerator is i
loaded with the essential loads.
(c) Verifying that all diesel generator trips, except
}
engine overspeed and generator differential, are automatically bypassed upos loss of voltage on the i
essential bus and/or an STAS test signal.*
l l
i 4.
VerifyAng the diesel generator operates for 160 minutes while leaded to 1 2000 kw.
I 5
i 5.
Verifying that the auto-connected leads to each diesel generator de met esteed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 2434 kw.
The 18 month surveillance which is due en January 3,1984 for EDG 1-1 and December 10, 1937 for EDG l-2, may be delayed for EDG l-1 until Narch 31, 1984 and EDG l-2 until Narch 20,19s8.
)
,I h
5 DAVIS-aESSE, UNIT 1 3/4 s 4 Amendment No. 97_, 105_
_