ML20237K620

Exam Rept 50-348/OL-87-02 on 870622-26.Exam Results:Six of Six Reactor Operators Passed Written & Operating Exam & 12 of 12 Senior Reactor Operators Passed Written Exam & 10 Passed Operating Exam.Exam Questions & Answer Key Encl

ML20237K620
Person / Time
Site:	Farley
Issue date:	08/07/1987
From:	Moorman J, Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20237K598	List: ML20237K620 ML20237L235
References
50-348-OL-87-02, 50-348-OL-87-2, NUDOCS 8708270232
Download: ML20237K620 (94)

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{{#Wiki_filter:m, e' { l ENCLOSURE 1 EXAMINATION REPORT 348/0L-87-02 Facility Licensee: Alabama Power Company j P. 0. Box 2641 i Birmingham, AL 35291-0400 Facility Name: J. M. Farley Nuclear Plant 1 Facility Docket No.:60-348/364 Written and operating examinations were administered at the J. M. Farley Nuclear Plant near Ashford, AL. Chief Examiner: rt+as /I M f m ez. # [ O'7'O 7 di s H. Moorman, III Date Signed Approved by: dder[d 7 4vo 67 ohn F. Mtinro/Section Chief Date Signed Summary: Requalification Examinations were administered on June 22-26, 1987. Written and operating examinations were given to 6 Reactor Operators (RO) and 12 Senior Reactor Operators (SR0). 6 R0s passed the written examination and 6 R0s passed the operating examination.12 SR0s passed the written examination and 10 SR0s passed the operating examination. Those SR0s who failed the operating exam failed the simulator portion of the exam only. Based on the results described above, 6 of 6 R0s and 10 of 12 SR0s passed the overall examination. j B708270232 870813 PDR ADOCK 05000348 V PDR l L

p 1 i REPORT DETAILS 1. Facility Employees Contacted: McLean, C., Simulator Instructor Wiggins, R., Training Supervisor

• Williams, L., Training Manager
• Woodard, J., General Manager, Nuclear Plant
• Attended Exit Meeting 2.

Examiners:

Hemming, B., EG&G Idaho, Inc.

Jensen, N., EG&G Idaho, Inc. I

• Moorman, J., NRC, R II Picker, B., EG&G Idaho, Inc.

Rapp, C., NRC RII

• Chief Examiner 3.

Written Examination Review: At the conclusion of the written examinations, the examiners provided your 4 training staff with a copy of the written examination and answer key for review. The comments _ made by the facility reviewers are included as to this report. The NRC resolutions to these comments are listed below. Questions marked by an asterisk (*) were changed as a result of insufficient, inadequate or contradictory reference material provided by the utility. Three of twelve (25%) changes made to the written examination answer key were due to inadequate or insufficient training material provided by your staff to the NRC for examination development. i 0

t' I i j a. R0 Examination Question 2.10* NRC Resolution: l Utility comment accepted. The charging pump oil coolers have been added to the answer key. Five of the six answers are required for full credit. It is suggested that the facility update its training material to reflect this 1 change. ] l Question 2.14* ] NRC Resolution: Utility comment accepted. The iron-water and aluminium-water reactions are added to the answer key with full credit given for correctly listing four of ) the six correct answers. It is recommended that the facility update Item 3 of-j OPS-52102H to ensure consistency in the training material. { Question 4.07 i NRC Resolution: j Utility comment accepted. The answer key has been changed to False. Question 4.08 NRC Resolution: Utility comment not accepted. The question specifies the initial conditions that are to be used in answering the question. No change to the answer key is warranted. I

b. SR0 Examination Question 5.02 NRC Resolution:

l Utility comment accepted. Since there is no correct answer in the distractors, the question will be deleted. I

Question 5.03 NRC Resolution: Utility comment acknowledged. The answer provided by the utility is equivalent to the answer key. The answer key will be annotated to accept either answer. Question 6.01a NRC Resolution: lity comment accepted. Maintaining 18 psig in the VCT ensures 15 psig ukpressure on No. I seal. The answer has been amended to allow accepting ' maintaining 18 psig in the VCT' or 'having a minimum backpressure of 15 psig on the no. I seal'. Question 6.01c NRC Resolution: Utility comment accepted. The answer key has been amended to delete ' discharge valves' from the required answer. Question 7.03 NRC Resolution: Utility comment not accepted. The word TURBINE in distractor 'a' was capitalized to ensure that the candidate was aware that turbine power was to be i considered and not reactor power. If the candidate is knowledgeable of the plant response after losing one RCP, he will eliminate distractor 'a' and choose the correct answer. Question 7.10* NRC Resolution: Utility comment accepted. Due to the L ige to A0P 9, Loss of Train A or B Component Cooling Water, there is no cor rect answer to this question. The question has been deleted. The facility should ensure that training material is updated to cover procedural changes. l f ) l { I l 1 L- )

l i Question 7.11 l NRC Resolution: I Utility comment accepted. The answer key has been corrected by deleting . Verify SI actuated' and replacing it with the correct answer, ' Trip RCPs'. Question 7.13 J 'NRC Resolution: 1 Facility comment accepted. ' Verify turbine trip' meets the intent of the answer. The phrase ' indicated by all turbine stop valves closed' was placed in parenthesis and not required as part of the answer. Question 8.15 NRC Resolution: Utility conrnent accepted. The answer key has been corrected to show 31.4% as the setpoint. The following question was changed during exam grading. Question 5.09 Point values of the answers were changed to ensure consistency. 4. Exit Meeting: At the conclusion of the site visit, the examiners met with nembers of your i staff to discuss items pertinent to the operating exam': and the examination process. _ _ ___-_ _a

s l l i There were no generic weaknesses noted during operating examinations. Various problems with the simulator were discussed. Among those problems were: 1. A spurious turbine trip 2. The inability to accurately model a turbine load rejection 3. The malfunction described as causing a Main Feed Reg. valve oscillation actually caused Main Feed Pump speed to fluctuate 4. The simulator erroneously modeled the RCDT pressure as negative during a Reactor Startup 5. The inability to model complete failure of the RCP seal package for all RCP's The cooperation given to the examiners and the effort to ensure an atmosphere in the control room conducive to oral examinations was noted and appreciated. The licensee did not identify as proprietary any. of the material provided to or reviewed by the examiners. A review of the simulator examination results revealed one potential weakness that the facility should address in future training activities. During one simulator scenario, one examinee hypothesized that a malfunction which should have opened the reactor trip breakers, did not do so. The examinees, although aware that an ATWS possibly existed, did not pursue the problem to a final resolution. In light of recent events concerning the malfunction j of reactor trip breakers, it is suggested that the facility emphasize this in their training program. 4 l l 4

( ) U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR REQUALIFICATION EXAMINATION r FACILITY: FARLEY 1&2 REACTOR TYPE: EWR-WKg3 STary '. ' O 'f S 6 DATE ADMINISTERED: h14Qg422 - 5 roF '- I 8#t" EXAMINER: EigKE8 _[im__ CANDIDATE " f' T i O f d. INSTRUCTI0t4S_TO QaNDIDATE: i Read the attached instruction page carefully. This examination replaces the current cycle facility administered requalification examination. Retraining requirements for failure of this examination are the same as for failure of a requalification examination prepared and administered by your training staff. 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_ _IGIbL SCgBE___ _VALUE CATEggBY 19.0D -20.90 _ & 00 _ __ ___ 5. THEORY OF NUCLEAR POWER PLANT OPERAT!ON, FLUIDS,AND THERMoi:YNAMICS _d0m00 26.00 6. PLANT.5YSTEMS DESIGN, CONTROL, AND INSTRUMENTATION 19 00 _25.UQ _ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL l _20.00 _26.00 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS ~19.oo %w Totals Final Grade All work done on this examination is my own. I have neither given nor received aid, m_M MM+ Candidate's Signature .]

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS i a During the administration of this examination the following rules apply: 1. Cheating on the examination means an automatic dental of your application and could result in more severe penalties. 2. Restroom trips are to be limited and only one candidate at a time may ' leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating. 3. Use black ink or dark pencil only to facilitate legible reproductions. 4. Print your name in the blank provided on the cover sheet of the examination. 5. Fill in the date on the cover sheet of the examination (if necessary). 6. Use only the paper provided for answers. 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet. 8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet. 9. Number each answer as to category and number, for example, 1.4, 6.3.

10. Skip at least three lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

12. Use abbreviations only if they are commonly used in facility literature.

13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

l

15. Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the examiner only.

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.

This must be done after the examination has been completed. )

18..Nhen-You' complete your examination, you shall: .Assemb'le'your examination as follows: a. (1) Exam questions on. top. (2) Exam aids - figures, tables, etc. (3) Answer pages including figures which are part of the answer. b. Turn in.your copy of the examination and all pages used to answer the examination questions. c. Turn'in all scrap paper an'd the balance of the paper that you'did l not use for answering the questions, i d. Leave the examination area, as defined by the examiner. If after j leaving, you are found in this area while the examination is still 1 in progress, your license may be denied or revoked. i j 1 1 l D

5.. . THEgBY OF NEGLEAE_EQEER_EkdMI_QEEEdllGL.' Page 4 ~ _EkMISSM MQ_IMERMODYNAMICS f QUESTION. 5.01 (1.00) Indicate which item below DOES NOT ensure the Enthalpy Rise Hot Channel N Factor (F deltaH) remains within limits. a '. Control Rads in group move together within-+/- 12 steps. b. Control Rods are maintained above.the withdrawal limits. c. . Axial Flux difference is maintained within limits, d. Control Rods are sequenced with overlapping groups. QUESTION 5.02 (1.00) In order to maintain a minimum 200.F subcooling margin in the RCS when reducing RCS pressure to 1600 psig, steam generator pressure must be reduced to approximately: .1 a. 200 psig l b. 245 psig I c. 260 psig d. 275 psig j k ^' QUESTION 5.03 (2.00) a. Define the term Departure from Nucleate Boiling Ratio (DNBR). (0,5) b. As the reactor coolant pressure decreases, explain how the DNBR changes INCREASE, DECREASE OR NO CHANGE and WHY. (1.5) i i (***** CATEGORY 5 CONTINUED ON NEXT PAGE tt***) =_:___ __

Si lBEORY OF NUCLEAR POWER PLANT QPERAT19E. Page 5 . FLUIDS.AND TBEEMQRYUddIES QUESTION. 5.04 .(1,00) Multiple Choice What is the specific volume of saturated steam with a quality of 85% and a temperature of 500F7 (Choose the MOST CORRECT answer.) a. 0.58 ft3/lbm b. 0.67 ft3/lbm c. 0.93 ft3/lbm d. 1.16 ft3/lbm 1 QUESTION 5.05 2.00) Guerr3 tes90 List FOURscriteria that must exist to ensure natural circulation subsequent to a loss of all RCPs. QUESTION 5.06 (1.00) TRUE or FALSE 7- 'Concerning centrifugal pumps: a. A pump running at shutoff head has no volumetric flow rate. b. The faster a pump rotates, the greater tha NPSH required to prevent cavitation. QUESTION 5.07 (1.00) Indicate how (LESS NEGATIVE, MORE NEGATIVE or NO CHANGE) differential boron worth changes with an increase in each of the following: j a. Boron concentration b. Moderator temperature (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) .]

5.. HIEQRY OF_t[QQLEAB_ POWER PLANT QEEBATION. Page 6 ,ELEQS.ANDTREEdQDlHadlGE -QUESTION 5.08 (2.00) What FIVE factor must be'taken into account when calculating a Shutdown Margin. ' QUESTION 5.09-(1.00) Briefly explain the effects that clad creep has on the doppler only power coefficient. QUESTION 5.10-(1.00) During a startup it was determined that Keff was equal to 0.9 when the Source Range (SR) instrument was reading 50 cps. What would the source ' range instrument be reading if rods were withdrawn to bring Keff equal to 1 0.95? Assume.BOL conditions. a. 75 cps b. 100 cps c. 125 cps d. 150 cps QUESTION 5.11 (1.00) If reactor power is increased from 1000 cps to 5000 cps in 30 seconds, WHAT is the Startup Rate? a. 0.8 DPM b. 1.0 DPM c. 1.2 DPM d 1.4 DPM l l l l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) ._____-.-.-.__________________________J

5... THEQBV OF NUQLEASJOMER PLANT OPERAllph Page <7 FLUIDS,AND THEBMQPlN6MIGE ,o QUESTION 5.12 (1.00) a. What is the approximate 50% BOL equilibrium value for Xenon? b. What' is the approximate peak BOL Xenon value for trip from 100%? QUESTION 5.13 (1.00) 'Which one of the following is CORRECT concerning Moderator Temperature Coefficient (MTC)? a. MTC is not permitted by Technical Specification to be positive for any plant operating mode, b. MfC becomes less negative as fuel depletion occurs. c. 'MTC'causes axial flux distribution to be tilted toward the top of the

core, d.

MTC becomes more negative as temperature increases due to non-linear expansion of the moderator. QUESTION 5.14 (1.00) State the effect, MORE NEGATIVE, LESS NEGATIVE or NO EFFECT, that the following have on delta I: a. Control Rods positioned to the All Rods Out position from 170 steps, b. Increased power level. i I (***** CATEGORY 5 CONTINUED ON NEXT PAGE

• • • • k)

J

Sa -IHEQBLQLMECLE6R POWER PLANT REEBAIlo._L. Pade 8 .Ek21P,E.t.AMD TRERdQpIM&dlCS pd QUESTION 5.15 (1.00) g. Which one. of the following iM.L! JOT ensurQ='#fi&ntShutdown Margin? 3 a. The reactor will not be made critical with the Reactor Coolant System average temperature less than 541 degrees F. b.. The reactivity transients associated with postulated accident conditions are controlled within acceptable limits. c. The reactor will be maintained sufficiently suberitical to preclude inadvertent criticality in the shutdown condition, d. The reactor can be made suberitical from all ooerating conditions. 4 QUESTION 5.16 (1.00) l During a reactor trip recovery, the initial 1/M data point was 1.0. After a 1-hour delay, rod withdrawal was commenced. Upon stopping rod withdrawal to take 1/M data, the RO reported that the second 1/M point was 1.1. Which one of the following explains this increase in the 1/M value? I a. This is not possible, the RO must have made an error when taking count ~ rate data. ( b. The buildup of Xenon during the 1-hour delay added more negative reactivity than the rod withdrawal had added in positive reactivity. c. The source-detector geometry is incorrect. d. An inadvertent dilution is in progress. QUESTION 5.17 (1.00) Concerning equilibrium Samarium-149 (Sm) reactivity, which one of the following statements is correct? 50% equilibrium Sm reactivity is: a. one quarter of 100% equilibrium Sm reactivity. b. one-half of 100% equilibrium Sm reactivity. c. three quarters of 100% equilibrium Sm reactivity. d. equal to 100% equilibrium Sm reactivity. (***** END OF CATEGORY 5 *****) 1 ___________________a

6. PLANT SYSTEMS DESIGN. QQUIBOL. ANR_INSTREMENTATTON Page 9 t QUESTION-6.01 (1.50) -State the RCP precaution / limitation associated with each statement below. (ONE precaution / limitation per statement.) a. Ensures adequate seal water flow to 42 seal. b. Ensures #1 seal not riding on runner, minimises possibility of seal damage. I c. Provides overpressure protection during solid plant operation. QUESTION 6.02 (1.50) State'the THREE conditions that will cause a condensate pump to auto start. Include coincidence as applicable. ' QUESTION 6.03 (1.50) Indicate whether the MAIN FEEDWATER STOP VALVE, FEEDWATER REGULATING VALVE or the FEEDWATER REGULATING VALVE BYPASSES is described by each statement

below, a.

Protects against S/G blowdown in event of a pipe rupture. b. Auto close on trip of both main feed pumps. c. Controls water level in S/G and receives auto signal frcm Steam Generator Water Level Control System. ) l QUESTION' 6.04 (1.00) j a. What is the purpose of the Turbine Driven Auxiliary Feedwater Pump steam supply warmup line? b. Where does the condensed steam from the warmup line drain? l QUESTION 6.05 (1.00) What are the design features of the Component Cooling System that prevent i release of radioactive material to the environment? (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

6..

PLANT SYSIEMS_REglGN. CONTROL. AND INSTRUMENI&IION Page 10 C l E QUESTION 6.06 (1.50) List FIVE of seven conditions that will cause a Solid State Protection System general warning alarm to occur. DISREGARD LOSS OF DC POWER. QUESTION 6.07 (1.50) List ALL conditions that will AUTO CLOSE the Letdown Orifice Isolation Valves. DISREGARD A LOSS OF MOTIVE FORCE. -QUESTION 6.08 (2.00) List FOUR of the FIVE ECCS acceptance criteria as identified in 10CFR50. QUESTION 6.09 (1.00) i l How is the containment cooling system assisted during accident conditions l by the function of dropout plates? j l 1. i QUESTION 6.10 (1.50) State THREE arming signals for the Steam Dumps. Assume the C-9 (condenser available) interlock is satisfied? l QUESTION 6.11 (1.00) l Which one of the following is an indication of an Intermediate Range 1 Channel being slightly (5 - 10 % voltage error) undercompensated? a. Automatic energising of the source range when the first intermediate range channel drops below the P-6 setpoint. b. Actual neutron level falls into the source range without indication. l c. Indicaticn remains above 10E5 cps in the source range on both channels. d. Automatic energising of the source range whenthe P-10 interlock was cleared on both channels. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) )

Si PLANT SYSTEMS HF&lGH&_9DHTROL. AHQ_JNSTRUMENT&IlRM Page.11-QUESTION. -6.13 (1.00) The type of detector used for the Gamma-Metrics system is a/an: a. G-M tube. b. BF3 proportional counter, c. proportional fission chamber. d. uncompensated ion chamber. QUESTION 6.13 (1.00) Which one of the following indicates the response of Tavg and Delta T if a control channel Tc failed HIGH? a. 'Tavs decreases, Delta T decreases. b. Tavg increases, Delta T increases. Del'a T increases, c. Tavg decreases, t d. Tavs increases, Delta T decreases. QUESTION 6,14 (1.00) List the loads supplied by the 120 VAC Uninterruptible Power Supply (UPS). QUESTION 6.15 (1.00) Rod motion will be stopped on a logic cabinet urgent failure by: a. inhibiting the pulser. b. opening contacts from the BOU. c. freesing the slave cyclers. d. providing simultaneous current orders to stationary and movable grippers. (***** CATEGORY 6 CONTINUED ON NEXT PAGE t****)

6,-PLANT SYSTEMS DESIGN. CONTROLd@_1H. lMMEEIElRN Pace 12 l l QUESTION 6.16 (1.00) -What are the devices used to protect the Spray Additive' tank from extremes of positive and negative pressure? l (***** END OF CATEGORY 6 *****) l

7. - PROCEQUEES - NORMAL. ABNORMaku_ EMERGENCY Page 13 l

.Al!QJADIOLOGICAL CQtEBQL 1 I QUESTION 7.01 (1.00) Under what conditions should the auxiliary feed flow be limited to 150 gpm. per S/G, according to SCP 22.0 " Auxiliary Feedwater System"7 i QUESTION 7.02 (1.50) List THREE reasons why criticality shall not be achieved at a rod position below the zero power rod insertion limit. i QUESTION 7.03 (1.00) According to AOP-4.0, " Loss of Reactor Coolant Flow". Which one of the following is a true statement? a. Reactor trip will occur if flow is lost in one loop above 35%, -TURBINE power. b. Steam generator water level will decrease on the loss of a RCP in the affected loop. c. Reactor trip will occur if turbine power is above 10% and flow is lost in one loop. i d. Steam generator water level will not be affected in the loop with the loss of a RCP. QUESTION 7.04 (1.00) List the immediate operator actions for a continuous bank withdrawal according to AOP-19.0, " Malfunction of Rod Control" l QUESTION 7.05 (1.50) List THREE general methods of collapsing a bubble in the reactor vessel head in the order directed in FRP-I.3 " Response to Voids in Reactor Vessel". 1 4 (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)

7.- ESQCERESEE - NORMALJ ABNORMAIu_ MEEGENCl Page l'4 . At@_$ADIOLOGlGAL CONTROL QUESTION-7.06 (2.00) a. What TWO procedural related conditions dictates when monitoring of the Critical Safety Function Status Trees (CSFST) should begin? i b. During what plant condition will the CSFSTs be munitored for 'information only? QUESTION 7.07 (1.50) During the execution of an Emergency Procedure, the Critical Safety Function Status Trees indicate that a RED path exists. a. What is the required operator response for this condition? b. Under What TWO conditions can a red path procedure be exited? QUESTION 7.08 (1.00) Which one of the following is NOT an immediate operator action for ECP-0.0, Loss of All AC Power? a. Check total auxiliary.feedwater flow > 377 gpm. b. Verify reactor trip and bypass breakers open. c. Verify turbine tripped. d. Restore power to any AC emergency bus. QUESTION 7.09 (2.00) List the' steps required to perform an emergency boration per AOP-27.0, " Emergency Borat1Hn" Valve numbers not required. e e l. 3, l' u 1 .I 4 (*++** CATEGOhY 7 COFN,eNUED ON 'JFXT PAGE t m* ) g ', J. P l i ,, h I i N 'f Y 9 ,) j v t /< t

7 PRQQEQHRES - NQBMAL1_6HEQBMAkt_EMERGEEY Page 15 .,6ND RADIOLOGigak._QONTRQL _q O fa, t QUESTION 7.10 (1,00) Which'onu ;f the following is an immediate action in accordance with AOP-9.0, " Loss of Train A or B Component Cooling Water"? kl a. When high bearing temperature is indicated, then trip the RCPs. i b. If CCW surge tank indicates system leakage,'then determine'the location and isolate. c. If required, fill the CCW surge tank to the normal level, d. Refer to Technical Specification 3.7.3.1 for limiting conditions for operation. .k N___ ( QUESTION 7.11 (1.50) While in EEP-0, " Reactor Trip or SI", at step 15 the STA reports the following information: Containment Pressure is 4.2 psig, subcooling is 25 degrees based on core f exit thermocouple and 50 degrees based on hot leg indications. Also j pressurizer level is at 5%., RWST is at 21 feet and CST is at 4 feet. In accordance with the foldout page for EEP-0, WHAT action (s) are required? QUESTION 7.12 (1.00) When forced to do the Response Not Obtained actions of an Emergency Procedure, what should the operator do if the item in this column CANNOT be completed? QUESTION 7.13 (2.00) List the FOUR immediate operator actions for FRP S.1, ATWT. I J I (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****) U

~7.,~ PROCEDURES - UQFMAL'. ABNORMAb _EMEBGENCY Page 16 t ,AND',RADIOLOGlGbL_CQUIBQL QUESTION 7.14 (1.00) Which one of the following is a symptom of AOP-8, " Partial Loss of Condenser Vacuum? a. Automatic start of condensate pump. b. Decreasing condenser PRESSURE. c. Loss of Circulating Water Pump, d. Start of Cooling Tower Fans. QUESTION 7.15 (1.00) State TWO of the THREE frequent start limits on the Motor Driven-Auxiliary Feedwater Pump as specified in SOP-22.0, " Auxiliary Feedwater System". .i i ) ) (***** END OF CATEGORY 7 *****) l I 4 l l )

8'.- ADMINLEIEAIIVE PROCEDURER, CONQ1ILQMS Page.17 1 t .&MQuklMII&Il0NS- . QUESTION 8.01 (1.00) Indicate the reason for the recent change to Technical Specification 3.4.1.2 (mode 3 operation with < 3 RCP's) QUESTION 8.02 (2.00) What iu the minimum combined crew composition for the following positions with Unit 1 and 2 operating in mode 1 according to AP-16, " Conduct of Operations - Operations Group". a. Shift Supervisor b. Shift Foreman c. Plant Operator d. System Operator e. Shift Technical Advisor QUESTION 8.03 (2.00) Define the'following LCO conditions according to AP-16, " Conduct of Operations - Operations Group". a. Mandatory LCO (0.5) b. Administrative LCO (1.5) QUESTION 8.04 (1.00) 'What are the area boundaries in which a Shift Supervisor must be present in at all times? QUESTION 8.05 (1.00) Where can Operations Group Administrative Policies that are not identified in AP-16, " Conduct of Operations - Operations Group" be located? (***** CATEGORY 8 CONTINUED ON NEXT PAGE *****) i 0 w -__-__--_a

8. - @E1HISIS&TIVE PROCEDgEES, _ CQMDlILONS',

Page.18 .un_Mu1IAIIRES ' QUESTION' S.06 (1.00) Per.the instructions of AP-16, " Conduct of Operations - Operations Group" WHO can' authorize deviation from plant procedures and WHAT extenuating circumstances must the deviation. meet? QUESTION 8.07 (1.50) List the FIVE individuals, by title, who report to the Technical Support Center (TSC) following full activation of the TSC. . QUESTION 8.08 (1.50) What are the THREE purposes of EIP-3, " Radiation Exposure Estimation and Classification of Emergencies"? . QUESTION 8.09 (1.00) How can latching the Main Turbine affect Main Feedwater Pump (MFP) speed, as described in LEE 86-005 for FNP Unit 2, (Reactor Trip While Performing Trip Testing On The Main Turbine)? Include in your answer whether MFP speed will INCREASE, DECREASE, or REMAIN THE SAME during Main Turbine latching, AND STATE the reason for this effect. QUESTION 8.10 (1.00) What is the minimum recommendation requirements to off-s.ite agencies following a General Emergency (EIP-19, -26)? QUESTION 8.11 (1.00) During the performance of the Emergency Plan: a. When is initial accountability deemed complete? b. What is the time limit for completing initial accountability per i EIP-10? I (***** CATEGORY 8 CCNTINUED ON NEXT PAGE *****)

f 8.. '6DM1HIEIE&IlVE EBOCEggBES. CONDITIONS Page 19 6HQ_.kidlIAILOME l i QUESTION 8.12 (1.00) WHO is responsible for obtaining clearances and WHEN must a clearance be obtained (when equipment maintenance is required) according to AP-14, " Safety Clearance and Tagging"7 QUEST 10N-8.13 (1.00) The Unit is operating in Mode 1 at 6% power when the "A" RCP trips. In accordance with Technical Specifications, which one of the following is a correct response? I a, Restart the pump within 5 minutes or be in hot standby within the next 30 minutes. b. Be in hot standby within one hour. c. Return the loop to operable status prior to raising power above 10%. d. Immediately suspend all operations involving a reduction in boron concentration. QUESTION 8.14 (1.00) Using the accident classifications I, II, III, IV designate the classification number for the frequency of the occurrences listed below, a. Might reaconably occur once in lifetime of the plant. b. Might reasonably be expected to occur once per year. i i QUESTION 8.15 (2.00) i State the FOUR Technical Specification operability requirements associated with the accumulators in mode 1. Include applicable values and limits. I i l (***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)

Q. ADMINISTRATIVE _ESQCERQ8ES. CQMDITlGES Page 20 u oARQ_kLdlIATIONS l-l QUESTION 8.16 (1.00) During an ascension to full power, the shift chemist reports that the RWST boron concentration is at 1935 ppm. What action must be taken in accordance with Technical Specifications? l i l 1 I l 1 I (***** END OF CATEGORY 8 *****) (*********t END OF EXAMINATION **********)

4 EQUATION SHEET' ~. f = ma v = s/t 2 v = ag s = v,t + isac Cycle efficiency = E = mc a =-(vI-y')/t 2 -At KE = Irmy v A = AN A=Ae g = v, + a t o PE = mgh w = 8/t A =.in 2/tg = 0.693/tg W = vaP' q(eff) = (t, )(t ) s . t AE = 931Am ( ) =fnCAT I = 1 IX p Q = UAAT ' 9 -VX I=Ie ~ Pur = W, In -X/ M I=I lo o SUR(t), 'TVL = 1.3/u P=P 10 e /T HVL

• 0.693/v t

y=p o 'SUR = 26.06/T ~ T = 1.44 DT SCR = S/(1 - K,ff) /A ph

• ff SUR = 26 CR = S/(1 - K,ggg) 6 x

C eff)1 " 2(1 - K,ff)2 T " '(i*/p ) + {(f p)/A,gg ] ~ I o T = 1*/ (o - T) M " I/(I ~ Keff) = CR /CR0 g T = (5 - p)/ A,ggo g * (I ~ geff)0/II ~ Keff)1 8"I ~I)I eff eff = AK,gg/Keff SDM = (1 - K,gg)/K,gg [i*/TK,ff.] + [I/(1 + A,gf )] 1* = 1 x 10 seconds ~ p= T P = I$V/(3 x 10 0) xeff = 0.1 seconds A E = No I d; = I d22 g WATER PARAMETERS Id =Id g 22 2 1 gal. = 8.345 lbm R/hr = (0.5 CE)/d (meters) 2 1 gal. = 3.78 liters R/hr = 6 CE/d (g,,t) 1 ft = 7.48 gal. . MISCELLANEOUS CONVERSIONS 3 10 Density = 62.4 lbm/ft 1 Curie = 3.7 x 10 dps 1 Density = L gm/cm 1 kg = 2.21 lbm Heat of vapori:stion = 970 Etu/lbm 1 hp = 2.54 x 103 BTU /hr l 6 Heat of fusica = 144 Btu /lbm 1 Mw = 3.41 x 10 Btu /hr 1 Atm = 14,7 psi = 29.9 in. I'g. 1 Stu = 778 ft-lbf I ft. H O = 0,4333 lbf/in 1' inch = 2.54 cm 2 F = 9/5 C + 32 "C = 5/9 (*r - 32) __J

PIMS&/T @/77cw/ g REAGTOR COOLANT SYSTEM HOT STANDBY l LIMITING CONDITION FOR OPERATION 1 3.4.1.2 All three Reactor Coolant Loops listed below shall be QPERABLE and in operation when the rod control system is operational or at least two Reactor Coolant Loops listed below shall be OPERABLE with one Reactor Coolant Loop in oeration when the rod control system is disabled by opening the Reactor Trip Breakers or shutting down the rod drive motor / generator sets:* 1. Reactor Coolant Loop A and its associated steam generator and j Reactor Coolant pump, 2. Reactor Coolant Loop B and its associated steam generator and Reactor Coolant pump, 3. Reactor Coolant Loop C and its associated steam generator and Reactor Coolant' pump. APPLICABILITY: MODE 3 ACTION: a. With less than the above required Reactor Coolant loops OPERABLE, restore the required loops to OPERABLE status within 72 hours or be in HOT SHUTDOWN within the next 12 hours, I b. With less than three Reactor Coolant loops in operation and the rod control system operational, within 1 hour open the Reactor Trip Breakers or shut down the rod drive motor / generator sets. c. With no Reactor Coolant loops in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation. SURVEILLANCE REQUIREMENTS E 4.4.1.2.1 At least the above required Reactor Coolant pumps, if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability. 4.4.1.2.2 The required Reactor Coolant loop (s) shall be verified to be in operation and circulating Reactor Coolant at least once per 12 hours. 4.4.1.2.3 The required steam generator (s) shall be determined OPERABLE by verifying secondary side water level to be greater than or equal to 10% of wide range indication at least once per 12 hours. 'All Reactor Coolant pumps may be de-energized for up to 1 hour provided (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature. FARLEY-UNIT 1 3/4 4-2 AMENDMENT NO. 26,*65 \\

[ . REACTOR COOLANT SYSTEM r: NOT STAN08Y LIMITING CONDITION FOR OPERATION q l 3.4.1.2 a. At least two of the Reactor Coolant' loops listed below shall be OPERABLE: 1. Reactor Coolant Loop A and its associated steam generator and Reactor Coolant pump, 2. Reactor Coolant Loop B and its associated steam generator ). 'and Reactor Coolant pump, 3. Reactor Coolant Loop C and its associated steam generator and Reactor Coolant pump, b. At least one of the above Reactor Coolant loops shall be in l -operation.* i APPLICABILITY: MODE 3 ACTION: a. With less than the above required Reactor Coolant loops OPERABLE, restore the required loops to OPERABLE status within 72 hours or be in HOT SHUTDOWN within the next 12 hours. b. With no Reactor Coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant . System and immediately initiate corrective action to return the required coolant l yp to operation. SURVEILLANCE REQUIREMENTS 4.4.1.2.1 At least the above requir'ed' Reactor Coolant pumps, if not in 1 cperation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability. 4.4.1.2.2 At least one Reactor Coolant loop shall be verified to be in i cperation and circulating reactor coolant at least once per 12~ hours. l 4.4.1.2.3 The required steam generator (s) shall be determined OPERABLE by verifying secondary side water level to be greater than or equal to 10% of wide range indication at least once per 12 hours.

• All reactor coolant pumps may be de-energized for up to 1 hour provided 1

(1) no operations are permitted that would cause dilution of the reactor ( *. j coolant system boron concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature. FARLEY-UNIT 1 3/4 4-2 AMENDMENT NO. 26 b --_Q

'2 L _ TJ!EQBY QF NUCLEAR POWER EL&HI_QEEEATION, Page 21 ~T" ELpl.DLAND_IHEEMQDYNAMIcs ANSWh.R '5.01 (1.00) REFERENCE FNP 1987 License Operator Retraining Cycle 4, Review Material, p. HT-72/73 193009K107 .(KA's) ANSWER 5.02 (1.00) %b REFERENCE Steam Tables NUREG-1122 193003K117, 193008K115 .j FNP 1987 License Operator Retraining Cycle 4, Review Material,

p. HT-8/11 193008K115 193003K117 (KA's)

ANSWER 5.03 (2.00) a. The ratio of the heat flux that will cause DNB at s g pg t g tg# actual heat flux at that point in the reactor. OR adad N24 ax b. As pressure drops the coolant is closer to saturation con tsons [1.0). Thus the DNBR decreases [0.S]. . REFERENCE FNP 1987 License Operator Retraining Cycle 4, Review Material, p. HT-37 FNP 1987 License Retraining Objectives Cycle 4, OPS-309, item 6 193004K110 ..(KA's) ANSWER 5.04 (1.00) a. REFERENCE ) FNP Licensed Operator Retraining Cycle 4 Review Material p. HT 8-11. 193003K125 ..(KA's) i i (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) )

,5. ISEQRY_OF EHQLE&B_EQHEB_EL&MI_QEEEAIIGEu Page 23- .'[LQlDJt&HQ_ISEBMQDYMadlGS_ ANSWER-5.05 (2.00) Any four @ 0.5 each l 1. Heat Sink 1 2. Heat Source 3. Heat Sink higher than Heat Source i i Working Fluid 4. Piping connecting Heat Sink and Paat Source ihv3 f1dl-5. REFERENCE 'FNP 1987 License Operator Retraining Cycle 4, Review Material, p. HT-61 193008K122 193008K121 ..(KA's) ANSWER 5.06 .(1.00) a. .TRUE b. TRUE REFERENCE FNP 1987 License Operator Retraining Cycle 4, Review Material, p. HT-24 FNP 1987 License Retraining Objectives Cycle 4, OPS-309, item 13 & 19 i 191004K112 191004K106 191004K105 .(KA's) ANSWER 5.07 (1.00) a. less negative b. less negative REFERENCE FNP 1987 License Retrainine Objectives Cycle 4, OPS-313, item 13 192004K110 192004K109 ..(KA's) l l (***** CATEGORY 5 CONTINUED ON NEXT PAGE ****v)

'.5, ,TEEQBY.J2E_E!LC1EAE_.EQWER PLAHLQEEBATION. Page 23 FLUIDS adQ THEBBQQldadlQS t .t. ANSWER 5.08 (2.00) 1. Power Defect .2. Boron 3. Fission product poisons 4. ' Temperature 5. Rod worth [0.4 each] REFERENCE FNP.1987 License Retraining Objectives Cycle 4, OPS-313, item 19 192002K113 ..(KA's) ANSWER 5.09 (1.00) The clad to fuel gap decreases [0.2], increasing heat transfer capabilities [0.2] Thus resulting in lower fuel temperatures for same power [0.3]. The lower fuel temperature causes less negative reactivity to be added 64r&}s(, Therefore the doppler coefficient is less negative [0.3 ] . REFERENCE FNP 1987 License Retraining Objectives Cycle 4, OPS-313, item 15 192004K107 (KA's) ANSWER 5.10 (1.00) b REFERENCE FNP 1987 License Retraining Objectives Cycle 4, OPS-313, item 6 192003K102 (KA's) ANSWER 5.11 (1.00) d' (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l i )

) 5, THEORY OF NgghE&B_EQWEB_ELMI_QEER&ILON. Page 24 , oELHISL.MR_IBEBdQDINMICS REFERENCE FNP 1987' License Retraining' Objectives Cycle 4, OPS-313, item 5 192003K109 (KA's) j ~ ANSWER 5.12 (1.00) a. 2200 pcm +/- 50 pcm j b. 4600 pcm.+/- 50 pcm REFERENCE FNP 1987 License Retraining Objectives Cycle 4, OPS-313, item 10 192006K102-(KA's) ANSWER 5.13 (1.00) d REFERENCE FNP 1987 License Retraining Objectives Cycle 4, OPS-313, item 16 192004K107 ..(KA'c) ANSWER 5.14 (1.00) a. LESS NEGATIVE b. MORE NEGATIVE REFERENCE FNP 1987 License Operator Retraining Cycle 4, Review Material, p. THE-33 192005K114. 192005K110 ..(KA's) ANSWER 5.15 (1.00) a l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) ]

5, idEQBLQF NUCLE 6R POWEB_P1AL4I._QEERATION Page 25 t ..,. /EkJllf2t6t!D_IHERMODXtMMlQE REFERENCE FNP Technical Specifications, B 3/4 1-1 192002K114 192002K110 ..(KA's) ANSWER 5.16 (1.00) 'b 4 REFERENCE FNP 1987 License Retraining Objectives Cycle 4, OPS-313, item 8 192008K103 192008K102 192008K105 ..(KA's) ANSWER 5.17 (1.00) ) i d REFERENCE FNP 1987 License Retraining Objectives Cycle 4, OPS-313, item 10 1 192006K115 ..(KA's) l i I 1 (***** END OF CATEGORY 5 *****) )

6. PL&MI._SYSIMS DESIGN. COJTROL. AND INSTRUMEE"iATION Page 26 ANSWER. 6.01 (1.50) CR [0.5 each answer] a. Minimum back pressure of 15 psig on RCP #1 sea 1 by maintaining at least 4 18 psig in VCT. i b. Minimum of.200 paid maintained across #1 seal (OR) RCS pressure > 400 l psig c. Verify'open-loop 1A and 10 RHR suction imd disch'rgg valves prior toistarting any RCP. REFERENCE FNP 1987-License Retraining Objectives Cycle 1, OPS-52101D, item 5-003000K602 003000K104 ..(KA's) ANSWER 6.02 (1.50) [0,5 each] 1. 2/3 feed pump suction pressures (less than 300 psig) low. 2. 1/2 running condensate pumps trips with the third pump in auto. 3. With one pump running, take either of the other two from off to auto. REFERENCE FNP 1987 License Retraining Objectives Cycle 1, OPS-52104C, item 1 056000K601 ..(KA's) ANSWER 6.03 (1.50) a. Feedwater Stop Valve, b. Feedwater Stop Valve. c. Feedwater Regulating Valve. [0.5 each] l REFERENCE FNP 1987 License Retraining Objectives Cycle 1, OPS-52104C, item 2 059000K416 059000K409 059000K419 .(KA's) . ANSWER 6.04 (1.00) J a. Prevent Thermal Shock during pump starts. -{ b. Auxiliary Steam Condensate Tank. i i i j i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) I _------_____-----_--__-___J

6 '..jE,LANT SYSTEMS DESIGE. CONTROL', AHD INSTRUMENTATION Page 27' ~.

• n REFERENCE

-FNF 1987 License Retraining Objectives' Cycle 1, OPS-52102H, item 2 06:.000K111 ..(KA's) ANSWER 6.05 (1.00) 1. CCW~ surge tank vents auto close on high radiation. 2. CCW thermal' Barrier overpressurization protection OR [1/3 of 0.5 for each of the following] -- High pressure auto closure valve. -- Hi flow from thermal barrier. -- Piping design to withstand RCS pressure. REFERENCE FNP 1987 License Retraining Objectives Cycle 2, OPS-52102G, item 4 008030K402 008000K104 ..(KA's) ANSWER 6.06 (1,50) [5 @ 0.3 each] 1. Train's bypass breaker is closed. 2. INPUT ERROR INHIBIT switch in INHIBIT. 3. MULTIPLEXER TEST switch in INHIBIT. 4. LOGIC A switch out of 0FF. 5. PERMISSIVES switch out of 0FF. 6. MEMORIES switch out of 0FF. 7. MODE SELECTOR switch in TEST. . REFERENCE ~ FNP 1987 License Retraining Objectives Cycle 2, OPS-52201I, item 11 012000K610 012000K101 012000K604 ..(KA's) ) ANSWER C.07 (1.50) l 1. PZR level <= 15%. 2. LCV 459 or 460 close. 1 3. "T" signal. [0.5 each] i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) .. 1

6. _JLAUT SYSTEMS DESIGN, CONTROL _bND INSTRUMENTATION Page 28 t ~* REFERENCE 'FNP 1987 License Retraining Objectives Cycle 1, OPS-52101F, item 4 011000K404 011000K407 ..(KA's) ANSWER 6.08 (2.00) 1 .[4 required at 0.5 each]- ' 1. . Calculated peak fuel clad temperatu :a will not reach 2200 F. 2. Amount of hydrogen generated f rom tae fuel cladding that chemically reacts with water or steam will net exceed 1% of the total amount that could be generated-if all the fue' cladding in the core were to react. .3. Oxidation of the cladding will not exceed 17% of wall thickness. i 4. A coolable core geometry will be maintained. 5. Long term cooling can be provided. [0.5 each] REFERENCE i .FNP 1987 Licerise Retraining Objectives Cycle 1, OPS-52102B, item 4 006050SG05 . ( KA '~s ) ANSWER 6.09 (1.00) When the plate drops out it reduces the backpressure on the fan (load reduction becauce it is blowing a heavy wet vapcr mixture during an accident). REFERENCE FNP 1987 License. Retraining Objectives Cycle 3, OPS-521020, item 4 022000K400 (KA's) ANSWER 6.10 (1.50) 1. Turbine Trip. 2. Loss-of-load (C-7) 3. Steam prescure mode selected. [0.5 each] REFERENCE FNP Exam Questions from the 1987 Licensed Operator Retraining Program FNP 1987 License Retraining Objectives Cycle 1, OPS-52201G, item 5 041020K407 .(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

6'. J PLANT 'SYST& tie _DEElGEmCQHIRQIu_6ER_lHEIBEMENIAIlQE ' Page 29 H [ ,e' 1 E l . ANSWER 6;11 (1.00) l b REFERENCE l FNP Exam Questions from the 1987 Licensed Operator Retraining Program l 'FNP 1987 License Retraining Objectives Cycle 1, OPS-52201D, item 3 -01500GK401 015000K604 ..(KA's) ANSWER 6.12 (1.00) f c. REFERENCE FNP Exam Questions from the 1987 Licensed Operator Retraining Program FNP 1987 License Retraining Objectives Cycle 1, OPS-52201D, item 1 015000K601 ..(KA's) i 4 ANSWER 6,13 (1.00) d REFERENCE FNP Exam Questions from the 1987 Licensed Operator Retraining Program FNP 1987 License Retraining Objectives Cycle 2, OPS-56202, item 1 016000K403 ..(KA's) ' ANSWER 6.14 (1.00) 1. > Turbine Driven Auxiliary Feedwater (TDAFW) control panel. 2. TDAFW steam admission valves. 3. TDAFW speed controller. [0.33 each] REFERENCE FNP Exam Questiona from the 1987 Licensed Operator Eetraining Program FNP 1987 Licence Retraining Objectives Cycle 2, OPS-52103D, iten 2 062000K201 ..(KA's) I (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) .________________________-__s

/>. ' ELANT EX51Ed&_ des 21Gth. CONIROJ,u_AED INSTgt dEMIAIlQH Page 30 j i l i ANSWER 6.15 (1.00) a REFERENCE FNP Exam Questions from the 1987 Licensed Operator Retraining Program FNP 1987 License Retraining Objectives Cycle 1, OPS-52201E, item 5 001000K407 ..(KA's) i ANSWER 6.16 (1.00) 1. POSITIVE -- relief valve 2. NEGATIVE -- (two) vacuum breakers REFERENCE FNP 1987 License Retraining Objectives Cycle 3, OPS-521020, item 8 026020SG07 (KA's) l i i i ( v u t* END OF CATEGORY 6 *****) .___________-__-____-__a

7, PRQGEDJUEEE - NOEM&Lu_AHEQBM&LddEEGEECX Page 31 l:

• 6ND--RADIOLOGlG&L CONIBQL ANSWER 7.01 (1.00)-

During Auto actuation if' level falls below 17% [0.5]'until level exceeds 25%,(except in emergency conditions) [ 0. 5 ].. REFERENCE FNP Exam Questions from the 1987 Licensed Operator Retraining Program FNP 1987 License Retraining Objectives Cycle 1, OPS-52102H, item 3 061000K101 ..(KA's) ANSWER 7.02 (1.50) [0.5 each] 1. Acceptable power distribution limits are maintained. 2. Minimum Shutdown Margin is maintained. 3. Limit potential effects of rod misalignment on associated analysis. REFERENOE FNP 1987 License Retraining Objectives Cycle 3, UOP-1,2, item 5 0010SOSG05 ..(KA's) ANSWER 7.03 (1.00) b REFERENCE FNP-1-AOP-4.0 Loss of Reactor Coolant Flow 000017K103 ..(KA's) ' ANSWER 7.04 (1 00) 1. Attempt to stop rod motion by placing the Bank Selector switch in AUTO or MANUAL. 2. If rod motion does not stop then, trip the reactor and refer to EEP-0. l i (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****) i

L._2E9CEDUBES - EDEME_. ABNORMAL _EMEB9EM.G1 Page 32 2 ._MD JbDIOLOGLQhk_CQHTBQ.6 REFERENCE FNP Exam Questions from the 1987 Licensed Operator Retraining Program FNP-1-AOP-19.0, Malfunction of Rod Control 000001SG11' ..(KA's) ANSWER 7.05 (1.50) [0.5 each] '1. Raise RCS pressure. 2. Start a RCP. 3. Open Head Vents. REFERENCE FNP 1987 License Retraining Objectives Cycle 3, OPS-52302, item 5 000009K321 000009K310 000009K326 ..(KA's) 4 ANSWER 7.06 (2.00) a.

1. When directed by EEP-0 (at step 29).

2. Any time EEP-0 directs the operator to a different procedure. b. During a loss of All AC Power, ECP 0.0 REFERENCE FNP-1986 License Retraining Objectives Cycle 3, Emergency Response Procedures, item 3 000009K321 (KA's) ANSWER 7.07 (1.50) a. Immediately exit the procedure in effect and go to FRP directed by red i path [0.5]. l b. 1, When directed by the red path procedure [0.5]. 2. Exit for red path of a higher priority [0.b]. REFERENCE I FNP 1987 License Retraining Objectives Cycle 3, Emergency Response Procedures, item 5 000009K321 ..(KA's) l (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****) I j

l 7; RROCEDURES -_HQBM&Lu_&3 NORMAL &_EMERg&NCY Page 33 1 4U2 RADIOLQGIG&L CONTROL-ANSWER. 7.08 (1.00) d ) i REFERENCE ) I FNP 1987 License Retraining Objectives Cycle 3, Emergency Response I Procedures, item 9 FNP-1-ECP-0.0, Loss of All AC Power 000055K302 ..(KA's) !l i ANSWER 7.09 (2.00) .) I 1. Start Boric Acid Transfer pump (1A or 1B). 2. Open Emergency borate to charging pump valve (1-CVC-MOV-8104). 3. Verify ene charging pump running. 4. Verify charging pump suction header isolation valves are open (1-CVC-MOV-8131A or B). REFERENCE FNP Classroom Objectives, License Training, II H, Reactor Makeup Control and Chemical Addition System. FNP-1-AOP-27.0, Emergency Boration U00024K302 .(KA's) / ANSWER ~s, -~. 7.10 (1.00) h a REFERENCE t FNP Exam Questions from the 1987 Licensed Operator Retraining Progran FNP 1987 License Retraining Objectives Cycle 2, OPS-52102G, item 7 000026K303 (KA's) ANSWER 7.11 (1.50) 1. krif:> SI e t"ated. Fif 20# ~ 2. Use adverse Containment condition numbers during procedure. 3. Shift AFW pump suction to service water. (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****) ._---_____-_-_____n

.E..PROCEpl!RES - NORM &Lu_ABEQEM6k. EMEBGENCY Page 34 /ANp $6DIOLOGE6k_GQHIRQL L o REFERENCE FNP Exam Questions from the 1987 Licensed Operator Retraining Program FNP 1987 License Retraining Objectives Cycle 3, OPS-52302, item 2 FNP-1~-EEP-0 foldout page 000007K301 ..(KA's) . ANSWER 7.12 (1.00) (Unless specifically told to hold), proceed to the. next Action /Respor.se item REFERENCE FNP 1986 License Retraining Objectives, Emergency Response Procedures, item 6 000007K301 ..(KA's) I ANSWER 7.13 (2.00) VerifyreactorTrip.kndicatedbyallturbine stopvalvesclosed) 1. Verify Turbine trip 2. 3. Verify all available auxiliary feedwater pumps running. 4. Determine if emergency boration is required. REFERENCE FNP 1986 License Retraining Objectives, Emergency Response Procedures, item 8 000029K312 .(KA's) ANSWER .7.14 (1.00) e REFERENCE FNP 1987 License Retraining Objectives Cycle 1, OPS-52104C, item 1 & 8 000051K202 (KA'c) (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)

'7. 'PRQGEQGBES -'_NORMAku&EHQR_ti&LLEMEEGENGY Page 35 ,v&ND RADIOLOG K6L_CQHIEQL ANSWER 7.15 (1.00) Any TWO of the following THREE @ 0.5 each 1. Two successive starts from ambient temperature. 2. One' start from rated temperature. 3. Subsequent starts: allow 30 minutes running time or 60 minutes idle time between starts. REFERENCE FNP 1987. License Retraining Objectives Cycle 1, OPS-52102H, item 4 FNP-1-SOP-22.0 Auxiliary Feedwater System 061000K406 ..(KA's) i (***** END OF CATEGORY 7

• • • 4*)

4 __________w

18. ,ADMINISTRAllEE_EBOCEDUBES. CONDITIQNS. Page 36 ofED_hldlI&TIONS i ANSWER 8.01 (1.00) Ensures sufficient heat removal capability in the event of a bank withdrawal accident, (this situation requires all 3 RCP's to be operating in modes 1, 2, and 3.) REFERENCE FNP 1987 License Retraining Objectives Cycle 1, OPS-52101F, item 6 003000SG05 003000K505 003000K501 ..(KA's) ] ANSWER 8.02 (2.00) a. 1 b. 1 c. 3 d. 3 i e 1 REFERENCE FNP-0-AP-16, pp. 27 and 28 FNP 1987 License Retraining Objectives Cycle 1, OPS-52301B, item 2 191001A110 (KA's) i ANSWER 8.03 (2.00) a. Mandatory -- LCO becomes effective due to circumstances.beyond the shift supervisor's control. (0.5) b. Administrative -- LCO becomas effective when a piece of equipment is removed from service that is not required in the present plant mode but is required in a higher mode, [0.75] or if it reduces the redundancy but is less l than Technical Spec requirements [0.75]. (1.5) REFERENCE FNP 1987 License Retraining Objectives Cycle 1, OPS-52301B, item 6 191001K105 (KA'c) j l l (***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)

y

8. 'I'ARMlHIEIR&IlYE_EROCEDQRES, CONDITIONS.

Page 37 .J6tJp_ kid 1IATIONE: ANSWER 8.04 (1.00)

All control room areas which fall within the TWO security access doors.

. REFERENCE FNP 1987 License Retraining Objectives Cycle 1, OPS-52301B, item 3 ~ y 'FNP-0-AP-16, figure 4 note. 191001K110 ..(KA's) ANSWER 8.05 (1.00). 1. Night Orders Book. 2 '. Operations Standing Policies Book. .l ' REFERENCE FNP 1987 License Retraining Objectives Cycle 1, OPS-52301B, item 6 191001K101 ..(KA's) ANSWER 8.06 (1.00) 1. Plant operator or licensed supervisory personnel. [0.5] 2. Due to extenuating circumstances -- adherence to procedure would create and undue hazard to personnel, equipment, or health and safety of the general public. [0.5] REFERENCE FNP 1987 License Retraining Objectives Cycle 1, OPS-52301B, item 4 JS1001K101 ..(KA's) ANSWER 8.07 (1.50) Emergency director Operations manager Maintenance manager Technical manager Health Physica manager [0.3 each] (***** CATEGORY 8 CONTINUED ON NEXT PAGE *** ** ) {

l ,8. ADMINISTRATIVE PROCEDURES. CONDITIONS. Page 38 ibHDshldITAT19ES { i REFERENCE FNP 1987 License Retraining Objectives Cycle 3, OPS-565, item 1 191001K102 ..(KA's) l i ANSWER 8.08 (1.50) 1. Rapid projection of off-site radiation exposure as a result of release of radioactive material. 2. Provide a basis for classifying emergencies. i 3. Provide guidance for determining protective action recommendations. REFERENCE FNP 1987 License Retraining Objectives Cycle 3, OPS-565, item 7 191001K101 ..(KA's) l ANSWER 8.09 (1.00) /1 Decrease [0.5], because latching the Main Turbine can cause significant' drops in EH fluid pressure LO.5]. REFERENCE LER 86-005 for FNP Unit 2. FNP-SOP-28.1 precaution 3.33. 045010K110 045010K102 .(KA's) . ANSWER 8.10 (1.00) i Recommend immediate evacuation or shelter for all of the general pcpualtior< within a two-mile radius of FNP and 5 miles downwind of FNP. REFERENCE I FNP 1987 License Retraining Objectives Cycle 3, OPS-563, item 21 191001K101 (KA's) (***** CATEGORY 8 UONTINUED ON NEXT PAGE *****)

f f . ;Q gfl,- C6Dt11El&IEAllm1EEIEEWiFL. OOLIPl.I2;1hL. Page 39 i vDR_1HiITATIOff,j$ l 3 f-j3 (. .e ,y ); s-i v-f ' +, !, ( a 4 f e \\ 1 / ANSWER 8.11 (1.00) <J / .4 s Upon repcNting of the total'caumfer of, missing personnel by. name in the a. protected ayea to the emergency'.dir~4ctpr. b. 30 mimte:S' r ['je (c: e

• t

< / .A REFERENCE ' s /,c / } ,,v FNP-158hLicense Retraining Objec';'~ves Cycle 3, OPS-565, item 18 19400yA116 ..(KA's) ',f l l 3, 1 ANSWER. 8.12 (1.00) o G 4i f 1. La#ch individudl'in, charge of a task requiring clearance (for safe excuation of-work) 2*:[hustobtain61earancepriortoallowingworktocommence. [0,5 each] j REFERENCE FNP 1987 License Retraining Objectives Cycle 1, AP-14, item 2 191001K107 j ..(KA's) E i ANSWER 8.13 (1.00) g' b REFER $NCE c FNP Exam Questions from the 1987 Licensed Operator Retraining Program \\ FNP 1987 Licence Retraining Objectives Cycle 1, OPS-52101F, item 6 191001K105 ..(KA's) 1 1 ANSWER 8.14 (1.00) a. III i b. II (***** CATEGORY 8 CONTINUED ON NEXT PAGE *****) J

8. JDMINISIBallVE PHQQERGBEL_GQMRIIlQML Page 40 dalf2_hlMlI6IlQUE i REFERENCE FNP Exam Questions from the 1987 Licensed Operator Retraining Program l FNP,1987 Licence Retraining Objectives Cycle 2, OPS-52201I, item 6 j 000011SG00 ..(KA's) ANSWER 8.15 (2.00) 1 1. Isolation valve open. 31.1*/, 2. Volume between 7555 (s4%) and 7780 (58%) gals. J 3. Boron concentration 1900-2200 ppm. 4. Nitrogen cover pressure between 601 and 649 psig. [0.5 each] REFERENCE FNP Exam Questions from the 1987 Licensed Operator Retraining Program l FNP 1987 Licence Retraining Objectives Cycle 3, OPS-52102B, item 7 191001K105 ..(KA'c) i ANSWER 8.16 (1.00) Restore the RWST to operable status within one hour. (or be in hot standby within the next 6 hours and cold chutdown within the following 30 hours.) REFERENCE FNP Exam Questions from the 1987 Licensed Operator Retraining Program FNP 1987 Licence Retraining Objectives Cycle 3, OPS-52102B, item 7 l 191001K105 (KA's) (***** END OF CATEGORY 8

• • • • t)

(********** END OF EXAMINATION **********)

U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR REQUALIFICATION EXAMINATION l FACILITY: FARLEY 1&2 REACTOR TYPE: PWR-WEC3 I DATE ADMINISTERED: 87/06/22 EXAMINER: dEEREN. N. CANDIDATE i INSTRUCIlQH3 TO CANDIDATE: Read the attached instruction page carefully. This examination replaces the current cycle facility administered requalification examination. Retraining requirements for failure of this examination are the same as for failure of a requalification examination prepared and administered by your. training staff. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% g 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 i CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 25.00 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW 20.00 25.0q 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS 20.00 25.00 3. INSTRUMENTS AND CONTROLS i 20.00 25.00 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 80.00 Totals Final Grade All work done on this examination is my own. I have neither given nor received aid. Candidate's Signature I 1 L_ _---- - --_

s.

.y 'NBC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS Daring the administration of this examination the following rules apply: 1. Cheating on the examination means an automatic denial of your applicatio.. and could result in more severe penalties. 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid'even the appearance or possibility of cheating. 3. Use black ink or dark pencil only to facilitate legible reproductions. 4. Print your name in the blank provided on the cover sheet of the examination. 5. Fill in the date on the cover sheet of the examination (if necessary). 6. Use only the paper provided for answers. '7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet. 8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet. 9. Number each answer as to category and number, for example, 1.4, 6.3.

10. Skip at least three lines between each answer.

'11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table,

12. Use abbreviations only-if they are commonly used in facility literature.

13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.'

15. Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the examiner only.

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.

This must be done after the examination has been completed. I

18.nWhen you' complete you'r examination, you shall: j La. Assemble your examination as follows: f ~ (1) -Exam questions on top. (2) ' Exam aids - figures, tables, etc.. (3) Answer pages including figures which are part of the answer. b. Turn in your copy of the examination and all pages used to answer the examination questions. c. Turn in all1 scrap paper and the balance of the paper that.you did H not use for' answering the questions. ~d. ' Leave the examination area, as defined by the examiner. If'after leaving, you are found in this. area while the examination is still in progress,.your license may be denied or revoked. L 1 l 1 l i

1 '..PR'INCIELE.S OF NOCLEAR-POWER PLANT OPERATION. Page 4 THERMODYNAMICS. HEAT TRANSFER _AND FLUID FLOW j QUESTION. 1.01' (1.00) Multiple Choice ' Choose the CORRECT. definition of R6ff: a. The fractional-change in neutron population per generation. I l b. The number of neutrons in one generation divided by the number of 1 neutrons in the previous generation for a finite sized reactor. { l c. The number of neutrons in one. generation divided by the' number of neutrons in the previous generation for an infinite' reactor. d. The number of fast neutrons produced by fissions of all energies '4 divided by the number of neutrons absorbed in the fuel. -QUESTION 1.02 (1.00) State how.each of.the following will affect the value of control bank D differential rod worth, assuming all other conditions remain unchanged. Limit your answer to-INCREASE, DECREASE, or NO EFFECT. l a. Control bank:D rod position is changed frcm 150 steps withdrawn to i I ~220 steps withdrawn. b. Moderator temperature DECREASES. l l l i (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) l ______________j

it.. PRINCIPLES OF-NUCLEAR POWER PLANT ^ OPERATION. 'Page.5 THERMODYNAMICS. HEAT' TRANSFER AND FLUID FLOW x + f ' QUESTION-1.03 ( 1L. 00 ) . Multiple Choice -During:a reactor tripJrecovery, theLinitial 1/M data point was11.0. After- =a.1-hour delay, rod withdrawal wasLeommenced. Upon stopping rod withdrawal ~ 'to take 1/M data, you find that the second 1/M point is 1.1.

Which-

.of:the-following. explains this' increase in the 1/M value? a, This'is'not possible, the RO must have made an e,rror when taking Ecount: rate data. b. The' buildup of Xenon during the 1-hour delay added more negative reactivity than'the rod withdrawal had added in positive reactivity. c. The source-detector geometry is incorrect., j ' d.' An inadvertent dilution is in progress. GUESTION' 1.04 (1.00) Multiple: Choice: During a startup it.was determined that Keff was equal'to 0.9 when_the Source Range (SR) instrument was reading 50 cps. Whatwou?.d~thesource/(be. -seading if rods were withdrawn to bring Keff equal to 0.957 Assume BOL p/- conditions. rd I MN a. 75 cps b. 100 cps c. 125 eps 'l d. 150 cps i (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

ci, P91NCIPLES OF NUCLEAR POWER PLANT OPERATIQN. Page 6 p LIHEBM0 DYNAMICS. HEAT TRANSFER AND FLUID FLOU 1 l i -QUESTION 1".05 (1.00) d Multiple Choice What11s the startup rate if power increases from 3000 cps to 8000 cps in- . twenty. seconds? '(Choose the MOST CORRECT answer.) a. 0.4 DPM-b. 0.7 DPM c. 1.0 DPM d. 1.3 DPM -QUESTION 1.06 (1.00) i State how each of the following will affect the value of differential Boron worth, acsuming all other conditions remain unchanged. Limit your answer to LESS NEGATIVE, MORE. NEGATIVE, or NO EFFECT. 3 i c. Reactor coolant temperature decreases, b. Boron concentration increases. . QUESTION 1.07 (1.00) State how each of the following will affect the value of shutdown margin, assuming all other conditio.ns remain unchanged. Limit your answer to INCREASE, DECREASE, or NO EFFECT. a. Reactor coolant temperature decreases. b. Xenon concentration increases. i QUESTION 1.08 (0.50) True or False? 1 The occurence of clad creep causes the doppler-only power coefficient to become MORE NEGATIVE. i 1 a I (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) _-_--______________D

EE1HC_%PLES OF NUCLEAR POWER PLANT OPEBATION. Page 7 li_, THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW j i l QUESTION 1.09 (1.00) For each of the conditions listed below, state whether the moderator temperature coefficient becomes MORE NEGATIVE, LESS NEGATIVE, or REMAINS THE SAME. Assume all other conditions are unchanged. a. Control bank D is withdrawn. b. Core age increases. QUESTION 1.10 (1.00) Multiple Choice Which one of the following statements is correct? ~ a. With all other conditions constant, the reactor responds MORE QUICKLY to a given reactivity change at EOL than at BOL, because the value of Beta-bar effective is GREATER. b. With all other conditions constant, the reactor responds LESS QUICKLY to a given reactivity change at EOL than at BOL, because the value of Beta-bar effective is GREATER. i c. With all other conditions constant, the reactor responds MORE QUICKLY to a given reactivity change at EOL than at BOL, because l the value of Beta-bar effective is LOWER. ~ d. With all other conditions constant, the reactor responds LESS QUICKLY to a given reactivity change at EOL than at BOL, because the value of Beta-bar effective is LOWER. l i \\ I l 1 (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) l a

1. PRINCIPLES OF' NUCLEAR PQWER PLANT OPERATION, Page 8 'IHEBMODYNAMICS ; BEAT TRANSFER AND FLUID FLOU -QUESTION 1.11 (1.00)' ~ Multiple Choice = Which one ofLthe following statements MOST CLOSELY describes the value of Xenon' reactivity following a reactor trip from 100% equilibrium conditions? a. Approximately six hours after the trip, Xenon reactivity will be approximately 170% of the equilibrium value, b. Approximately six hours after the trip, Xenon reactivity will be approximately 190% of the equilibrium value, c. Approximately nine hours after the trip, Xenon reactivity will be approximately 170% of the equilibrium value, d. Approximately nine hours after the trip, Xenon reactivity will be approximately 190% of the equilibrium value, I QUESTION 1.12 (1.00) n Concerning equilibrium Samarium-149 (Sm) reactivity, which of the following. statements is correct? 50% equilibrium Sm reactivity is: a. one-quarter of 100% equilibrium Sm reactivity. 1 b. one-half of 100% equilibrium Sm reactivity, c. three-quarters of 100% equilibrium Sm reactivity. d. equal to 100% equilibrium Sm reactivity. t L I p i (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) \\^ L \\

r__ _ li PRINCIPLES OF NUCLFAR POWER PLANT OPERATION. Paga 9 ' THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW QUESTION 1.13 (1.50) Multiple Choice Which THREE of the following statements are TRUE, with regard to centrifugal pump cavitation? a. Assuming proper valve lineup, cavitation can be diagnosed from control board indications of pump discharge pressure, pump suction pressure, a'nd pump flow, b. The point where cavitation is most likely to begin is the high-pressure discharge area of the pump. l c. If available net positive suction head (NPSH) is positive, cavitation will not occur. d. The system fluid velocity has no effect on the probability of pump cavitation. l 5 e. Undesirable consequences of cavitation may include erosion and pitting of the pump impeller, reduced flow rate b'eing maintained by the pump, and damage from excessive vibration. QUESTION 1.14 -(1.50) Multiple Choice What is the specific volume of saturated steam with a quality of 85% and c temperature of 500F? (Choose the MOST CORRECT answer.) a. 0.58 ft3/lbm b. 0.67 ft3/lbm c. 0.93 ft3/lbm d. 1.16 ft3/lbm (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

t I h PRINCIPLES OF NUCLEAR POWER PLANT'OPERATIONi -Pago 10 .THEI6MODYN AMICS. HEAT TRANSFER AND FLUID FLOW I 'j -QUESTION 1.15 (2;00) State'how an INCREASE in each of the following parameters affects the . Departure from Nucleate Boiling Ratio-(DNBR). Limit your answer to INCREASE, DECREASE, or NO.EFFECT. i a. Coolant temperature b. Coolant pressure i c. Coolant flow d. Reactor power- -; QUESTION 1.16 (0.50) t True or False? Concerning Pressurized Thermal Shock (PTS) events, only those transients which. involve a rapid cooldown of the reactor coolant system are capable of subjecting the reactor pressure vessel to a thermal. shock. -QUESTION 1.17 (1.00) Multiple Choice 'Which ONE of the'following statements is CORRECT concerning a secondary l calorimetric (procedure STP109)7 I a. If feedwater temperature is read erroneously high, then the calculated reactor power will be higher than actual, b. The calorimetric equation does not take into consideration the heat added by the reactor coolant pumps, or the heat lost to the containment atmosphere (ambient losses), because these values are nearly equal and their net effect is negligible, i c. Mass flow rate of the secondary system is determined by totaling the average steam flows from each of the three steam generators. d. The results of the secondary calorimetric may be used as the basis r for calibration of the power range nuclear instrumentation. (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

71. EPRINCIPLES OF NUCLEAR POWER' PLANT ~ OPERATION. Page:11'

THERMODYNAMICS. HEAT TRANSFER'AND FLUID FLOW-

?;(QUESTION 1.18 . ( 1. 00 ) : ' Multiple Choice I . Indicate which item below does NOT ENSURE that the Enthalpy Rise Hot ~ w N ! Channel Factor:(F Delta-H), remains-within prescribed limits: Control rods in' group 1 move together withih +/- 12 steps.. a. 4 b. Tavg vs.. Tref are.kept matched to'within 5.0F. y i i .c. Axial flux differences (AFD) is maintained.within-limits. l "d. Control. rods are sequenced with overlapping. groups. ^ QUESTION' 1'.19 (1.00) Multiple Choice

Which ONE of the foll'owing items. is NOT a' requirement in-order to -

establish natural ~ circulation? a.. Heat source b.. Heat sink c. . Heat source higher than heat sink d. ! Working fluid-l [ (***** END OF CATEGORY 1 *****)

12: 'PL&NT DESIGN INCLUDING' SAFETY'AND EMEPGENCY-Pago 12) EXEICME-1 i QUESTION! 2.01' (2.00) ' State she~ purpose of each of the following Reactor Coolant Pump (RCP). l components. For each case, include the circumstance-under which the i purposeLwill be fulfilled. ~ fa. JFlywheel b. oThermal Barrier" Heat Exchanger . QUESTION ~

2.02 (0.50)

True or False? Component Cooling Water-(CCW) pump B, the swing pump, will automatically start on-a safety injection signal if it is selected to REMOTE on the hot shutdown. panel, if.its control switch is in AUTO on"the Main Control . Board, and if EITHER one of the dedicated CCW pumps (A or C) has tripped on overload. QUESTION 2.03 (1.00) a. What is.the purpose of the Turbine Driven Auxiliary Feedwater Pump steam supply warmup.line?. b.- Where-does the condensed steam from the warmup line' drain? ! ' QUESTION 2.04 (1.00) State the TWO sources of makeup water to the Component Cooling Water-(CCW) System surge tank. l QUESTION 2.05 (1.00) How is the containment cooling system assisted during accident conditions .by the function of' dropout plates? y l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

P.LANT E IGN I CLUDING SAFET'Y AND MERGENCY-Page'13 ' SYSTEMS . QUESTION' 2'.06 '(1.00) i l List.the? loads supplied by the 120 VAC Uninterruptible Power Supply (UPS). L l QUESTION 2,07 (1.50) The following pertain to the Temperature Divert Valve (TCV-143)-.in'the CVCS: State the'TWO high temperature signals which will cause automatic a. action. (Setpoints not required.) b. -State.the failure position on loss of air. QUESTION 2.08 .(1.00) State the purpose of the automatic-closure feature of-the turbine build-l ing service water isolation valve (MOV-514 -517.) on high flow. . QUESTION 2.09 (1.00) How is overpressurisation of the heat exchangers which are supplied by l the Service Water System prevented? 1 -QUESTION 2.10 (2.50) List FIVE loads supplied by the ESF/ primary loops of the Component Cooling Water System. l l QUESTICN 2.11-(2.00) What are the FOUR major accidents that the ECCS is designed to mitigate? l 1 l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) 1

2 i-PQFl_ DESIGN' INCLUDING SAFETY AND EMERGENCY Pagef14 ' SYS.TEliS i n QUESTION' 2.12-(1.50) What THREE changes to the containment fan coolers take place upon the - i I . receipt of a safety injection sign.;17 Include any applicable control . switch positions which must be in effect for these actions to occur. ] QUESTION '2.13 (1.00) tiultiple Choice i 'Which of.the following is NOT cooled by the reactor cavity cooling system? a, ~ Primary shield, b. Reactor vessel cold leg nozzle supports. c. Incore instruments penetration area, d. Nuclear instrumentation detectors. QUESTION 2.14 (2.00) 'What are FOUR sources of hydrogen in the contairement structure following a Design Basis Accident? -QUESTION 2.15 (1.00) What will cause a rod control non-urgent failure alarm? l l (*****.END OF CATEGORY 2 *****)

!.3; INSTRUMENTS AND CCNTROLS Page 15- -QUEhTION 3.01-(1.50) y State the THREE conditions that will cause a condensate pump to auto start. Include coincidence as applicable. QUESTION' 3.02 (1.50) Indicate whether the' Main Feedwater Stop Valve,.Feedwater Regulating Valve or the Feedwater Regulating Valve Bypasses is described by each statement below. a. Protects against S/G blowdown in event of a pipe rupture. b. Auto close on trip of'both main feed pumps. c. Controls. water. level in S/G and receives auto signal from Steam Generator Water Level Control System.

QUESTION 3.03 (1.50) l List FIVE of seven conditions that will cause a Solid State Protection System - general warning alarm.tx) occur.

Disregard loss of DC power. ~ . QUESTION 3.04 (1.50) List ALL conditions that will directly cause an AUTO CLOSE of the . Letdown Orifice-Isolation Valves, OTHER.THAN a loss of motive force. 1 . QUESTION 3.05. (1.50) State the THREE arming signals for the Steam Dumps. Assume the C-9 (condenser available) interlock is satisfied. (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

Fy ' 3.' - ' INSTRUMENTS AND CONTROLS-Page 16. 1-, i. QUESTION 3.06 (1.00) Multiple. Choice Which one of the following is an indication of an. Intermediate Range. Channel being slightly (5 - 10 % voltage error) undercompensated? a. Automatic energizing of.the source range when the first intermediate range channel-drops below the P-6 setpoint. b. . Actual neutron level falls into the source range without' indication. c. Indication remains above 10E5 cps in the source range on both channels. d. Automatic energising of the source range when the-P-10 interlock was cleared on both channels. TQUESTION 3.07 (1.00)~ Multiple Choice The type of detector used for the Gamma-Metrics system is a/an: a. G-M tube, b. BF3 proportional counter. c. Proportional fission chamber. d. Uncompensated ion chamber. j l f 1 (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

"ds INSTRUMENTS'AND: CONTROLS-Page 17 l I i 'UESTION 3.08 (1.00) Q a ' Multiple Choice Which of.the.below indicates the response of~Tavg and Delta T'if a control channel Tc failed HIGH7 ) a. Tavg decreases, Delta T decreases. b. 'Tavgfinereases', Delta T increases. c.

Tavg decreases, Delta T increases.

d. Tavg increases, Delta T. decreases. 1 QUESTION 3.09

(1.00)

Multiple Choice _ Rod motion will be stopped on a logic cabinet urgent failure by: .a. inhibiting the-pulser. b. opening contacts-from the BOU. o

c.. freezing the slave cyclers, d.

-providing simultaneous current orders to stationary and movable grippers. l ' QUESTION 3.10 (1.50) List all feedwater isolation signals,' including setpoints and coincidences as applicable. ' QUESTION 3.11 (2.00) zList all the signals that will automatically start the Motor Driven . Auxiliary Feedwater Pumps. Setpot.ats and coincidence not required. i (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

' 3 INSTRUMENTS ~AND CONTROLS Paga 18 QUESTIONi 3.12 (1.00) t . Multiple Choice l ' Which one of the:following is NOT a condition-that-must be met to start a circulating. water pump. ?a. LOSP sequencer must be reset.

b.

.Its discharge MOV must be closed.

c.

Wet pit level > 151'. d. No. differential current protection signal present. QUESTION 3.13 (1.00) What TWO automatic-open signals are provided to the accumulator isolation valves to ensure that they are open, or will open, when needed .in mode 1. QUESTION 3.14 (1.00) e Multiple Choice Concerning the SGWLC system, the reason that the steam flow input is compensated and the feedwater flow input is uncompensated is because: a. Different flow restrictors are used to develop the Delta P signals. b. The steam flow delta P signal is proportional to volumetric flow rate and'not' mass flow rate, unless compensated. c. The feedwater flow input signal is derived from a Delta P signal. d. Steam is non-compressible while feedwater is compressible. - QUESTION 3.15 (2.00) Describe the TWO features associated with the steam dump pressure 1 controller that prevents " controller windup". l (***** END OF CATEGORY 3 *****) i u________.____.______

'P4,-' PROCEDURES - NORMAL ABNORMAL. EMERGENCY 'Paga 19' AND. RADIOLOGICAL CONTROL LQUESTION 4.01 (3.00) Concerning FNP-0-AP-14," Safety Clearance and Tagging": 1. ' State the purpose of HOLD TAGS. (1.00) 2. Stat'e the purpose of CAUTION TAGS. (1.00) 1 3. True or. False? a. Caution tags are utilised for abnormal conditions only. (0.50) { i I -b. A hold. tag placed on an electrical circuit breaker, or on the circuit breaker cubicle door, indicates that the circuit breaker is within the boundaries of the clearance. (0.50)

QUESTION 4.02-(0.50)

True.or False?- .The reactor.may be started up, but the turbine may NOT be loaded, if les's than'three reactor coolant pumps are in operation. i QUESTION 4.03 (1.00) Why must all shutdown rods be in the fully withdrawn position'before the reactor may be taken critical? ) QUESTION 4.04 (1.00) State the purpose of the precaution included in the FNP startup procedures which states: "IF the source range count rate increases by a factor of two during any step involving Boron dilution, THEN the dilution shall be stopped immediately AND suspended until core reactivity has been evaluated by the Shift Supervisor." (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) t

iz,,EROCEDURES - NORMAL. ABNORMAL, EMERGENCY Paga 20 AND RADIOLOGICAL CONTROL t j QUESTION 4.05 (2.00) Match the appropriate reason in Column B with the precaution to which it applies in Column A. NOTE: It may not be necessary to use all of the responses listed in Column B. X Column A Column B l 1. Reactor Coolant Pump (RCP) seal a. Prevents damage to the RCP-water injection flow of 6 GPM OR motor bearings. Component Cooling Water (CCW) to the RCP thermal barrier must be continuously supplied.when RCS b. Ensures the #1 seal is not I temperature exceeds 150F. riding on the runner. 2. Whenever a RCP is running, c. Ensures cooling is provided maintain a pressure of at least for the lower radial bearing 18 psig in the Volume Control and the seal package. Tank (VCT). d. Provides overpressure j 3. For RCP operations, a minimum protection. pressure differential of 200 paid must be maintained across e. Ensures adequate seal water RCP #1 seals. flow to the #2 seal. 4. If CCW flow to the RCP motor bearing oil coolers is lost, f. Ensures proper #1 seal pump operation may be continued leakoff flow is maintained. until the motor upper or lower bearing temperature reaches 200F. QUESTION 4.06 (2.00) Assume the reactor is at power. According to SOP-1.1 Reactor Coolant System, Precaution 3.12, what TWO actions must be taken if the

1. 1 seal for a reactor coolant pump has failed, as evidenced by excessive #1 seal i

leakoff flow (>5 GPM). INCLUDE time limits. (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) )

L (4,- PROCEDURES NORMAL._ABN RMAL. EMERGENCY-

Paga 21 c

• AND. RADIOLOGICAL _ CONTROL L

l -QUESTION-4.07. J(0.50)- -True or False?- TA'uxiliary feedwater-flow to any steam generator must be limited to'150 GPM maximum;any time.that steam generator's level drops belowL25%. In an' emergency, however; this. flow limit may be drep;cd. Obsr arc /ed ' QUESTION-4.08 (2.00) Assume:the reactor is operating at power with the control' rods in automatic. According to FNP-1-AOP-19.0 " Malfunction of Rod Control' l System": j a' 10aat are 'the TWO.immediate operator actions for a continuous bank insertion?' b. What are the'TWO immediate operator actions for a single droppe'd rod? QUESTION 4.09 (2.00)

AccordingtoNNP-0-EIP-14,."Re-entryProcedures", list the TWO-emergency whole body exposure limits, AND state-the conditions for which each is used.-

QUESTION 4.10 (2.00) In accordance with FNP-1-EEP-0 " Reactor Trip or Safety Injection", what are-the~FOUR symptoms of a Safety Injection? ]

QUESTION 4.11 (2.00)

State the FOUR steps required to perform an emergency boration, as i identified in FNP-1-AOP-27.0, " Emergency Boration." NOTE: Valves may'

beTidentified either by Name (description), or Number.

l j l (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) .i ___ 0

14t ' PROCEDURES - NORMAL'.-ABNORMAL'. EMERGENCY Page 22-AND. RADIOLOGICAL CONTROL {m. LQUESTION 4.12- -(1.00) Multiple. Choice-Which of theLfollowing is NOT an immediate operator. action for ECP-0.0, "LossJof All'AC Power".7 a. Check total auxiliary feedwater flow >1377 gpm. b. Verify reactor trip-and bypass breakers open. I c.. Verify turbine tripped, d. Restore" power to any AC emergency bus. QUESTION 4.13 - ( 1. 00 )1 m Multiple Choice-1The' control room operatorsJare performing FNP-1-FRP-C.2, " Response to Degraded Core-Cooling",.in response to an orange path condition shown 1 on1the cor'e cooling. Critical Safety Function.(CSF).~ status tree.. Which nONE of the following statements is CORRECT with regard to; transitions-out of this procedure?- ,Theoperatorsmustleave.thisprocedurebIforecompletionand-1 a.. go to FNP-1-FRP-S.2, " Response to Loss of Core Shutdown",'if the' subcriticality status tree indicates a yellow path' condition. Lb. The operators may leave'this procedure at any step as soon as the core cooling'CSF'is satisfied.(Green). c. The.operatorsEmust leave this procedure before completion and go to FNP-1-FRP-H.1, " Response to Loss'of. Secondary Heat Sink",.if the' heat sink CSF status tree indicates a red path condition, di The: operators must leave this procedure before completion and go to FNP-1-FRP-Z.1, " Response to High containment Pressure", if the containment CSF status tree indicates an orange path condition, i i I (***** END OF CATEGORY 4 *****) (********** END OF EXAMINATION **********) L ._______________-_-__________i

EQUATION SHEET t f = ma v = s/t_ ~ w = mg s=vt+ hac Cycle efficiency = " "I ' 2 o E = mc a = (vg - v )/t A = A,e" E KE = mv vg=v +a A = AN PE = mgh w - e/t A = In 2/tg_ = 0.693/tg-W = v4P' q(eff) = (t, )(t ) ~ s t OE " 931A" (t_g+t) b Q = mC aT I = 7. IX a p [}=UAAT I = z,-UX 9 Pwr = W' [a -x/ m g I=1 to 9 SUR(t). TVL = 1.3/u P=P 10 e /T HVL

• 0.693/u t

P=P o ~SUR = 26.06/T ~ T = 1.44 DT SCR = S/(1~- K,gg) f1 o\\

• ff g

= S/(1 - K,gg ) SUR = 26 l CR CR (1 'Keff'1 = CR (1 *Keff)2 } T = '(1*/o ) + [(6 ' o)/ A,f f ] n y 2 o T = 1*/ (p - D M " I/(I ~ Keff) = CR /CR g 0 T = (I - p)/ 1,ggo g " (l ~ Keff)0/II ~ Keff)1 p = (K,ff-1)/K,gg = 6K,gg/Kaff SDM = (1 - K,gg)/K,gg [1*/TKygg.] + [E/(1 + A,gf )] 1* = 1 x 10 seconds ~ p= T P = I4V/(3 x 10 ) ~ A,gg = 0.1 seconds A I = No Idg1=Id22 j WATER PARAMETERS Id =Id g 2 2 1 gal. = 8.345 lbm R/hr = (0.5 CE)/d (meters) 2 I gal. = 3.78 liters R/hr = 6 CE/d (g,,t) 'l ft = 7.48 gal. MISCELL\\NEOUS CONVERSIONS 10 Density = 62.4 lbm/ft 1 Curie = 3.7 x 10 dps 3 Density = 1 gm/cm I kg = 2.21 lbm 3 Heat of var ori:ation = 970 teu/lbm I hp = 2.54 x 10 But/hr 0 Hest of fusica = 144 Btu /lbm 1 Hw = 3.41 x 10 Btu /hr 1 Atm = 14.7 Psi = 29.9 in, l'g. 1 BLu = 778 ft-lbf 1 ft. H O = 0,4333 lbf/in 1' inch = 2.54 c= 2 F = 9/5 C + 32 "C = 5/9 ( P - 32) { ______-______________D

_ gtNCIPLES'OF NUCLEAR' POWER PLANT OEERATION. .Page 23-w$ ' THERMODYNAMICS. HEAT TPANSFER AND FLUID FLOW-e 9 1 kASF:=R CCPY ANSWER .1.01'- -(1.00) .b. REFERENCE 1 1 j FNP 1987 Reactor Theory Retraining Ob'jectives Cycle ~4,.I;em'1. 192002K108- ..(KA's) ' ANSWER : 1.02 ( 1.' 0 0 ) -a. Decrease. b. ' Decrea.se: REFERENCE

FNP-1987 Reactor Theory' Retraining Objectives Cycle 4, Item 14.

~ 92005K107 192005K106 ..(KA's) 1 ANSWERt 1.03 -(1.'00) b.

FSFERENCE FNP 1987 Reactor Theory Retraining Objectives Cycle 4, Item 7.

192008K106 192008K103. ..(KA's) ANSWER l'. 0 4. (1.00) b ) ~ REFERENCE FNP 1987 Reactor Theory Retraining Objectives Cycle 4, Item 6. 192003K102 ..(KA's) ANSWER 1.05 (1.00) i 'd. 1 (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) 'l I L.

i kiRINCIPLES OF' NUCLEAR POWER PLANT OEEBATION' Page 24

THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW v

' REFERENCE FNP.1987. Reactor Theory Retraining Objectives Cycle'4, Item 5. .192003K109 ..(KA's) i I ANSWER-1.06. (1.00) a. 'More negative' b. Less negative REFERENCE FNP 1987. License Retraining Objectives Cycle 4, OPS-313, Item 13. 192004K110 192004K109 ..(KA's) ANSWER 1.07 (1.00) a. Decrease b. Increase j i REFERENCE FNP 1987 Reactor Theory Retraining Objectives Cycle 4, Item 19. L 192002K114 ..(KA's) ANSWER 1.08 (0.50) False REFERENCE FNP 1987 Reactor Theory Retraining Objectives Cycle 4, Item 15. 192004K107 ..(KA's) i ANSWER 1.09 (1.00) l a. Less negative b. More negative l l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) c

7 '1. T.RINCIELES OF NUCLEAR POWER PLANT' OPERATION. Page 25~

• THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW

-REFERENCE 'FNP 1987. Reactor Theory Retraining Objectives Cycle 4, Item 16. 192004K106 ..(KA's)

ANSWER.

1.10 (1.00)' c. I REFERENCE FNP 1987 Reactor Theory Retraining Objectives Cycle 4, Item 4. 192003K107 ..(KA's) -ANSWER 1.11 (1.00) c. . REFERENCE-FNP 1987. Reactor Theory' Retraining Objectives Cycle 4, Item 10. 192006K112 192006K102 .. ( KA ' s ') ANSWER 1.12 (1.00) d REFERENCE FNP 1987 License Retraining Objectives Cycle 4, OPS-313, item 1.0. 192006K115 ..(KA's). ANSWER 1.13 (1.50) i c 'j e (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

'i. FRINCIPLES QF NUCLEAR POWER PL6NT OPERATION. Page 26 ETHERt10 DYNAMICS. HEAT-TRANSFER AND FLUID FLOW

REFERENCE:

FNP Licensed Operator Retraining Cycle 4 Review Material p. HT 32-34.

191004K101-

..(KA's) -ANSWER' 1.14 (l.50)

a.

. REFERENCE FNP Licensed Operator Retraining Cycle 4 Review Material p. HT 8-11. 1193003K125 ..(KA's) ANSWER-1.15 (2.00). a. Decrease b. Increase c... Increase d. -Decrease ' REFERENCE-FNP' Licensed Operator Retraining Cycle 4 Review Material p. HT 37. 193008K105 ..(KA's) s ANSWER 1,16 (0.50) .True REFERENCE FNP Licensed Operator Retraining Cycle 4 Review Material p. HT 45. 193010K106 ..(KA's) . ANSWER .1.17 (1.00) j d-i l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

• 1.

PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, Page 27 THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW REFERENCE FNP Licensed Operator Retraining Cycle 4 Review Material p. HT 62-64. 193007K108 193007K106 ..(KA's) ANSWER 1.18 (1.00) b REFERENCE FNP Licensed Operator Retraining Cycle 4 Review Material p. HT 72-73. 193009K107 ..(KA's) i ANSWER 1.19 (1.00) c REFERENCE FNP Licensed Operator Retraining Cycle 4 Review Material p. HT 61. 193008K121 ..(KA's) 4 (***** END OF CATEGORY 1 *****)

72 ' PLANT DESIGN INCLUDING SAFETY AND EMERGENCY -Page 28 'SYST.EME-ANSWERL 2.01 (2.00) .a. Ensures an extended coastdown of coolant flow through the reactor core [0.5) in the event of a loss of electrical power to the pump [0~.5]. b. Prevents transfer of heat-from the reactor coolant to the pump. bearings and seals [0.5] during.a loss of seal injection [0,5]. 4 REFERENCE' FNP 1987 License Retraining: Objectives Cycle 1, OPS-52101D, Item 11. 003000K606 003000K410 ..(KA's): -ANSWER 2.02 (0.50) False . REFERENCE FNP 1987-License Retraining. Objectives Cycle'2, OPS-52102G, Item 6. 008000K401 ..(KA's) -ANSWER 2.03' ( 1.00 ) a. Prevent Thermal Shock during pump starts. -b. . Auxiliary Steam Condensate Tank. sREFERENCE FNP 1987 License Retraining' Objectives Cycle 1, OPS-52102H, item 2 I .061000K111 ..(KA's) . ANSWER 2.04 (1.00) 1. Reactor Makeup Water. 2. Demineralized Water. -REFERENCE o FNP 1987 License Retraining Objectives Cycle 2, OPS-52102G, Item 1. 008010K101 ..(KA's) (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

'Ec_,.. PLANT DESIGN INCLUDING SAFETY'AND EMERGENCY Paga 29 I SYST. EMS i ANSWER 2.05 (1.00) When the plate drops out it reduces the backpressure on the fan (load reduction because it ir. blowing a heavy wet vapor mixture during an accident). { l REFERENCE FNP 1987 License Retraining Objectives Cycle 3, OPS-52102C, item 4 022000K402 ..(KA's) ANSWER 2.06 (1.00) 1. Turbine Driven Auxiliary Feedwater (TDAFW) control panel. 2. TDAFW steam admission valves. 3. TDAFW speed contro11'er. [0.33 each] REFERENCE FNP Exam Questions from the 1987 Licensed Operator Retraining Program FNP 1987 License Retraining Objectives Cycle 2, OPS-52103D, item 2 062000K201 ..(KA's) i ANSWER 2.07 (1.50) a. High temperature on:

1. BTRS inlet (160F)

[0.5]

2. Letdown (135F)

[0.5] b, Divert to VCT. [0.5] REFERENCE FNP 1987 License Retraining Objectives Cycle 1, OPS-52101F, item 4 004000K603 004000K405 ..(KA's) ANSWER 2.08 (1.00) To prevent flooding (in the turbine building). ) l l l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

'2. PLANT DESIGN INCLUDING SAFETY AND EMEPGENCY Page 30 -SYSTEMS REFERENCE FNP 1987 License Retraining Objectives Cycle 2, OPS-52102F, item 3 076000K110 076000K401 ..(KA's) ANSWER 2.09 (1.00) Dilution bypass valves (PCV-562 and -563) open (to maintain <100 psig). REFERENCE FNP 1987 License Retraining Objectives Cycle 2, OPS-52102F, item 6 076000K606 ..(KA's) ( 2. 50 ) Is ANSWER 2.10 Carring Pung% Ci/ 6elers 1. Charging pup . zk. 32. SFP Heat Exchangers y JP. RHR Heat Exchangers S N. RER Pumps 6 H. Secondary Heat Exchanger [ hy 5~ @ 0,5 ea,] REFERENCE FNP 1987 Licenae Retraining Objectives Cycle 2, OPS-52102G, items 2&3 FNP 1987 bicense Retraining Cycle 2, Volume 1, OPS-52102G, fig. 2 008000K101 ..(KA's) ANSWER 2.11 (2.00) 1. LOCA 2. Rod Ejection 3. Main Steam Line Break 4. Steam Generator Tube Rupture REFERENCE FNP 1987 License Retraining Objectives Cycle 3, OPS-52102B, item 2 006000SG04 006000SG07 ..(KA's) (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

I r2;'~FLANT DESIGN INCLUDING-SAFETY'AND EMERGEN._91 Pagel31 3 ' SYST-EMS

t.

'I, 5NSWER 2.12 .(1.50) f l d s1. .All running fan coolers shi t to s ow spee. 2 ^. Service Water flow shifts from 800 to 2000 gpm. 3. Any operable fan cooler in remote, and not running will auto start in slow speed.. REFERENCE FNP 1987 License Retraining Objectives Cycle 3,. OPS-521020, item 5 022000K402 ..(KA's) JANSWER-2.13 - ( 1. 00 )' c REFERENCE-FNP Exam Questions from the 1987 Licensed Operator Retraining Program o FNP 1987 License Retraining Objectives Cycle 3, OPS-52107A, item 1 022000K101 ..(KA's) . ANSWER 2.14 (2.00) 1. RCS-H2 inventory. 2.- Zirc-water ~ reaction. .3. .Radiolysis of core and sump water. 4. Aluminum'- NaOH reaction. ~5 Iron-kkler rea clion

d. Alas.ii,,w.,- k/aler reae /lon U 'Y b @ O' S C' U

' REFERENCE Gre Dama/e de's*n Plan COPS-532) y f3'Yf' FNPMilIreling' License Setraining Objectives Cycle 3, OPS-52102D, item 2 FNPfl987 028000K503-- ..(KA's) ANSWER 2.15 (1 00) .. Loss of any redundant DC power supply in rod control. -(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

2,_.P.LANT DESIGN INCLUDING SAFETY AND EMERGENCY Page 32 ' SYSTEMS REFERENCE FNP 1987 License Retraining Objectives Cycle 3, OPS-52201E, item 7 001000K203 ..(KA's) 4 1 j i I ) { i i I l (***** END OF CATEGORY ? *****)

'O. 1NSTRUMENTS AND CONTROLR Page 33 ANSWER 3.01 (1.50) [0.5 each] 1. 2/3 feed pump suction pressures (less than 300 psig) low. 2. 1/2 running condensate pumps trips with the third pump in auto. 3. With one pump running, take either of the other two from off to auto. REFERENCE FNP 1987 License Retraining Objectives Cycle 1, OPS-52104C, item 1 056000K603 056000K601 ..(KA's) ANSWER 3.02 (1.50) a. Feedwater Stop Valve. b. Feedwater Stop Valve. c. Feedwater Regulating Valve. [0.5 each] REFERENCE FNP 1987 License Retraining Objectives Cycle 1, OPS-52104C, item 2 059000K416 059000K409 059000K419 ..(KA's) ANSWER 3.03 (1.50) l [Any.five, @ 0.3 each] 1. Train's bypass breaker is closed. 2. INPUT ERROR INHIBIT switch in INHIBIT. 3. MULTIPLEXER TEST switch in INHIBIT. 4. LOGIC A. switch out of 0FF. 5. PERMISSIVES switch out of 0FF. 6. MEMORIES switch out of 0FF. 7. MODE SELECTOR switch in TEST. REFERENCE FNP 1987 License Retraining Objectives Cycle 2, OPS-52201I, item 11 012000K610 012000K101 012000K604 ..(KA's) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

--*Gi 3NSTRUMENTS'AND CONTROLS-Paga 34 i f ANSUER L3,04 (1.50) ~ 1.

PZR-leveli<= 15%.

' - 2. LCV 459 or 460 close'. j 3. T signal (Phase-A: isolation). [0.5 each] , REFERENCE FNP 1987 License Retraining Objectives Cycle.1,' OPS-52101F, item 4 - 011000K404 011000K407- ..(KA's) ANSWER 3 ~. 0 5 ' '(1.50), i 1. Turbine trip. - 2. Loss-of-load:(C-7.) t

3.

Steam pressure-mode selected. [0.5'each] . REFERENCE - FNP Exam Questions from the 1987' Licensed' Operator Retraining Program FNP 1987 License-Retraining Objectives Cycle 1, OPS-52201G,. item 5 041020K407 ..(KA's)- -ANSWER 3.06 ( l'. 00 ) b REFERENCE-FNP Exam Questions from' thel 1987 Licensed. Operator Retraining Program. FNP 1987 License Retraining Objectives Cycle 1, OPS-52201D, item 3 015000K401-C15000K604 ..(KA's). i ANSWER ^ '3.07 -(1.00) c REFERENCE. FNP Exam Questions from the.1987 Licensed Operator Retraining Program FNP 1987 License Retraining Objectives Cycle 1, OPS-52201D, item 1 015000K601 ..(KA's) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

.G. "INSTRQUENTS AND CONTROLS' Page 35 ANSWER 3.08 (1.00) d REFERENCE-FNPLExam Questions'from the 1987 Licensed Operator Retraining Program FNP.1987 License Retraining Objectives Cycle 2, OPS-56202, item 1 016000K403- ..(KA's) ANSWER 3.09 (1.00) a REFERENCE FNP Exam Questions from the 1987 Licensed Operator Retraining' Program FNP 1987 License Retraining Objectives Cycle 1, OPS-52201E, item 5 001000K407 ..' ( KA ' s ) I ANSWER 3.10 (1.50) [0.25 - signal, 0.25'- setpoint and coincidence]- -1. SI. 1/2 trains 2. Hi-Hi level in one S/G - greater than or equal to 75% on 2/3 sensors. 3. Low Tave 554 F, 2/3 loops, and P4.. REFERENCE FNP 1987 License Retraining. Objectives. Cycle 1, OPS-52104C, item 6 059000K419 ..(KA's) ANSWER 3.11 (2.00) [0,5 each] 1. S/G Lo-Lo level (of 17% on 2/3 detectors on 1/3 S/Gs and no LOSP). 2. Both main feed pumps tripped (and no LOSP). 3. ESF sequencer signal. l

4.. LOSP sequencer signal.

(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

"S. , INSTRUMENTS AND CONTROLE Paga 36 ~ REFERENCE FNP 1987 License Retraining Objectives Cycle 1, OPS-52102H, item 1 061000K406 ..(KA's) ANSWER 3.12 (1.00) a j REFERENCE FNP 1987 License Retraining Objectives Cycle -1,' OPS-52104D, item 1 075000K401 ..(KA's) ANSWER 3.13 (1.00) 1. >2000 psig (P-11). 2. S signal (Safety Injection). REFERENCE FNP 1987 License Retraining Objectives Cycle 3, OPS-52102B, item 5 006020K404 ..(KA's) ANSWER 3.14 (1.00) b REFERENCE FNP Exam Questions from the 1987 Licensed Operator Retraining Program 039000.K506 ..(KA's) ANSWER 3.15 (2.00) 1. Tavg position on steam dump mode selector switch causes the pressure controller to automatically shift to manual. 2. In steam pressure mode, controller shifts to manual when the Low-Low Tavg (P-12) signal exists. 1 l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l t ________]

.3, INSTRUMENTS AND CONTROLS Page 37 = REFERENCE. FNP Exam Questions from the 1987 Licensed Operator Retraining Program FNP 1987 License Retraining Objectives Cycle 1, OPS-52201G, items 2 & 3 041020K404 ..(KA's) ~ f t W (***** END OF CATEGORY 3 *****) ---m____________.-__

al. P.ROCEDURES - NORMAL. ABNOBMAL. EMERGENCY Page 38 'AND.R&DIOLOGICAL CONTERL i ANSWER 4.01 (3.00) ( i 1. Hold tags are tags which are placed on control points or devices to ensure personnel safety [0.5] and/or equipment protection [0.5]. 2. Caution tags are tags which provide special instructions to an operator. [1.0] 3. a. True b. False RkFERENCE FNP Tng Obj for Licensed Operator Retraining, Cycle 1, AP-14' Items 1, 3. FNP-0-AP-14 pp. 3, 6, 12. 194001K102 ..(KA's) ANSWER 4.02 (0.50) False REFERENCE' FNP 1987 License Retraining Classroom Objectives Cycle 3, Unit'Operat-ing Procedures, Item 7. 000000K301 ..(KA's) ANSWER 4.03 (1.00) I To ensure that if a positive reactivity accident were to occur [0.5], the reactor would be capable of being shutdown (0.5]. REFERENCE FNP 1987 License Retraining Classroom Objectives Cycle 3, Unit Operat-1 ing Procedures. Item 3. j 1 001010K506 ..(KA's) l ) (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) l a

M " PROC.EDURES - NORMAL. MNORMAL. EMERGENCY ~Page 39; = 'AND. RADIOLOGICAL CONTROL ' ANSWER '4.04 (1.00)' If.'the amount of. reactivity which was added to cause source range counts toldouble is added'again, the reactor will be slightly.supercritical. j J OR: To prevent achieving inadvertent criticality by Boron dilution, .j (which is. prohibited except for-initial criticality). q -[ Paraphrase of either antwer acceptable for full credit.] REFERENCE -) j FNP 1987. License. Retraining Classroom Objectives _ Cycle 3, Unit Operat- ) ing Procedures, Item.4. J FNP-1-UOP-1.2, S/U'of Unit From Hot Standby to Minimum Load, P&L-#3.8. FNP-1-UOP-1.3,.S/U of Unit Following and At-Power-Reactor Trip, P&L l

1. 3.8.

001000K405 ..(KA's) j ANSUER 4.05 (2.001 1. c 3. e 3. b '4. a REFERENCE-FNP Tng Obj for Licensed Operator Retraining, Cycle 1, OPS-52101D Item'5-003000K112 - 003000K103 ..(KA's) ANSWER 4.06 (2.00) 1. Close the seal leakoff isolation valve [0.5] within five minutes [0.~5]. 2. . Remove the affected Reactor coolant pump from service [0.5] within thirty minutes [0,5]. (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

4. FROCEDURES'- NORHAL. ABNORMAL. EMERGENCY Page 40 'AND. RADIOLOGICAL CONTROL REFERENCE' FNP.Tng Obj for Licensed Operator Retraining, Cycle 1, OPS-52101D Item 4 FNP-1-SOP-1,1,.p. 3. i 003000A201 ~..'.KA's) ANSWER-4.07 (0.50) w False REFERENCE .i FNP 1987 License Retraining Objectives Cycle 1, OPS-52102H, Item 3. FNP-1-SOP-22.0, Caution Note following Step 4.5.3. 061000K101 ..(KA's)- I ANSWER ,4.08 (2.00)' ') a. 1. Place the bank selector switch in MANUAL. [0. 5] ' ~ 2. If rod motion does not stop, then. trip the reactor (and refer to EEP-0). [0.5] l b. 1. Place the rod bank selector switch-in MANUAL [0.5]. 2. Place the turbine on HOLD [0,5]. REFERENCE FNP Tng Obj for Licensed Operator Retraining, Cycle 1, OPS-52201E Item 8 FNP-1-AOP-19.0, pp. 2-3. 0010SGA014 ..(KA's) 1 ANSWER 4.09 (2.00) L 1. 25-rem [0.5] - to eliminate a source or potential. source that represents a hasard to the generalSpublic [0.25], or to-prevent a substantial loss in property [0.25]. 2. 75 REM [0.5] - lifesaving operations (rescue or searching for known missing persons) [0.5]. I I (***** CATEGORY 4 CONTIPUED ON NEXT PAGE *****) ] w=_ _ _ _.- - _ _ _ _

4. -PROCEDURES - NORMAL. ABNCEMAL, EMERGENCY Pago 41- 'AND RADIOLOGICAL CONTROL REFERENCE FNP Tng Obj for Licensed Operator Retraining, Cycle 3, OPS-565 Item 17. FNP-EIP-14. 194001K104 194001K103 ..(KA's) i ANSWER 4.10 (2.00) I 1. Any SI annunciator lit. 2. SAFETY INJECTION ACTUATED window on the Bypass and Permissive panel CN. 3. Safety Injection MLB1 9-1 (OR 19-1) bistables ON. 4. Flow indicated thru the BIT. [0.5 ea.] REFERENCE FNP Tng Obj for Licensed Operator Retraining, Cycle 3, OPS-52302 Item 1. FNP-1-EEP-0 Step B.IV. 0060SGK015 ..(KA's), ANSWER 4.11 (2.00) 1. Start Boric Acid Transfer pump (1A or IB). 2. Open Emergency borate to charging pump valve (1-CVC-OV-8104). S. Verify one charging pump running. (C ross - con nec 4. Verify charging puup suction header isolationAvalves are open (1-CVC-MOV-8131A and B). '\\ REFERENCE FNP Classroom Objectives, License Retraining, II H, Reactor Makeup Control and Chemical Addition System, Item 5. FNP-1-AOP-27.0, Emergency Boration 000024K302 ..(KA's) i ANSWER 4.12 (1.00) d l l \\ 1 l l (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) {

gy.- -

PROC' EDifRES - NORMAL. ABNORMAL. EMERGENCY Page 42-

'AMD RADIOLOGICAL CONTROL-II {;' '

REFERENCE-i FNP 1987-. License' Retraining Classroom Objectives Cycle 3 Emergency Response Procedures,-. item 9.

FNPal-ECP-0.0, Loss of All AC Power. O. ..000055K302' .,(KA's) ? ANSWER 4.13 (1.00) c . REFERENCE License Retraining 1986-Cycle III Emerg. Response Procedures Classroom ~ Objectives, Items 4'& 5. '000038K01L ..' ( KA ' s ) i t 1 (***** END OF CATEGORY 4 *****) (********** END OF EXAMINATION **********)

TEST CROSS REFERENCE Page 1

o..

QUESTION VALUE REFERENCE 1.01 1.00 ZZZ0000163 1.02 1.00 ZZZ0000164 1.03 1.00 ZZZ0000165 1.04 1.00 ZZZ0000166 1.05 1.00 ZZZ0000167 1.06 1.00 ZZZ0000168 1.07 1.00 ZZZ0000169 1.08 0.50 ZZZ0000170 1.09 1.00 ZZZ0000171 1.10 1.00 ZZZ0000172 1.11 1.00 ZZZ0000173 1.12 1.00 ZZZ0000174 1.13 1.50 ZZZ0000175 1.14 1.50 ZZZ0000176 1.15 2.00 ZZZ0000177 1,16 0.50 ZZZ0000178 1.17 1.00 ZZZ0000179 1.18 1.00 ZZZ0000180 1.19 1.00 ZZZ0000181 20.00 2.01 2.00 ZZZ0000182 2.02 0.50 ZZZ0000183 2.03 1.00 ZZZ0000184 2.04 1.00 ZZZ0000185 2.05 1.00 ZZZ0000186 2.06 1.00 ZZZ0000187 2.07 1.50 ZZZ0000188 2.00 1.00 ZZZ0000189 2.09 1.00 ZZZ0000190 2.10 2.50 ZZZ0000191 2.11 2.00 ZZZ0000192 2.12 1.50. ZZZ0000193 2.13 1.00 ZZZ0000194 2.14 2.00 ZZZ0000195 2.15 1.00 ZZZ0000196 20.00 3.01 1.50 ZZZ0000197 3.02 1.50 ZZZ0000198 3.03 1.50 ZZZ0000199 3,04 1.50 ZZZ0000200 3.05' 1.50 ZZZ0000201 3.06 1.00 ZZZ0000202 3.07 1.00 ZZZ0000203 3.08 1.00 ZZZ0000204 3.09 1.00 ZZZ0000205 3.10 1.50 ZZZ0000206 3.11 2.00 ZZZ0000207 3.12 1.00 ZZZ0000208 3.13 1.00 ZZZ0000209 3.14 1.00 Z220000210 3.15 2.00 ZZZ0000211 L

a,3,x.y, ' TEST CROSS REFERENCE. . Paga ; 2' ..g. " QUESTION VALUE' . REFERENCE q 1 O' 20.0'0. 4.01 3.00 ZZZ0000216. 1 4.02' O.50 'ZZZ0000221 l 4.03- '1.00-ZZZ0000220-l 4.04'. 1.00 'ZZZ0000223' .4.05 '2.00 .ZZZ0000212 i 4.06. 2.00 ZZZ0000213- ,{ 4.07 0.50: ZZZ0000224 ,J 4.08 2.00 ZZZ0000214- -4.09_ < 2. 00:

ZZZ0000215

.) 4.10; 2.00-ZZZ0000217- .4.11: 2.00'- ZZZ0000219 4.12 ' 1 ~. 0 0 ZZZ0000218' .]G - 4,13 - 1.00 ZZZ0000222- '20.00 Our _ _ _ sig eum ' 80.00 1 4 I l I l t_ D}}