ML20127D804

Exam Rept 50-302/OL-85-02 on 850514-16.Requalification Exam Results:Five of Six Senior Reactor Operators & Seven of Eight Reactor Operators Passed.Requalification Training Program Successfully Correcting Deficiencies

ML20127D804
Person / Time
Site:	Crystal River
Issue date:	05/23/1985
From:	Lawyer S, Wilson B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20127D789	List: ML20127D783 ML20127D804
References
50-302-OL-85-02, 50-302-OL-85-2, NUDOCS 8506240342
Download: ML20127D804 (124)

Text

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l ENCLOSURE 1 EXAMINATION REPORT 302/0L-85-02 Facility Licensee: Florida Power Corporation P. O. Box 14042, M.A.C.H-2 St. Petersburg, FL 33733 Facility Name: Crystal River Unit 3 Facility Docket No. 50-302 Requalification examinations were administered at Crystal River Nuclear Plant near Crystal River, F .

Chief Examiner: ,

Sdndy Law er V Date Signed Approved by: . S M!96~

Bpste A. Wilson, Section Chief Date Signed Summary:

Requalification examinations on May 14-16, 1985 Written requalification examinations were administered to six SR0s and eight R0s; oral requalification examinations were administered to three SR0's and four RO's; five of the SR0s and seven of the R0s passed these examinations.

This was the first of two scheduled re-examinations following the March 1985 Requalification Program evaluation conducted by the NRC. Oral examinations were waived for those seven individuals who passed this phase of the requalification examinations in March.

The performance on this portion of the requalification examinations (85.7% pass rate) is an indication that corrective actions applied to the Crystal River requalification training program are having the intended result of correcting past deficiencies.

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' Enclosure 1 2 REPORT DETAILS

1. Facility Employees Contacted:

R. C. Zareck, Nuclear Operations Instructor, (R)

L. C. Kelley, Manager Nuclear Operations Training, (E)

E. M. Howard, Director, Site Nuclear Operations, (E)

P. F. McKee, Plant Manager, (E)

G. L. Boldt, Plant Operations Manager, (R/E)

R. T. Wittman, Jr., Operations Superintendent (E)

M. F. Penovich, Training Superintendent (E)

J. L. Bufe, Nuclear Compliance Specialist (E)

E. R. Carlson, Training Consultant (E)

J. G. Smith, Nuclear Shift Supervisor (R)

M. P. Holmes, Nuclear Operations Instructor (R)

NOTE: "R" indicates present at examination review "E" indicates present at exit meeting

2. Examiners:

B. A. Wilson, NRC S. Lawyer, NRC*

J. C. Huenefeld, PNL

• Chief Examiner

3. Examination Review Meeting At the conclusion of the written examination, the examiners met with facility representatives (identified in 1. above) to review the written examinations and answer keys. Specific facility comments and associated NRC resolution of those comments follow:

NOTE: Comments on questions duplicated between exams are only detailed once,

a. R0 Exam (1) Question 1.18 l Facility Comment - This question does not seem to be at a Reactor Operator (RO) level of knowledge.

NRC Resolution - This question requires only a very general knowledge of the basis of the shutdown margin requirement. This level of knowledge is consistent with that necessary to understand the functions of the related safety systems. (See 10 CFR 55.21g).

No change required.

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- Enclosure 1 3 (2) Question 1.22a Facility Comment - Use of the words " full flow" in reference to HPI makes the question ambiguous.

NRC Resolution - We concur with this comment. The question was obtained from the Crystal River draft manual on " Reactor Heat Transfer and Thermal Hydraulics." The statements are made:

"The size of the leak in a LOCA situation determines the need of OTSG cooling. Simply supplying water (HPI) to the core may not be sufficient."

It is later stated in this manual that:

If the leak is small ... the OTSG must be used to augment the energy removal from the (RCS). During final efforts to cool the core during a small leak without OTSG availability, the operator may have to " create a larger leak" by opening the PORV.

This is supported by AP-450, " Emergency Feedwater Actuation" which requires the operator to establish HPI-PORV core cooling if no feedwater is available (therefore, no GTSG's). Also, step 24 of AP-580, " Engineered Safeguards System Actuation" gives the same instruction. The term " full flow" is not defined explicitly, but is generally interpreted as two HPI pumps running and the four injection valves open. AP-530, " Natural Circulation" lists the condition of HPI-PORV cooling as:

BWST Suction Valves Open 2 HPI pumps running 4 injection valves open PORV and block valve open We therefore agree that HPI-PORV cooling can be equated with full HPI flow which renders question 1.22a ambiguous. The question was deleted.

-(3) Question 1.23 Facility Comment - We suggest that alternate wording also be accepted for A and C. The proposed wording for A is "RCS pressure axis" and for C " minimum DNBR limit (1.30)".

NRC Resolution - The proposed wording is equivalent and was added to the answer key.

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Enclosure 1 4 (4) Question 2.4 Facility Comment - Choice (b) is also an incorrect statement. The STM provided to the NRC was in error. A copy of NAO-91 will be provided to support out recommendation that both answer (b) and (d) be accepted.

NRC Resolution - NAO-91 was provided and supports the recommen-dation. The answer key was changed.

(5) Question 2.11 Facility Comment - Choice (d)' is also a correct answer. This is not reflected in STM-405 which was provided to the NRC, but is in ANO-91 on pg. 15.

NRC Resolution - Based upon the additional reference material, we concur. The answer key was changed.

(6) Question 2.13 Facility Comment - The SF cooling pump air handling fans are not required for emergency operation even though they are powered from ES buses. The STM incorrectly states that the fans will continue operating during post accident conditions. It should more pro-perly state that they may be operated. . We recommend this question be deleted.

NRC Resolution - Review of training material and discussion with senior operating personnel confirms the facility comment. The question was deleted.

(7) Question 2.19 Facility Comment - On the answer key drawing, the device shown as a switch below the leftmost transformer is a voltage regu'reor.

NRC Resolution - The answer key drawing was incorrectly labeled by us. The facility comment is accepted. The answer key was changed.

(8) Question 2.23 Facility Comment - The answer key is incorrect. It should read "No circulating water pump operating; condenser vacuum of <5" Hg.

This is reflected in the newly revised STM, Chapter 504, Rev. I dated 1/15/85, Pg. 110.

NRC Resolution - We concur. The answer key was changed.

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Enclosure 1 5 (9) Question 3.03 Facility Comment - The quality of this question could be improved by changing choice (c) to read " .. will stop further out travel...". We suggest this be rephrased before entry into the question bank.

NRC Resolution - We concur. . The wording was consistent with the STM provided; however, the suggested wording should be used in future usage of this question. No change to the current question or answer sheet is appropriate.

(10) Question 3.11 Facility Comment - This task is not performed by plant operators at Crystal River.

NRC Resolution - This is an instrument within the scope of 10 CFR 55.21(f). Power gain adjustments, if not made by a licensed person, must only be made under his cognizance. Also, the STM provided clearly indicates how the power gain adjustment is made.

'No change required.

(11) Question 3.19 Facility Comment - The question is somewhat ambiguous in that (b) could be seen as a correct statement, i.e., all heater banks will be de-energized if pressurizer level <30".

NRC Resolution - We concur. The question was intended to measure knowledge of the heater cutoff setpoint of 40 inches. The wording of the question however, did not properly elicit this knowledge.

The question was deleted. '

(12) Question 3.21 Facility Comment - In choice (d), when the pressure comes back up, the air fail reset will auto reset. Tnis is a recent revision to the lesson plan. Since the candidates should not be confused, no change to the current questions or answer key should be made but the question should be reworded prior to future use.

NRC Comment - We concur. Ho change to current questions or answer key is warranted.

(13) Question 4.03)

Facility Comment - During administration of the examination, a candidate notified the examiners that there were two correct answers due to a recent revision to AP-330. This was verified by

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the examiners. Facility reviewers were notified of the change to the answer key.

NRC Resolution - Revision .1 to AP-330, dated 3/6/85 had deleted

, step (d). The answer key was changed.

. t (14) Question 4.09 Facility Comment - While the question is acceptable, it could be improved by recognizing that there is a two second time delay on the 110 psig auto start. This should be reworded, if.possible, before future use.

NRC Resolution - The procedural reference from which the question was obtained did not~ mention "the two secon'dstime delay. I No change.

required. I

b. SRO Exam ,

(1) Question 5.14a

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Facility Comment - Same as RO Question 1.22a.

NRC Resolution - The question was deleted.

5 (2) Question 5.15 Facility Comment - Same as R0 Questi,on 1.23.

NRC Resolution - The proposed wording was added to the answer key.

(3) Question 6.3 g

Facility Conaent - Same 'as R0 Question 2.11.

NRC Resolution - The answer key was changed to accept choice (a) or(d).

"t (4) @estion 6.9 Facility comment'- Same as R0 Question 2.19 NRC Resolution - The answer key drawing 'was relabeled 'appro-priately. ,

(5) Question 6.19 f

Facility' Comment - Same as RO Question 3.21 NRCResolution-Nochangereduired.

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Enclosure 1 7 (6) Question 7.3 Facility Comment - Same as R0 Question 4.3 NRC Resolution - The answer key was changed to accept- either (b) or (d). '

(7) Question 7.9 Facility Comment - Same as R0 question 4.9 NRC Resolution - No change required.

(8) Question 7.13 Facility Comment - None NRC Resolution - Post grading review showed all candidates to answer " grapple tube up" light as one of the two required answers. This was not on the answer key which was obtained from FP-203, Rev. 12, page 22 which states:

After a fuel assembly has been lifted, the Operator shall not move the bridge / trolley until the "Z-Z" tape has been read to verify grapple position and the "Z-Z tape " full up" reading has been reported to the CCRO.

However, on page 12, the procedure states that:

After a fuel assembly has been lifted, as indicated by the

" grapple tube up" light, check the "Z-Z" tape to verify the grapple position before moving the bridge or trolley.

Therefore, any two of these three answers are accepted.

(9) Question 8.7 Facility Comment - This question should be revised in the future to reflect the conditional requirement on Mode 2 applicability in STS, i.e., Keff > 1.

NRC Resolution - This change will be considered prior to future use of this question. No change to current question or. answer key required.

(10) Question 8.17 .

Facility Comment - This question should be revised prior to future use to say "when an STS required deluge and sprinkler system...".

NRC Resolution - The proposed wording will be considered. No change to current question or answer key required.

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4. Exit Meeting ,

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e At the conclusion of the- site visit, the examiners met with _ representatives "

.of the plant staff _ to discess the results ,of) the examinations. Those-individuals who clearly passed the oral examination were identi.'ied.

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No generle) weaknesses were' nqied by the examiners, at this time. A compre- d!

hensive' summary of' generic weaknesses will be presented at 4he, conclusion of

.the requalification reexaminations.

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I ENCLOSURE 3

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• o' U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR REQUALIFICATION EXAMINATION

. Facility: Crystal River Unit 3 Reactor Type: PWR B&W Date Administered: May 14, 1985 Examiners: S. Lawyer Candidate:

INSTRUCTIONS TC CANDIDATE:

Use separate paper for the answers. Write answers on one side only. Staple question sheets on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up four (4) hours after the examination starts.

% of Category % of Candidate's Category .

Value Total Score Value Category 25 25 5. Theory of Nuclear Power Plant Operation, Fluids and Thermodynamics 25 25 6. Plant Systems: Design, Control

& Instrumentation 25 25 7. Procedures-Normal, Abnormal, Emergency and Radiological Control 25 25 8. Administrative Procedures, Conditions and Limitations 100 100 TOTALS Final Grade  %

All work done on this exam is my own, I have neither given or received aid.

t Candidate's Signature

7-O 9 3.0 THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS AND THERMODYNAMICS (25.0) ,

5.1 T'he ratio of both Pu-239 and Pu-240 atoms to U-235 atoms changes over core life. Which one of the pairs of parameters below are most affected by this change? (1.0)

a. Moderator temperature coefficient and doppler coefficient

b. Doppler coefficient and beta

c. Beta and thermal neutron diffusion length

d. Thermal neutron diffusion length and moderator temperature coefficient 5.2 A moderator is necessary to slow neutron.s down to thermal energies.

Which of the following is the CORRECT reason for operating with thermal instead of fast neutrons? (1.0)

a. Increased neutron efficiency since thermal neutrons are less likely to leak out of the core than fast neutrons.

b. Reactors operating primarily on fast neutrons are inherently unstable and have a higher risk of going prompt critical,

c. The fission cross section of the fuel is much higher for thermal energy neutrons than fast neutrons.

d. Doppler and moderator temperature coefficients become positive as neutron energy increases.

5.3 Which one of the following fa'ctors will help, rather than hinder,

? natural circulation? (1.0)

a. Lowering OTSG 1evel

b. Lowering RCS pressure

c. Increasing RCS teinperature L

d. Lowering turbine bypass valve setpoint ,

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5.4 -Following a trip from full power with the reactor shutdown and 4 RCPs .

operating, the 125 psi bias is suddenly removed from the turbine bypass valves. Which one of the following statements best describes plant response? (1.0)

a. OTSG pressure drops and levels rise. The increased OTSG 1evels cause an overcooling of the RCS.

b. TheOTSGsaturationtemperaturedropscausingadecreashin RCS cT and a rapid drop in pressurizer level.

c. Since OTSG pressures drop 125 psi, BTU limit alarms will be received on both generators and feedwater will cut back.

d. The resulting cooldown of the RCS will decrease the shutdown margin to less than Tech Spgc limits.

5.5 During a xenon-free reactor startup, critical data was inadvertently taken two decades below the required Intermediate Range (IR) level (10 " amps). The critical data was then taken at the proper IR level (10

• amps). Assuming RCS temperature and boron concentrations did not change, which one of the following statements is CORRECT 7 (1.0) ,

a. The critical rod position taken at the proper IR level is LESS THAN the critical rod position taken two decades below the proper IR level. .

b. The critical rod position taken at the proper IR level is THE SAME AS the critical rod position taken two decades below the

- proper IR level.

c. The critical rod position taken at the proper IR level is ,

! GREATER THAN the critical rod position taken two decades ,

below the proper IR level.

d. There is not enough information given to determine the relationship between the critical rod position taken at the proper IR level and the critical rod position taken two decades below the proper IR level. ,

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3 5.6 The reactor trips from full power, equilibrium xenon conditions. -

Twenty-four hours later the reactor is brought critical at 10 ' amps on the intermediate range. If power level is maintained at 10 ' amps for several hours, which of the following statements l is CORRECT concerning control rod motion? (1.0) l

a. Rods will have to be withdrawn due to xenon build-in.

Rods will have to be rapidly inserted since the critical' b.

reactor will cause a high rate of xenon burnout.

c. Rods will have to be inserted since xenon will closely follow its normal decay rate.

d. Rods will approximately remain as is as the xenon establishes its equilibrium value for this power level.

5.7 Which one of the following is CORRECT concerning starting of positive displacement (PD) and centrifugal pumps? (1.0)

a. Neither type of pump should be started with its discharge valve shut.

b. Both types of pumps should be started with their discharge valves shut.

c. A PD pump should be started with its discharge valve shut and a centrifugal pump started with its discharge valve open.

d. A PD pump should be started with its discharge valve open and a centrifugal pump started with its discharge

! valve shut.

5.8 Runout of a centrifugal pump is best characterized by which one of the following? (1.0)

a. high motor current, high flow rate and high discharge pressure.

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b. low motor current, high flow rate and low discharge pressure.

c. low motor current, low flow rate and high discharge pressure.

d. high motor current, high flow rate and low discharge pressure.

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4 5.9 Which one of the following is the CORRECT order of the heat -

transfer processes as heat flux increases? (1.0)

a. bulk boiling, sub-cooled nucleate boiling, film boiling, DNB

b. sub-cooled nucleate boiling, bulk boiling, film boiling, DNB

c. bulk boiling, sub-cooled nucleate boiling, DNB, film boiling

d. sub-cooled nucleate boiling, bulk boiling, DNB, film boiling 5.10 In performing an estimated critical boron concentration pursuant to OP-210, the attached worksheet is being utilized. Assuming the information shown on that sheet, which one of the following pairs of items will be positive (+)? (1.0)

a. A&D

b. B&D ,

c. B&C

d. A&C 5.11 Which one of the following is NOT part of the accident postulated for the basis of the shutdown margin requirement? (1.0)

a. Main steamline break

b. Beginning-of-Life (BOL) condition

c. Tavg at no load operating temperature

d. Most reactive rod struck out 5.12 Which one of the following is NOT one of the DNB related parameters that must be maintained within Tech Spec limits? (1.0)

a. Hot leg temperature

b. Reactor Coolant pressure

c. Reacter Coolant flow rate i d. Axial power imbalance 5.13 Which of the following will NOT change over core life? (1.0)

a. The minimum acceptable shutdown margin

b. The acceptable flux imbalance band

c. The control rod reactivity worth

d. The power defect reactivity worth.

5.10 TTJ: e, IAL0C

e. Teile.ias e LOCA, if lL" ectuete; and de.;1;p; full fisw,

f'icient ;;r; ceeling is eu ...d .;ihvoi its n. J iv, GT5G

!'7;, 7:; rd!::: Of th: ;i;: f th: LOC.^ (0.5)

b. Since the RCP Trip criteria is based on the SBLOCA analyses, you are not required to trip the RCPs following ES actuation due to a Main Steam'Line Break Accident. (0.5)

5 5.15 Refer to Figure 1, " Reactor Core Safety Limit." Identify by name .

,' or title the parts of the Figure marked A, B, C, and D. (2.0) 5.16 Following an accident that results in excessive core damage, what are two significant sources of Hydrogen generation. (1,0)  ;

5.17 When synch'ronzing the generator to the grid, OP-203, " Plant Startup" directs the operator to regulate turbine speed to .

slowly rotate the synchroscope in the fast (clockwise) direction.

Which choice below CORRECTLY gives the two parameters that the synchroscope is indicating? (1.0)

a. Current and voltage differences

b. Current and frequency differences

c. Voltage and phase differences

d. Frequency and phase differences 5.18 Which one of the following statements is CORRECT concerning the paralleling of electrical systems? (1.0)

a. Although it is desireable to have speed and phase position matched, it is much more..important to have voltages matched.

b. If voltages are not matched at the time the synchronizing switch is closed, there will be VAR flow from the lower voltage source to the higher one,

c. If the incoming machine is at synchronous speed but out of phase with the running when the breaker is closed, heavy

, currents will flow to either accelerate or retard the incoming machine.

d. If the incoming machine is in phase but slightly faster than synchronous speed when paralleled, the system will tend to speed up the incoming machine to synchronous speed.

5.19 Which one of the following is NOT one of the ECCS Acceptance Criteria as specified in 10 CFR 50.467 (1.0)

a. Peak cladding temperature shall not exceed 2200*F ,

b. DNB and Kw/ft limits shall be maintained s 1.30 and 2 18.0 kw/ft. respectively.

c. Total oxidation of cladding shall nowhere exceed 17% of the  !

total cladding thickness before oxidation.

d. Total amount of hydrogen generated shell not exceed 1% of the

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6 5.20 Figure 5.20 is a temperature profile from the fuel centerline to the .

coolant. Which of the following is CORRECT concerning anticipated temperatures as shown in this Figure? (1.0)

a. A thumb rule approximation is 1000*F from centerline to fuel surface, 500*F across the gap and 100' across the cladding (for ' nominal heat rate)

b. A thumb rule approximation is 1000*F from centerline to fuel surface,100*F across the gap and 50*F across the cladding (for nominal heat rate)

c. For the nominal heat rate, the AT across the fuel, across the clad, and across the gap are approximately the same

d. AT from fuel cegterline to fuel surface must be kept less than 1000*F to maintain peak clad temperature less than 2200*F.

5.21 A negative MTC is great to have for safe reactor control, but creates a problem when it comes to cold water accidents or a steam /feedline break. What inherent feature of the CR3 low enriched core acts intially to limit the severity of these transients? (1 )

a. Moderator Temperature Coefficient

b. Doppler Coefficient

c. Voids Coefficient

d. Redistribution 5.22 Which of the following is CORRECT concerning temperatures at which fuel and/or cladding damage will occur? (1.0)

a. The cladding will melt at approximately 2200'F.

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b. Uranium dioxide fuel will melt at approximately the same melting temperature as the cladding.

c. U02 melt limit is approximately 5000*F while Zirconium will melt at about 3300*F.

d. The melting temperature for both fuel and cladding drop sharply over core life.

. . 7 5.23 Answer the following statements concerning core power -

distribution and thermal design limits TRUE or FALSE.

a. Axial Power Imbalance limitations only apply in Mode 1 above 40% of Rated Thermal Power. (0.5)

b. Hot Channel Factors (Fg and FNAH) are only monitored once for each new core prior to exceeding 75% Full Power. .

(0.5)

c. The Quadrant Power Tilt Limits are less restrictive when measured by Power Range Channels than by the Symmetrical Incore Detector System. (0.5)

d. Power distribution limits are based on maintaining minimus DNBR, peak linear power density and LOCA analyses criteria. (0.5)

END OF SECTION 5 i

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6.0 PLANT SYSTEM DESIGN, CONTROL AND INSTRUMENTATION (25.0) -

6.1 Which of the following statements concerning the Reactor (1.0).

Building Isolation and Cooling System is CORRECT 7

a. Diverse Containment Isolation occurs when HPI is automatically or manually initiated,

b. Diverse Containment Isolation will isolate NSCCCW to the Reactor Coolant Pumps.

c. Diverse Containment Isolation will close the CI flow to the RB fans and open the SW valves.

d. When HPI automatically initiates, Diverse Containment Isolation occurs and the RB fans are started or shifted to slow speed.

6.2 Many important pumps have annunciators which indicate when the pump (1.0) is out-of-service, for example: ES Annunciator D-3-3 is labeled "DH Pump 'B' OUT OF SERV". Which one of the following is an indicated

condition for this type of annunciator?

i a. No breaker DC control power.

b. Breaker control switch in normal after start, breaker open, breaker racked in,

c. Overload relay actuated.

d. Excessive motor amps.

6.3 With regard to the Reactor Building Spray System, which of the (1.0)

, following statements is CORRECT 7

a. Upon receipt of an ES actutation signal of 4 psig in the RB, the NaOH tank outlet valves (BSV-11 and 12) will automatically stroke to the full open position.

b. A high RB pressure signal (30 psig increasing) starts the 2 RB spray pumps and automatically strokes open the suction valves (BSV-16 and 17). i

c. The spray pumps start on the 4 psig signal while the spray 1 header supply valves (BSV-3 and 4) stroke open on the 30 psig RB signal.

d. The 4 psig signal opens all three sets of valves (BSV-3 and 4, BSV-11 and 12, and BSV-16 and 17).

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9 6.4 Select the CORRECT statement concerning the Nuclear Services (1.0) -l Booster Pumps and CRD Cooling, System.

a. One pump is normally operated'with the other serving as backup.

A drop in line pressure (25 psi) will start the idle pump.

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b. On an ES signal, the supply and return valves to the CRDM coolers will close and the booster pumps will have to be manually secured.

c. SWP-2A is powered from ES MCC 3A2 and SWP-2B is powered from ES MCC 382.

d. Low level in the SW surge tanks will trip the NS booster pumps.

6.5 Select the CORRECT statement concerning.the Makeup Pump Lube (1.0) 011 System.

a. If the main gear oil pump control switch is in Auto, the pump will start and run for three minutes after the makeup pump starts,

b. The backup gear oil pump will start (if in Auto) when oil pressure reaches 7 psig and will automatically stop when oil pressure reaches 20 psig.

c. If the main lube oil pump control switch is in Auto, the pump will start and run for three minutes after the makeup pump starts,

d. The backup lube oil pump has no auto start provisions and can be used as a back up for the gear oil system.

O 6.6 Select the CORRECT statement about the Makeup and Purification (1.0)

System.

a. The block orifice has two bypasses, (MUV-51 and MUV-48) both of which are remotely operated from.the control room,

b. The letdown line connections to the Decay Heat Removal System are prior to the prefilters and af ter the makeup filters.

c. A temperature element (TE-5) on the letdown line alarms at 130 'F-and closes the letdown cooler outlet valves (MUV-40 and MUV-41) at 135 *F to protect the letdown coolers.

d. The deborating domineralizer may be operated in parallel or series with the makeup demineralizers.

10 6.7 Which one of the following statements is CORRECT regarding the (1.0) - ,

design of the internels vent valves?

a. The vent valves are designed to open in the event of a hot leg break when the pressure differential reaches at least 43 psj.

b. The vent valves are designed to open in the event of .

a cold leg break when the pressure differential reaches '

at least 43 psi.

, c. In the event of a hot leg break, the vent valves should

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begin to open with a AP of about 0.3 psid and be fully open at 1.5 psid.  ;

d. In the event of a cold leg break, the vent valves should begin 3

to open with a AP of about 0.3 psid. and be fully open at 1.5 psid.

6.8 Which one of the following is NOT monitored for in the (1.0)

RANGE subsystem of the Post Accident Sampling System?

a. High range noble gas I

b. Hydrogen

c. Particulate j d. Iodine l 6.9 On Figure 2.19, show the connections and components between 480V MCC Safeguards Bus ar' a typical 120V A.C. Vital Bus. Include the following: Battery chargers, inverters, automatic and manual i

? switches and transformers. It is not necessary to show breakers or

to label components (the labels shown - 3A and 3A-1 are for i illustration only). (2.0) 6.10 Select the CORRECT statement concerning the site fire protection systems. (1.0) 4

a. All areas protected by a fixed 4 water spray system use heat detectors to actuate the alarms.

b. To prevent accidental actuation, it requires two detectors

actuating to cause operation of the fixed water spray system i on the charcoal filter banks.

I c. A wet pipe sprinkler system is used to protect the Emergency Diesel Generators.

l d. Lube oil systems on the reactor coolant pumps, feedwater pumps and main turbine are protected by a fixed water j spray system.

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6.11 TRUE or FALSE -

a. Maximum flow for one HPI pump is approxima'tely 540 gpm 9 6D0 psig. (.5)

b. LPI pump high flow alarm occurs at about 3400 GPM and runout i

flow'is about 4100 GPM. (.5) 6.12 Which of the following Decay Heat System Interlocks is CORRECT? (1.0)

a. Separate RC pressure transmitters will shut DHV-3 and DHV-4 at approximately 284 psig.

b. Separate RC pressure transmitters will shut DHV-3, DHV-4 and  ;

DHV-41 at approximately 284 psig.

c. A single RC pressure transmitter will shut DHV-3 and DHV-4 at approximately 284 psig.

d. A single RC pressure transmitter will shut DHV-3, DHV-4, and DHV-41 at approximately 284 psig.

l 6.13 Which of the following statements is INCORRECT regarding bypassing the Steam Line Rupture Matrix? (1.0)

a. During a normal cooldown, when OTSG pressure drops below 725 psig, the matrix can be bypassed by depressing two bypass pushbuttons on the main control board.

4 b. During a normal cooldown, the four maintenance bypass key switches must be utilized before the operator can depress the two bypass pushbuttons.

c. Following an actuation, if either the < 725 or < 600 pressure switch has actuated, a bypass permit will be present.

d. Following an actuation, in addition to a bypass permit, the operator must depress the two main control board push 4 buttons in order to bypass thetmatrix, t

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s 6.14 Which of the following statements is CORRECT concerning the '

Intermediate Range Compensated Ionization Chamb,ers? (1.0)

a. The detectors are surrounded by four inches of lead for shielding fast neutron radiation.

b. The b'oron lined chamber is sensitive to neutron and gamma radiation while the unlined chamber is sensitive only to gamma rays.

c. The compensated ion chamber is designed to remove the gamma signal only at high reactor power levels,

d. Undercompensation will cause loss of some neutron current as well as blocking gamma current.

6.15 Which of the following statements is CORRECT concerning the operation of a typical Atmospheric Radiation Monitor (for example, RM-Al or A2)? (1.0)

a. The sampled air will pass through a fixed particulate filter. The particulate buildup on the filter is then measured by a GM detector which outputs the measurement in CPM.

b. After passage through the particulate filter the air is i drawn into a gas sampler which detects gaseous activity with a scintillation detector,

c. A gamma scintillation detector is used to measure the iodine activity on a fixed iodine filter (activated charcoal).

f d. The flow path of the sampled air through RM-A2 is the particulate filter, the gas sampler, followed by the iodine filter.

6.16 Select the CORRECT statement with regard to speed control (1.0)

(Governor) of the Emergency Diesel Generators.

a. As a general rule, D-G units running alone should have the SPEED OR00P control set on 0 (zero).

b. The synchronizer motor, mounted on top of the governor, allows the operator to match the voltage of the D-G with running voltage before synchronizing to the system.

c. The LOAD LIMIT control may be used for shutting down the diesel by turning the LOAD LIMIT control to zero,

d. The SYNC INDICATOR, located directly below the SYNCHRONIZER control indicates if the D-G is in phase with the system.

13 6.17 When the RPS is in Shutdown Bypass, which one of the following is (1.0)

CORRECT? ,

't

a. A.high pressure trip of 1720 psig is administrative 1y imposed and an overpower trip of 5% automatically imposed.

b. The high pressure trip at 2355 psig is bypassed.

c. The four trips bypassed are high temperature, low pressure, variable low pressure and flux / delta flux / flow,

d. The RCP Power Monitor trip is bypassed.

6.18 Cross-Tie Blocking Interlocks are provided to prevent paralleling of both D-G. Refer to Figure 3.18 and select the CORRECT statement. (1.0)

a. If breakers 3209, 3210 and 3205 are all closed, the amber lamp (Block Closing Actuated 3206) will be lit, thus permitting breaker 3206 to be closed.

b. If breakers 3209 and (1) 3205 and 3206, or (ii) 3207 and 3208, or (iii) 3211 and 3212 are closed, the amber lamp (DG Parallel Block Act) will be lit and breaker 3210 can ,

not be closkd.'

l c. If the amber lamp (Block Closing Actuated 3208) is lit, it

r. cans breaker 3208 cannot be closed because the 38 bus is already being fed from the 3A bus (through 3207) and no Diaspisarerunning.

d. If both Diesels are feeding their respective buses (3209 closed and 3210 closed) all Block Closing Actuated Lamps will be lit.

P 6.19 Which one of the following is CORRECT concerning the " Air Fall (1.0) 4 Reset" pushbuttons for MUV-16, 31 and 51?

a. The pushbutton only indicates loss of air to the associated valve E/P controller.

b. The pushbutton indicates loss of air to E/p controllers for MUV-16 and 51 and also loss of air to the valve positioner for MUV-31.

1

c. On loss of air supply, the solenoid valve supplying air to the air lock valve will de-energize, causing the affected valve (10, 31 or 51) to close,

d. When air pressure has increased, depressing the air fail reset 4 pushbutton will unlock MUV-16, 31 or 51.

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i 14 6.20 a. What two control room indications of abnormal RCP operation, (1.0) -l' require the pump to be shutdown immediately?

b. What control room indication of abnormal RCP operation, (1.0) requires power level to be reduced to 72%, at 30%/ min, then tripping the affected RCP?

6.21 Which one of the following is NOT a Tech Spec required monitgring channel for the Waste Gas System? -

(1.0)

a. Hydrogen

b. Noble gas

c. Tritium

d. Oxygen ,

6.22 Answer the following TRUE or FALSE concerning the Meteorological Measurement System.

a. A strongly positive AT indicates a temperature inversion. (0.5)

b. A strong thermal inversion may cause wind direction values between the upper and lower levels to be significantly different. (0.5)

c. The wind direction is the way towards which the wind is blowing (e.g., 180' means the wind is blowing toward the South) (0.5)

d. Tech Specs require Waste gas releases to be terminated if the meteorological monitoring instrumentation channels are inoperable. (0,5)

END OF SECTION 6 i

L __-______.____.______-_.______m______

..' 15 7.0 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL (25.0) -

7.01 Match the Condition with the appropria'te Radiation ,

Monitor Alarm. (2.5)

Radiation Monitor Condition

a. RM-Al 1. Control complex ventilation return air has exceeded setpoint on gas or iodine / particulate channels,

b. RM-A2 2. Possible spent fuel radio-activity leak,

c. RM-A3 3. Reactor Building purge duct

' exhaust to the atmosphere has exceeded setpoint on gas channel,

d. RM-A4 4. Auxiliary Building ventilation exhaust to the atmosphere has exceeded setpoint on gas channel,

e. RM-A5 5. Possible waste gas tank or piping leak.

7.02 List your Immediate Actions in response to an alarm from RM-L2. (0.5) 7.03 Which of the following is NOT an Immediate Action required in AP-330, " Loss of Nuclear Services Water". (1.0)

a. Trip all NSCCCW pumps: SWP-A, SWP-8, SWP-C, SWP-2A, SWP-2B.

O

b. Establish OTSG levels with emergency feedwater pumps,

c. Trip reactor AND refer to AP-580

d. Close: MUV-50 and MUV-51 i

16 7.04 Immediate Action step 3 of AP-380, " Engineered Safeguards System -

Actuation," states the following: ,

Ensure HPI trains itart

• 2 HPI pumps

• SWPs

• RWPs Step 6 of the same procedure states: ,

Ensure LPI trains start

• DHPs

• DCPs

• RWPs Which statement is CORRECT concerning the "RWPs" referred to in AP-3807 (1.0)

a. The RWPs in step 3 and step 6 are t'he same. The verification is repeated to ensure it is accomplished.

b. The RWPs in Step 3 refer to RWP-3A and 3B; the RWPs in Step 6 refer to RWP-2A and 28.

c. Step 3 refers to RWP-1, 2A and 2B while step 6 refers only to RWP-2A and 2B.

d. In Step 3, the RWPs are the Nuclear Services (Emergency)

Seawater Pumps while in Step 6, RWPs refer to the Decay Heat (Emergency) Seawater Pumps.

7.0$ An Immediate Action of AP-380, " Engineered Safeguards System Actuation," is to:

,' " Place RB sump pump in PULL-TO-LOCK":

• WDP-2A

• WDP-2B What is the Remedial Action associated with this step? (1.0)

_ 17 .

7.06 The statements below are contained in AP-380, " Engineered Safeguards -

System Actuation." Fill in the blanks with the appropriate numbers where indicated. (3.0)

When the following conditions exist:

• High Pressure

- Adequate subcooling margin; 'F when > 1500 psig

'F when s 1500 psig

- PZR level 2 M "

- OTSG heat removal OR

• Low pressure ,

LPI flow 2 @ GPM in each train and stable for 2 M minutes, Then STOP HPI.

If TC < then refer to EP-220, " Pressurized j

Thermal [ Shock."f} *F,

• Required Cooldown Rates Normal s 'F/hr Natural Circulation h F/hr MUV-53 and JM' V-257 (recire valves) must be open when total HPI flow s W GPM Establish required OTSG 1evel W"

' Any RCP operating

• No RCP's, adequate subcooling margin @%

• Less than adequate subcooling margin L1_) %

• < 2 HPI pumps available Om %

• If subcooling margin < M , then go to EP-290, " Inadequate Core Cooling."

• When RC Press 2 M psig, then open PORV.

18 7.07 Select the INCORRECT statement for the following Limit and - -

Precaution as contained in OP-404, Decay Heat Removal System. (1.0)

"In order to assure that redundant or diverse DHR methods are available during all modes of operation, the following require-ments must be met prior to removing a DH train from service."

a. The LPI pump suction valves from BWST (DHV-34 and DHV-35) will be closed and the breakers racked out during periods when the BWST is empty and a BAST is being utilized for emergency boration control.

t b. No more than one DH train shall be removed from service at any one time.

c. The requirements for voluntarily entering a degraded mode 4 of operation listed in CP-115 have ,been met.

d. The refueling transfer canal is flooded, or at least one ,

OTSG is available for cooling either by forced flow or i

natural circulation, or there is a readily accessible source I of borated water during periods of low DH load and the plant is in Mode 5 or 6.

7.08 Which of the following statements is CORRECT concerning DH pump operation in the recirculation mode? (1.0)

a. As long as the minimum flow rate of 80 gpm is not violated, DH pump operation in the recirculation mode is unrestricted,

b. In no event shall the DH pump operate in the recirculation mode '

continuously for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> per month.

l c. DH pump operation in the recirculation mode shall be timed and an entry made in the Control Center notebook.

d. The maximum flow from the DH system to the MVP is restricted to 140 gpm when the DH pumps are in the recirculation mode.

7.09 Select the CORRECT statement concerning the Nuclear Services Cooling System (as per OP-408). 1 (1.0)

a. When SW system pressure drops to 110 psig, SWP-1B automatically starts.

b. When RW system pressure drops to 110 psig, RWP-28 automatically starts.

! c. When either emergency SW pump starts, the normal pump will trip in 30 seconds,

d. When either emergency RW pump starts, the normal pump will trip in 30 seconds.

- w-- - y - - 4y4-- g----- g ,-=y- apyvw+ w a , w

18a 7.10 Where would you expect to find the correct procedure to transfer cooling water for the 3A 'and 3C makeup pumps from the OC System to the SW System? (1.0)

a. OP-402, Makeup and Purification System

b. OP-705, Emergency Power-DC System -

c. OP-408, Nuclear Services Cooling System

d. All three of the above procedures contain these instructions.

7.11 Select the CORRECT statement concernin.g transfer of Non-Nuclear Instrumentation signals to the ICS (as per 0P-501). (1.0)

a. Disconnecting the RC flow signal source from the RPS cabinets has no affect on the ICS,

b. If operating signal source malfunctions make signal source transfer necessary, transfer to another source should be done immediately regardless of ICS operating 7

mk.

c. When changing narrow range RC pressure signals, the PORV (RCV-11) should be open, with the heaters and 4

spray valves in manual.

. d. Buffer cards or buffer card modules may be replaced

• while leaving the affected controllers in auto.

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4 7.12 During fuel handling operations, the polar crane will be

" Blue-Tagged" to: (1.0)

a. the Shift Supervisor on duty

b. the person operating the crane

c. the Refueling Consultant

d. the Refueling Supervisor on duty 7.13 The Fuel Handling Bridge Operator in the RB has picked up a fuel assembly and is ready to move it to a position above the designated reactor core location. LIST TWO steps that must be verified or accomplished before he is alloEed to move the Bridge / Trolley.

(NOTE: Two steps to ensure that the element has been completely raised). (1.0) 7.14 What is the proper orientation of fuel assemblies during refueling

' operations? (1.0)

a. Identification plates on fuel assemblies should be oriented in the West direction. Serial numbers on control rod assemblies should be in the opposite direction.

b. Identification plates on fuel assemblies should be oriented in the West direction. Serial numbers on control rod assemblies should be in the same direction as the fuel assembly Identification number.

c. Identification plates on fuel assemblies should be oriented in the North direction. Serial numbers on control rod assemblies should be in the opposite direction.

d. Identification plates on fuel assemblies should be oriented in the North direction. Serial numbers on control rod assemblies should be in the same direction as the fuel assembly Identification number.

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7.15 Which of the following statements is CORRECT concerning operation -

of the turbine bypass valves? _

(1.0)

a. If automatic operation of turbine bypass valves is desired when CR0 breakers are open, set turbine header pressure controller to 27% to compensate for +125 psig reactor trip bias,

b. If automatic operation of turbine bypass valves is desired when CRD breakers are open, the ISO psig throttle pressure error logic must be bypassed,

c. If automatic operation of turbine bypass valves is desired when CRD breakers are open, the ULD.must be less than 15% to reset the +50 psig bias.

d. Automatic operation of turbine bypass valves is not possible without first resetting the CRD tri,p breakers.

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7.16 In order to startup a main feedwater pump, (Section 11.3 of OP-605) you must depress and hold the " Speed Signal Bypass" push button.

After which of the following steps can you release the " Speed Signal Bypass" without causing the FW Pump Turbine to Trip? (1.0)

a. Verify all white " Permit" lights and speed control at

" minimum" with green light on governor speed control switch,

b. Place " Trip / Reset" switch in " Reset" position.

c. Verify the fcilowing occurs:

LP Stop Open HP Stop Open

d. Verify turbine speed greater than 100 rpm.

7.17 During all evolutions involving the makeup pumps, verify operable flow paths for each pump to be operated. Less of flow through a makeup pump will destroy the pump within approximately: (1,0)

a. 3 seconds

b. 15 seconds

c. I minute

d. 3 minutes i

21 7.18 Which of the following choices will correctly complete the -

(1.0) statene,nt below?

"The maximum weekly exposure is (1) . h/The (2) may authorize exposures to (3) by use of Form 912801, Authorization to Exceed Radiation Exposure Limits."

a. (1) 600 mrem .

(2) Nuclear Plant Manager -

(3) 1250 arem

b. (1) 300 mrem (2) Nuclear Plant Manager (3) 1250 arem

c. (1) 300 mrem (2) ChemRad Supervisor (3) 600 mrem

d. (1) 600 mrem (2) ChemRad Supervisor (3) 2 Rem 7.19 Which cf the following statements is CORRECT concerning RWP's and SRWP's? (1.0)

a. SRWP's are generally required for non-routine work.

b. For emergency, short-term or special situations, the continuous presence of a qualified ChemRad representative may meet the RWP requirement,

c. SRWPs may be issued when periodic radiation surveys show that l individuals will not encounter a dose rate in excess of 100 mrem /hr.

d. The RWP will list all equipment allowed to be taken into and removed from a designated area.

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,7.20 Select the CORRECT statement concerning entrance into a Contaminated Area. (1.0)

a. Only rubber gloves are allowed in contaminated areas.

b. Rubber or plastic gloves used in wet contaminated areas should be taped to the inside of a plastic suit, if one is being worn. ,

c. Personnel dosimetry and identification badges should be worn inside protective clothing such that they will not fall off and/or become contaminated.

d. In cases of routine or special maintenance that involves high contamination levels, a plastic suit will be required.

7.21ListyourImmediateActionsforAP-990,."ShutdownFrom Outside Control Room" (1.5) 7.22 TRUE or FALSE (0.5)

The first Immediate Action of AP-580, RPS Actuation, is to ensure group 1-7 rods are inserted. The Remedial Action for this step .

directs you to EP-140, Emergency Reactivity Control.

i END OF SECTION 7

m _ _ _

23 8.0 ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS (25.0) -

8.1 According to Administrative Procedure AI-100, an individual should (1.0) not be permitted to work more than hours in any 48-hour period (excluding shift turnover time) unless authorized at the Nuclear Plant Manager level or above. (Choose the correct number below). ,

a. 12

b. 16

c. 24

d. 32 .

8.2 According to the Crystal River Emergency Plan Implementing Procedure (1.0)

EM-202, during a Site Area Emergency personnel accountability SHALL be verified within minutes of Site Evacuation.

a. 15 minutes

b. 30 minutes

c. 45 minutes

d. 60 minutes 8.3 While in Mode 2, which one of the RCS Chemistry analysis values given (1.0) below is between the steady state chemistry limit and the transient limit?

l a. Fluoride 1.4 ppm

b. Boron 2000 ppm

c. Dissolved oxygen 1.4 ppm

d. Chloride .14 ppm 8.4 According to AI-500, " Conduct of Operations", which one of the following (1.0) positions has the authority to both 1) shutdown the reactor or cause it to be shutdown and 2) start it up and return it to power operation?

a. Chief Nuclear Operator

b. Assistant Nuclear Shift Supervisor

c. Nuclear Shift Supervisor

d. Nuclear Operations Superintendent

j' y, 24 .

8.5 Which of the following is responsible for maintaining the refueling (1.0) -

log? , C Con' trol Center Refueling Operator

b. Refueling Consultant

c. Refueling Supervisor .

d. Shift Supervisor 8.6 Wh'ich one of the following choices CORRECTLY states the source (1.0) range N1 monitor requirements during core alterations as specified in FP-203?

At least two source range NI monitors shall be operable:

a. each with audible indication in the Control Center and one with visual indication in the Control Center and one with audible indication in containment,

b. .each with vi!;ual indication in the Control Center and

'one with audible indication in both the Control Center and containment.

c. one with visual indication in the Control Center and one with audible' indication in containment.

d. each with audible and visual indication both in containment I and in the' Control Center, j 8.7 Which one of the following conditions requires action according to (1.0)

Tech Specs in less than I hour if in MODE 27

a. The shutdown margin is 1.4%.

b. One train of. heat tracing on the BAST is inoperable.

- c.'TheReactorCoolantSystemfowestlooptemperature(Tavg)is520'F.

, d. Two of the three makeup pumps,are inoperable.

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s 23 8.0 ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS (25.0) -

8.1 According to Administrative Procedure AI-100, an individual should (1.0) not be permitted to work more than hours in any 48-hour period (excluding shift turnover time) unless authorized at the Nuclear Plant Manager level or above. (Choose the correct number below). .

a. 12

b. 16

c. 24

d. 32 ,

8.2 According to the Crystal River Emergency Plan Implementing Procedure (1.0)

EM-202, during a Site Area Emergency personnel accountability SHALL be verified within minutes of Site Evacuation.

a. 15 minutes ,

b. 30 minutes

c. 45 mirutes

d. 60 minutes 8.3 While in Mode 2, which one of the RCS Chemistry analysis values given (1.0) below is between the steady state chemistry limit and the transient 4

limit?

l a. Fluoride 1.4 ppm

b. Baron 2000 ppm

c. Dissolved oxygen 1.4 ppm

d. Chloride .14 ppm ,

8.4 According to AI-500, " Conduct of Operations", which one of the following (1.0) positions has the authority to both 1) shutdown the reactor or cause it to be shutdown and 2) start it up and return it to power operation?

a. Chief Nuclear Operator

b. Assistant Nuclear Shift Supervisor

c. Nuclear Shift Supervisor

d. Nuclear Operations Superintendent ,

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8.8 Which one of the following situations, while in MODE 1, requires some (1.0) -

action to be taken in I hour or less? ,(No surveillance testing in process). .

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a. One safety rod not fully withdrawn. '

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b. The overlap between regulating rod groups 6 and 7 is determined i to be 28%. .

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c. Two pulse stepping position indicator channels inoperable with all reed switch position indicator channels operable.

d. One APSR is misaligned from its group average height by 5%.

8.9 Which one of the following statements is CORRECT regarding the axial power imbalance? (1.0)

a. Axial power imbalance is not a directTy observable quantity and therefore, limits have been established 'on the nuclear heat flux hot-channel factor produced by the imbalance.-

b. Axial power imbalance, in addition to maintaining control rod overlap, sequence, and insertion limits, v.111 ensure that hot channel fattors are maintained within acceptable limits,

c. The axial power imbalance is defined as the maximum local , fuel rod linear power density divided by .the average feel rod linear power density.

d. Negative axial power imbalances are more' restrictive due to the coolant temperature rise across the core.

8.10 Which one of the following statements is CORRECT according to the (1.0)

OSIM for; " Documenting Reactor Trip, Recovery, and Plant Shutdown"?

a. A reactor trip is any reactor protection system (RPS) action,

' manual or automatic, which causes the opening of generator breakers 1661 and 1662. ~

b. When a reactor trip or plant shutdown occurs, the nuclear shift supervisor notifies the SOTA, Nucletr Operations Superintendent, person on call, the NRC (red phone), and the NRC Resident Inspector. *

c. The SOTA is the team leader in assessing and justifying restart,

d. A log of reactor trip and shutdown report dates and types will be maintained in the Nuclear Operations Sd'erintendent's p office.

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8.11 Which statement is CORRECT concerning the " Operator of the Controls"? (1.0) -

a. He shall not, under any circumstances, leave the red-carpeted general area.

b. For emergency reasons, he may leave the red-carpeted area only after obtaining a qualified relief Operator at the Controls,

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c. In the event of an emergency affecting the safety of operations, he may be momentarily absent from the general area in front of the board. This includes responding to back panel (e.g., ventilation system) indications.

d. At all times (unless properly relieved) he must remain within the confines of the Control Center with an unobstructed view of the operational control panels.

8.12 TRUE OR FALSE

a. Open annunciator links are to be logged in the Equipment Out-of-Service Log. (0.5)

b. Out-of-Service classification can be removed with surveillance outstanding provided functional tests have been completed. (0.5)

c. Short term instructions shall expire in 90 days unless properly amended. (0.5)

d. For non-safety related procedures, a short term instruction may be issued instead of a temporary procedure change. (0.5) 8.13 Which one of the following is properly classified as " Controlled Leakage"? -

(1.0)

a. Valve packing leaks that are captured and conducted to a sump.

b. Seal water flow from reactor coolant pump seals.

c. Identified and monitored steam generator tube leakage.

d. Leakage into containment atmosphere from known sources.

. . 27 8.14 During plant startup with the reactor about 2% power, you find that -

the PORV Block Valve is stuck open and incapable of closing. Which of the following is a CORRECT ACTION (see the attached LCO)? . (1.0)

s. Continued operation is allowed provided the PORV is operable and power is removed from the block valve.

b. If Action b. is satisfied you are allowed to increase power into Mode 1.

(Block valve cannot be restored to OPERABLE).

c. The PORV must be closed, power removed from the solenoid valve and the block valve must be repaired prior to going to Mode 1.

d. Since the block valve is incapable of closing, you must proceed to Hot 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 Cold Shutdown within the following 3Q hours.

8.15 The specific activity of the secondary coolant system shall be

< Dose Equivalent I-131. The accident this is based on is a . Which choice CORRECTLY provides the missing information? (1.0)

a. 1.0 pCi/gm, Steam Generator Tube Rupture

b. 0.1 SC1/gm, Steam Generator Tube Rupture ,

c. 1.0 pC1/gm, Steam Line Rupture

d. 0.1 pCi/gm, Steam Line Rupture 8.16 The , or his designated alternate, assumes (1.0) the position of Emergency Coordinator when relieving the NSS.

l a. Site Director

b. Operations Superintendent

c. Director of Emergency Planning

d. Nuclear Plant Manager 8.17 When a deluge and sprinkler fire system is inoperable, which statement below is the CORRECT required action? (1.0)

a. Commence a unit shutdown within one hour.

b. Establish an hourly fire watch patrol for the affected area.

c. Establish a continuous fire watch with backup fire suppression equipment in the affected area within one hour,

d. Log ambient temperature readings for the affected area hourly.

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8.18 A quarterly surveillance requirement of Tech Specs may be extended (1.0) -

up to days without declaring the component, inoperable due to the surveillance testing not being performed.

a. 9

b. 23

c. 32

.d. 41 8.19 The attached drawing shows the primary and secondary evacuation (1.0) areas. Which of the numbered points is the " Crystal River Generation Complex secondary evacuation area (SEA)"?

a. 1 ~

b. 2

c. 3

d. 4 8.20 When is the Incore Monitoring System required to be operable? (1.0)

a. Only in Mode 1

b. Only in Mode 1 above 40% power

c. In modes 1 and 2

d. When surveillance is required for Axial Power Imbalance and Quadrant Power Tilt.

8.21 List the two methods that will be used to track and document valve l lineups if they are different from that required by a procedure. (1.0) 8.22 CP-115, "In-Plant Equipment Clearance and Switching Orders" states four conditions that require PRC approval of a clearance prior to issuance. List these four conditions. (2.0) 8.23 Is a pump operable if its control svitch is in " Pull-to-Lock"? (1,0)

Explain. 1 END OF CATEGORY 8 END OF EXAM l

l

([ O 1/2 Gv 40 (V g e / )/1 4o 1,* AoAg

- PL o agn ~

. V f a y, + et . *

• e/t ae an2/tif2 = 0.493/t1/2 y,,p -

A =. n D, I t l/2'ff*[(*D')(**)) ~

.[(g/2)+(t,))

1 at 931 am g = m,ah m = V,,A, -Ix I = I,e ,

Q = aCp at Q = UA T I = I c

e'"* '

Pwr = Wfah I

• I , 10'*/DL TVL = 1.3/v P = P 10'"'II) HVL = -0.693/s t

P = P ,e /T SUR = 26.06/T SCR = 5/(1 - K,ff)

CR, = 5/(1 - K,ff,)

SUR = 26s/a= + (s - e)T j (1 - K,ffj) = CR2 I1 ~ "eff2)

CR T = (**/s) + [(8 - *YIe3 M

• I/II ~ "eff) = CA /CR j ,

y = s/(e - s)

M * (1 - K ,ffe)/(I - Keff1)

T = (s - e)/(Ie) SDM = ( - K,ff)/K ,ff a = (K,ff-1)/Keff * *eff/K eff 5 '""

[*Da=0.1secones,j o = [(t*/(T K,ff)) + [s,ff /(1 + IT))

j = led 2

, P = (teV)/(3 x 1010) II d)d) 2 =221 d I = eN R/hr = (0.5 CE)/c2 (3,t,73)

R/hr = 6 CE/d (feet)

Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lee. -

1 curie = 3.7 x 1010aps 1 ga; . = 3.78 liters 1 kg = 2.21 lbm 1 fte = 7.48 gal. I hp = 2.54 x 103 8tu/nr Density = 62.4 14/ft3 1 m = 3.41 x 106 8tu/hr Density = 1 gm/cse lin = 2.54 cm Heat of vaporization = 970 8to/lom =F = 9/5'C + 32 Heat of fusion = 144 8tu/IDm ,

'C = 5/9 ('F-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-Ibf i

1 ft. H 2O = 0.4335 Itf/in.

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40 152 97 00lt 3e llle) 90 63 120 he. 100t4 1827.3 50 C 2896 1.H27 1.8625 162.24 0 01640 73.52 lb I) 1001.0 1131.1 0.2M7 2 4094 f.8441 60 110D6 0 01MS 61.95 137.9o 996.2 l134 2 0.2472 1.5820 1.8292 1.0 14 85 0 01649 53 64 144 % 9921 1836 9 0.2581 1.5586 1.8167 80 152.86 0 01653 47.34 ISO 79 9th 5 1139 3 0 2674 1.5343 1.8051 90 188.26 0 016 % 4:40 l$6 22 965 2 1141 4 0.2759 1.5203 1.7962 10 193.21 0 01659 34 42 161 17 982 1 1843.3 0 2835 1.5041 1.78 4 14 69o 212 00 0 01672 26 80 150 07 970.3 IISO 4 0 3120 1.4446 1.7566 15 213 03 0 01672 26 29 181 11 %97 l150 8 0.3133 1.4415 1.7549 20 227.96 0.0168) 20 089 19t, It. 960I II56 3 0.3356 1.3962 1.7319 2$ 240 01 0 01692 16 30) 206 42 952 1 1160 6 0.3533 1.360e 30 230 33 0.01101 1.7139 13.14e 218 62 945) 1864 1 0.3680 1.3313 1.6993 35 259.26 0 01706 l l.89b 227.91 939.2 1867.1 0.3007 1.3063 1.6870 40 267.25 001715 10 496 236 03 933.7 1169 7 0 3919 1.2644 45 274 44 0 01721 9.401 1.643 243.36 9286 l172 0 0 4019 1.2630 SO 28101 0.01721 1.6669 8.515 230 09 924 0 l174.1 0 4110 1.2474 55 2t?D7 1.6 58

• 0.01732 7.787 236 30 919.6 l173.9 0 4193 1.2316 I.630s to 292 71 0 01738 7.175 262 00 915.5 1l77.6 65 297.97 0 4270 1.2165 1.6436 0 0174) 6 655 267.50 911 6 1879 1 10 0 4342 1.2032 1.4314 302 92 0 01748 6 20e 272 61 907.9 1180 6 0 4409 I.1906 16315 15 307.60 0 0175) $.816 27743 904.5 1881.9 0 4472 1.1747 to 312 03 0 01757 $ 472 262 02 901.1 1.6259 1l83 1 0 4331 1. I6% 1.6207 83 316.25 0 01761 S.168 266.39 897.6 1864 2 0 4587 1.1571 1.6154 90 320.27 0014e 4 89e g 95 290.56 894 1 t il! ) 04641 1.1471 1.6112 324 12 0 01770 4 652 294 Se 898.1 lite.2 10D 127 51 0 4692 1.13 4 1.6066 0 01774 4 432 296 40 886 8 1187.2 0 4740 110 1.1266 1.6026 334 77 0 01742 4 049 30$ 66 843.2 II86 9 0 4432 1.1117 1.594F a

• I 1

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TABLE D Is Properties of Dr3 $stursted steam reveria rt, Pressure .

' I

• obs 1emp.

"" *) Sei tai tai Sai Sa' IP Est s era- i.ev.c IP s er a' l. eve . rce 1.ev d

s. 8, p e *, *, 4, 4 4, s.

3 72> 312 44 877.9 1190 4 0 4916 1.09t: 1.587) 120 M l.25 001789 0 4995 10617 1.581:

ID )47.3 00l?9t 3 455 316bl 87 9 1191 7 3:46: 86b 2 1193 0 O Ne9 1.065 1.5751 140 353 6: 0 0t802 3 :20 3 015 330 51 863 6 1894 1 0 51M l.05.4 l.M94 1.% 356 4 0 01809 1.0436 I.% 40 2SM 335 93 859 : 1895 1 0 5204 160 M) 53 0 01815 BM9 I?96 0 052t#. 1 0324 1.5590 110 M 41 0 0182: 2 675 341.00 346 0) 8%> 1996.9 0 53:5 10:11 1.554 180 373 06 0 01627 2'532 2 404 350 79 846 6 1897 6 0SMI I0116 1.5497 190 377.51 0 0183.1 S43 0 11 % 4 0 M35 1.0016 1.5453 200 MI.79 0 01839 2.2th 355. %

376 00 825 i 1301.1 0.% 15 0 9586 1.5263 250 400.95 0 01865 1.6436 1.543.1 393 84 809 0 1202 8 0 5879 09:25 1.5104 300 417.33 0 01890 409 69 794 2 1203.9 0 60 % 0 8910 1.4966 350 431.72 0 01913 1.3260 0 6214 0 8630 1.4844 400 444.59 0 019.1 1.161) 4:40 780 5 1204.5 437.2 1614 12046 0 63 % 0 8378 14754 450 AM.26 0 0195 1.0320 0 6487 0 8147 1.4634 500 467.01 0 0197 0924 449 4 755 0 1204 4 0 8424 4608 1431 1203 9 0 6606 0 7934 1.4 54 550 476 94 0 0199 0 0201 0 7696 471.6 131.6 1203.2 0 6720 0 77N 1.4454 600 486.21 481.8 720.5 1202.3 0.6826 0 7546 1.4374 650 494.90 0 0203 0.1083 491.5 109.7 1201.2 0.69:5 0.7371 1.4296 700 303.10 0.0205 0 6554 0609: 500 8 699.2 1200.0 0.1019 0.7204 14223 750 $10 86 0.0207 509.1 688 9 1198 6 0.7108 0.1045 1.4153 800 518.23 0 0209 0.% 87 518.3 678.8 1197.1 0.7194 0 6891 1.4085 850 525.26 0 0:10 0.5327 M88 1895 4 0.7275 0.6744 I.4020 900 531.98 00:12 0.5006 526 6 0 0214 0 4711 534 6 6591 1893.7 0 7355 0 660: 1.3957 950 534 4) 0 4456 54 4 649 4 1191.8 0 1430 0.6467 1.3897 1000 544 61 0.0 16 0 4001 551 4 630 4 1187.7 0 1575 0 6205 1.3780 1100 5%.31 0 0:20 g 0.3619 57) ? 611.1 1883 4 0.7711 0.59 % l.3661 1200 M7.22 0 0:23 53; e 593.2 1178 6 0.7640 0.5719 1.3559 1300 577 46 0 0:21 0.3293 '

0 0:31 0.301: 596 7 574 7 1873 4 0 7963 03491 1.3454 1400 587.10 0.0:35 0 2765 611.6 5%.3 1167.9 0 806: 0 5269 l.3351 1500 596.23 63582 0 0257 0187) 671.1 463 4 11351 0 5619 04:30 1.2849

' 2000 1.2322 0 0287 0.1307 730 6 3605 1091.l 0.9126 0 3197 2500 665 13 0 0858 802.5 217.5 1020.3 0 9731 0 1885 1.1615 3000 695.M 00346 0 0503 902.1 0 90: 7 I.0580 0 10580 3206 2 705 40 00$03 L

-t ,

1 ABLE D Ib Propertm of Dr3 Ealutaled Sleam f amtmectJ ~

Temperature Specifer eenome Embelps 8mter.i Temp. A >'

M" 5: Est Sei le Se:

4 P

Sei l.q. 4 espo. i.g..e I'*P =epo, i.eu c IP espo-a r e j *, 4, 4, 4, 8., 8 8 3X= 0 00 1075 8 10755 0 0000 2 1871 2 1877 32 00e854 0 0160 2 1709 2 1770 294' 30 10741 1077.1 0 00t l 35 0 09995 0 0160 0 016; 2 1435 2 1597 2444 8 05 1071.3 1079 3 40 0 12:10 0 0160: 2 1867 2 1429 20 % 4 13 0e- 106b4 1061.5 0 0262 45 0.14752 0.0160?

0 17611 0 01603 1703 : 18.07 1065 6 1063 7 00Mt 2 0903 212M 50 60 02%) 0 03604 120( 1 28 06 1059 9 10860 0 0555 2.0393 2 0946 70 0 3631 0 0160e- 807 9 38.04 1054 3 109:) 0 0745 1.990: 2ON' 0 01606 633.1 48 0: 1046 6 1096 6 0 0932 1.9426 2.0MO 30 0.5069 0 6982 0 01610 468 0 57.99 1042.9 1100.9 0.1115 1.8972 2 0087 90 0.9492 0.0161) 350 4 67.97 1037.2 1105.2 0 1295 1.8531 1.9826 100 2654 77.94 103).6 1809.5 0.1417 l.8106 1.9577 110 1.2743 0 01617 87.92 1025.8 1113.7 0.1645 1.7694 1.9339 120 14924 0 01620 203 27 97.90 1020 0 t il1.9 0.1816 l.7296 I.9112 130 2.2225 0016 5 157.34 1.8894 123.01 107.89 10141 1122.0 0.1964 14910 140 2.8886 0.01629 97.07 117.09 1006.2 1126.1 0.2149 l.6537 1.8605 150 3.718 0.01634 4 741 0 01639 77.29 127.89 1002.3 1130.2 0'311 1 6174 1.8485 160 1.8293 0 01645 62 0t- 137.90 996.3 1134.2 0.2472 1.5422 170 5992 147.92 990.2 18381 0.2630 1.5400 1.8109 180 7.510 0 01651 50.23 40 96 157.95 964.1 1142.0 0.2785 1.5147 1.7932 190 9.339 0 01657 3344 167.99 977.9 Il45.9 0.2938 1.4824 1.7762 200 11.526 0.01663 27.82 178.05 971.6 1149.7 0.3090 1.4508 1.7598 210 14.I23 0.01670 26.30 180.07 970.3 1150 4 0.3120 1.4446 1.1566 212 14 6 % 0.01672 0 01677 23.15 188.13 965.2 1853.4 0.3239 I.4201 1.7440 220 17.186 19.382 1 % .23 958.8 1857.0 0.3387 1.3901 1.1286 230 20.780 0 01664 16.323 206.34 952.2 1960.5 0.3531 1.3609 I.7140 240 24.969 0 0169:

216 48 945.5 1164 0 0.M75 1.3323 14998 250 29 825 001700 13 821 11.763 226.64 936 7 1867.3 0.3817 1.3043 14860 260 35 429 0.01709 10.061 238.84 931.8 1l70.6 0.3958 1.2769 14727 270 41.858 0 01717 8 445 249.06 924.7 1873.8 0.4096 1.2501 14597 280 49.203 CD1726 1.461 259.31 917.5 18768 0 4234 1.2238 14472 290 57.556 0.01735

' 6 466 269.59 910t i179 7 0 4369 1.1980 1.6350 300 67.013 001745 5.626 279.92 907 5 1882.5 0 4504 1.1727 1423 310 7748 0 01155 4.914 290 25 89 6 1185.2 0.4637 1.1478 1.6115 320 89 66 0 01765 330 103 06 0 01776 4.30? 300 68 887.0 1187.7 0 4769 1.1233 16002 340 118 01 0 01787 3.781 311.13 879.0 11901 0 4900 1.099: 1.5891 i

I L

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TABLE D lb Properties of Dr5 Satursted Steam Imarl==rd.

T tmrtraturc 3, $recif sei.me 6 mihair leirer.

Temr " " '

• F Sai Sa' Sai Sa. Sa' Sa-bewie terce leeved I'*P tem I.evie Ii verr..

e r i, e, A. 4 4, s, v. s, 350 IM 63 001799 3M 3:5 63 870 7 1892.3 05029 1.0iM l.5763 360 15304 0 0l> l1  : 95* 33:16 850.0 l194 4 05156 1.0519 1.56?7 370 173.37 0 0160) 26:5 34: 79 853 5 1890 .i 03:66 100ti 1.5573 360 195.77 00164  : 335 353 45 644 e i196 1 0.5413 1.0059 1.5471 390 220.37 0 01450 2 0eh 3M l7 8354 1899 6 0.2339 0 9b32 1.5371 400 247.31 0 01664 1 8633 374 97 826 0 1201.0 0.5664 09606 1.5272 410 2475 0 01876 1690 385 83 816.3 1202.1 0.5786 09M6 1.5174 420 30683 0 01894 1.5000 396 77 306.3 12031 0.5932 0 916e 1.50 %

430 M3.7 0 01980 1.3499 407.79 796 0 12036 0 6035 0.8947 1.496 440 Mt.59 0 01926 1.2171 41690 785.4 1204.3 0 61 % 0 8730 1.4867 450 422 6 0.0194 10993 4301 774.5 1204 6 0680 0 8513 1.4793 460 46e 9 0 0196 0 9944 441 4 763 2 1204 6 0 640 08296 14700 410 $14 7 0 0196 0 9009 4526 751.5 1204 3 0 65:3 0 8063 1.460e 460 See 1 0 0200 0 517 464 4 739 4 1203 7 0.6645 0 % 66 14513 490 6:14 0 020 0 74 3 44 0 726 6 1200 6 06%6 0 % 53 1.4419 SOD 680 6 0 0204 06149 457 6 ?l39 1201.1 0 685* O 1436 1.43 5 520 812 4 0 0209 0.5594 511.9 686 4 Il9b.: 07 30 0.7006 1.4136 540 962.5 00:15 0 4649 536 6 656 6 1193 2 07374 0.6%6 1.3942 560 1133 1 0 0:28 0 3858 %22 624.2 1866 4 0 %:n 06121 1.374: ,

580 13258 0 0:26 03:17 566 9 588 4 1177.3 0 787 0.5659 I.353 6CO 1 54: 9 00:M 02666 610 0 544 5 1865.5 0 8131 0514 1.3307 620 1%e6 00:4? 0.2201 646 7 503 6 Ii50.3 0 1391 04664 1.30C 640 2059 7 0 0260 0 1796 64 6 452 0 1130.5 0 6679 0 4110 1.2769 660 2365 4 00:4 0.1442 7I4.0 390.2 1104 4 0 8967 0.M85 1.247 680 2706.1 0 0305 0 1115 157.3 309.9 1067.2 0 9351 0.2719 1.2071 100 30937 0OM9 0041 3 33 172.1 995 4 0 9905 01464 1.1389 s 105 4 320e 00%) 0 0503 90: 7 0 90: 7 1.05t's 0 10560 s

a e

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• ta- Rs em les lin 13m saat

. . e. . . . . . . . 302 6 4523 512 0 $114 631.2 HUS 124 809 9 869.5 9291 988 7 1807A

) A........... 1190 4 1195.8 1241.1 1288.3 13357 IM38 1432 8 4482.7 1533.5 1585.2 1637.7 BM57 2A512 2.1153 2173D 22233 2.2702 2.3137 2.3H2 2.3921 2 4253 2 # 25 2. # 52 2.55m (21.14) s . ......... ....

e .............. 18 86 90.25 602.36 194 22 136 86 13s.90 190D3 161.95 413 87 185.79 397.78 Itta 5 A............ 1148 8 litSA l241.2 1288 0 1335 8 13834 14327 14s2A 1533 4 1985.1 1437.7 , 1945.7 13718 3.9370 1.9942 2.04M 2.0927 1.1361 2.1%7 2.214m 2.2309 2.2851 23178 23792 (462.341 4 ..............

63A) 69.01 N 9s 30 95 as 92 92.88 98 84 100.77 l e.............. 38A% 45.00 SIA4 57AS 90 &............. 1146 6, l193.9 1240 6 1287.5 1335.1 1383 4 1432.5 les2.4 l$13 2 15s5 0 1637A IMSA. 1 1.1927 LAMS B3172 1.9689 2 0160 2A596 2.8002 2IDI 2 1744 2 2068 2.241) 2.3038 (193.21) s .. ..... . ..

e ... . . . . . . 30.53 34 68 38 78 4286 46 94 5120 55.07 M 13 63 19 67.25 75.37 34496 & .. . . 1892.8 1239 9 1287 l 13M S 1383 2 1432 3 1452 3 15331 15s4 5 1637.5 INS.5 (21220) s. ..... I8160 l.8743 1.9261 1.97M 2.0170 2 05 % 2.0958 2 1319 2lu2 2.1989 2.2e03

,. . 22 M 25 43 28 46 3 47 34 47 37 46 40 45 43 44 46 42 49 41' 55.37 Jo A. . . 1891 4 1239.2 1286 6 1334 4 IM29 14321 14821 1533 0- 15647 1637.4 1745 4 (227.96) s. .. I.7808 1.839e 1.8918 1.9392 1.9s29 2 0235 2 0618 2004 ' 2 1321 2 1648 2.2263

,. 11.040 12 628 14 169 15 686 17.19s 18102 20.20 28.10 23 29 24 69 27 40 40 A. 1186 8 12k 5 12648 13331 1381.9 1431.3 1488 4 1532 4 15:41 1637.0 IN51 (367.25) J. . . I 6994 l.MOS 1.8140 1.8619 1.9058 1.9467 I.9850 2.0212 2 0m 2.0553 2.1#6

, . . . 7.2 59 8.357 9 403 10 427 11.441 12 449 13 452 14454 1545.1 16 451 18 446 to &. . . Illi4 12336 1283.0 1331.8 1380 9 1430 5 1450 8 1531.9 15mi n 16% 6 17448 I.8162 1.0405 1.9015 1.9400 1.942 2 0lta, 2 0434 2.1049 (292.11) s .. . . . 14492 8.7135 1. % 76

, . . . . . . . . . . . . 6.120 1.020 7.797 8.%2 9.322 90.077 10 830 ll.5m2 12.332 13.8 2 80 & ..... .. .. . . 1230.7 1281.1 1330.5 1379.9 1429 7 1400.1 1531.3 15s).4 16M.2 IMd.5 I6791 8.73 # l.78 %  !.8281 1.8694 1.9079 8.9442 1.97m? 2.0115 2D731 (312 A3) s .. ... ... . . . .

.......... . . 4 937 5.589 6.218 6.835 7.446 8.052 86M 9.259 9.840 ll Ato 600 a........ . 12274 1279.I 1329.l 13 4.9 1.0029 14289 1479.5 13829 1530.8 1.9193 1542.9 1.9538 1635.7 1.9867 IM4.2 2 Dead 14518 1.7085 1.1581 1.8443 (32731) s .. . . . .

, . . . . . . . .. 4.081 44M 5.165 5483 5.195 6.102 7.27 7.710 8.212 9.214 110 &. .. .. . 1224 4 1277.2 1327.7 1377.8 14281 1478 8 1530.2 1582 4 1635.3 IN3.9 im .251 s. . . . . . .. {.. ;IAh9 1.1310 1.7822  ; i.8237 , 2.8625 iA990 1.9335 I.the 2A2st

.. {. . . .] 1 A287 l

,... 3 466 3.954

.. . . . . 4 413 4.861 5.301 5.738 6.172 ' 6.804 7A35 7 av' 140 &... . . 1221.1 1275.2 1326 4- 13 4.8 I427.3 (353A2) s.. 1A087 8.uS3 1.7190 1478.2 1529.7 1581.9 16H.9 IN35 1.M45 1.8063 I.8451 1.8817 1.9163 1.9493 2 Allo O ,. 3.008 3 443 3.849 4.244 4 631 5.015 5.396 5.775 6.152 6.906 160 4. .. 12174 12731 1325.0 1375 7 1426 4 1477.5 1529.I 15814 (363.53) s. 1.5906 I6589 1634.5 IN3.2 I.7033 1.7491 1.7911 1.8308 1.8667 I.9014 I.9344 1.9962

,. 2 649 3.044 3 411 3.%4 4 110 4 452 180 &. 4 792 5.l29 5.4% 6.1%

. . 1234.0 1271 0 13235 1374 7 1425 6 14 4 .8 1528 6 s.. 1581.0 1634.1 IN2.9 (373.06) 1.5745 1.6373 14494 1.7355 1.77 % IJI67 1.8534 1.8482 1.9212 1.9831

e. 2.MI 2.726 3 060 3.380 3 693 4 002 4 309 4 613 EO A. 4.917 5.521 1210.3 12619 1322.1 1373 6 1424 6 1528 0 (341.19) s. l.5594 1A240 16%7 14 % .2 1580 5 1633.7 IN26 8.7232 1. 4 55 1.0046 1.8415 8.8763 1.9094 1.9713

e. . 2 125 2.465 2.772 3 066 3.352 3.6 34 3 913 4 191 4 467 5.017 220 &. 1206.5 12667 1320 7 1372 6 1424 0 1475.5 1527.5 1580.0 1633.3 IN2.3 (309461 a . . 1.5453 16117 16652 8.7120 1 7545 1 7939 1.8306 1.86 % 1.8987 1.9607

e. l.9276 2 247 2 533 2 804 240 4.

3 066 3 327 3.5bi 3 839 4 093 4 $97 I202 5 1264 5 1319 2 1371.5 1423 2 14N b (397.37) s. 1.5319 I6003 1526 9 1579 6 1632 9 IN20 1.6546 1.7017 i N44 I7839 I8209 18558 1.8869 1.9510

e. 2 0t3 2.330 2 562 2 :27 3 067 3 305 3 541 3 776 4.242 2eo &. .

1262 3 13177 1370 4 1422 3 14N.2 1526 3 1579.1 1632.5 1741.7 (404.42; s . 1.5897 14447 14922 1.7352 1.7748 l.8818 1.8467 1.8799 1.9420

,. 1.9047 2.856 2.392 2 621 2 845 3.066 3.286 3.504 3.9M 200 &... 1260 0 1316.2 IM94 142I 5 1473.5 1525.5 15 % 6 1632.1 INI4 (41125) s *. * . . . .. l.5796 I 6354 14 34 1.7265 8.h62 1.8033 IJ383 1.8716 1.9337

,. . . . . 1. % 75 2.005

. . . . 2.227 2 442 2 652 2 859 3.065 3.269 3AN 300 &... . . ... . 1260 0 1316.2 1%83 I420 6 1472N (417.33) s.

8525.2 15781 1631.7 INI .0

. . 1.570s 14268 1.6751 1.7184 1.1582 1.7954 f.8305 1.8638 1.9260 i e. I.4923 1.70k 1 8980 2 064 2.266 2 445 2 622 2 798 3 147 350 A. 1251.5 1310 9 1 %5.5 1418 5 1471.1 15236 1577.0 1630 7 1740.3 (431.72) s. . 1.5461 16070 16%3 1.7002 1.7403 1.7771 18130 1.8463 1.906e 1.2851 I4770 1 6506 I8161 19767 2 134 2 290 2 445 2 75 40D &. 1245i 130t 9 Ik27 1416 4 1469 4 (444 59; s . 1522 4 1575b 1629 6 1734 5 I$281 15894 16396 I 6b42 1724? I %2) I79?? I6311 Isw

i

-WORKSMEET 11- ENCusNR22 (PaSe 1 of 2)

BSTDLATED CRITICAL DORON CONCttrtATION 532*F, 01 FF, No Renon, No Control Rods, REFERENCE CONLITIONS:

l Equilibrius Samarino

1. Fuel Reactivity 200 grpo h 3,gfg

a. Core Burnup  ;

b. Read Curve 3.1 of OP-103, Plant Curve Book. ,

2. Xenon Rasetivity (Use Step 2.1 or 2.2) 2.1 Talue calculated by SA10N 1 (submit printout). 1 ak/k

( I ak/k) =

on

s. Last power level was 100 1 FF for 8 0 4 hrs.

2.2

b. Time Shutdown hrs.

c. If time at last power level was < 40 hra. and SAKON is unavailable, consult with Reactor Specialist.

( I ak/h) = I ak/k

3. Samarius Reactivity Buildup After Shutdown Talue calculated by SAKON 1 (submit printout) I ak/k 3.1

4. Rasetivity Effect From Tesperature

s. Average RC Temperature 82.5 #F

b. Reference temperature is 5320T.

c. Temperature coef ficient at ppaB is obtained from Curve 3.6 of 0F-103, Plant Curve Book, to be z 10-21 ak/k/*F. '

, , d. Reactivity = [T(ave) - 532) [ Temp. Coef f.]2% ak/k/0F)= 2 ak/k

)( z 10-

' e. Reactivity = (

5. Rasetivity of Control Rods at Desired Insertion Croups 1-4 at 100 I WD Group 5 at soo 1 WD Croup 6 at 100 1 WD <

50 1 WD Resulating Group Worth I ak/k Group 7 at I ak/k Group 8 at 8PO 1 UD Group 8 Worth

~

Calculated By Date l

Date 11/16/82 Fate 18 OP-210 Rev. 16

[8 l W *

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c I A H-

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O D

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F)G0F.E 1 ItEACTOR CORE SATE 77 LIIi)T I

I o~- Amendment No. M 41 l ClifiA RIVI' UNIT I --

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JEACTOR COOLANT SYSTEM -

POWER OPERATED ttELEF VALVES

~

3.4.3.2 The power operated relief valve (PORV) and its associated block valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With the PO R Y inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORY to OPERABLE status or close the associated block valve and remove power from the block valve; otherwise, be in at least HOT 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 SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />,

b. With the block valve inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the block valve to OPERABLE status or close the block valve and remove power from the block valve or close the PORY ard remove power from the associated solenoid valve; otherwise, be in at least HOT 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

5HUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />,

c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.4.3.2.1 In addition to the requirements of Specifications 4.0.3, the PORY shall be demonstrated OPERABLE at least once per 18 months by performance of a CHANNEL CALIBRATION.

4.4.3.2.2 The block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel.

4 l

CRYSTAL RIVER - UNIT 3 3/4 4-4a Amendment No. 55, 54 i

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( NUCLEAS OFFICES OPERATIOma CC' NUCLEAR PLANT ~l

PARKING AREA l -

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1 ANSWERS 5.0 (25.0) -

5.1 (b) (1.0)

Reference:

NUS, NETRO, p. 11.4-3.

5.2 (c) (1.0)

Reference:

NUS, NETRO, p 1,4-1 5.3 (d) '. (1.0)

Reference:

GP, HTT and FFF, S3.3 p. 355 5.4 (b) (1.0)

Reference:

STM-504 5.5 (b) (1.0)

Reference:

1. NUS, NETRO

2. Westinghouse Reactor Physics, Sect. 3, Neutron Kinetics and Sect. 5, Core Physics.

5.6 (c) (1.0)

Reference:

NUS, NETRO, 10.3 5.7 (d) (1.0)

Ref: NUS - Plant Performance pp 6.2-5 and 6.4 - 5 5.8 (d) (1.0)

Ref: NUS Plant Performance pp 6.4-5+6 5.9 (d) (1.0)

Ref: NUS Plant Performance, pp 3.3-2 e

,. _ _ - _ , + . . . . . - .

l 2 l 5.10 (d) (1.0) -

Reference:

OP-210, p. 18 5.11 (b) (1.0)

Reference:

T.S. pp B3/4 1-1 5.12 (d) (1.0)

Reference:

T.S. pp 3/4 2-12 5.13 (a) (1.0)

Reference:

OP-103 curves 4.7A, B, 4.8, 3.8A, B, C, D, 3.15A, 3.17 and STS 3/4 1-1.

5.14 2. _ "' M ) -

b. FALSE (0.5)

Reference:

a. CR3 HTFF/Thermo, last page

b. AP-460 and AP-380 5.15 A - Core Outlet Pressure, psig c a . Rc.5 N (2.0)

B - RCS - Pressure High Trip C - Safety Limit *, A ^^lr i- MSR M. . (/ 30)

D - Unacceptable Operation

Reference:

T. S. Safety Limit Curve, pg 2-2 5.16 Answer: Zr - H2O Reaction (1.0)

Dissolved H2 in RCS Radiolytic decomposition of Water any 2 Aluminum - NaOH reaction (.5 ea)

Reference:

CR3 Draft HTFF/Thermo, Section 4, Post-LOCA H2 Sources.

5.17 Answer: (d) (1.0)

Reference:

Power System Operation,i R. H. Miller, pg. 22-24 5.18 Answer: (c) (1.0) l

Reference:

Power System Operation, R. H. Miller, pg. 22-23 5.19 Answer: (b) (1.0)

Reference:

CR3 Draft HTFF/Thermo l . .

1

_. - . . .. . . ._- .=

/

3 i- 5.20 Answer: (b) (1.0) -

Reference:

CR3 Draft HTFF/Thermo 5.21 Answer: (b) (1.0)

Reference:

General Physics Corp. Academic Program for Nuclear Plant Personnel Vol. II Physics pg. 4-76, 77.

5.22 Answer: (c) (1.0)

Reference:

CR3 Draft HTFF/Thermo 5.23 a. T - TS 3/4 2-1 .

(2.0)

b. F - TS 3/4 2-5 + 2-7 (and ogce per month)

c. F - TS 3/4 2-11 ~

d. T - TS 3/4 B 2-1 i

L

4 ANSWERS 6.0 (25.0) -

6.1 '. (1.0)

Answer: (d)

Reference:

RB Isolation and Cooling System Lesson Plan, AND-91 6.2 (1.0)

Answer: (a)

Reference:

AP-304, p. 4 6.3 (1.0)

Answer a .

d e: STM-405

' Refer

].

8WC-98 j f' f f' (b) -

(BSV-16 & 17 are normally open)

(c) -

(Valves open on 4 psig, pumps start on 30 psig)

(d) - (BSV-16 & 17 are normally open)

MTfT * * *PS" 5 %"d Answer: (b)

Reference:

1. STM 23-7

2. OP-502, p. 3

3. OP-408, Rev. 32 6.5 (1.0)

Answer: (a)

Reference:

STM-17-12, 12, 10, 10.

(b) - Must be manually stopped (c) - No auto position (d) - Has auto start 4

6.6. (1.0)

Answer: (b)

Reference:

STM 17-4, 4, 5, 7.

(a) -

MUV-48 is remotely operated (c) -

Closes MUV-49, not 40 & 41 (d) -

makeups demins may be parallel or series

.~.

5 .

,6.7 (1.0) -

Answer: (d) .

Reference:

STM-1-17 to 20 6.8 (1.0)

Answer: (b)

Reference:

PASS Lesson Plan, R0-105 6.9 (2.0)

Answer: (See attached drawing)

1. Normal and bypass inverter supplies (0.5)

2. Inverter feed to vital (0.3)

3. DC to inverter (0.3)

4. Two normal battery chargers (0.3)

5. One back up battery charger (0.3)

6. Bypass transformer and switches (0.3) 6.10 (1.0)

Answer: (b)

Reference:

Site Fire Protection Systems 1 ANAO-39 6.11 (1.0)

Answer: a. TRUE

Reference:

AP-380, pg. 9 (0.5)

b. TRUE i

Reference:

OP-404, pg. 5 (0.5) 1

-_ - . ~ . . ._. _,r,., . . _ , . . , .

,.m, ,- 6m, 1.-

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6 6.12 a (1.0) -

).ef: STM-20-2 (Separate Transmitters for DHV 3+4) OP-404, .

pg. 6, 7 (Alars on DHV-41, no interlock) 3 6.13 b (1.0)

Ref: Steam Line Rupture Matrix Handout, pg. 5 .

6.14 b (1.0)

Ref: STM-6-15, 17 6.15 e (1.0)

Ref: STM-43-17 6.16 a (1.0),

Ref: STM-10-36, 37 6.17 d (1.0)

Ref: STM-9-11-21 Also T. S. pg. 2-6 6.18 b (1.0)

Ref: STM-10-56, 57 6.19 d (1.0)

Ref: STM-17-17, 18 6.20 a. Controlled bleed off temp. 2 170*F (Verified) (0.5)

High seal stage pressure drop 2 2/3 RCS pressure (0.5)

b. Total seal outflow exceeds 2.5 gpm (0.5) and is rapidly increasing (0.5)

Ref: OP-302, Rev. 21, pg 5

, i l

6.21(c) -

Reference:

TS 3/4 3-51 .

and 3-53 (1.0) 6.22 a. T pg. 25 (0,5)

b. T pg. 26 (0.5)

c. F - EM-207, Rev. 16, p. 16 '

(0.5)

d. F - TS 3/4 3-31 (0.5)

Reference:

CR 3 Lesson Plan - Meterological Measurement System 4

4 i

4 i

I e e t

t

- - - - - - - - - , .--3, ,4,. -w-- -. - . -, .- . . , . . - . - , - _ - , - - - - . _ - -- .-,,,-v.s , , - - -c.-% , . ~ , + , n,,.- r- - . ,e,.--- ,e-i- -

j.

.)

'_ 8 -

7.0 ANSWERS (25.0) -

i 7.01la - 3 Ref. AP-241 (2.5) b-4 Ref. AP-242 1(0.5 each)

, c-5 Ref. AP-243 d-2 Ref. AP-244 e-1 Ref. AP-245 7.02 Notify Aux. '.iuilding Operator to ensure closed: (0.5)

WDV-891, WDV-892 Ref. AP-272 7.03 b (Establish OTSG levels w/MFP is a subseq. action) (1.0)

Ref. AP-330 , b l j 6[f[ .

7.04 (d) , (1.0)

NS Seawater Pumps - RWP-2A/2B (Step 3)

DH Seawater Pumps - RWP-3A/3B (Step 6)

Ref: AP-380 ,

STM-20-9 (RWP-3A/3B)

STM-4-10 (ECCS)

STM-23-2/3 (NSCW) ,

7.05 Notify AB operator to open affected BKG at MCC: (1.0)

(* Reactor 3A2) Not req. for full credit

(* Reactor 3B2)

Ref: AP-380, pg 4 7.06 a. 20 1.j ' 100 (3.0)

b. 50 jc' low level limit (30") (0.2 each)

c. 50 k. 50%

d. 1000 1. 95%

e. 20 m. 95% s

f. 500 n. " O i /

g. 100 c. 2300 t

h. 10 Ref: AP-380, pg. ,

)-

t I 1 f

.-s

+ _

). . _ . - . . _ _ _

9 ,

~

7.07 (a) (1.0) -

Ref: OP-404, Rev. 45, pgs. 4 and 5 .-

7.08(c) (1.0)

Ref: OP-404, Rev. 45, pgs 2 and 3 7.09 (a) (1.0)

Ref: OP-408, Rev. 32, pg 3 (Incorrect statements) b - 12 psig c - 15 sec.

d - 15 sec.

7.10 (c) , (1.0)

Ref: OP-408, Rev. 32, Section 10.2 7.11 (b) (1.0)

Ref: OP-501, Rev. 8, pgs. 2, 3 and 6 7.12 (d) (1.0)

Ref: FP-203 Rev. 12, pg. 10 7.13 1. ZZ 1 ape has been read to verify that the grapple tube is (0.5) fully up.

2. ZZ Tape full up reading has been reported to the CCR0 (0.5)

? r ^ Ref: FP-203, Rev 12 16 7.14 (b) k(1.0)

. Ref: FP-203, Rev. 12 7.15 (a) (1.0)

L j Ref: OP-504, Rev. 08, pg. 7 l 7.16 (d) (1.0) l Ref: OP-605 pg. 21 STM 27-37 i i i 7.17 (b) (1.0) l Ref: OP-402, Rev. 43, pg. 4 l

5 "e ' .: 5 ,f o " A [ b G- bu' 9ey 6, *4"* '

l yd'yr g:V % % ,f "L* Y' .

) l 10

,7.18(c) (1.0)/

{

, l

~

Ref: RP-101, Rev. 19 pg. 9 .

7.19 (b) -

(1.0)

Ref: RP-101, Rev. 19, pg. 13 7.20 (d) . >

(1.0)

Ref: RP-101, Rev. 19, pgs. 21 and 22 7

7.21 1. Announce over the PA tystem

' that the Contqol Center is being (1.5) evacuated!

2. Transfer the 6900V and 4160, unit buses from the unit auxiliary transformer to unit startup transfo.rmer. ,

/

3. Trip the reactor from the MCB or remotely by opening 480V -

CRD breakers ,"A" emd "B". ..

4. Depress " Reactor Trip" pushbotton AND perform Immediate Actions of AP-580.

5. Close FWV-161 and 162, EFW bypass valves.

6. Trip the main turbine and FWP's and assure EFWP's start and are controlling OTSG 1evel.

Ref: AP-990 7.22 False - '

(0.5)

? Ref: AP-580 and EP-140 -

/

p  ? l

?'

D

+4-f f

11 .

Answers 8.0 (25.0) -

8.1 Answer

(c)' '(1.0)

Reference:

AI-100, pg. 6. Rev. 7

8.2 Answer

(b) .

(1.0)

Reference:

EM-202, page 29

8.3 Answer

(a) (1.0)

Reference:

CR STS, page 3/4 4-18

b. not in TS Table 3.4-1 -

c. above transient limit

d. below SS limit

8.4 Answer

(d) (1.0)

Reference:

AI-500, pages 2 & 3

8.5 Answer

(b) (1.0)

Reference:

FP-203, page 2

8.6 Answer

(b) (1.0)

Reference:

FP-203, page 7, Rev. 12

8.7 Answer

(c) (1.0) i _

Reference:

CR STS pg. 3/4 1-5

8.8 Answer

(a) (1.0)

Reference:

CR STS pg. 3/4 1-24, 25, 21 and 20

b. w/in to 5% (besides 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> action statement)

c. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a

d. t 6.5% in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

8.9 Answer

(b) (1.0)

Reference:

CR STS pg. B 3/4 2-2, 3, I and 1.

(, 8.10 Answer: (b) (1.0)

Reference:

OSIM pg. IV-I

/

12

,8.11 Answer: (d) (1.0) -

Reference:

OSIM, page III-2, Rev. 36 8.12 a. T - Ref: OSIM, III-9 (0.5)

b. T - Ref: OSIM, III-9' (0.5)

c. F - (shall not be amended) Ref: OSIM III-10 (0.5)

d. F - (shall not be issued for procedure changes) '

(0.5)

Ref: OSIM III-10 8.13 Answer: (b) (1.0)

Reference:

TS page 1-3 and 1-4 8.14 Answer: (b) _

(1.0)

Reference:

TS 3/4 4-4a ,

8.15 Answer: (d) (1.0)

Reference:

TS page 3/4 7-7 and page B 3/4 7-2 8.16 Answer: (d) (1.0)

Reference:

EM-202 pg. 1 8.17 Answer: (c) (1.0)

Reference:

TS page 3/4 7-41 8.18 Answer: (b) (25% of 92 days) (1.0)

Reference:

TS 3/4 0-2 8.19 Answer: (d) (1.0)

Reference:

EM-205, pg. 10 8.20 Answer: (d) (1.0)

Reference:

TS 3/4 3-26 t 8.21 Answer: 1. Issue a clearance per CP-115 (1.0)

2. Make a temporary change to an existing procedure.

13 8.22 Answer: The PRC shall approve any Clearance prior to issuance (2.0) -

which meets any condition specified below:

The Clearance is to be issued'for an unusual, non-routine,

~

a.

or abnormal evolution (i.e., repair of RCV-11 in other than Mode 5 or 6, and other emergency repairs).

b. The Clearance to be issued cannot meet the double valve-protection guidelines of 500 psig and/or 200*F and s 1/2' inch in diameter opening.

c. The Clearance to be issued cannot meet the ES train

, separation criteria. ,

d. The Clearance to be issued cannot meet the limiting conditions for voluntarily entering a degraded mode of operation.

In addition to those items listed above," any questionable Clearance shall be forwarded to the pRC for approva'l prior to issuance.

Reference:

Cp-115 8.23 Answer: No, not capable of performing its intended function. (1.0)

Reference:

TS page 1-1 I

L 9 ee

a c' U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR REQUALIFICATION, EXAMINATION Facility: Crystal River Unit 3 Reactor Type: FWR B&W Oate Administered: May 14, 1985 Examiner: S. Lawyer Candidate:

INSTRUCTIONS TO CANDIDATE:

Use separate paper for answers. Write answers on one side only. Staple question sheet,on top of the answers sheets. Points for each question are indicated in

+

parenthesis after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up four (4) hours after the examination gtarts.

% of Category  % of Candidate's Category Value Total Score Value Category 25 25 1. Principles of Nuclear Power Plant Operation, Thermodynamics, Heat Transfer and Fluid Flow 25 25 2. Plant Design Including Safety and Emergency Systems 25 25 3. Instruments and Controls 25 25 4. Procedures - Normal, Abnormal, Emergency, and Radiological Control 100 TOTALS Final Grade  %

All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

. e 1.0 PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT (25.0)

TRANSFER AND FLUID FLOW

'1.1 Which one of the following CORRECTLY states the four contributors or factors that establish equilibrium xenon? (1.0)

a. Decay of xenon to Sm Direct production from fission Decay of iodine Decay of xenon to Cs

b. Direct production from fission Decay of iodine -

Decay of xenon to Cs ~

6-Burnout by neutron absorption

c. Decay of iodine Decay of xenon to Cs Burnout by neutron absorption Decay of xenon to Sm

d. Decay of xenon to Cs Burnout by neutron absorption Decay of xencn to Sm Direct production from fission 1.2 The ratio of both Pu-239 and Pu-240 atoms to U-235 atoms changes over core life. Which one of the pairs of parameters below are most affected by this change? (1.0)

a. Moderator temperature coefficient and doppler coefficient

, b. Doppler coefficient and beta

c. Beta and thermal neutron diffusion length

d. Thermal neutron diffusion length and moderator temperature coefficient A

4

2 1.3 A moderator is necessary to slow neutrons down to thermal energies.

Which of the following is the CORRECT reason for operating with thermal instead of fast neutrons? (1.0)

a. Increased neutron effi'ciency since thermal neutrons are less likely to leak out of the core than fast neutrons.

b. Reactors operating primarily on fast neutrons are inherently unstable and have a higher risk of going prompt critical.

c. The fission cross section of the fuel is much higher for thermal energy neutrons than fast neutrons.

d. Doppler and moderator temperature coefficients become positive as neutron energy increases.

1.4 i5ich one of the following factors will help, rather than hinder, natural circulation? (1.0) j

a. Lowering OTSG level

b. Lowering RCS pressure 4

c. Increasing RCS temperature

d. Lowering turbine bypass valve setpoint 1.5 Following a trip from full power with the reactor shutdown and 4 RCPs operating, the 125 psi bias is suddenly removed from the turbine bypass valves. Which one of the following statements best describes plant response? (1.0)

a. OTSG pressure drops and' levels rise. The increased OTSG

, levels cause an overcooling of the RCS.

b. The OTSG saturation temperature drops causing a decrease in RCS cT and a rapid drop in pressurizer level.

c. Since OTSG pressures drop 125 psi, BTU limit alarms will be received on both generators and feedwater will cut back,

d. The resulting cooldown of the RCS will decrease the shutdown margin to less than Tech Spec limits.

i 3

1.6 Sufficient reactivity is added to a shutdown reactor to cause the count rate to double. If the same amount of reactivity is added '

again which of the following is CORRECT 7 .

(1.0)

a. The count rate will double again,

b. The count rate will more than double but the reactor will still be suberitical.

c. The reactor will be critical or supercritical.

d. The source strength must be known to determine the new count rate.

1.7 During a xenon-free reactor startup, critical data was inadvertently taken two decades below the required Intermediate Range (IR) level (10 " amps). The critical data was then taken at the proper IR level (10 ' amps). Assuming RCS temperature and boron concentrations did not change, which one of the following statements is CORRECT? (1.0)

a. The critical rod position taken at the proper IR level is LESS THAN the critical rod position taken two decades below the proper IR level.

b. The critical rod position taken at the proper IR level is THE SAME AS the critical rod position taken two decades below the proper IR level.

c. The critical rod position taken at the proper IR level is GREATER THAN the critical rod position taken two decades, below the proper IR level.

. d. There is not enough information given to determine the relationship between the critical rod position taken at the proper IR level and the critical rod position taken two decades below the proper IR level.

l

4 1.8 The reactor trips from full power, equilibrium xenon conditions.

Twenty-four hours later the reactor is brought critical at 10 ' amps on the intermediate range. If power level is maintained at 10

• amps for several hours, which of the following statements' is CORRECT concerning control rod motion? (1.0)

a. Rods will have to be withdrawn due to xenon build-in.

b. Rods will have to be rapidly inserted since the critical reactor will cause a high rate of xenon burnout- ,

c. Rods will have to be inserted since xenon will closely follow its normal decay rate.

d. Rods will approximately remain as is as the xenon establishes its equilibrium value for this power level.

1.9 Which one of the following is CORRECT concerning starting of positive displacement-(PD) and centrifugal pumps? (1.0)

a. Neither type of pump should be started with its discharge valve shut.

b. Both types of pumps should be started with their discharge valves shut.

c. A pD pump should be started with its discharge valve shut and a centrifugal pump started with its discharge valve open.

d. A PD pump should be started with its discharge valve open and a centrifugal pump started with its discharge s valve shut.

1.10 Runout of a centrifugal pump is best characterized by which one of the following? (1.0)

a. high motor current, high flow rate and high discharge pressure.

b. low motor current, high flow rate and low discharge pressure, i c, low motor current, low flow rate and high discharge pressure.  !

d. high motor current, high flow rate and low discharge pressure.  !

• 5 1.11 Which one of the following is the CORRECT order of the heat tran,sfer processes as heat flux increases? (1.0)

a. bulk boiling, sub-cooled nucleate boiling, film boiling, DNB

b. sub-cooled nucleate boiling, bulk boiling, film boiling, DNB

c. bulk boiling, sub-cooled nucleate boiling, DNB, film boiling ,

d. sub-cooled nucleate boiling, bulk boiling, DNB, film boiling 1.12 With the main steam temperature and pressure at 600' F and 900' psia respectively, a main steam relief valve seat begins to leak to atmospheric pressure. The temperature of the steam three feet out of the relief valve is approximately: .

(1.0)

a. 600 F

b. 535* F

c. 444' F

d. 212 F 1.13 Concerning the behavior of Samarium-149, which of the following statements is CORRECT? (1.0)

a. Once equilibrium Sm is established, Sm reactivity does not change regardless of power level changes.

b. Equilibrium Sm reactivity at 50*4 power is equal to equilibrium Sm reactivity at 100'4 power.

c. Sm is only removed by radioactive decay.

d. Sm is produced by the decay of iodine.

1.14 Given the power history shown on Figure 2 attached, select the most accurate curve displaying the expected xenon history. (1.0)

a. I by*1-

b. 2 we e.,eQLz c- 3 t_n +

aas

. , 6 1.15 The reactor is being shutdown. A stable neutron population decay with a -78 second period (-1/3 DPM SUR) has been established. The intermediate range is reading 5E-8 amps. How long will it take before the source range high voltage cutoff bistable will reset? (1.0)

a. 4.5 minutes

b. 5.1 minutes

c. 6.0 minutes

d. 8.1 minutes 1.16 In performing an estimated critical boron concentration pursuant to OP-210, the attached worksheet is being utilized. Assuming the information shown on that sheet, which one of the following pairs of items will be positive (+)? .

(1.0)

a. A&D

b. B&D

c. B&C

d. A&C i

1.17 Which one of the following statements about condenser vacuum is CORRECT? (1.0)

a. The pressure difference between the actual vacuum and absolute zero is termed condensate depression.

b. The vacuum prevents the steam entering the condenser from giving up its latent heat of vaporization, thereby increasing cycle efficiency.

. c. The vacuum serves to allow more energy to be withdrawn from the steam in the turbine,

d. The vacuum prevents the condensed steam from becoming subcooled, thereby increasing cycle efficiency.

1.18 Which one of the following is NOT part of the accident postulated for the basis of the shutdown margin requirement? (1.0)

a. Main steamline break

b. Beginning-of-Life (BOL) condition

c. Tavg at no load operating temperature

d. Most reactive rod struck out

~ _ . . .~ L_ . - _ . . _ _ , _ _ .

y 1.19 Which one of the following is NOT one of the DNB related parameters that must be maintained within Tech Spec limits? , (1.0)

a. Hot leg temperature

b. Reactor Coolant pressure

c. Reactor Coolant flow rate

d. Axial power imbalance 1.20.Which of the following will NOT change over core life? (1.0)

a. The minimum acceptable shutdown margin

b. The acceptable flux imbalance band

c. The control rod reactivity worth

, d. The power defect reactivity worth.

1.21 Which of the following statements about Net Positive Suction Head (NPSH) is INCORRECT? (1.0)

a. NPSH is the amount by which the suction pressure is greater than the saturation pressure for the water being pumped.

b. NPSH is essential for operation of centrifugal pumps but not for positive displacement pumps.

c. NPSH can be calculated by subtracting the saturation pressure from the actual suction pressure.

d. When a pump is started, the NPSH will decrease by the amount of the pressure drop in the suction piping.

. 1.22 TRUE or FALSE

. r

11: wing : LOCA, ,, un ::gg3te: e.g geje,e7 <g31 <!em,

f'icient : : :: !'ng i :n;;r:d without th; n::d f:r CTEC

ling, r:;;rdle;; cf th: ;i:: Of the LOCA. (0.5)

b. Since the RCP Trip criteria is based on the SBLOCA analyses, you are not required to trip the RCPs following ES actuation due to a Main Steam Line Break Accident. (0.5) 1.23 Refer to Figure 1, " Reactor Core Safety Limit." Identify by name or title the parts of the Figure marked A, B, C, and D. (2.0) l 1.24 Following an accident that results in excessive core damage, I what are two significant sources of Hydrogen generation. (1.0)

END OF SECTION 1 l

l l

8 2.0 PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS (25.0) 2.1 Which of the following. statements concerning the Reactor -(1.0) t Building Isolation and Cooling System is CORRECT?

a. Diverse Containment Isolation occurs when HPI is automatically or manually initiated.

b. Diverse Containment Isolation will isolate NSCCCW to the Reactor Coolant Pumps,

c. Diverse Containment Isolation will close the CI flow to the RB fans and open the SW valves.

4

d. When HPI automatically initiates, Diverse Containment Isolation occurs and the RB fans are started or shifted to slow speed.

2.2 The secondary cycle system is sampled for pH, Hydrazine, (1.0) conductivity, oxygen, sodium and silica. Which one of the following will generate a computer alarm and lead you to initiate an Abnormal procedure for Secondary Chemistry Control?

l

a. pH

b. Conductivity

c. Oxygen

d. Sodium 1

2.3 Many important pumps have annunciators which indicate when the pump (1.0)

. is out-of-service, for example: ES Annunciator D-3-3 is labeled "DH

. Pump 'B' OUT OF SERV". Which one of the following is an indicated condition for this type of annunciator?

a. No breaker DC control power,

b. Breaker control switch in normal after start, breaker open, breaker racked in. *

c. Overload relay actuated.

d. Excessive motor amps.

9 2.4 Select the INCORRECT statement regarding the Condensate Insection (1.0)

System.

'a. Condensate injection is used for main turbine hood sprays, .

pump seals in the feedwater system, and valve.tbeam-sealing to prevent in-leakage of air to the condenser. 5T0ern

b. When condensate pressure is above 220 psig the condensate pumps are supplying seal and spray water. ,

c. If the discharge pressure decreases to -200 psig, the G.W.P.

that has been selected will start automatically.

d. The selector switch on the main control board, lines up the alternate G.W.P. for automatic start.

2.5 Which one of the following statements concerning the Reactor Coolant (1.0)

Pump design is CORRECT?

a. An RCP motor may be started three times successively from ambient temperature, or four times from rated motor temperature.

b. An RCP motor may be started as many as three successive times regardless of temperature.

c. The pump is designed for continued operation on either loss of cooling water or loss of injection fluid, but not both,

d. The RCP must be secured immediately upon loss of seal injection OR loss of NSCCCW flow.

. 2.6 Which one of the following statements is accurate concerning (1.0) the OTSG?

, a. Primary and secondary side blowdown (during plant heatup) is accomplished by means of drain connections near the lower tubesheet.

b. The startup range instruments will provide indication of flooding of the aspirating ports.

c. The auxiliary feedwater header penetrates near the top of the OTSG shell and sprays the feedwater on the upper cylindrical baffle,

d. Orifice plates, located in the. lower downcomer section may be adjusted to balance out the internal circulation system.

10 2.7 During Long-term Post-Accident cooling, which one of the following (1.0) flow paths is most desirable?

a. Condition "A"; open drop line to RB Sump.

b. Condition "B"; Open auxiliary spray line to pressurizer.

c. Condition "C"; Combination of Conditions "A" and "B".

d. Condition "D"; Backflush with LPI Pump via open internal.

vent valves.

2.8 Which statement is CORRECT concerning the Core Flood (CF) System? (1.0)

a. Isolation valves CFV-5 and 6 receive an open signal following ES actuation even though they are required to be open with their breakers in the " Locked Reset" position.

~

b. Du-ing plant operation, the CF tank levels may be increased by adding from the makeup and purification (MVP) system and decreased by draining to the Auxiliary Building Sump.

l

c. When the breakers for CFV-5 and 6 are in " Locked Reset" position, they lose position indication in the control room,

d. During plant operation, high CF Tank pressure may be relieved by venting to the Reactor Building.

2.9 Which of the following statements concerning the Control Rod Drive (1.0)

System is INCORRECT 7

a. When the rotor assembly rotates, the leadscrew is kept from rotating by keying it to the torque tube through the torque

. taker.

b. Four ball check valves are installed at the base of the thermal barrier to permit in-flow to the CRD mechanism during a reactor trip,

c. The ApSRs are prevented from tripping by physical restraints on the segment arms; this prevents the arms from pivoting outward.

d. The stator coils are sequentially energized in a repetitive 2-3-2-3 manner. When rod motion ceases, three coils remain energized.

- - . , . , , - - - - , , - - w, e

11 2.10 Which one of the following correctly describes the trip system of (1.0) the main turbine?

a. When the auto-stop (turbine control) oil pressure dect, eases,

. the interface trip valve will open allowing the EHC Control oil to dump to drain,

b. When the EHC 011 pressure decreases, the interface trip valve will open, allowing the auto-stop (turbine control) oil to dump to drain. ,

c. The interface trip valve is solenoid actuated and when open, will dump both auto-stop (turbine control) oil and EHC control oil to drain.

d. A full turbine trip requires the servo valves for all four sets of turbine valves (throttle, governor, reheat and interceptor) to open.

2.11 With regard to the Reactor Building Spray System, which of the (1.0) following statements is CORRECT?

a. Upon receipt of an ES actuation signal of 4 psic in the RB, the NaOH tank outlet valves (BSV-11 and 12) will automatically stroke to the full open position.

b. A high RB pressure signal (30 psig increasing) starts the 2 RB spray pumps and automatically strokes open the suction valves (BSV-16 and 17).

c. The spray pumps start on the 4 psig signal while the spray header supply valves (BSV-3 and 4) stroke open on the 30 psig RB signal.

. d. The 4 psig signal opens all three sets of valves (BSV-3 and 4, BSV-11 and 12, and BSV-16 and 17).

2.12 Select the CORRECT statement concerning the Nuclear Services (1.0)

Booster Pumps and CRD Cooling System,

a. One pump is normally operated with the other serving as backup.

A drop in line pressure (25 psi) will start the idle pump.

b. On an Es signal, the supply and return valves will close to the CRDM coolers and the booster _ pumps will have to be manually secured.

c. SWP-2A is powered from ES MCC 3A2 and SWP-2B is powered from ES MCC 3B2.

d. Low level in the SW surge tanks will trip the NS booster pumps.

12 0.13 With r:;;rd t; th: "l:nt V:ntil:ti:n Sy t::, wht:h :n: Of th: (1.0)- .

' ell: wing V:ntil:ti:n y t::: i: r:;uir:d fr : :r;r cy i

r

t'

(in::'d::tth:t:::::: ES :tu!!?0-)?

g(jfhD  :. *:::t:rC:vityC::linif;n:

5. " ::te- Buildi g D

urge Supply Syste-

<_ Spent rue' Cc-c!'9; D u p: a4. u3ng74 3; gytt  ;

M- Descte- But' din; Oper: ting c10er Fant 2.14 Select the CORRECT statement concerning the Makeup Pump Lube (1.0)

Oil System.

a. If the main gear oil pump control switch is in Auto, the pump will start and run for three minutes after the makeup pump starts,

b. The backup gear oil pump will start (if in Auto) when oil pressure reaches 7 psig and will automatically stop when oil pressure reaches 20 psig.

c. If the main lube oil pump control switch is in Auto, the pump will start and run for three minutes after the makeup pump starts.

d. The backup lube oil pump has no auto start provisions and can be used as a back up for the gear oil system.

2.15 Select the CORRECT statement about the Makeup and Purification (1.0)

System.

a. The block orifice has two bypasses, (MUV-51 and MUV-48) both of which are remotely operated from the control room.

b. The letdown line connections to the Decay Heat Removal System are prior to the prefilters and after the makeup filters.

c. A temperature element (TE-5) on the letdown line alarms at 130 'F and closes the letdown cooler outlet valves (MUV-40 and MUV-41) at 135 'F to protect the letdown coolers,

d. The deborating demineralizer may be operated in parallel or series with the makeup demineralizers.

I

13 4

2.16 The air start reservoirs for each emergency diesel will allow how many successive start attempts without recharging?

a. 3

b. 6

c. 9 .

d. 12 ,

2.17 Which one of the following statements is CORRECT regarding the (1.0) design of the internals vent valves?

a. The vent valves are designed +o open in the event of a hot leg break when the pressure differential reaches at least 43 psi.

b. The vent valves are designed to open in the event of a cold leg break when the pressure differential reaches at least 43 psi.

c. In the event of a hot leg break, the valves should begin to open with a Ap of about 0.3 psid and be fully open at 1.5 psid.

d. In the event of a cold leg break, the valves should begin to open with a AP of about 0.3 psid and be fully open at 1.5 psid.

2.18 Which one of the following is NOT monitored for in the (1.0)

RANGE subsystem of the Post Accident Sampling System?

.a. High range noble gas

b. Hydrogen

c. Particulate

d. Iodine 2.19 On Figure 2.19, show the connections and components between the 480V MCC Safeguards Bus and a typical 120V A.C. Vital Bus. Include the following: Battery chargers, inverters, automatic and manual switches and transformers. It is not necessary to show breakers or to label components (the labels shown - 3A and 3A-1 are for illustration only). (2.0)

14 i 2.20 Select the CORRECT statement concerning the 250/125 VDC System. (1.0)

a. All battery chargers have a 125V DC output even though some DC buses are rated for a 250V DC output. . j

b. Oniy one battery charger is required to maintain a full charge on its respective bus. '

c. The equalizing charge (137VDC) is below the high alarm setpoint (140 VDC), i.e.s when on equalizing charge, a ,

high voltage alarm should not be indicated.

d. Low battery electrolyte level is indicated by an annunciator alarm in the control room.

2.21 Which one of the following FW booster pump parameters is in both the FW booster pump trip logic and the permit light logic? (1.0)

a. Lube oil pressure

b. Ground overcurrent

c. Phase evercurrent

d. Bus undersoltage 2.22 Select the CORRECT statement concerning the site fire protection systems. (1.0)

a. All areas protected by a fixed water spray system use heat detectors to actuate the alarms.

b. To prevent accidental actuation, it requires two detectors actuating to cause operation of the fixed water spray system on the charcoal filter banks.

c. A wet pipe sprinkler system is used to protect the Emergency Diesel Generators.

d. Lube oil systems on the reactor coolant pumps, feedwater pumps, and main turbine are protected by a fixed water sray system.

I I

^

15 2.23 List TWO conditions that will prevent the turbine bypass valves from dumping main steam to the condenser. (1.0) s i

2.24 TRUE or FALSE

a. Maximum flow for one HPI pump is approximately 540 gpm 9 600 psig. (.5)

b. LPI pump high flow alarm is about 3400 GPM and runout flow about 4100 GPM. (.5)

END OF SECTION 2

'l

-k i

m - -.--. . , . - , . . - + , , - . - . , , , - , - - - - - . . - , _

16 3.0 INSTRUMENTS AND CONTROLS (25.0) 3.01 Which one of the following load limiting conditions and

~

(1.0) corresponding load limit is CORRECT for an Asymmetric Rod?

a. 30%/ min to maximum limit of 75%.

b. 30%/ min to maximum limit of 60%.

I

c. 20%/ min to maximum limit of 75%. -

d. 20%/ min to maximum limit of 60%.

3.02 If the Diamond or Reactor Demand Stations are in HAND, the (1.0) feedwater system will accept responsibility for control of Tave only if certain conditions are met. Of the following conditions that will prevent feedwater from controlling Tave, which one is stated CORRECTLY?

a. Either steam generator high level l'imited,

b. Either steam generator low level limited.

c. Either steam generator BTU limited.

d. Either loop A or B hand / auto station in manual.

3.03 Which one of the following statements concerning the Control Rod Drive position Indication System is CORRECT 7 (1.0)

a. The 0% switch is located 1.5 inches below the in-limit switch.

b. The 100% switch is located 1.5 inches above the out-limit switch.

c. The first rod in any group to reach the out-limit switch will

, stop further travel of all rods in that group.

d. A key switch in the control room can bypass the group 7 out-limit of 91.4% withdrawn.

3.04 Which of the following Decay Heat System Interlocks is CORRECT? (1.0)

a. Separate RC pressure transmitters will shut DHV-3 and DHV-4 at approximately 284 psig.

b. Separate RC pressure transmitters will shut DHV-3, DHV-4'and D>V-41 at approximately 284 psig.

c. A single RC pressure transmitter will shut DHV-3 and DHV-4 at approximately 284 psig.

d. A single RC pressure transmitter will shut DHV-3, DHV-4, and DHV-41 at approximately 284 psig.

17 3.05 Select the CORRECT statement concerning the interlocks on the low load feedwater valves. (1.0)

a. Low load feedwater control valves begin to ramp open when the respective low load block valves reach their 80% open position,

b. Low load feedwater block valves open when the main feedwater block' valves shut.

c. Low load feedwater block valves shut when the low load control valves reach the 80% closed position.

d. Low load feedwater control valves begin to ramp open when the respective startup control valves open to their approximate 90%

open position.

3.06 Which of the following statements is INCORRECT regarding bypassing the Steam Line Rupture Matrix? (1.0)

a. During a normal cooldown, when OTSG pressure drops below 725 psig, the matrix can be bypassed by depressing two bypass pushbuttons on the main control board,

b. During a normal cooldown, the four maintenance bypass key switches must be utilized before the operator can depress the two bypass pushbuttons.

c. Following an actuation, if either the < 725 or < 600 pressure switch has actuated, a bypass permit will be present.

d. Following an actuation, in addition to a bypass permit, the operator must depress the two main control board push buttons in order. to bypass the matrix.

3.07 Which one of the following statements is CORRECT concerning the (1.0) reset pushbuttons for the Steam Line Rupture Matrix System.?

a. The reset pushbutton will reset the actuation, not the bypass.

2. If the reset pushbuttons are pressed when the Matrix is bypassed below 600 psig, the Matrix will actuate.

3. During heatup, the reset pushbuttons must be depressed in order to reset the Matrix once OTSG pressure increases to

> 725 psig. -

4. If the Maintenance Bypass Keys are in "Maint." position, the Reset Pushbuttons have no affect.

18 3.08 Which of the following statements is CORRECT concerning the Intermediate Range Compensated Ionization Chambers? (1.0)

a. The detectors are surrounded by four inches of lead for shielding fast neutron radiation.

b. The boron lined chamber is sensitive to neutron and gamma radiation while the unlined chamber is sensitive only to gamma rays.

c. The compensated ion chamber is designed to remove the gamma signal only at high reactor power levels,

d. Undercompensation will cause loss of some neutron current as well as blocking gamma current.

3.09 Which of the following statements is CORRECT concerning the operation of a typical Atmospheric Radiation Monitor (for example, RM-Al or A2)? (1.0)

a. The air sampled will pass through a fixed particulate filter. The particulate buildup on the filter is then measured by a GM detector which outputs the measurement in CPM.

b. After passage through the particulate filter the air is drawn into a gas sampler which detects gaseous activity with a scintillation detector.

c. A gamma scintillation detector is used to measure the iodine activity on a fixed iodine filter (activated charcoal).

d. The flow path of the sampled air through RM-A2 is the

. particulate filter, the gas sampler, followed by the iodine filter.

3.10 Select the CORRECT statement concerning the Area Radiation Monitoring Subsyster.. (1.0)

a. All of the channels, RM-G1 through RM-G19, use G-M detectors, i

b. All of the channels, RM-G1 through RM-G19 use a Sr-90 check source. l

c. To check the WARNING and HIGH setpoints you must first turn the Alarm Reset / Operate / Check Source Switch to the Alarm Reset position.

d. To set the WARNING or HIGH alarms you must first turn the Warning / Operate /High switch to either the WARNING or HIGH position then adjust the appropriate internally mounted ,

Alarm setting control shaft.

l

. . 19 3.11 Adjustments are made to the Power Range Nuclear Instruments as (1.0) determined by Heat Balances. Power gain adjustments are made  ;

to which one of the following modules?

a. Linear amplifer .

b. Bistable

c. Summing amplifier 4

d. Difference amplifier 3.12 Which of the following is CORRECT concerning the Rod Withdrawal (1.0) interlocks from the Source and Internediate Channels?

a. A SUR signal from the sou*cc range halts rod withdrawl when the SUR exceeds 2 DPM. This is reset at 1 DPM.

b. A SUR signal from the intermediate. range halts rod withdrawl when the SUR exceeds 2 DPM. This is res'et at 1 DPM.

c. At > 10 ' amps, NI-3 or NI-4 will bypass the source range rod withdrawl prohibit.

l d. At > 10 ' amps, NI-3 and NI-4 will bypass the source range rod withdrawl prohibit.

3.13 When synchronzing the generator to the grid, OP-203, " Plant Startup" directs the operator to regulate turbine speed to slowly rotate the synchroscope in the fast (clockwise) direction.

Wnich choice below CORRECTLY gives the two parameters that the synchroscope is indicating? (1.0)

a. Current and voltage differences

. b. Current and frequency differences

c. Voltage and phase differences

d. Frequency and phase differences a

4 i

f

20 3.14 Which one of the following statements is CORRECT concerning the paralleling of electrical systems? (1.0)

a. Although it is desireable to have speed and phase position matched, it is much more important to have voltages matched.

b. If voltages are not matched at the time the synchronizing switch is closed, there will be VAR flow from the lower voltage source to the higher one.

c. If the incoming machine is at synchronous speed but out of phase with the running when the breaker is closed, heavy currents will flow to either accelerate or retard the incoming machine.

d. If the incoming machine is in phase but slightly faster than synchronous speed when paralleled, the system will tend to speed up the incoming machine to. synchronous speed.

3.15 Select the CORRECT statement with regard to speed control (1.0)

(Governor) of the Emergency Diesel Generators,

a. As a general rule, D-G units running alone should have the SPEED DR00P control set on 0 (zero).

b. The synchronizer motor, mounted on top of the governor, allows the operator to match the voltage of the D-G with running voltage before synchrcnizing to the system,

c. The LOAD LIMIT control may be used for shutting down the diesel by turning the LOAD LIMIT control to zero.

d. The SYNC INDICATOR, located directly below the SYNCHRONIZER control indicates if the D-G is in phase with the system.

3.16 When the RPS is in Shutdown Bypass, which one of the following is (1.0)

CORRECT?

1

a. A high pressure trip of 1720 psig is administrative 1y imposed I and an overpower trip of 5% automatically imposed. j

b. The high' pressure trip at 2355'psig is bypassed. l l

c. The four trips bypassed are high temperature, low pressure, variable low pressure and flux / delta flux / flow.

d. The RCP Power Monitor trip is' bypassed.

21 3.17 Which o.ie of ti;t following statements is CORRECT concerning the (1.0)

Overspeed Protection Control (OPC) .. the main Turbine?

Assume the OPC is in the "In Service" position,

a. At 103%, only the governor and interceptor valves will ekose.

b. At 103%, all valves - Throttle, governor, reheat and interceptor, will close.

c. At 111%, the OPC will close only the governor and interceptor valves will close.

d. At 111%, the OPC will close all valves - throttie, governor, reheat and interceptor, will close. ,

3.18 Cross-Tie Blocking Interlocks are provided to prevent paralleling of both D-G. Refer to Figure 3.18 and select the CORRECT statement. (1.0)

a. If breakers 3209, 3210 and 3205 are all closed, the amber lamp (Block Closing Actuated 3206) will be lit, thus permitting breaker 3206 to be closed.

b. If breakers 3209 and (1) 3205 and 3206, or (ii) 3207 and 3208, or (iii) 3211 and 3212 are closed, the amber lamp (DG Parallel Block Act) will be lit and breaker 3210 can not be closed.

c. If the amber lamp (Block Closing Actuated 3208) is lit, it means breaker 3208 cannot be closed because the 3B bus is already being fed from the 3A bus (through 3207) and no Diesels are running.

d. If both Diesels are feeding their respective buses (3209 closed and 3210 closed) all Block Closing Actuated Lamps

, will be lit.

0.10 0 lv.i ;Le INCCRRECT siete.. ant ;;ncerning the n ;;m- ;e r llee t,. (1.0)

te:!:.

2. "::ter 5: ' *., 9 :nd C ;;: :d 1: ting ::ntral (;C03), .hile 5:nt: 0:dE:: :trf tly : '-f' cent 1

5. If pr:::;ri::r 1;.;l d;;r; ;;; t; 1;;; th;r 30 inch.3,

-:!' '::ter 5:r'.: af 5: d: :::r;t::d.

. S:r' C h:: ft: ; ::;; f '::t:r: ;5t:5 :r: ::;;::::d :r t: pr::::t tu: gr:;;; i- th: :::: 5::a fr;; ;;;ing en

i ;1t;;;;;;ie.

d. Conk; A and 0 cent;in enly :n; gr: ; Of 5::t r , 5: : ::

te;; ed tu- er., and  : 5 th fully :r at 2:25 ;;i;.

• p 22 e  !

3.20 Which of the following is CORRECT concerning OTSG 1evel instruments? (1.0) i 1

a. The startup range (0-250") and the Operate Range (0-100%) l share the same upper and lower level instrument taps. l

b. If a startup level transmitter fails low while at power, there

.'will be no noticeable effect on the ICS (all subsystems in auto),

c. The'operaterangEistemperaturecompensatedbythelower, downcomer temperature.

d. The startup range has a low level input to the ICS ana is temperature compensated.

- e 3.21 Which one of the following is CORRECT concerning the " Air Fail (1.0)

Reset" pushbuttons for MUV-16, 31 and 517

a. The pushbutton only indicates loss of air to the.asscciated i

valve E/P controller.

b. The pushbutton indicates loss of air to E/P controllers for MUV-16 and 51and also loss of air to the valve positioner for MUV-31. ,

c. On loss of air supply, the solenoid valve supplying air to the air lock valve will de-energize, causing the affected valve (16, 31 or 51) to close,

d. When air pressure has increased, depressing the air fail reset pushbutton will unlock MUV-16, 31 or 51.

3.22 List five of the seven interlocks required to, start a Reactor (2.0)

Coolant pump. Include setpoints where applicable.

. 3:23 a. What two control room indications of abnormal RCP operation, (1.0)

. require the' pump to be shutdown immediately?

b. , What control room indication of abnormal RCP operation, (1.0)

- =requi'res power level to be reduced to 72%, at 30%/ min, then tripping the affected RCP?

8 f 1

~END OF SECTION 3

?

i i

J

23 4.0 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL (25.0)

. 4.01 Match the Condition with the appropriate Radiation Monitor Alare. (2.5)

Radiation Monitor Condition

a. RM-Al 1. Control complex ventiTation return air has exceeded setpoint on gas or iodine / particulate channels.

b. RM-A2 2. Possible spent fuel radio'-

activity leak,

c. RM-A3 3. Reactor Building purge duct exhaust to the atmosphere has exceeded setpoint on gas channel.

d. RM-A4 4. Auxiliary Building ventilation exhaust to the atmosphere has exceeded setpoint on gas channel.

e. RM-A5 5. Possible waste gas tank or piping leak.

4.02 List your Immediate Actions in response to an alarm from RM-L2. (0.5) 4.03 Which of the following is NOT an Immediate Action required in AP-330, " Loss of Nuclear Services Water". (1.0)

a. Trip all NSCCCW pumps: SWP-A, SWP-8, SWP-C, SWP-2A, SWP-28.

t

b. Establish OTSG levels with emergency feedwater pumps.

c. Trip reactor AND refer to AP-580

d. Close: MUV-50 and MUV-51 L

1 1

24 i

4.04 Immediate Action step 3 of AP-380, " Engineered Safeguards System

~ , Actuation," states the following: .

Ensure HPI trains start '

• 2 HPI pumps

• SWPs

~'

• RWPs Step 6 of the some procedure states: ,

Ensure LPI trains start

• DHPs -

• DCPs

• RWPs t' ,

Which statement:15 CORRECT concerning the "RWPs" referred to in AP-3807 (I.0)

a. The RWPs in step 3 and step 6 are th'e same'. The verification is repeated to ensure it is accomplished.

b. The RWPs in Step 3 refer to RWP-3A and 3B; the RWPs in Step 6 refer to RVP-2A and 28.

c. Step 3 refers to RWP-1, 2A and 2B while step 6 refers only to RWP-2A and 2B.

d. In Step 3, the RWPs are the Nuclear Services (Emergency)

Seawater Pumps while in Step 6. RWPs refer to the Decay Heat (Emergency) Seawater Pumps.

4.05 An Immediate Action of AP-380, " Engineered Safeguards System Actuation," is to:

, " Place RB sump pump in PULL-TO-LOCK":

• WDP-2A

• WDP-28 ,

What is the Remedial Action associated with this step? (1.0)

( t I

. eh '

25 4.06 The statements below are contained in AP-380, " Engineered Safeguards System Actuation." Fill in the blanks with the appropriate numbers where indicated. .

(3.0)

When the following conditions exist:

• High Pressure

- Adequate subcooling margin; 'F when > 1500 psig

'F when s 1500 psig

-PZRlevel2{cj"l

- OTSG heat remova OR

• Low pressure .

LPI flow 2 {d} GPM in each train and stable for 2 fe} minutes, Then STOP HPI.

If TC < W 'F, then refer to EP-220

• Required Cooldown Rates Normal s 'F/hr Natural Circulation F/hr MUV-53 and MUV-257 (recirc valves) must be open when total HPI flow s W GPM Establish required OTSG 1evel

.

• Any RCP operating Q} "

• No RCP's, adequate subcooling margin {kJ %

• Less than adequate subcooling margin  %

• < 2 HPI pumps available  %

• Ifsub'coolingmargin<{n},thengotoEP-290.

• When RC Press 2 fo} psig, then open PORV.

. . 26

-4.07 Select the INCORRECT statement for the following Limit and Precaution as contained in OP-404, Decay Heat Removal System s (1.0)

"InoNertoassurethatredundantordiverseDHRmethodsare available during all modes of operation, the following require-ments must_be met prior to removing a DH train from service."

a. TheLPIpumpsuctionvalvesfromBWST(DHV-34andDHV-35) will be closed and the breakers racked out during periods ,

when the BWST is empty and a BAST is being utilized for emergency boration control.

b. No more than one DH train shall be removed from service at any one time,

c. The requirements for voluntarily entering a degraded mode of operation listed in CP-115 have.been met.

d. The refueling transfer canal is flooded, or at least one OTSG is available for cooling either by forced flow or natural circulation, or there is a readily accessible source of borated water during periods of low DH load and the plant is in Mode 5 or 6.

4.08 Which of the following statements are CORRECT concerning DH pump operation in the recirculation mode? (1.0)

a. As long as the minimum flow rate of 80 gpm is not violated, DH pump operation in the recirculation mode is unrestricted.

I

b. In no event shall the DH pump operate in the recirculation mode continuously for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> per month.

t

c. DH pump operation in the recirculation mode shall be timed and an entry made in the Control Center notebook,

d. The maximum flow from the DH system to the MUP is restricted to 140 gpm when the DH pumps are in the recirculation mode.

4.09 Select the CCRRECT statement concerning the Nuclear Services Cooling System (as per OP-408). (1.0)

a. When SW system pressure drops to 110 psig SWP-1B l automatically starts.

b. When RW system pressure drops to 110 psig,-RWP-2B automatically starts.

c. When either emergency SW pump starts, the normal pump will trip in 30 seconds.

d. When either emergency RW pump starts, the normal pump will trip in 30 seconds, f

. . 27 4.10 Where would you expect to find the correct procedure to transfer cooling water for the 3,A and 3C makeup pumps from the DC System to the SW System? (1.0)

a. OP-402, Makeup and Purification System

b. OP-705, Emergency Power-DC System

c. OP-408, Nuclear Services Cooling System

d. All three of the above procedures contain these instructions.

4.11 Select the CORRECT statement concerning transfer of Non-Nuclear Instrumentation signals to the ICS (as per OP-501). (1.0)

a. Disconnecting the RC flow signal source from the RPS cabinets has no affect on the ICS..

b. If operating signal source malfunctions make signal source transfer necessary, the transfer to another source should be done immediately regardless of ICS operating mode,

c. When changing narrow range RC pressure signals, the ,

PORV (RCV-11) should be open, with the heaters and '

spray valves in manual.

d. Buffer cards or buffer card modules may be replaced while leaving the affected controllers in auto.

4.12 Select the CORRECT Limit and Precaution concerning the Control (1.0)

Rod Drive System (as per OP-502).

a. Maximum stator . temperature is 200*F with CRD energized.

s

b. Minimum reactor power for placing the ICS reactor demand station in auto is 5%.

c. If a Safety Group is backed away from its "Out-limit" the Diamond must be in auto to enable Dilute Signal #1.

d. The " Auto" mode cannot be selected with " Sequence Inhibit" indicated.

1

.=. _. . - -. - -_ -_ - - _ - -- _ _ _ .

. . 28 4.13 Which of the following statements is CORRECT concerning the (1.0) temperature of the cooling water supplied to the CRD's?

a. Maximum allowable temperature is 180'F, there is no minimum temperature.

I

b. Maximu'm allowable temperature is 180*F, the minimum is 10*F above the dew point at the 3V head. ,

c. Maximum allowable temperature is 120*F, there is no minimum i -

temperature.

d. Maximum allowable temperature is 120*F, the minimum is 10*F above the dew point at the RV head.

4.14 Which of the following statements is CORRECT concerning the ICS Limits and Precautions? . (1.0)

a. If a feedwater cross-limit occurs while controlling the reactor from either the reactor demand or Diamond station, increase reactor power to be compatible with total feedwater flow.

b. If a feedwater cross-limit occurs while controlling the reactor from either the reactor demand or Diamond stations,

decrease reactor power to be compatible with total feedwater flow.

c. If a reactor cross-limit occurs while controlling both feedwater i demand control stations in hand, reduce the reactor power to be compatible with total feedwater flow. -

d. If a reactor cross-limit occurs while controlling both feedwater ,

. demand control stations in hand, increase the reactor power to be compatible with total feedwater flow.

4.15 Which of the following statements is CORRECT concerning operation of the turbine bypass valves? (1.0)

a. If automatic operation of turbine bypass valves is desired ,

when CRD breakers are open, sets turbine header pressure ,

controller to 27% to compensate for +125 psig reactor trip bias,

b. If automatic operation of turbine bypass valves is desired when CRD breakers are open, the 150 psig throttle pressure error logic must be bypassed.

c. If automatic operation of turbine bypass valves is desired when CRD breakers are open, the ULD must be less than 15% to reset the +50 psig bias.

, d. Automatic operation of turbine bypass valves is not possible without first resetting the CRD trip ~ breakers.

1

29 4.16 In order to startup a main feedwater pump, (Section 11.3 of OP-605) you must depress and hold the " Speed Signal Bypass" push button.

After which of the following steps can you release the " Speed Signal Bypass" without causing the FW Pump Turbine to Trip? (1.0)

a. Verify all white " Permit" lights and speed control at

" minimum" with green light on governor speed control switch,

b. Place " Trip / Reset" switch in " Reset" position

c. Verify the following occurs:

LP Stop Open HP Stop Open

d. Verify turbine speed greater than 100 RPM 4.17 During all evolutions involving the makeup pumps, verify operable flow paths for each pump to be operated. Loss of flow through a makeup pump will destroy the pump within approximately: (1.0)

a. 3 seconds

b. 15 seconds

c. I minute

d. 3 minutes 4.18 Which of the following choices are the correct fillins for these-statements? (1.0)

"The maximum weekly exposure is (1) . A/The (2) may authorize

. exposures to (3) by use of Form 912801, Authorization to Exceed Radiation Exposure Limits."

a. (1) 600 mrem (2) Nuclear Plant Manager (3) 1250 mrem

b. (1) 300~ mrem 4 (2) Nuclear Plant Manager (3) 1250 mrem

c. (1) 300 mrem (2) ChemRad Supervisor (3) 600 mrem

d. (1) 600 mrem (2) ChemRad Supervisor (3) 2 Rem

. . 30 4.19 Which of the following statements is CORRECT concerning RWP's and SRWP's? . (1.0)

a. SRWP's are generally required for non-routine work.

b. For emergency, short-term or special situations, the continuous presence of a qualified ChemRad representative may meet the RWP requirement. ,

c. SRWPs may be issued when periodic radiation surveys show that individuals will not encounter a dose rate in excess of 100 mrem /hr.

d. The RWP will list all equipment allowed to be taken into and removed from a designated area.

4.20 Select the CORRECT statement concerning entrance into a Contaminated Area. (1.0)

a. Only rubber gloves are allowed in contaminated areas.

b. Rubber or plastic gloves used in wet contaminated areas should be taped to the inside of a plastic suit, if one is being worn.

c. Personnel dosimetry and identification badges should be worn inside protective clothing such that they will not fall off and/or become contaminated.

d. In cases of routine or special maintenance that involves high contamination levels, a plastic suit will be required.

4.21 List your Immediate Actions for AP-990, " Shutdown From

. Outside Control Room" (1.5) 4.22 TRUE or FALSE (0.5)

The first Immediate Action of AP-580, RPS Actuation, is to ensure group 1-7 rods are inserted. The Remedial Action for this step directs you to EP-140, Emergency Reacti.vity Control.

END OF SECTION 4 END OF EXAM

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R/hr = 6 CE/d2 (feet) water Parameters Miscellaneous Conversions 1 gal. = 8.345 Itn. '

1 ga; . = 3.78 liters 1 curie = 3.7 x 1010aps 1 kg = 2.21 lbm 1 fte = 7.48 gal. 1 hp = 2.54 x 103 Stu/nr Density = 62.4 14/ft3 .

Density = 1 gm/cW 1 m = 3.41 x 105 itu/hr lin = 2.54 cm Heat of vaporization = 970 8ta/lom 'F = 9/5'C + 32 t

Heat of fusion = 144 8tu/lbm .

'C = 5/9 ('F-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf

( 1 ft. H 2O = 0.4335 Itf/in.

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• p., .y Sai Sat Sa: Sat Sat I.ew.4 *epo, i.ev 4 I'*P .apc. 1.q.,e 8'ar Sei 7 8 ', 8, A,

', A, s, s, s, l .0 101.74 0.01614 333 6 69 10 1036 3 l106 0 0 1326 1 84 % 1.9782 20 126 06 0 01623 173 73 93 99 1022.2 1116 2 01749 30 1.7451 l.9200 14!.4k 0 01630 118 71 109.37 1013.2 1122.6 02006 1.6855 1.8863 40 152 97 0.016 % 90 63 120 h6 1006 4 1827.3 0.2198 l.6427 1.8625 5.0 162.24 0.01640 73.52 IM 13 1001.0 1831.1 0.2347 2.6094 1.0441 6.0 110D6 0 01645 61.9F 137.96 996.2 1I34 2 0.2472 1.5820 1.8292 7.0 176 85 0 01649 53 64 I44. % 992.1 1136 9 0.2581 1.5586 1.8167 0.0 182.86 0.01653 47.34 150 79 988.5 1139.3 0.2674 1.5383 1.8057 9.0 188.26 0.016 % 42 40 1 % 22 985.2 1141.4 0.2759 1.5203 l.7962 10 193.21 0.01659 38 42 161.17 982.I 1843.3 0.2835 I.5041 8.7876 14.696 212.00 0 01672 26 to 180 07 970.3 l150.4 0.3120 1.4446 1.7%6 15 213.03 0 01672 26 29 181.11 969 7 1150.8 0.3135 1.4415 1.7549 20 227.96 0.01683 20 089 196.16 960.1 11 % .3 0.33 % 1.3962 1.7319 25 240.07 0 01692 16.303 20b42 952.1 l1606 0.3533 1.3606 1.7139 30 250.33 0.01701 13.746 218.82 945.3 18641 0.3680 1.3313 1.6993 35 259.28 0.01108 II.894 227.91 939.2 1867.1 0.3807 1.3063 1.6810 40 267.25 0.01715 10 498 2 % 03 933.7 1869.7 0.3919 1.2844 45 274.44 0 01721 1.6M3 9.401 243.36 928 6 1172 0 0 4019 50 281.01 1.2650 1.6669 0.01727 8.515 250.09 924 0 1174.5 0 4110 1.2474 1.6585 287.07 0.01732 7.787 2 %.30 919.6 ,

1875.9 0 4193 1.2316 I.6509 60 292 11 0 01735 7.175 262 09 915.5 l177.6 0.4270 1.2168 I.6438 65 297.97 0 01743 6.655 267.50 911.6 1879.1 0 4342 1.2032 1.6374 10 302 92 0.01148 6.206 272 61 907.9 1880.6 0 4409 1.1906 75 307.60 0.01753 5.816 1.6315 277.43 904.5 1881.9 0 4472 1.1787 30 312.03 0.01757 f.6259 5.4 72 282.02 901.1 1183.1 0 4531 1.1676 1.6207 85 316.25 0.01761 5.168 286.39 897.8 IIB 4 2 0 4587 1.1571 1.6:58 90 320.27 0.01 % 6 4 890 290.% 894 7 o 1185.3 0 4641 1.1471 1.6112 95 324 12 0.01770 4.652 294 % 891.7 1186.2 0 4692 1.1376 1.606b 100 327.81 0.01774 4 432 298 40 3888 1887.2 0 4740 1.1286 1.6026 110 334 77 0 01782 4.049 305.66 883.2 l186 9 0 4632 1.1117 1.5946 4

_ _ _ _ v - , ,-

TABLE D la Properte of Dr3 Soluteled Steam Inwim ct,

• Pressure Emnetr> t meory g $recit.c vos.me 7emp.

"' *f Ec Sei Set $si 5ei Sat

"* 1. quid Ig .d Eier , ,p,. lieved her ,, p,,

werew 9 * 'o *e b, h, h, og s, s,,

120 341.25 0 01789 3 72b 312 44 877.9 1890 4 0 4916 I0962 1.587b 0 01796 3 455 318 81 872 9 1191 1 0 4995 1.0617 1.5812 130 34732 140 353 02 0.01802 3.220 324 8: 86b 2 1193 0 0 50t4 1.0682 1.5751 150 3 % 42 0 01809 3 015 330 51 863 6 Il941 0 513h 1.0556 1.% 94 160  %).53 0.01815 28M 335.93 859.2 Il951 0 5204 1 04 % 1.5640 kb 41 0 0182: 2.675 341.09 3M9 11 % 0 0 5266 1.0324 1.5590 110 0 0lE27 2'532 346 0.1 350 16 11 % 9 0 5325 1.0217 1.5542 180 373 06 190 377.51 0.01833 2 404 350.79 846 8 1197.6 0.5%I 1.0116 1.5497 0 01839 2.286 355.36 843.0 1998 4 0.5435 1.0018 1.5453 XIO 381.79 250 400.95 0.01865 1.8438 376.00 825.1 1301.1 0.5675 0.9588 1.5263 417.33 0 01890 1.5433 393.84 809 0' 1202 8 0.5879 0.9225 1.5104 30D 431.72 0 01913 1.3260 409.69 794 2 1203.9 0 60 % 0 8910 14966 350 400 444.59 0.0193 1.1613 424.0 780 5 1204.5 0 6214 0.8630 1.4844 450 456 28 0 0195 1.0320 437.2 767.4 1204 6 0 63 % 0 8378 l.4734 500 467.01 00197 0 9276 449.4 755 0 1204 4 0 6487 0.8147 1.4634 476 94 0 0199 0.8424 460.8 743 l 1203.9 0 6606 0 7934 1.4542 550 600 466.21 0 0201 0.7698 471.6 131.6 1203.2 0.6720 0 7734 1.4454 650 494.90 0 0203 0.7083 481.8 720.5 1202.3 0.6826 0.7548 1.4374 700 503.10 0.0205 0.6554 491.5 709.7 1201.2 0.6925 0.7371 1.42 %

750 510.86 0.0207 0.6092 500.8 699.2 1200.0 0 7019 0.7204 1.4223 800 518.23 0 0209 0.5687 509.7 688.9 1198 6 0.7108 0.7045 1.4153 850 525.26 0 0210 0.5327 SIS 3 678.8 1197.1 0.7194 0.6891 1.4085 900 $31.M 0 0212 0.5006 526.6 6688 1895 4 0.7275 0.6744 1.4020 950 538 43 00:14 0 4717 534 6 6591 1893 7 0 7355 0 6602 1.3957 1000 544 61 0.0216 0 44 % 542 4 649 4 1191.6 0.7430 0.6467 1.3897 1100 5 % .31 0 0:20 0 4001 557.4 630 4 1887.7 0.7575 0 6205 1.37a0 0.3619 578.1 611.7 1983 4 0.7711 0.59 % l .3i,67 1200  % 7.22 0.0:23 1300 577 46 0 0:27 0.3293 585 4 593.2 1178.6 0.7640 0 5719 1.3559 1400 587.10 0 0231 0.3012 $98.7 574 7 1173 4 0 7963 0.5491 1.3454 1500 596.23 0.0235 0.2765 611.6 5% 3 II67.9 0 806: 0 5269 1.335I i

20]O 635 82 0 0257 0 1878 671.7 463 4 1835.1 0 8619 04:30 1.2649 2500 668 13 0.0287 0.1307 730 6 360.5 1091.1 0 9126 0.3197 1.2322 3000 695.% 0.0346 0.0858 302.5 217.8 1020 3 0.9731 0.1885 1.1615 320e.2 705 40 0.0503 0 0503 90 .7 0 902.7 1.0580 0 1.0580 L

e

TABLE D.lb Properties of Dr) Satursted Steam (amtmeedi Tempetatute EnAair> Enteor)

SpecJac volume 1emp. Ab Sei Sa'. San

.F P'*

• Sat Sai 5i I'*P *epo' lieved I'*P wepor P liqu4 *are- l. quid h, h, h, s, s, s, s  ! 's 's 3Xe 0 00 1075.li 1075 8 0 0000 2.1877 2.1871 32 0 0s854 0 0160 0.0061 2 1709 2 1770 35 0 09995 0 0160 2947 30 10741 1077.1 8 05 1071 3 1079.3 0 0162 2.1435 2 1597 40 0 12.170 0 0160 2444 20k 4 13 0o 106b 4 1081.5 0 026: 2.1167 2.1429 45 0.14752 0 0160: 2.1264 1703.2 18 07 1065 6 1083 7 OOMI 2 0903 50 0.178 t l 0 01603 1059 9 1088 0 0 0555 2.0393 2 0944 60 02%3 0.01604 120e 7 28 06 1054.3 1092.3 0.0745 1.990: 2.0647 70 0 M31 0.01606 867.9 38.04 48.0: 1048.6 1096 6 0 0932 1.9428 2.0340 80 0.5069 0 01608 633 1 1042.9 1100.9 0IIl5 1.8972 2.0087 to 06982 0 01610 4680 57.99 1037.2 1105.2 0.1295 1.8531 1.9826 0.9492 ODl61) 150 4 67.91 100 71.94 1031'.6 1109.5 0.1417 1.8106 1.9577 110 1.2748 0 01617 265 4 87.92 1025 8 1113 7 0.1645 1.7694 1.9339 120 169 4 0.01620 203 27 2.22:5 0.016:5 157.34 97.90 1020.0 lll7.9 0.1816 1.7296 1.9112 130 14910 1.8894 0 01629 123 01 107.89 1014.1 1122.0 0.1984 140 2.8886 1.6537 1.8685 0 01634 97.07 111.89 1008.2 1126.1 0.2149 150 3.718 1002.3 1130.2 0.2311 1.6174 1.8485 160 4 741 0.01639 77.29 127.89 996.3 1134.2 0.2472 1.5422 1.8293 170 5.992 0.01645 62 06 137.90 990.2 1138.1 0.2630 1.5480 1.8109 180 7.510 ODl651 5023 147.92 984,1 1I42.0 0.2735 1.5147 1.7932 190 9.339 0.01657 40.% 157.95 3344 167.99 977.9 1145.9 0.2938 1.4824 1.742 200 11.526 0.01663 178.05 971.6 1149.7 0.3090 1.4508 1.7598 210 14.123 0.01670 27.82 180.07 970.3 1150 4 0.3120 1.4446 1.7566 212 14 496 0.01672 26 80 188.13 965.2 1853 4 0.3239 1.4201 1.7440 220 17.186 0 01677 23 15 198 23 958.8 1857.0 0.3387 I.3901 1.7288 230 20 780 0 01684 19 382 16.323 208.34 952.2 1160.5 0.3531 13609 1.7140 240 24 % 9 0.0169 13 821 216 46 945.5 1164.0 0.M75 1.3323 14998 250 29.825 ODI700 228.64 9 38.7 1167.3 0.3817 1.3043 14860 260 35 429 0.01709 11.763 10 06I 238.84 931.8 1870.6 0.3958 1.2%9 14727 270 41.858 OD1717 8 645 249.06 924.7 1873.8 0.4096 1.2501 14597 280 49.203 OD1726 7.461 259.31 917.5 1176.8 0.4234 1.2238 14472 290 57.5 % 0.01735 s

300 67.013 0 01745 6 466 269.59 910.1 1179.7 0.4M9 1.1980 1.6350 310 77.68 0.0175! 5.626 279 92 902.6 1182.5 0 4504 1.1727 14231 320 89.66 ODl76f 4.914 290.28 894.9 1185.2 0.4637 1.1478 f.6115 330 103 06 0 0177o 4.307 300.68 887.0 1887.7 0.4769 l.1233 1.6002 340 118.01 0.01787 3.788 311.13 879.0 1890.1 0 4900 1.099: 1.5891 4

. TABLE D.lb Properties of Dr3 Satursted SteamIcontinued, 1emper41ure g Speed.c solume Lmiha h k muori 7emr.

'F Sai Sai Sai Sai lei Sai lequid w aro' liquid I'*P veror liquid I'*I waror

• r e, *, A, A. A, s, s. 8, 350 134 6.1 0 01799 3.34: 3:1 63 870 7 1892.3 0.5029 1.0754 1.5763 MO 153 N 0 01611 2 95' 33 18 852.2 1894 4 0 SIM i0519 1.5677

• 370 173.37 00ll:t 26:5 34 79 853 5 119t> 3 052b6 102ti7 1.5573 380 195.77 0016k 2.335 353 45 1644 6 1896 1 0.5413 1.0059 1.5471 390 220.37 0 01850 2 06 % 36417 835 4 1199 6 0.5539 0.9832 1.5371 400 247.31 0 01864 1.8633 374 97 826 0 1201.0 0.5664 0 9606 1.5272 410 276 75 0 01876 1.6700 385 83 816.3 12011 0 5788 0 9386 1.5174 420 30683 0 01894 1.5000 396 77 806 3 12031 0.5932 09166 1.5076 430 343 72 0.01910 1.3499 407.79 796 0 120.1 8 06035 0 8947 I4982 440 381.59 0 01926 1.2171 418 90 7854 1204.3 0.6156 0 8730 1.4887 450 4:2.6 0.0194 1.0993 4301 774.5 1204 6 0.6280 0.8513 1.4793 460 466 9 0 01 % 0 9944 441 4 763 2 1204 6 0 6402 08296 14700 470 514 7 00198 0 9009 452 6 751.5 1204 3 0.65 3 0 8063 14606 480 566 1 0 0200 0 8172 464 4 7394 iM37 0.6645 0 7866 14513 490 621 4 0 0202 0 1423 476 0 7268 120 8 06766 0 7653 1.4419 500 680 6 002W 06749 487 6 71).9 1201.7 064Bi 07436 1.4325

$3) 812 4 0 0209 0.5594 511.9 686 4 1196 2 0 7130 0.7006 1.413e 540 9615 0 0215 0.4649 SM 6 6%6 1893 2 0.7374 0.6%8 1.3942 560 1133 1 0 0:21 0.M68  %:2 624.2 lib 6 4 0.7621 0 6121 1.3742 ,

580 13 5.6 0 0:26 0.3217 58h 9 588 4 1177.3 0 7872 0.5659 1.3532 600 154:9 0 02 % 02666 610 0 546.5 1165 5 0 8131 0.5176 1.330?

620 17 % 6 0 0247 0 2201 646 7 503 6 1150.3 0 8396 0 4664 1.3062 640 2059.7 0 0260 0 1796 678.6 452.0 1830.5 0.8679 0.4110 12789 660 2365 4 0 0278 0.1442 714.2 390 2 1804 4 0 8987 0.3485 1.2472 680 2108 1 0 0305 0.I115 757.3 309.9 1067.2 0 9351 0.2719 1.2071 700 3093 7 0 0369 0 0761 853.3 172 I 995 4 0 9905 O.I464 1.1389 a 105 4 320e 2 0 0503 0 0503 902.7 0 90:7 1 0580 0 10580 L

Ann p m . 1emperasen.4 paa Is semp.gI zoo 300 doo sao sou 1eu Iso suo lecu IHau lago tax,

e. . . . . . . M24 452.3 512.0 571 4 631.2 890 8 7T54 809.9 SH.5 929.1 988.7 1907.8 I & ....... .... 1150.4 l195.8 1241.1 1288.3 1335.7 1383 8 1432.8 1482.7 1533.5 1585.2 1637.7 INS 7 ,

(II.74) s...... .... 2D512 2.1153 2.l72 2.2233 2.2102 2.3137 2.3542 2.M2.1 2 4283 2.4625 2 # 52 2.53m I e.......... 78 le 90.25 102.M 114.22 136 16 138.10 150D3 161.95 173 87 185.19 197.71 221 4 5 A... . . . . . . . 18488 litSD 12 l.2 1288.0 1335 4 13834 1432.7 1482A 1533 4 1585.1 1637.7 , IM57 1 (862.M) s.............. 1.8718 1.9370 1.9962 2.04 % 2A827 2.lMI 2.147 2.214a 2.2309 2.2851 2.3178 2.3792 l e............ 38.85 4540 SID4 57AS 63 03 69 01 14.98 80 95 iw. 92 92 88 98.64 190 77 IO A........ 1I46 6 1193.9 1240 6 1287.5 1335.1 1383 4 1432.5 1482 4 1513.2 15s5 0 leDA INSA (193.21) s . . . 1.1927 1.8595 1.9172 1.9689 20:40 2 0596 2.1002 2.13s t 21m 2 2068 2.2413 2.3028 e..... . 30.53 34 68 38.78 42 86 46 94 SI DO $5 07 59 13 63 19 67.25 75.31 14A96 A .. . 1192.8 1239.9 1287.1 1334 8 1383.2 1432 3 1442 3 ISM I 15s4 8 1637.5 IN55 (212AO) s. . 1.8160 1.8743 1.9261 1.9734 2.0170 2.05 4 2.0954 2.1319 2 1662 2 1989 2.3003

e. 22.36 25 43 28 46 3147 34 47 37 46 40 45 4344 . 46 42 49.41 55.37 Jo 4. 1891.6 1239.2 12864 1334 4 1382 9 14321 14821 1533 0 15s4 7 1637.4 1745 4 (227.96) s. . l.7808 1.8)96 l.8918 1.9392 1.9s29 2.0235 2 0615 2 0978 2.832l 2 1644 2.2263

e. . . 11.040 12 628 14 168 15 68b 17.19e 18702 20.20 21.10 23 20 24 69 27 48 40 &. 1886.5 12 %.5 1284 8 13331 1381.9 1431.3 1481.4 1532 4 15a4 1 1637.0 1745I (M7.25) S... 14994 1.% 08 1.8140 1.8619 4.9058 I.9467 1.9850 2.0282 2 0555 2 054) 2.1496

e. 7.259 8.357 f.403 10 427 11.441 12 449 13 452 14 454 1540 16 451 18446 to A..... . . . Illik 12334 1283 0 13318 1380.9 1430.5 lea 0 8 1511.9 I$ai n 16MA 1744 8 (292.11) s . .. .. . . . . . . 14492 I.7135 l.1678 l.8162 1.8405 1.9015 1.9400 1.542 2.uiub 2 0434 2.1049 e ... . . . . . . . . . . . . . . . . . 6.220 7.020 7.797 8.%2 9.322 10.077 10.830 11.5m2 12.332 13.BXI 80 &... . . . . . . . . 1230.7 1281.1 1330.5 1379.9 1429.7 1480.1 1531.3 15m).4 16M.2 1744.5 (312A3) s...... . . . ... l.6791 1.7346 1.78 % 1.8281 1.8694 1.9079 1.9442 1.97m7 2.0115 2A731 e... . . . . . . . 4.937 5.589 6.218 6.835 7.446 8.052 8.6% 9.259 9.860 11.000 800 6. . . . . . . 12274 1279.1 1329.1 1378.9 1428.9 1479.5 1530.8 1582.9 1635.7 IM4.2 (327.81) s . . .. ... . ..... . l.6518 1.1085 1.7581 1.8029 1.8443 1.8829 1.9193 1.9538 1.9867 2D464

e. . . . . . 4.081 46M 5.165 5483 5.195 6.102 7.307 7.710 8.212 9.214 lE 6 . . .. . .. . . 1224.4 1277.2 1327.7 1377.8 1428 1 1478.8 1530.2 1582.4 1635.3 1743.9 lApto p en a s . ... . . . {.. .

{. . . . ..[1A281 l 14869 1.7310 l.1822 1.8237 , 2.8625 I.9335 I.9664 2A281 e.... 3 468 3.954 4.413 4.861 5.301 5.738 6.I 72 140 &. 6.404 7.035 78e

. .. . ... 1221.1 1215.2 1326 4- 13 4.8 1427.3 1478.2 (353.02) s. 1529.7 1581.9 1634.9 1741 %

. .. IA087 1.M83 1.7190 1.7645 1.8063 1.8451 1.8817 1.9163 1.9493 2Also O e. 3.008 3.443 3.849 4.244 4.631 5.015 5.396 160 4. 1217.6 12731 1325.0 1375.7 1426 4 5.775 6.152 6 90t.

1477.5 1529.1 1581.4 1634.5 (M).531 s . 1.590b l.6519 1.70D 1.7491 1.7911 1743.2 1.8301 1.8667 1.9014 1.9344 1.9962

e. .. 2 649 3 044 3 411 3.764 4.110 4 452 4.792 180 &. 5.129 5 466 6.1%

. . . . . 1214.0 1278.0 1323.5 1374.7 1425 6 1476.8 (373A6) s. . 1528 6 1581.0 1634.I 1742 9 1.5745 16373 14894 1.7355 1.77 4 1.8167 1.8534 I.8882 1.9212 1.9831

e. .

2.361 2.726 3 060 3.380 3 693 4 002 4.309 4 613 4 917 EO A. 1210.3 5 521 1268 9 1322.1 ID36 1424.8 1476.2 1528 0 1580.5 1633.7 1742.6 s (381.793 s. 1.5594 1.6240 16767 1.7232 1.% 55 f.8048 1.8415 I.8763 1.9094 1.9713

e. 2.125 2.465 2.772 3 066 3.352 3 634 3 913 220 A. 4.191 4 467 5.017 1206.5 1266 7 1320.7 1372 6 I424 0 1475.5 1527.5 1580 0 1633.3 1142.3 (389 861 s . 1.5453 1.6117 I6652 1.7120 1.7545 1.7939 1.830h 1.8656 I.8987 1.9607

e. 1.9276 2.247 2.533 2 004 3 06B 3.327 3.5bi 3 839 4 093 240 &. 1202 5 1264 5 1319 2 1371.5 1423 2 4.597 1474 8 152o 9 1579 6 1632 9 1742 0 (397.371 s . 1.5319 1.6003 1.6546 1.1017 1.7444 1.7839 18209 18558 1.8889 f.9510

e. 2.063 2 330 i

2 542 2827 3.067 3 305 3 541 3.776 260 &. . .

1262.3 1317.7 1370 4 1422.3 4.242 1474.2 1526 3 1579 1 1632.5 1741.7 (404.42) s. . . 1.5897 14447 14922 1.7352 1.7748 3.8818 14467 1.8799 1.9420

e. .

l.9047 2.1 %

2.392 2 621 2$45 3 066 3.286 3.504 280 &. . . 1260 0 1316.2 IM94 1421.5 3.9 36 j 1473.5 1525.8 1578 6 1632.1 1741 4 (411A5) s.

. . ... .. 1.5796 14354 1.6834 1.7265 1.% 62 1.8033 1.3383 1.8716 1.9337

e. .. ..- 1. % 75 2.005

.. . .. 2.227 2.442 2.652 2 859 3.065 3.269 3474 300 &. . . . . . 1260 0 1316.2 1 M8.3 1420 6 1472.8 (417.33) s. 1525.2 1578l 1631.7 1741.0

. .. 1.5701 1.6268 14751 1.7184 1.7582 1.7954 1.8305 1.8638 1.9260

,. . . . . l.4923 1.70 % 1 8980 2 0b4 2.266 2 445 2 622 350 &. 2.19b 3 147 1251.5 1310 9 1365.5 1418.5 1471.1 1523t (431.72) s. 1577.0 1630 7 1740.3 1.5481 1.6070 16563 l.7002 1.7403 1.7777 1.8130 I$463 1.9066

e. l.2851 1.4770 16506 1.8161 400 A. 1.9767 2.134 2 290 2 445 2.751 1245.1 1306 9 IM27 1416 4 1469 4 1522 4 1575.8 16294 17395 (444 59) s. . 15281 1.5894 1.639b i6842 1724? I % 23 17977 L8311 I t91, i

.m- _s

. Power History:

m.

Reactor ...

Power g 6-

[

-w u ** * ** 95 % .... % % , . . . . ,

TIME (Hours)

XENON transien0

1. Equiv. .

Xenon Conc.

[ - - - - - - - - - - .

e .. sc = e se un w. s s . . ..,

TIME (Hours)

2. Equiv. '

Xenon Conc. . , , . . . . . , , ,

u% % .... % .. .. %

. . . w s . 2 TIME (Hours)

3. Equiv. ,

Xenon

. Conc. . , . , . . . . . , , , ,

. . w s. .. . 2. *% . . . ...s....

TIME (Hours) l I

l 4 Equiv. .

Xenon j '

Conc. - - - - - - - - - - -

. s. .. s . ,.

w . .. . . . % % . . . s,,

TIME (Hours)

., -- . , . . - . _ . ,. _ . , . . . ,,,.y -.-_r _ -, , - -%,- .- _ - . - -, ,,-, .r.- ,

i

-WORK $REET 11- ENC 1hSURE 2 (Page 1 of 2)

ESTIMATED CRITICAL 90 ROM CONCENTRATION 5320F, 01 FF No Xenon, No Control Rode, REFERENCE CONDITIONS:

Equilibrius Samarina

1. Fuel Reactivity Core Burnup 200 gFF0 h 2 gfg

a. _

b. Read Curve 3.1 of oP-103, Plant Curve Book. .

2. Renon Rasetivity (Use Step 2.1 or 2.2) 2.1 Talue calculated by SAION I (submit printout). I ak/k

(  ! ak/h)

• OR 2.2 a. Last power level was 100 I FF for 5 0 4 hrs.

b. Time Shutdown hr s. -

c. If time at last power level was < 40 bra. and SAKON is unavailable, consult with Reactor Specialist.

I ak/k

( I ak/k) =

3. Samarius Reactivity Buildup After Shutdown Talue calculated by SAXON I (submit printout) I ak/k 3.1

4. Rasetivity Effect From Temperature

a. Average RC Temperature 816 0F

b. Reference temperature is 5320T.

c. Temperature coef ficient at ppaB is obtained from Curve 3.6 of 0F-103, Plant Curve Book, to be z 10-21 Ak/k/oF.

' , d. Reactivity = [T(ave) - 532] [ Temp. Coeff.)  % ak/k

e. Reactivity = ( -

)( x 10-2% ak/k/oF)=

I

5. Reactivity of control Rods at Desired Insertion Groups 1-4 at 100 1 WD Croup 5 at too 1 WD .

Group 6 at 300 1 WD Croup 7 at 50 1 UD Regulating Group Worth I ak/k Group 8 at 8PO 2 WD Croup 8 Worth I ak/k l

J~ Calculated By Date l

Date 11/16/82 Page 18 OF-210 Rev. 16

i l f8 .\

I A H- C 4

hY G (woT fc'aI) 4%' O E Aa- nor po xt i

4 FIGUKE 1 REACTOR CORE SATE 77 LIIilT

~

i 2-2 Amendment No. X , 41 CRYSTAL RI!8. UNIT !

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• • ""e----+m_. , , , ,, _

82.ock 0 0ss% &ock 01osing NLocx0.osrug E Acrusreo 3206 Acrunrco 3208 Acrunin:o 32/2 Annun MAer.

% /,  % /  % / \ /

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~ 3 205 ~ 320 7

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J212 I

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, ANSWERS 1.0 (25.0) -

-1.1 (b) . (1.0)

Reference:

NUS, NETRO, 10.2-2.

~

. 1.2 (b) (1.0)

Reference:

NUS, NETRO,'p. 11.4-3.

1.3 '(c) (1.0)

Reference:

NUS, NETRO, p 1.4-1 1.4 (d) (1.0)

Reference:

GP, HTT of FFF, B3.3 p. 355 1.5 (b) (1.0)

Reference:

STM-504 1.6 (c) (1.0)

Ref: NUS, NETRO Unit 12 1.7 (b) (1.0)

Reference:

1. NUS, NETRO, Unit 6

2. Westinghouse Reactor Physics, Sect. 3, Neutron Kinetics and Sect. 5, Core Physics.

1.8 (c) (1.0)

Reference:

NUS, NETRO, 10.3 1.9 (d) (1.0)

Ref: NUS - Plant Performance pp 6.2-5 and 6.4 - 5 s

1.10 (d) .

(1.0)

Ref: NUS Plant Performance pp 6.4-5+6 1.31-(d) (1.0)

Ref: NUS Plant Performance, pp 3.3-2

g 1.12(c) (1.0) -

Reference:

Steam Tables or Mollier Diagram. -

1.13(b) (1.0)

Reference:

1. Westinghouse NTO, pg I-5.77

2. NUS, NETRO, 10.5-2 ,

1.14 (b) (1.0)

Reference:

1. Duke Power Co. FNRE

2. NUS, NETRO, 10.4-2 1.15 (c) (1.0)

Reference:

1. STM-6-19

. 2. NUS, NETRO, Section 6.3 1.16 (d) (1.0)

Reference:

OP-210, p. 18 1.17 (c) (1.0)

Reference:

1. GP, HTT & FFF, II B2, p. 182

2. CR, HTT, Section 1 p. 71, 157 1.18 (b) (1.0)

Reference:

T.S. pp B3/4 1-1 1.19 (d) (1.0) i

Reference:

T.S. pp 3/4 2-12 1.20 (a) (1.0)

Reference:

OP-103 curves 4.7A, B, 4.8, 3.8A, B, C, D, 3.15A, 3.17 and STS 3/4 1-1.

1.21(b) (1.0) l

Reference:

NUS Plant Performance, pp 6.5-1 to 6.5-3

- ;.22 .. "/_:5 Aalati. M

b. FALSE (0.5)

~

Reference:

a. CR3 HTFF/Thermo, last page

b. AP-460 and AP-380

3 1.23 A - Core Outlet Pressure, psig O k CS (2.0) -

B - RCS - Pressure High Trip C - Safety Limit et eh.de D - Unacceptable Operation

1. 1. 5 4 M. . U'3#)

Reference:

T. S. Safety Limit Curve, pg 2-2 1.24 Answer: Zr - H2O Reaction (1.0)

Dissolved H2 in RCS Radiolytic decomposition of Water any 2 Aluminum - NaOH reaction (.5 ea)

Reference:

CR3 Draft HTFF/Thermo, Section 4, Post-LOCA H2 Sources.

~

I I

- - - - - , - - - - -. - - - - ~ _ , , , _ _ _, _,

a

• 4

~

ANSWERS 2.0 (25.0) 2.1 (1.0) -

Answer: (d) l l

Reference:

RB Isolation and Cooling System Lesson Plan, ANO-91 2.2 (1.0)

Answer: (b) .

Reference:

STM-25-21, 22, 23, 24, and 25.

AP-1071, p. 1.

2.3 (1.0)

Answer: (a) l

Reference:

AP-304, p. 4 2.4 (1.0)

Answer: - Selector switch is located at GW pumps Aho -

Reference:

STM-25-14 K: 4 % - NAO-9l Answer: (c)

Reference:

STM 2-105, 106, 67, 106.

OP-302. REV.22, pg 2.

2.6 , (1.0) 1 Answer: (d) ,

Reference:

STM 2-34, 27, 54 and 16- '

4 2.7 (1.0)

Answer: (a) .

Reference:

OP-404, p. 32 2.8 (1.0)

Answer: (b) .

Reference:

OP-401, p. 7 and 8 l ._ _ _ _ _ _ , , _ . . _ __. _ _ , , . -- .__ __

5 2.9 (1.0)

Answer: (d)  :

Reference:

STM 12-4, 10, 9 and 4.

2.10 (1.0)

Answer: (a)

Reference:

STM-28-5.

2.11 (1.0)

Answer (a)

, , A\so (d)

Reference:

STM-405 ir e m AMO-M gtr 3 (b) -

(BSV-16 & 17 are normally open)

(c) -

(Valves open on 4 psig, pumps start on 30 psig)

(BSV-16 & 17 are normally open) 2.12 (d)1 ht %ese vdves a6w tu o( a.w e gew S ty d .

(1.0)

Answer: (b)

Reference:

1. STM 23-7

2. OP-502, p. 3

3. OP-408, Rev. 32 e 2.13 M

[ An ne r - (:)

";f;rence. STM 22-13, 25, 30, 17.

I 2.14 (1.0)

Answer: (a)

Reference:

STM-17-12, 12, 10, 10.

(b) - Must be manually stopped (c) - No auto position (d) - Has auto start 2.15 (1.0)

Answer: (b)

Reference:

STM 17-4, 4, 5, 7.

(a) -

MUV-48 is remotD y operated (c) -

Closes MUV-49, not 40 & 41 (d) -

makeups demins may be parallel or series

6 2.16 (1.0)

. Answer: (b) -

Reference:

STM 10-2 .

2.17 (1,0)

Answer: (d) i .

Reference:

STM-1-17 to 20 2.18~ (1.0)

Answer: (b)

Reference:

PASS Lesson Plan, R0-105 2.19 .

(2.0)

Answer: (See attached drawing)

1. Normal bypass inverter supplies (0.5)

2. Inverter feed to vital (0.3)

3. DC to inverter (0.3)

4. Two normal battery chargers (0.3)

5. One back up battery charger (0.3)

6. Bypass transformer and critr'er '3k) (0.3)

Soldte -ve\qe regu.h 2.20 (1.0) t Answer: (a) l

Reference:

OP-705, Rev. 3 1 l

2.21 (1.0) i Answer: (a)

Reference:

OP-605, Rev. 28, pp 5 & 15 2.22 (1.0)

Answer: (b) -

Reference:

Site Fire Protection Systems ANAO-39

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2.23 0 pmp o'em --W (1.0)

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Answer: CirculatingWaterPumpOperating) Condenser vacuum of ) 5" Hg ':r ' 25") y

Reference:

STM 13-18 Ra$: sTM. c.R. Eb 4, Re.t i/irlssy g Lto 2.24 (1.0)

I Answer: a. TRUE ,

Reference:

AP-380, pg. 9 (d.5) l

b. TRUE

Reference:

OP-404, pg. 5 (0.5)

I 4

8 ANSWERS 3.0 , (25.0) 3.01 b (1.0) -

Ref: OP-504, Rev. 7., pg. 3 3.02 e (1.0)

~

Ref: STM-13-34 3.03 c (1.0)

Ref: STM-12-11 3.04 a (1.0)

Ref: STM-20-2 (Separate Transmitters for DHV 3+4) OP-404, i pg. 6, 7 (Alarm on DHV-41, go interlock)  !

l 3.05 d (1.0)

Ref: OP-504, Rev. 08, pg. 8 3.06 b (1.0)

Ref: Steam Line Rupture Matrix Handout, pg. 5 3.07 b (1.0)

Ref: SLRM Handout, pg. 9.

l 1. F (It resets the bypass)

( 3. F (It resets automatically)

4. F (Pushbuttons work anytime matrix is bypassed) 1 3.08 b (1.0)

Ref: STM-6-15,~17 3.09 c (1.0)

Ref: STM-43-17 3.10 d (1.0)

Ref: STM-43-7 3.11 a (1.0)

Ref: STM -24, 25

9 3.12 a (1.0)

Ref: STM-6-10, 11 -

3.13 d .

(1.0)

Ref: Power System Operation, R. H., Miller, pg. 22-24 3.14 c -

(1.0)

Ref: Power System Operation, R. H. Miller, pg. 22-23 3.15 a (1.0)

Ref: STM-10-36, 37 3.16 d .

(1.0)

Ref: STM-9-11-21 Also T. S. pg. 2-6 3.17 a (1,0)

Ref: STM: 28-22 3.18 b (1.0)

Ref: STM-10-56, 57 4 3.1^ L $6 4>

\u M S f ST"-2-121, 222 1 3.20 c (1,0)

Ref: STM-2-27, 28 3.21 d (1.0)

Ref: STM-17-17, 18 3.22 1. Reactor power > 30% (2.0)

- 2. Oil lift pressure > 200 r 19

3. NSCCCW Return Flow > 260 gpm/ pump

4. Upper and lower oil Reserv. above low alarm

5. Seal Infection flow > 3 gpm/ pump (5 answers

6. Controlled bleed off valves (MUV-258/261) open req. - 0.4

7. Tc > 500 'F to start 4th RCP each)

Ref: STM CH. 420, Rev. 1. pg. 19.

OP-302, Rev 21 pg 3

3.23 a. Controlled bleed off temp. 2170'F (Verified) (0.5)

High seal stage pressure drop k 2/3 RCS pressure (0.5) .

b. Total seal outflow exceeds 2.5 gpa (0,5)

. and is rapidly increasing (0.5)

Ref: OP-302, Rev. 21, pg 5 9 .

e 4

4 ~ , - .

q w,- 4 3,- m-- --,n y p. y4 -

la o .- ,

, Answers 4.0 (25.0) -

4.01 a - 3 Ref. AP-241 (2.5) b-4 Ref. AP-242 (0.5 each)

/ c-5 Ref. AP-243 d-2 Ref. AP-244 e-1 'Ref. AP-245 4.02 Notify Aux. Building Operator to ensure closed: (0.5) l l

l WDV-891, WDV-892

{

l Ref. AP-272 4.03 (Establish OT levels w/MFP is a subseq (1.0)

Ago -b wu hw ion)M m l j 3/6/dr

. AP-330 - R.sV, I LAA n l 4.04 (d) (1.0)

NS Seawater Pumps - RWP-2A/2B (Step 3)

DH Seawater Pumps - RWP-3A/3B (Step 6)

Ref: AP-380 STM-20-9 (RWP-3A/3B)

STM-4-10 (ECCS)

STM-23-2/3 (NSCW) 4.05 Notify AB operator to open affected BKG at MCC: (1.0)

( Reactor 3A2) Not req. for full credit

(* Raactor 3B2)

Ref: AP-380, pg 4 4

4.06 a. 20 i

'. 100 (3.0)

b. 50 j.

low level limit (30")

c.

(0.2 each) 50 k. 50%

d. 1000 1. 95%

e. 20 m. 95%

f. 500 n. O

g. 100 o. 2300 *

h. 10 Ref: AP-380, pg.

r- ,

....-- 12 .

fl.07(a) (1.0) -

Ref: OP-404, Rev. 45, pgs. 4 and 5 .

4.08 (c) (1.0)

Ref: OP-404, Rev. 45, pgs 2 and 3 4.09 (a) (1.0)

Ref: OP-408, Rev. 32, pg 3 (Incorrect statements) b - 12 psig c - 15 sec.

d - 15 sec.

4.10 (c) . (1.0)

Ref: OP-408, Rev. 32, Section 10.2 4.11 (b) (1.0)

Ref: OP-501, Rev. 8, pgs. 2, 3 and 6 4.12 (d) (1.0)

Ref: OP-502, Rev. 13, pgs. 3-6 4.13 (d) (1.0)

Ref: OP-502, Rev 13, pg 3 4.14 (b) (1.0) 1 Ref: OP-504, Rev. 08, pg. 4

• 4.15 (a) (1.0)

Ref: OP-504, Rev. 08, pg. 7 4.16 (d) *

(1.0)

Ref: OP-605 pg. 21 STM 27-37 4.17 (b) (1.0)

Ref: OP-402, Rev. 43, pg. 4 l

l i

i

r 33

,4.18 (c) (1.0) -

Ref: RP-101, Rev. 19, pg. 9 4.19 (b) (1.0)

Ref: RP-101, Rev. 19, pg. 13 4.20 (d) (1.0)

Ref: RP-101, Rev. 19, pgs. 21 and 22 4.21 1. Announce over the PA system that the Control Center is' being (1.5) evacuated.

2. Transfer the 6900V and 4160 unit buses from the unit auxiliary transformer to unit startup transformer.

3. Trip the reactor from the MCB or remotely by opening 480V CRD breakers "A" and "B".

4. Depress " Reactor Trip" pushbutton AND perform Immediate Actions of AP-580.

5. Close FWV-161 and 162, EFW bypass valves.

6. Trip the main turbire and FWP's and assure EFWP's start and are controlling OTSG 1evel.

Ref: AP-990, pg. 2 ,

4.22 False ,

(0.5) 1 Ref: AP-580 and EP-140 9