Text

Exam Rept 50-335/OL-86-02 on 861117.Exam Results:All Candidates Passed Oral & Written Exams & One Senior Reactor Operator Passed Written Reexam
	ML20211H251
Person / Time
Site:	Saint Lucie
Issue date:	02/06/1987
From:	Bill Dean, Munro J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20211H227	List: L-86-491, Forwards Comments on Exam Administered on 861117.Attachment Suppls & Replaces Comments Provided at 861120 Exam Exit Meeting & Contained in Util; ML20211H221; ML20211H251;
References
	50-335-OL-86-02, 50-335-OL-86-2, NUDOCS 8702260127
	Download: ML20211H251 (150)
	v • d • e

{{#Wiki_filter:. p2 Kto f, UNITED STATES r / 'o NUCLEAR REGULATORY COMMISSION [' REGION 11 g' ,j 101 MARIETTA STREET.N.W. ~t ATLANTA, GEORGI A 30323 '+9 ,o +...+ ENCLOSURE 1 EXAMINATION REPORT 335/0L-86-02 Facility Licensee: Florida Power and Light Company P. O. Box 14000 Juno Beach, FL 33408 Facility Name: St. Lucie Nuclear Plant Facility Docket No.: 50-335 and 50-389 Written and oral examinations were administered at St. Lucie EOF near Ft. Pierce, Florida. Oral examinations were administered at St. Luc e Nuclear Plant near Jensen Beach, Florida. y 4 Chief Exami -X LA- 'k d@bl //#//k[ William M. Dean / ' Date Signed M Shh7 Approved by: John ~ F. Munro'idection Chief /Dat6 Signed Summary: Examinations on November 17, 1986. Oral and written examinations were administered to eight candidates; all of whom passed. A written re-examination was administered to one SR0 candidate, who passed. Based on the results described above, six of six RO's passed and three of three SRO's passed. 87022 k5 PDR V

m REPORT DETAILS 1. Facility Employees Contacted:

M. Shepherd, Operations Training Supervisor
J. Spodick, Operations Training
W. Peake, Operation Superintendent
Attended Exit Meeting 2.

Examiners: Dr. Joe Upton

W. M. Dean
Chief Examiner 3.

Examination Review Meeting At the conclusion of the written examinations, the examiners provided your staff with a copy of the written examination and answer key for review. The comments made by the facility reviewers are included as Enclosure 3 to this report, and the NRC Resolutions to these comments are listed below. The " generic comments... intended as constructive feedback only" were treated as such and therefore are not addressed here. The " supplementing and replace-ment" comments and supporting documents while not reviewed until December 16, were accepted due to a potential misunderstanding. However, future post examination comments and supporting material must be provided in accordance with ES-201H, i.e., "within five working days from the day the exam is given...". One of the seven changes required on the examination questions / answers was due to faulty or outdated material having been supplied by the facility. Question 1.09a - This question is not peculiar to the SR0 knowledge level. A candidate who can fully perform the referenced learning objective can correctly answer part a. The referenced lesson and learning objective do not distin-guish between SR0 and R0 candidates. The referenced K/A catalog ratings for R0 and SR0 differ by less than 10L No change required. ) Question 1.11 - The question clearly states Upper-Lower summer output. The multiplication by (-1) is performed in the RPS cabinets - not in the U-L summer. The interface block diagram referenced in the utility comment does not distinguish in this regard between summer and RPS. Question 1.12 - The thickness of the Tube Sheet is negligible with regard to this question and it will be graded accordingly. No change required. t

2 Question 1.15 - The answer key adequately states an answer that will indicate student knowledge of unnecessary challenges to Reactor Safety. No change required. Question 1.17 - The question addresses only a small fraction of the material covered by the learning objective. An explana-tion of the (phenomena) addressed in the question is easier than " explaining (all) the effect of delayed neutrons on reactor control". Neither the learning objective nor the question asked the candidate to do a quantitative calculation. While that may be a valid area for examination, such was not the case here and therefore the equation sheet was not provided. No change required. Question 1.19b - The utility contention that "the knowledge of the variance of steam viscosity with temperature is of no significance while the similar variance for water is worthy of a learning objective" is unsupported by reference material and is without merit. No change required. Question 1.20b - There is nothing in the question to lead one to believe that steam loads are not maintained. If, however, a candidate assumes a changing steam load, accurately describes that changing steam load and states that his answer is based a that assumption, it will be carefully considered. No change required. Question 1.24c - The question cannot be accurately answered using the supplied curves and therefore the band of acceptable answers has been broadened on the answer key. It is realized that the curves supplied to the candidates require a great deal of both background knowledge and interpolative ability. However, they are the ones supplied to the examiners under a request for " plant curve information as used by operators" (ES 201-1 p. 9). The transient posed in the question is one which must be anticipated and to which a licensed operator must be prepared to respond; presumably with the curves provided here. The answer key was changed to broaden the band of acceptable answers. Question 2.08 - The question on the December 1985 exam was almost identical. Alternative d was reworded and has been changed as requested by the utility. The utility comment on the December 1985 version (parallel) was that c & d would "both accomplish the function of the question". The NRC response was to accept either c or d and change choice d prior to future use. i

e 3 As usid here, alternative d is not " equivalent" to alternative c. The cooldown rate is not controlled by throttling the LPSI flow control valve (FCV-3306) (RC-207, p. 21) but rather the temperature conf.rol valve (HCV 3657). Furthermore, the L/SI flow control valve is not in seriesewith-the SDC heat exchangers asLis the temperature control valve. No; change required. i Question 2.11a - Accepted. Tne RC-202 textual / material should be modified 4 to reflect the recent change. as well as Figure 18. The answer key was changed accordingly. Question 2.14a - The. lesson terminal objective for Lesson Text 504 states "the student shall be familiar with the location of all N major components and controls, associated with the... Vital AC system." The unit which permits diagnosis of the power supply that is -in alarm is a major compppent. The question does not ask for 100 locations but rather "whichswall of the cable spreading room.".No encnge requirgd. \\ Question 2.18b - The recommendation was accepted due to lack of specifi- \\ city in the question. However, it should be noted that ' design flow rate is a design feature that operators arp expected to know. The answer key was chanced accordingly. Question 2.20b - Agreed. The b portion of the question was deleted. Question 2.21 - The answer key was chanced to clarify "its' appropriate solenoid valve" by changing to "the solencid valve to those two day tanks..." Question 3.05 - Agreed. The question was deleted. Question 3.11a - Agreed. The answer key was changed accordingly. Question 5.10 The question and answer were taken verbatim from' currently supplied training material. No reference was supplied supporting the contention that ttlis o i material being taught at St. Lucie and tested here is "an outdated system design". The referenced learning objective states " explain the cayse of water hammers in steam generators". Even assuming "an:cutdated system t design" would not be sufficient to establish lack of content validity. The content (concepts and theory) is equally valid to water hammers in steam / water systems wherever they occur. No change required. Question 5.12 Same as question 1.12. 4

i 4 Question 5.15 The tested knowledge is operational as well as main-tenance and construction related. Aluminum components such as ladders, radiation monitoring equipment, clip boards, etc., can introduce unacceptable amounts of aluminum to containment. The reference material indicates that the hydrogen recombiner capacity assumes these materials are controlled during operations. No material was supplied supporting the contention that h this is a construction and maintenance concern only. No change required. Question 5.20 - The answer key explains the location of the cooldown curve relative to the heatup curve in terms of several factors. It is not necessary to make the reverse statements about the heat up curve, either in the answer key or by the candidate. The answer key will be changed to accept inner wall, inner wall at the beltline or at the beltline if the reasoning previously reflected on the answer key is presented. Question 5.22 See Question 1.17. Question 5.25c' See Question 1.24c. Question 6.08 Note that this question addresses potential sources. This would include off normal conditions such as low pressure in the B header, in which case the CCW pressure may not be greater than that of the fuel pool heat exchanger. l This question with this answer was identical on the 6/10/86 examination and no utility comment was made. t. The specific lesson material referenced was not supplied for preparation of this examination but we presume it 3 has not changed. The material supplied for future examinations should include these lesson plans and i system descriptions. The utility supplied no reference material supporting their comment. No change required. Question 6.16b See Question 2.18b. I Question 6.19 The utility comment does not state that the procedure will never be used in the future, that dry sipping will 'always be contracted out, that training material for - 1 operators will be purged of this information or that QA or Reactor Engineering are " responsible" for this process. (See 10 CFR 55.3b, 55.4f, and 55.22h and i). Enabling objective #5 for the lesson text states "Be able to describe the basic general purpose and function of... fuel dry sipping." No reference material supporting the utility comment was supplied. No change 9s i, required. s

c 94 5 s Question 8.01 Even though the # sign and footnote are part of the LCO, (a) is, essentially, an LCO. However, when asked to choose a statement which is not an LCO, (c) is the only logical choice. No change required. Question 8.15 - The question is in accordance with ES-202, Ell, p. 4 which dictates that approximately 75% of the examination i must be ot the long or short essay type. The point value is consistent with the information required. Nr, change required. 1 l 4 L s N a; 1 4 s 4 e

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6 4. Exit Meeting At the conclusion of the site visit, the examiners met with representatives of the plant staff to discuss the results of the examination. There were no generic weaknesses noted during the oral examination. The cooperation given to the examiners and the effort to ensure an atmos-phere in the control room conducive to oral examinations was also noted and appreciated. The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners. 1

pec / 4 COP 4 U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _STt_LUCIE_lh2___________ REACTOR TYPE: _PWR-CE__________________ DATE ADMINISTERED: _Q6/11/1Z________________ EXAMINER: _L8WYER _S@NpV___________ z CANDIDATE: INSIBUCIlgNS_Ig_CBNDIQ@IE1 Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at Irrast 80%. Examination papers will be picked up six (6) hours aftEr the examination starts. % OF CATEGORY % OF CANDIDATE'S CATEGORY __Y86UE_ _IQI@6 ___SCQBE___ _y@6UE__ ______________C@lEGQBy_____________ _29199-- 2Dz99 ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS _29z99__ _2Ez99 ________ 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION _29z99__ _29z99 ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL _29199_- 25z99 ________ B. ADMINISTRATIVC PROCEDURES, CONDITIONS, AND LIMITATIONS 129199-_ Totals Final Grade . All work done on this examination is my own. I have neither given nor received aid. Candidate's Signature ]

w \\. 4, t NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the f ollowing rules apply: 1. Cheating on the examination means an automatic denial 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 gLQy to f acilitate 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. Pr i n t your name in the upper right-hand corner of the first page of each section of the answer sheet. B. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write gnly gn gge 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 er 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 mathemat.ical problems whether indicated in the question or not.

15. Partial cr edit may be given.

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

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

1 9 ,s t ,a 4

18. When you complete your examination, you shall:

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

1 9'. STHEORY OF NUCLEAR POWER PLANT OPERATION _ELUlpS _9ND PAGE 2 ,5 z i 2 ' JHEBD9DYN9DICS 1 QUESTION 5.01 (1.00) Which one of the following sources can potentially introduce the largest (in standard cubic feet) amount of non-condensible gas into the RCS? a. Zirc-water reaction. b. Safety injection tanks. c. Pressurizer vapor space. d. 100% failed fuel. QUESTION 5.02 (1.00) After unit 1&2 main generators are synchronized with the grid, excitation current is proportional to: a. reactive load (MVAR) 6. real load (MW) c. output voltage (KV) d. generator speed (RPM) e. generator frequency (Hz) QUESTION 5.03 (1.00) i L l Select the CORRECT statement concerning pump cavitation. l Vapor bubbles are formed when the enthalpy difference between the a. pump discharge and pump suction exceeds the latent heat of vaporization. j b. When the vapor bubbles enter a higher pressure region, the bubbles collapse which produces high pressure pulses or shock waves. c. Vapor cavities (bubbles) are produced when the localized pressure exceeds the vapor pressure at the existing temperature. d. As the vapor bubbles are discharged from the pump they impinge on downstream piping and valves causing water hammer. (***** CATEGORY 05 CONTINUED ON NEXT PAGE

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4 ,5 NTHggRY_QF_ NUCLEAR _PgWgR_ PLANT _QPERATIgN _FLUIpS,_ANQ PAGE 3 1 ^"_TH_E_R_M_O_D_Y_N_A_M_I_C_S DUESTION 5.04 (1.00) Which one of the following statements is CORRECT concerning the paralleling of electrical systems? c Although it is desirable to have speed and phase position matched, it is much more important to have voltages matched. b. If voltages are not matched at the time the synchronizing switch is closed, there will be VAR flow from the lower voltage source to the higher one. c. If the incoming machine is at synchronous speed but out of phase with the running bus when the breaker is closed, heavy currents will flow to either accelerate or retard the incoming machine. d. If the incoming machine is in phase but slightly faster than synchronous speed when paralleled, the system will tend to speed up the system to synchronous speed, e. If the resistances are not matched at the time the synchronizing switch is closed, heavy currents will flow to tend to speed up the incoming machine to synchronous speed. QUESTION 5.05 (1.00) Which one of the following cor-ectly describes the response of core delta T if the RCS coolant flow rate is reduced while the steam system is controlling to maintain 80% electrical output? Unit 1 has been operating at 80% of full power, steady state, for 10 days. All control rods are fully withdrawn (ARO). a. Delta T will remain the same since the turbine / generator output power has not changed. b. Delta T will remain the same but nuclear power will increase to provide the same megawatt thermal output. c. Delta T will increase but nuclear power remains the same to provide the same megawatt thermal output. d. Delta T will increase and nuclear power must increase to provide more steam flow to the turbine. (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) J

,51-.11HEgBy_QE_NQCLE98_EgBEB_E(9NI_QEEBSIlgN _E6UlpS _6NQ PAGE 4 2 1 THERMODYNAMICS QUESTION 5.06 (1.00) One isotope of plutonium, Pu239, can be found in the nuclear reactor core of St Lucie unit 1 because a. of the non fission absorption of a thermal or epithermal neutron by U238 nuclei. b. of the doppler broadening of neutron absorption peaks for U235 nuclei. c. of the fissioning of U238 nuclei by fast neutrons. d. of the non fission absorption of a thermal neutron by U235 nuclei, e. of the prompt neutron emission of Pu240 nuclei. QUESTION 5.07 (1.00) The reactor is critical at 10E-3 */. power when a S/G Atmospheric dump valve failu open. Assuming BOL conditions, no rod motion, and no reactor trip, choose the answer below That best describes the values of Tavg and nuclear power for the resulting new steady state. (POAH = point of adding heat). g a. Final Tavg greater than initial Tavg, Final power above POAH. AR [ tad "l I - b. Final Tavg greater than initial Tavg, Final power at PDAH. 4 Iiaal-Tavy greater than Tniti'anavgTFina17ower-at-c. Final Tavg less than initial Tavg, Final power at POAH. d. Final Tavg less than initial Tavg, Final power above POAH. I QUESTION 5.08 (1.00) For the changes listed below (treat each one independently) indicate whether the moderator temperature coefficient will become MORE NEGATIVE, LESS NEGATIVE or have NO EFFECT. (Assume all other parameters are constant) l a. Boron concentration decreases 100 ppm while core is at MOL. l b. Increased number of burnable poisons are inserted into the core. (***** CATEGORY 05 CONTINUED ON NEXT PAGE

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,52_3TUEQ8Y_gE_ NUCLE @B_EgWE8_E(@NI_gEEB@llgN _ELUlDS _@ND PAGE 5 t t T_H_E_R_M_O_ D_Y_N_ A_M__I C_S_ DUEST1DN 5.09 (.50) A general rule is often stated " doubling the count rate halves the margin to criticality". This is mathematically stated by the equation: CR1/CR2 = (1-Keff2)/ (1-Keff1) Is the following statement True or False? "Both Keffl and Keff2 must be less than one in order for this to be true". l QUESTION 5.10 (1.00) The "J" tube change to the steam generator design was made to lessen water hammer. This could occur in the bottom discharge sparger type feedring (original design) because it would uncover during a trip allowing the feedwater to drain through the holes, emptying it of liquid and filling it with steam. When feedwater was reinitiated to the feedring, steam would begin to condense, creating a warm laminar film on the surface of the incoming liquid. The conditions were then set to initiate a waterhammer if either of two triggering events should occur. State the two triggering events. QUESTION 5.11 (1.00) List the five DNB-related reactor trips generated by the reactor protection system for PSL. QUESTION 5.12 (1.00) The driving force for subcooled natural circulation flow (steady state) at St. Lucie i s about 26 f eet. Between what two points in the RCS is this measured? i.e. Answer in the form "from the top / bottom of component A to the top / bot of component B". QUESTIbN 5.13 (.50) Which of the three unit 2 reactor safety limits is NOT specified as a l safety limit on unit 1? (Numerical value not required.) l l l i (***** CATEGORY 05 CONTINUED ON NEXT PAGE

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5[__%THE9By_QE_ NUCLE 98_PQWEB_EL9NI_9EEB9IJQN_ELUJpS_9ND PAGE 6 2 2 THERMODYNAMICS QUESTION 5.14 (1.00) Describe the photoelectric ef f ect as it occurs in certain radiation monitoring instrumentation in terms of the detected ray or particle, how it interacts, what it interacts with, and what causes the subsequent ionization. QUESTION 5.15 (1.00) The use of aluminum (ladders, stairs, etc), zinc and zinc base paint has been restricted inside the St Lucie unit 2 containment. What is the safety hazard of allowing an excess amount of these materials in containment? QUESTION 5.16 (2.00) fx ksniaar thetrippingd$uto manu2ED of the What is the PREFERRED sequence for or THREE components referred to in step 5.1.1 (RCP, Rx, Turb.) the event of a rapidily dropping level in the RCP lower oil reservoir? What are the two reasons for this sequence being preferred? See figure 1149. QUESTION 5.17 (1.00) What is the material used in the detector well surrounding the detector can for unit 1 wide range logarithmic safety channel? Why is this material necessary? Explain in terms of neutron energies and material cross sections. QUESTION 5.18 (1.00) What isotope is the largest contributor to fast fissions for neutrons of greater than 1 Mev energy? Explain in terms of the cross sections shown on figure 1151. (***** CATEGORY 05 CONTINUED ON NEXT PAGE

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5 '-' % THEORY OF NUCLEAR POWER PLANT OPERATION FLUIDS _AND PAGE 7 2 2 "_TH_E_R_M_O_DYN_A_M_IC_S QUESTION 5.19 (1.50) Ex pl ai n the reasons for the shape of the normalized RCS flow vs time curve following a loss of forced circulation event. Do this by discussing the. DOMINANT CAUSE of the flow behavior in each of the three regions, A(0-4 min), B(4-5 min) and C(5-30 min). (times are approximate). 1 The normalized RCS flow vs time with regions A,B,LC notated is shown on figure 1152 attached. QUESTION 5.20 (1.50) Explain why the " unit 1, non critical operation of the core cooldown" curve on the attached figure 1158 is below and to the right of the corresponding "heatup" curve. Limit your discussion to the reactor pressure vessel. Explain in terms of most limiting location, reason it is most limiting and the effect of that reason. Assume that the curves are based solely on the reactor pressure vessel. QUESTION 5.21 (1.00) Describe the changes that occur in the atomic number and mass number of an atom when it decays by negative beta emission. Remember the atomic number is the number of protons and the mass number is the number of neutrons plus protons. QUESTION 5.22 (1.00) The reactor is made to be subtritical by a very small amount of reactivity (less than the value of beta). Will the resultant stable negative startup rate approach -1/3 dpm? Explain. QUESTION 5.23 (1.00) Draw and l abel the ideal and real Rankine cycle curves for a FW or condensate PUMP on the attached figure 1145C. To aid you in better understanding the question, example figures 1145A&B have been provided. On these are drawn the TURBINE portion of i deal (1-2) and real (1-2' ) Rankine cycles on both T-S and Molli er (h-s) somewhat exaggerated diagrams to more clearly show the diagrams. These ar difference between the real and the ideal TURBINE cycles. CATEGORY 05 CONTINUED ON NEXT PAGE *****) (*****

PAGE 8 NUCLEAR POWER PLANT OPERATIONt_FLUIDSt_AND 5.' NTHEORY OF THERMODYNAMICS t DUESTION 5.24 (2.00) a Utube S/G and secondary temperature profiles for Sketch the primary (RCS) (at 100% power) which has a height of approximately L/2 (ie the tube length is L) on the attached figure 1147. Label the endpoints of the primary the direction of fluid flow on EACH curve Th and Tc. Indicate by arrows, curve. Label the horizontal axis at O, L/2 and L. Show the relation of Tsat to Tc and Th. QUESTION 5.25 (3.00) St Lucie unit 2 has been operating at a steady 100% of full power for 7 days with all of the CEAs fully withdrawn from the is 5000 EFPH on cycle 3. Answer a, b, and c below using core. The burnup Show your work and/or how you any of the provided figures and tables. arrived at your answer. See figures 1156 A-L. a. What is the value of boron worth in (% delta k/k)/ ppm and in pcm/ ppm. (1.0) b. The reattor power level is now reduced to 70% of full rated power at a 1 % per minute by inserting rods (programmed bank motion).(1.0) rate ofis the rod position when the power change is complete? What You are to maintain this 70% of full power for the first 20 hours You do not wish to move the control c. after the power level change. rods. Explain what change will be required to the baron concentration to compensate for xenon changes. Give numerical values. Neglect any (1.0) effect due to samarium poisoning and show calculations. QUESTION 5.26 (1.00) Define ASI as defined in Tech Specs (Ye - not the trip signal Yi) and utilize that definition to show whether ASI will be positive or negative for the following situation: Unit 1 is opeating at 80% power, steady state, that the control rods are concentration is adjusted such inserted (while in the manual-sequential mode) until bank 7 is at 70 ARO. The baron inches. All during this adjustment power level is maintained at 80%. (***** END OF CATEGORY 05 *****)

62, PLANT SYSTEMS DESIGN _CQNTBQLx_@NQ_JNSIBUMENIGIlgN PAGE 9 3 t QUESTION 6.01 (1.00) Which one of the following reactor trips DOES NOT receive an input from the core protection cal cul ators7 a. Thermal margin / low pressure b. Local power density c. High rate of change of power d. Variable over power QUESTION 6.02 (1.00) Which one of the f ollowing statements correctly describes how to reset the MECHANICAL overspeed on the turbine driven AFW pump? a. It must be reset locally, after driving the limitorque to the open position, to relatch the linkage, b. It must be reset locally by using a lever to relatch the linkage. c. It will reset automatically as turbine speed decreases below a pre-determined setpoint, d. It may be reset locally, but can also be reset from a switch on RTGB 102 in the control room. QUESTION 6.03 (1.00) Which one of the following describes the purpose of the suction stabilizers (dampeners) associated with the charging pumps? a. Prevent excessive pulsation levels in the piping downstream of the charging pumps. b. Prevent overpressure of the suction side of the charging pumps. c. Minimize system losses due to acceleration head and assure that sufficient NPSH is available. d. Provide an isolation signal for the appropriate charging pump if suction side pressure oscillations become too large. (***** CATEGORY 06 CONTINUED ON NEXT PAGE

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62_1,P6BNI_SYSIEUS_DEg1GNt_CQNIBQ(t_@ND_lNSIBudENI@IlgN PAGE 10 T DUESTION 6.04 (1.00) Which one of the following statements concerning the LPSI/ shutdown cooling system is correct? a. The hot leg suction valves to the LPSI pumps automatically close at a decreasing RCS pressure of 500 psig. b. The LPSI pumps can be used in fill and makeup to the SITS with RCS pressure less than 1500 psig. c. When using the system for shutdown cooling, purification of the RCS coolant using the CVCS demineralizers is not available. d. The LPSI pumps start automatically on SIAS and are stopped automatically when RCS temperature reaches 325 degrees. QUESTION 6.05 (1.00) Which of the following correctly describes the normal lineup of the 125 VDC Swing Bus? a. The swing bus AB is powered from the A-side train in UNIT 1. b. The C train is powered from either of the A or B buses via the swing bus AB in UNIT 1. c. The swing bus AB is powered from the A-side train in UNIT 2. d. The swing bus AB is supplied by either a battery charger or a battery backup in UNIT 2. 9 (***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

62_23L9NI_SYSIEDS_DESJGN _CQNIB061_9ND_JNSIBUDENI9IJQN PAGE 11 3 t QUESTION 6.06 (2.00) Indicate whether each of the following statements concerning the containment spray system apply to unit 1, unit 2 or both, c. When the RWT decreases to its low level setpoint, a RAS signal is generated which shifts the containment spray pump's suction from RWT to the containment sump, b. The containment spray system can be lined up to supply all or part of the suction to the HPSI pumps. c. The containment spray system utilizes hydrazine in the spray as an iodine removal agent. d. The containment spray pumps are provided cooling water by the CCW system. QUESTION 6.07 (2.00) Answer the parts of this question concerning the containment cooling system by supplying the appropriate number, word or phrase in place of the blank to correctly complete the sentence. c. Upon the receipt of a SIAS, (1,2,3cr4) containment cooling fans should start in _____ slow, fast or normal) speed at unit 1 while ( (1,2,3,or4) containment cooling fans should start in _____(slow, fast or normal) speed at unit 2. b. Water from the _____ system is supplied to the cooling coils of the containment cooling fan coolers through motor operated supply and return valves which should _____ open, close or stay the same) on a ( CIS. At unit 1 there is/are (1,2,3 or 4) motor operated supply valves while at unit 2 there are _____ (1,2,3 or 4) matcr operated valves. QUESTION 6.08 (1.50) List SIX potential sources of In-leakage causing excessive activity levels in the CCW System. (Leakage from redundant components will be considerea es one response) (***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

61_4P69NI_SYSIEDS_ DESIGN _CQNIBQLg_@ND_JNSIBydENI@IJQN PAGE 12 2 i QUESTION 6.09 (2.00) What automatic actions (other than alarms) occur, if any, when the following process radiation monitors exceed their setpoints? Consider each of the four monitors sep'arately. a. Liquid discharge monitor b. Steam generator blowdown monitor c. Letdown process monitor d. Component cooling water monitor QUESTION 6.10 (1.75) With the reactor at 30% power, all controllers in AUTO, heaters and sprays off and one charging pump running, the pressurizer level starts to decrease from its setpoint. Li st the changes in the CVCS and any alarm / protective functions that occur as pressurizer level decreases until a TM/LP trip occurs. Give the applicable setpoints and note any differences between UNIT 1 and UNIT 2. (Assume no operator action) QUESTION 6.11 (1.00) Indicate the color that will be displayed on the UNIT 1 CEA Core Mimic display for each of the following situations: a) Shutdown CEA in its operating band b) Regulating CEA is at its Upper Electrical Limit (UEL) c) Shutdown CEA is at 120 inches d) Regulating CEA is dropped QUESTION 6.12 (.50) The plant is at 100% of full power. All controllers of the steam bypass control system are in manual. Is the quick open signal disabled? Answer yes or no. No explanation required. (***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

,6[_ y GNI_SYSIEUS_DE@lGNt_CONIBObt_892_lySIBUdENI@TlQN PAGE 13 \\ QUESTION 6.13 (3.00) Consider the excore neutron detectors ar.d their instrumentation for unit 1. a. What are two indications of a failed section of a dual section UIC safety channel? po4reW b. ~ LIST three contro functions of the wide range channels. c. What are two functions (inputs to other systems) of the control channels? QUESTION 6.14 (2.00) Describe the 4 flow paths within the reactor vessel which BYPASS the fuel rods. QUESTION 6.15 (1.75) Describe the two operational modes of the UNIT 2 Main Feedwater Isolation Valves. Include a description of the motive force for the valves, number of valves per feedline, their response in both normal and accident conditions and the manner or method in which speed is controlled. QUESTION 6.16 (2.50) I In addition to fuel pool purification of the refueling cavity, and shutdown cooling purification, one unit has an additional filtration system to keep the cavity water clear, a. Name the system and unit. (1.0) b. What design feature allows it to maintain clarity? (0.5) c. From where does it take a suction and to where does it discharge?(1.0) QUESTION 6.17 (1.00) Describe how the Heated Junction Thermocouple (HJTC) System detects a collapsed liquid level above the core. (***** CATEGORY 06 CONTINUED ON NEXT PAGE

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PAGE 14 6[_JP69NI_@ygIEDS_gESIGN2_CQNIBgli_9Ng_INSIBUDENI9IJgy t QUESTION 6.18 (1.00) The AFAS actuates auxiliary feedwater to a steam generator on low level unless the steam generator or its associated auxiliary feedwater supply header have been identified as being ruptured. What criteria determines whether such a rupture exists? (i. e. what auto feature prevents AFW supply to the ruptured steam generator) QUESTION 6.19 (2.00) Explain in general the method utilized in fuel dry-sipping. Include flow paths of both of the two main fluids (gases or l i qui ds) involved, name of these fluids and how a cladding defect is detected. QUESTION 6.20 (1.00) During initial condensate pump startup with the system depressurized, the procedure requires that the main condensate retirc regulator controller cetpoint be reduced to 1000 gpm. (see step 9 on figure 1275 attached) Explain why this is done by stating the two reasons given in the procedure. (***** END OF CATEGORY 06

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PAGE 15 2:_jPBgCEQUBES_;_NQBd@63_@BNQBd863_gdEBGENCy_ONp _R _A _D _I O L O _G _I C A L _ C O N _T R _O L QUESTION 7.01 (1.00) Which one of the following is NOT a symptom of condenser tube leak as contained in off-normal DP-1-610030, " Secondary Chemistry -Off Normal"? a. Increase in cation conductivity in the condensate header b. lA S/G. specific conductivity increasing c. Increase in hotwell chloride monitor d. Hotwell quadrant cation conductivity increasing or alarming DUESTION 7.02 (1.00) Which one of the following is NOT a correct caution during filling and venting of the RCS? a. Do not attempt to vent if the RCS temperature is above 200 degF. b. Do not allow RCS pressure to decrease below atmospheric. c. Do not install the head on the reactor vessel unless two pressurizer safety valves are operable. d. Do not operate a RCP until the RCS has been pressurized and major air pockets removed. (***** CATEGORY 07 CONTINUED ON NEXT PAGE

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I

ZI_yPBgCEDUBES_ _NQBMAgi_ABNQBM862_gMgBQgNCY_AND PAGE 16 b69196991E96_ggNIBQL i i QUESTION 7.03 (1.00) Which one of the following is NOT a requirement for increasing 'RCS pressure to greater than 1750 psig on a unit 2 reactor plant heatup from cold to hot standby? c. 'iwo independent containment spray systems shall be,g erable with each spray capable of taking suction f rom the RWT on a JuWMP and automatically transferring suction to the containment sump on a RAS. b. At least three safety injection tanks operable with each tank containing 74-94% borated water with a concentration between 1720-2100 ppm, having nitrogen cover pressure between 235-650 psig and i ts i solation valve open. c. Two independent ECCS subsystems shall be operable consisting of at least one HPSI pump, one LPSI pump and one charging pump. d. RCS dissolved oxygen concentration shall be <O.1 ppm. QUESTION 7.04 (1.00) The ref ueling machine bridge drive has interlocks that make it inoperative in either direction. Which one of the following is NOT a correct interlock? c. The mast bumper is actuated. b. The grapple is in or below the upper grapple operate zone. c. The hoist is being operated. t ( d. The spreader is retracted. 1 I i I (***** CATEGORY 07 CONTINUED ON NEXT PAGE

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t t

~ 2:_APBQCEQUBgg_;_NQBd@b2_@gN9Bd861_EDEBGENCy_6Np PAGE 17 4 ( .B0D1969GIC06_C9NTBg6 DUESTION 7.05 (1.00) Which one of the f ollowing " Radiation Area" definitions" means the same as that given in HP-2, "FP&L health physics manual"? c. any area where the dose rate exceeds five mrem /hr or where, in any five consecutive' day period, exceeds 100 mrem /hr at any time. b. any accessible area where a major portion of the body could exceed a l dose of five mrem in any one hour, or in any five consecutive days a dose in excess of 100 mrem. c. any accessible area where any portion of the body could exceed a dose rate of five mrem /hr or where, in any five consecutive day period, could exceed a dose rate of 100 mrem /hr at any time. d. any area where the dose rate to any portion of the body could exceed a dose of five mrem in any one hour, or in any five consecutive days a dose in excess of 100 mrem. QUESTION 7.06 (1.00) If a steam generator tube rupture occurs on Unit 1 and if all RCPs are stopped, RCP restart criteria CANNOT be met if: (choose one) a. the CCW has been lost for four minutes. b. the RCS is 30 degF subcocled. c. the pressurizer l evel is 40%. d. the unaffected steam generator level is 30% wide range. (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****) l I

7$ ' PROCEDURES - NORMAL _ABNQRMAL _EMERGENgy_AND PAGE 18 2 i 8091969GIC66_CQNIBQ6 QUESTION 7.07 (1.00) The unit I hydrogen recombiner should always be placed in service when the hydrogen concentration in containment is in which one of the following ranges? a. 0.5% to 3.5% b. 0.5% to 4.5% c. 1.5% to 3.5% d. 1.5% to 4.5% e. O.0% to 4.0% QUESTION 7.08 (1.00) While operating at 100% of full power on unit 2, an increase in component cooling water (CCW) is observed on the indicators PLP-101 and PLP-102. This is f ollowed by an indicated rise in the level of the CCW surge tank. Which one of the following must be eliminated as a potential source of the ectivi ty in the CCW system? a. Letdown heat exchanger b. Sample heat exchangers c. LPSI pump seal coolers l d. Reactor coolant pump seal coolers I l e. HPSI pump seal coolers QUESTION 7.09 (1.00) Indicate whether each of the following statements regarding cooldown of the reactor plant are applicable to UNIT 1, UNIT 2 or BOTH UNITS. I a) The shutdown cooling system (SDC) shall NOT be placed in service until the RCS pressure is < 265 psia and the temperature is < 325 degF i b) When the RCS temperature is < 500 degF and RCS pressure is < 1500 psig rack in the breakers and close the SI Tank discharge valves. Rack the breakers out again once the valves are closed. (***** CATEGORY 07 CONTINUED ON NEXT PAGE

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l

.Zl PROCEQURES_ _NQRMALg_ABNQRMALt_EMERGENgY_ANQ PAGE 19 RADIOLOGICAL CONTROL QUESTION 7.10 (.50) Is the following statement TRUE or FALSE? If at 100% of full power on unit 1, a CEA has dropped into the core, the operator shoul d immediately commence emergency boration in order to reduce power to =or< 50% within 1 hour. QUESTION 7.11 (.50) Is the f ollowing statement TRUE or FALSE? An EXCLUSION AREA is defined in St Lucie plant procedures as ...any area specifically barricaded and locked to prevent unauthorized entry and conspicuously posted as an exclusion area (in addition to any other-required postings)". QUESTION 7.12 (2.50) Five of the ten immediate operator action steps on a complete loss of off-site electrical power are listed below. State the remaining five. I 1. Trip Turbine and reactor manually 2. Ensure all CEAs are fully inserted and reactor trip breakers are open 3. Ensure turbine valves are closed 4. Ensure generator exciter supply breaker and generator breakers are open 5. Ensure that diesel generators have started and are feeding only emergency buses I QUESTION 7.13 (1.50) List the three reasons / situations that require RWPs as specified in health procedure, HP-1, " radiation work permits" other than entry into the reactor containment or entry into a high radiation area. QUESTION 7.14 (2.00) In the unit 1 control room, sixteen positive indications of leakage of coolant from the RCS to containment or to other systems are provided by equipment which permits continuous monitoring of certain plant parameters and the activity of other systems. List eight of these; ie, eight different types of equipment, which may alarm and indicate when excessive leakage is present. (***** CATEGORY 07 CONTINUED ON NEXT PAGE

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F PAGE 20 ,2:__CBgCEgyBES_ _Nggd86,_8BNgBd8(i_EDEBGENCy_9Ng 8091969GJC86_CgNIBg6 QUESTION 7.15 (2.50) If it appears that critical conditions are going to be achieved 600 pcm LESS THAN the calculated ECC, what five actions, verifications and notifications are required as stated in OP 0030126, "ECC and ICRR"? QUESTION 7.16 (1.50) What five substeps constitute verification that plant electrical power requirements are satisfied in EOP-1? QUESTION 7.17' (1.50) List all the conditions that must have been completed, so that a system that had been tagged out for maintenance, can be considered to be " ready for service". QUESTION 7.18 (1.50) List three conditions for which an inverse count rate ratio (ICRR) shall be plotted during an approach to criticality at St Lucie unit 2. QUESTION 7.19 (2.00) While operating at 100% of full power, St Lucie unit 2 experiences a slow decrease in the condenser vacuum. List eight things that could be checked to determine the cause of the decrease in the condenser vacuum. QUESTION 7.20 (1.50) Assume unit 1 is operating at 100% power when a main feedwater pump trips. List the expected automatic actions AND your immediate actions assuming the transient does NOT cause a reactor trip. (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

.Zd_1 PROCEDURES _NQRM@6t_@BNQRMGLt_EMERGENQY_GND PAGE 21 88DlD6QGlG@6_QQNIBO6 QUESTION 7.21 (1.50) Certain limits and precautions are addressed in the unit 2 operating procedure 2-30124, " Turbine startup". State the reason for each of the f oll owing. a. Gland steam should be placed in service after the turbine is on the turning gear. b. Gland steam should be placed in service before a vacuum is drawn, c. Steam header drain valves must be open below 20% load. QUESTION 7.22 (1.00) Why are Core Exit Thermocouple temperatures > 700 degrees F an almost certain indication of an uncovered core situation? i QUESTION 7.23 (1.00) In the emergency operating procedure, 2-0120040, " Natural Ci r cul ati on / Cool - down", there is a step during cooldown which states, "When using auxiliary epray to decrease the pressurizer pressure, maximize the use of letdown flow through the regenerative heat exchanger, when available,...". What is the reason for this instruction? 3 1 (***** END OF CATEGORY 07

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PAGE 22 8 _tpDDJNJSIBBIJyE_BBgCEDUBES _CQNp]IJQNS _8Np_6]DJIBIJQNp 3 2 QUESTION B.01 (1.00) Which one of the following is NOT in an LCO at Unit 2? a. The reactor coolant system lowest operating loop temperature (Tave) shall be =or> 515 degF when the reactor is in modes 1 or 2. b. The calculated value_of TFR (total integrated radial peaking factor) shall be limited to =or< 1.70. c. Primary containment internal pressure shall be maintained between -0.7 and +2.4 psig. d. The pressurizer shall be operable with a minimum water level of =or) 27% indicated level and a maximum water level of =or< 68% indicated level. QUESTION 8.02 (1.00) During a Unit 1 startup with the reactor at 2% power, one power range neutron flux monitoring channel is found to be inoperable. Which of the f ollowing statements is correct? Refer to the attached Tech Specs. (figs. 981A-E) a. Operation above 5% rated thermal power is not allowed until the inoperable channel is repaired and declared operable. b. If the inoperable channel is placed in a tripped condition and the other three channels are operable, you must verify compliance with the shutdown margin requirements of Tech Specs. c. If the inoperable channel is placed in a tripped condition and the other three channels are operable, operation to 100% rated thermal power may proceed only if all functioning units receiving an input from it are tripped (may not be bypassed). d. The only restriction on proceeding to 100% rated thermal power are l that the inoperable channel be placed in a bypassed or tripped l condition; however, if it is bypassed it must be only for surveillance testing and must be tripped within an hour. l l l (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****) i

PAGC: 23 { & _2_090lN1EIB@llyE_E8QCEQUEE@g_CQNQlllQN@g_@NQ_(ldlI@llgN@ g N b ) A QUESTION 8.03 (1.00)

r m.

On unit 2, with_the reactor head closure bolts less,than fully-tensioned, the baron concentration of ther.RCS and refueling canal shall ;be maintained ln uniform and of sufficient concentration to enscr,? that the more restrictive' i of which of the f ollowing reactivity conditions *is met? .3 ),. s: g,, c. Keff of O.95 or boron coneentrat1^or eor > 1720 ppm. t t! ,s9 r b. Keff of 0.95 or baron concentratidn =or> 2100 ppm. i c. Keff of 0.97 or boron concentration =or> 1720 ppm. d. Keff of 0.97 or baron concentration =or> 2100 ppm.' .r t ,s QUESTION 8.04 (1.00) /' 3 .s. Immediate notification of NRC is required if the rel ease of ~radi oacti ve materials in concentrations which, if averaged over"A peri ~cid of 24 hours, would exceed ______ times the limits specified for such materials in 4' l' Appendix "B", Table II of 10CFR 20; ______ damage tol property in excess of f O______. Fill in the blanks with the correct information by choosing one of the below combinations, g' N e. 500; or; 2,000 b. 500; and; 2,000 t c. 5,000; or; 200,000 d. 5,000; and; 200,000 If 4 I ', d1 t t, j 4 i- > 3 ,s i ( ,k f' / i 4 e. r J f (***** CATEGORY 08 CONTINUED ON NEXT PAGC *****)

W,gt g, - m_ 1 -,3 y, n Bl 0Dd]NJSIB911VE_BBQCEDUBEg,_CgNp]IJQNS _8NQ_LIMJIBIJQN,5 PAGE 24 2 N 2bd e I ..O s' i 1 Q ESTION 8.05 (1.00) i Diesel Generator 1A, which supplies 4KV Bus 1 A3 i s INOPERABLE. LPSIP B supplied by 4KV Bus 1B3 )i s INOPERABLE. The Tech Specs for ECCS and AC cources are attached as Wigures 1259a thru d. Which statement is CORRECT qdncerning continued opdration in mode 1? c) p.

csiThe Action Statements for both the LPSIP and the DG are applied indepen-dently, each must be restored to operable in 72 hours.

\\ b. Since the DG is required in Mode 4 and the LPSIP is not, the Unit must be taken to Mode 4 wi' thin 72 hours. c. LCO 3.0.3 applies, d. LCO 3.0.5 applies. a 7 I. QUqSIlON B.06 (1.00) Acctyding?)o unit 1 Tech Spec 3. 7.1.5, the MSIVs are required to be operable in what modes?- (select one) p. ,1,2,3 and 4 only 3 (d,2, and 3 only 5 s x s. .s

f

\\ c. 1 and 2 only, i \\ d. All modes sg t t QUESTION 8.07 (1.00) According to unit 2 Tech Spec 3.7.1.6, the main feedwater isolation val ves are required to be operable in what modes? (celect one) h,2,3, and 4 only a. a s Q b., 1,2, and 3 only c. 1, and 2 only d. All modes (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

,el_j DUJNJSJB91]yE_E69CEDUBES2_CgNp))JQNS3_@ND_LJdJJOIJQNS PAGE 25 QUESTION B.08 (1.00) Which one of the following actions is correct if unit 2 is in mode 1 with one safety injection tank inoperable due to the discharge valve being closed? a. Open the valve within one hour AND be in at least hot' standby within the next six hours. b. Open the valve within one hour OR be in at least hot standby within the next six hours. c. Open Ehe valve immediately AND be in at least hot standby within one hour." d. Open the valve immediately OR be in at least hot standby within one hour. o. Continue operating. (Three accumulators operable meet the ' requirements of Tech Specs) i QUESTION 8.09 (2.00) Indicate whether the following statements are TRUE or FALSE with respect to plant work orders (PWO). a. If, in the opinion of the Nuclear Plant Supervisor or Assistant Nuclear Plant Sep9 vlsor, emergency work is required to restore equipment or systemu *n normal operating conditions; the work can be performed under these emergency conditions without a complete PWO package. b. All modification, preventative and corrective maintenance not covered by blanket work orders which is to be performed by Florida Power and Light personnel at the St. Lucie plant, shall be authorized through the plant work order, form 1784. 9+ c. When a condition requiring modification or maintenance is known, it must be reported and documented by requesting that the Operations Supervisor initiate a PWD. d. If an AO observes that a relief valve in the CVCS requires replacement or maintenance, he should report the situation by completing Section A of the PWO and by checking the "yes box" in Section B under " Rad work permit required". (***** CATEGORY 08 CONTINUED ON NEXT PAGE

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PAGE 26 pl-6901N151BB11?E EBDGE90BG&s GQNQ))]QNG,_BNQ_L]UJ191]QNS QUESTION 8.10 (2.00) With regard to Administrative Procedure AP-OOO5720; a. What are all the requirements for an operator to transfer from Unit 1 to Unit 2? (1.5) b. Under what time related condition can the requirements in (a) be (0.5) waived? QUESTION 8.11 (2.00) With the plant critical, the reactor operator reports to you that Tavg is 510 degF. (For a and b below note any unit 1/ unit 2 differences) a. What are the Tech Spec requirements? (Include time limit) b. What required action must you take if you cannot meet the time limit in "a" above? (Include this time limit also) QUESTION 8.12 (1.50) List five logs that the NPS and/or the ANPS shall acknowledge reading on each shift with an entry in Check Sheet #1 of AP 10125, " Schedule of Periodic Tests and Checks". QUESTION 8.13 (1.50) Generator maintenance has been completed with all grounded equipment a. cleared of grounding devices. AFTER verification of ground device removal, what two personnel (by position) are authorized to remove the caution tags on the equipment? l

b. How long can a Caution Tag remain in force before a status review must be made and reported to the Operations Supervisor?

QUESTION 8.14 (1.50) What are the three restrictions regarding approval and initiation of a temporary change to a procedure? (***** CATEGORY 08 CONTINUED ON NEXT PAGE

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82_ J0Dd] NJ S18911ME_ PBQgE gyBES1_ G QUpl1] QNg, _9hp_(J UJ J 81] QNS PAGE 27 DUESTION 8.15 (2.00) State the unit 1 TS LCO that ensures that the pressure induced stresses in the STEAM GENERATORS do not exceed the maximum allowable f racture toughness stress limits. In what mode (s) is this LCO applicable? pressures and time intervals specified in Tech Specs for this situation. bre e ou g r h JY +Le fgY/44 DUESTION 8.16 (2.00) ery State the overtime limit guidelines as stated in admin procedure 10119, " Overtime limitations for plant personnel". QUESTION 8.17 (1.50) List the three requirements relating to the availability of fuel for the diesel generators imposed by technical specifications (unit 1). (If a requirement includes an amount of fuel in gallons, the amount need only be specified within a factor of 2.) DUESTION 8.18 (2.00) AP 0010120 provides for an informal shift turnover. a. Under what conditions may this be utilized in lieu of a formal shift turnover? (0.5) b. What three items of information, as a minimum, must be given to the (1.5) persons releif? QUESTION 8.19 (2.00) a. A maintenance technican is performing troubleshooting which requires the individual to hold a jumper across two wire termination poi'its f or an inoperable Diesel Generator. Is this action permitted by Administrative Procedure no. 0010124 " Control and use of Jumpers "? Explain.

b. Per Administrative Procedure no. 0010124 under what two CONDITIONS can independent verification be waived?

(***** CATEGORY OB CONTINUED ON NEXT PAGE

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PAGE 28 .pl_19901NISIBBI1YE_BB99E99BESi_CQNplIJQN@g_@NQ_LidlIBIlgN@ QUESTION B.20 (2.00) Define IDENTIFIED LEAKAGE by listing the two types other than RCS leakage through a steam generator to the secondary system. i l' (***** END OF CATEGORY OB

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

l z .,,e T 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1.1 As a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2. ~ '~ ~ APPLICABILITY: As shown in Table 3.3-1. ACTION: As shown in Table 3.3-1. SURVEILLANCE REQUIREMENTS 4.3,1,1.1 Each reactor protective instrumentation channel shall be {- (-4 demonstrated OPERABLE by the perfomance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-1. 4.3.1,1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation. i 4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table

3. 3-1.

N s_ ST. LUCIE - UNIT 1 3/4 3-1 9g/A

i - 3 o C-18a ,U TABLE 3.3-1 4 E REACTOR PROTECTIVE INSTRUMENTATION l, MININJM [ TOTAL NO. CHANNELS CitANNELS APPLICABLE FUNCTI0tiAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 1 l -s 1. Manual Reactor Trip 2 U1 2 1, 2,and'*' 1 l 2. Power Level - High 4 2(a) 3(f) 1, 2 2f

3., Reactor Coolant Flow - Low

'4/SG 2(a)/SG 3/SG 1,2(e) 2fj 4. Pressurizer Pressure - High 4 2 3 1, 2 2f i S. Containment Pressure.- High 4 2 3 1, 2 2f j g i j y 6. Steam Generator Pressure - Low 4/SG 2(b)/SG 3/SG 1, 2 2f f N 7. Steam Generator Water Level - Low 4/SG 2/SG 3/SG 1, 2 2f-8. Local Power Density - High 4 ?.(c) 3 1 2f d(a) 3 1,2(e) 2f 9. Thermal Margin / Low Pressure 4 9a, Steam Generator Pressure f Difference - High 4 2(a). 3 1,2(e) 2f' .g

10. Loss of Turbine--Hydraulic Fluid Pressure - Low 4

2(c) 3 1 El e

_9 --O TABLE 3.3-1 (Continued) co G REACTOR PROTECTIVE INSTRUMENTATION O n m MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE E FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION i E

11. Wide Range Logarithmic Neutron Flux Monitor a.

Startup and Operating-- Rate of Change of Power - t High 4 T 2(d) 3 1, 2 and

2#

b. Shutdown 4 0 2 3, 4, 5 3

12. Reactor Protection System 4

2 4 1, 2* 4 Logic R

13. Reactor Trip Breakers 4

2 4 ' 1, 2* 4 = L@ t. Mo N N

l TABLE 3.3-1 (Continued) TABLE NOTATION ( l

With the protective system trip breakers in the closed position and the CEA drive system capable of CEA withdrawal.

The provisions of Specification 3.0.4 are not applicable.

(a) Trip may be bypassed below 1% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is > 1% of RATED THERMAL POWER. (b) Trip may be manually bypassed below 685 psig; bypass shall.be.;.,, automatically removed at or above 6B5 psig. (c) Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is > 15% of RATED THERMAL POWER. - (d) Trip may be bypassed below 10~4'% and above 15% of RATED THERMAL POWER; hpass shall be automatically removed when THERMAL power- ~ i s > 10 % or < 15% of RATED THERMAL POWER. ~ (e) Trip may be bypassed during testing pursuant to Special Test Excep-tion 3.10.3. (f) There shall be at least two decades of overlap between the Wide Range Logarithmic Neutron Flux Monitoring Channels and the Power Range Neutron Flux Moni.toring Channels. ACTION STATEMENTS ACTION 1 With the number of channels OPERABLE one less than ~ r_equired by the Minimum Channels OPERABLE require.mertt, restore the inoperable channel to OPERABLE status within 48 hours or be in HOT STANDBY within the next 6 hours and/or open the protective system trip breakers. With the number of OPERABLE channels one less than the f ACTION 2 Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: The inoperable channel is placed in either the bypassed a. or tripped condition within 1 hour. For the purposes of testing and maintenance, the inoperable channel may be bypassed for up to 48 hours from time of initial loss of OPERABILITY; however, the inoperable channel shall ,__f'(qib the tripped condi' tion.' then be either restored to OPERABLE status or placed in T ST. LUCIE - UNIT 1 3/4 3-4 Amendment No. 75, E7, 45 yw ---r- ,-,.w.--

TABLE 3.3-1 (Continued) ACTION STATEMENTS b. Within one hour, all functional units receiving an input from the inoperable channel are also placed in the same condition (either bypassed or tripped, as applicable) as that required by a. above for the inoperable channel. c. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be hypassed for up to 48 hours while performing tests and maintenance on than channel provided the other inoperable channel is placed in the tripped condition. ACTION 3 With the number of channels OPERABLE one less than, required l by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour and at least once per 12 hcurs thereafter. ACTION 4 With the number of channels OPIRABLE one less than required l by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours; however, one channel may be hypassed for up to 1 hour for surveillance testing per Specification 4.3.1.1.1. e l~bf 961 E ST. LUCIE - UNIT 1 3/4 3-5 Amendment No. - 27

e g I [ 2 z' l fcy A Tu r bin e-5 4 / S 2. F4 B Yur bla s T Fig C Pump s ll4b' fig u r e

t j l l M -m 4m y m e m .u' a Id.in f l w. Ma rg e w $m w e . e e e4 O 'S ust d-eus 4 e e ae e e 4 9aos e .e ee e a e . em e a - W w ee. O@ gae e e e ae ge M= eump -M ee e g. g e.= =we p o LA L ~ Tui.e /e n3 n t Fig 4 re ll 47 l l w.

.er a o ST. LUCIR UNIT 1 OFF-NORMAL OPERATING PROCRDLER No. 1-0120034, REVISION 17 REACTOR C001 ANT PIMP - WF-NORMAL 0PERATICN 4.0 SIMPICMS : (continued) 4.7 Reactor and turbine trip as indicated by annunciator D-8, l, " Turbine-Raaetor Trip."

5. 0 INSTRUCTIONS:

51 Immediate Automatic Actions: 1. If the resetor is critical when a RCP trips or is tripped, a reactor ard~ turbine trip will occuI 5.2 Immediate Operator Actions: 1. If either of the following conditions are observed: Valid full acale bearing temperature indication OR Valid rapidly dropping or no indicated level in either the upper or lower oil reservoir. THEN Trip the reactor. AND Trip the affected RCP. NOTE Bearing temperature and oil level abnormalities will normally have other attendant alarms and/or indications i l associated with them which may confira validity of alarm condition versus instrument failure s. l 2. If the reactor is critical and a RCP trips, refer to " Standard Pos t Trip Actions", (1-EOP-Cl). /R17 5.3 Subsequent Actions: 1. Refer to the following applicable section as appropriate from symptoms. 1 A. Reactor Coolant Pump High Vibration Alarm: I - 1. Ensure valid alsrm by cheeking: VB1S-01-1A1 VB1S-01-1A2 VBIS-01-131 VBIS-01-132 2. Compare and record affected pump readings with baseline i. readings. l fcwe // W e

E.- 4 3 A l 5 f C G 2 I = S ,f ,t Q48 QCS Q.1 0.3 4 5 10 NEUTRON DIERGY, MeV ( A) FISS10!' CROSS SECTION FOR U235 I.S E i ~ I.0 E i. 3 ) gu u 9 9 0 9 9 9 - 0 2 4 6 6 IQ 12 .4 NEUTRCN (MCMGY, MeV (B) FISSION CROSS SECTION FOR U238 FIGURE 2 MICROSCOPIC FISSION CROSS SECTIONS FOR U-235 AND U-238 ~ 0 i I b'l ~ 1: ip are a 37

E e 3 4 RCS PLOW FOLLOWING A LOFC EVENT fg.. e ( m, a m. A E .1 8 'e f 10 / a x 0 i 8 I i 0 5 10 15 20 25 30 TIME, MIN / b [7 Q }" 6

f o ....g .g. .g. .g..., .g, ..g. .g. .g. .g. .g. g . \\., g I g e i.. ~ u k., i. I$ u

u. i

n.

s

/ i,; = .= 1 o p 3, o } 1.. p. .\\ ..L. t 8 3 o l o i 2__.. s a = o l I 8 . =, 4 d, 4 l l li I i m [ E l I l t,3,J 5 i 1 l g j i U l i

>=

l l i i y o o e 4 r i c,u .r _.-_ 1 [ i l >i 8 M i E i m 5i; 1.LJ l i M .,e

O a

34 g

-J l ( l Hg o C./3 La o 3 t, wo h a pi 9l g i 4., a p,, t o i f I o l s s o 5, 1 e I I cu a 6 a 4 s A. 4 6 _4, g 4 o y t o e o s 6 a 6 4 4 i, 6 . 1 I 4 l u i. e-t t o o<, l l .s. .s. .t. .e. .t. .t .r. .t. .t. .I. .f. .t. o o o o Eo o o Eo8 E o. o o o o o o o o o o o o o o o o o 8e o o 88o I oe o r-m in w m cu - u o c.re re to w o .e w are .re as.e l cy cu are are [H3d) A1IAI13 G j$ $} ll 0 b

i ~ ST. LUCIE UNIT #2, CYCLE 3 FIGl5E A.2; 200 EFPH XENON BUILDLP TO EMILIBRILM 2800 I

u. 1 e

2700 - - - - - - - - - - - - - - f g 2600 2500 '-- - - - - f i .a 2400 ms M.e.m. " ~ 2300 / 2200 2100 2000 .m m ,,-g 1900 2 1800 ?- 1700 -- -l 9 1600 J M 1500 --/

r-l x

1400 l 1300 -f

n j

1200 Eg 1100 1000 900 .00 x.. =... 1 700 600 500

[

400 1 300 ( l 200 = 100 5 10 1'5 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 H URS FOLLOWING POWER CHANGE $d4 4 PREPARED BY: ACL= N' S-6-% i DATA SOURCE: F241E}H-678

,^ 0 e 0 j 1 f 5 a 9 ? s e. p 9& = 0 u / ^ ^ e m 58 m p = .= 0 Y: 8 B = D E = V ^ ^ O 5 R 7 P v# P A 0 7 ^ 3 p' 5 F 6 ^ t c 7': I EP , / 0 Y 6 C 4 ~ 5 2 5 / R HE Pl T FO 0 5 / N 0 U 0S 5 2V 4 7 j^ E H I R.M T I C 0 UA 4 / - LE I RN .UO 5 GN T IE 3 6 S FX 8 W 0 E-3 ^W 5 e 2 02 p 8 7 3 [ R 5 1 Y-f C 2F 0 A 1 /: YE BC Dm r 5 E0 RS A

L PA ET RA PD 0 0 0 0 0 0 0 0 0

0 0 0 0 o 0 n 0 o a0 0 0 0 0 0 0 0 0 0 0 0 0

0 0 o 0 c 2, 0 8 s 4 2 0 B 6 4 4 2 o 8 s 4 2 0 0 4 4 4 g 3 3 3 3 3 2 2 '2 i 1 1 1

$ mh e9 up e

d c. P ST. LUCIE UNIT #2, CYCLE 3 FIR 5E A.4 200 EFPH ^ 951TD0104 XENW4 Il0RTH ug 4400 4200 ^ D 4000 teos pa m = 3800 M W*- 3600 W n 3400 3200 "g -i =- 3000 T;-- 2000 gggg g N-f2400 [ [-: m -j - + - + - y 2200 l 2000' k: gggg .. _._.T._: i

X, i

l 1600 N- \\- - i 1400 k l 1200 \\- - 3\\-- ( 1000 - - - - - -l - -- \\ l-I 800 ~ -- -- l - -- - 600 g 400 200 1 %g

t---

1. l. 5 10 ' 15 20 25 30 3ti 40 45 50 55 60 65 70 75 80 85 90 PREPARED Bt , b b 8-G646 APPROVED BY: DATO SOURCE F2-CEiH-07S o

l-Ta P ST. LUCIE UNIT #2, CYCLE 3 - FI M A.5c 200 BPH i SANARNILM MH 530 l-I soo mut!sa.o s% pes 526 -- ^ ^ ^ = = I J (3' 522 / --v--- / 518 - - 4+ + l- - 514 - - -/ - 510

- A

~; ^ 506 --- - - - ~ ~~ 502 g--- 498 - - - --l

- ---f -

494 ~ ~- l 490 -- I /i 486

p

-g:---

- =j-482 --i -- - j -- -- 6 478 I -l: I ~ 474 t--- G g 470 ass p-462

p-

- -i-458 --- l-i -- - I - 8 i 454 450 i -- - 446 J-I I - f' 442 l 1-438 d - i.. - I 8 434 l_ . L .I. .l.. 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 360 380 400 420 440 460 480 500 PREPARED BY: I bJ 4'-C-f4 APPROVED BY: D DATA SOURCE: F2-06-R-078

\\\\ r-d ST. LUCIE UNIT #2, CYCLE 3 na5E A.6; HZP 0 EFPH INTEERAL NDHDt GADLPS 3,45 (OYER.AP) I ss 8300 1 1 ggg.. _ -. i _.a 1200 -j-- - -- 7 ~- h ggg _.. - I g ....-. g.. 1100 p-r- l 1050 - I,- --I-n s / 1000 - J: gg --;-= r -=- -4 : a /-- _ .I s 900 r.._ r-1 l 850 g W 800 750 --n--/ 700 7 1 650 ~ - - - - - - ;,;,W C s y C 600 e-eG 550 4 I i g -J 450 r - l - --- - j, : - 400 74-m'- f i -i 350 n- - + -- I 300 .. i.... - /= m-- = - - q: - g -L- - -- - I ---- 'l. - 250 l-1

[---

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L U

16 lL iL A

'"

= Wier 3 WWF4 WWF 5 PIEPAfED Bt J E-S-36 APPRDVED 8% m14 souace: re-a.4i-07, i

m ~ <-~ 11 e qg ST. LUCIE UNIT #2, CYCLE 3 FIlitfE A.7; HZP 0 EFPH INTEliRAL INT}t LEAD liR0lP

s g-440 -

~ ~~ ~ tr' m.: eI.s pee a p 7 s 1 -, - - nn e - .i... y y 420 D I l / 400 --l -/ I / 1 380 l i 360 I-1 1 i 340 f -- ='- g 320 -s p. I i 300 p g80 --~ - - - -.. - -. - --.1 m i b l 260 j = - ---~~- I 1 --I I.' l 240 --i I I e s } 220 i- = 1 j i i go0 4.. -. ..-. -- 3 l l t i

+i 180

--j- - ~ 4--: -~ t i. i t I i 160, t ---i------- i 3 i. .l.. ...I ....l. ....l... l. 60 65 70 75 80 85 90 95 100 105 110 115 120 125 130 135 140 W" PEPAED BY: / M 2 i'S-t6 APPROVED 8Y: DATA S0lflCE: 'F2-M il-078

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i g:

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i i

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O. N. M. N.

o. 2 W f*i,.

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. ~. ST. LUCIE UNIT #2 CYCLE 3 l \\e FIGUE C.2 IfP ARD CRITICAL BWM CSE. VS. BWMF ss 3200 V 1150 6 1100 -=e - 4g -= =-- --" I-1050 1000

=

N = 950 : -- ; 900 . +.

s. -

N .= l-. a50 000

b. -.

=- = g ,s0 I. v -j..= 700 = ^ E \\ = 650 i 600 ..p N= 330 h 500 I 450 N-- m 400 = =. 3' 350 '- 1 k,h q-l -- --- P l l I 300 g 250 I i l r- -i 200 -; = ='

--r:- i l \\- --p --j-- l 150 100 +

i:

)

1 50 c....l........i................l........I.......................................................'...4 1000 2'000 3000 4000 5000 6000 7000 8000 9000 10000 11000 12000 5/'[# APPROVED BY: PREPARED BY: DATA SOIRCE: F2--Cpfr-078

3M 0 .a 0 H i 0 2 -lpI -. 1 W = 0 0 h. 1 = 0 1 = -T = 5 0 0 3 = ^ ~ 0 \\ = = 0 Y 1 B = = D E = V = = O 0 R 0 P =\\ = 0 P 9 A h:= = = = L' 0 3 %\\' 0 = = F 0 = 8 F M lC W = = Y B = = y'. = C 0 0 + S 0 = ,V 7 E 2 E = F \\ = h==- E = F = E DE = E T RO 0 E 0 I AC =-

:-

E 0 N W 6 P E U FP j E H I E B W T W I C 4. R 00

\\

= = W 0 U CO = 5 W T L EA W W RR = \\ = .UE W W G0 T I0 =- 0 E N W S FN 0 M 0 = = 4 =\\ W = W W 6 = W W W 0 W 0 y = 0 W = =- = 3 w W v W l - =-

\\

W 8 W 7, W O 0 W 9-O _ N-d W 2 W 2 F W 0 YE W = W 0 BC K. = 0 R 1 DI W ED y S y A .-. M,. PA ET y A 5 PD l g 3 4 5 6 7 8 9 0 2 3 4 5 6 7 8 9 0 1 2 3 4 n 1 1 1 1 1 1 1 1 1 2 2 2 2 2 a i-V O Nq C gt 1 ~s e9

e y LP [ PIGURE C.5 EOL POST TRIP XENON OVERRIDE r INFORMATION ST. LUCIE 2 CYCLE 2 Approximate RCS Boron Concentration 300 PPM 200 PPM 100 PPM peg yeg pc3 Xenon ( < 5 hours during startup -375 , -390 -407 immediately following shutdown) HR BR HR PCM PCM PCM POWER DEFECT 3"/Hr - 48 - 51 - 54 BR HR HR PCM PCM PCM ( VS 20"./Br -319 -338 -353 HR HR HR l ESCALATION RATE PCM PCM PCM -537 HR [ 30"./Er -479 HR -507 HR j FCM PCM PCM '. 103 HR 2 Pumps 299 HR 207 HR BORON DILUTION 3 Pumps 456 304 152 HR gg, Gr UPS at Group 5 at Group 5 at ECC RECOMMENDED CEA GROUP HEIGHT

60" withdrawn 60" withdrawn 60" withdrawn Based o'n keeping the R critical @ vorst case Xenon, 37./Hr Escalation Rate, l

3 Charging Pumps, +500*PCM above PDIL, Temperature IAW RRS Program. ASI control as per OP-0030123 may prove restrictive. Referencesr 1) CZ Technical Data for Cycle 2

2) Physics curve Book Glossary, Boron Dilution Reactivity Equation, E. J. Wunderlich.

-t: 4 5 W h

g f ig

//i(c L ~ ~ O M

i \\ e N00 N NOTE 1 - REACTOR VESSEL SELTLINE MATERIAL g ~" ~ INITIAL RTag = S*F NOTE 3 - REACTOR VESSEL SELTLINE MATERIAL 40 VEAR RT ENIFT = 35*F ag .4a i 3 310 NOTE 3 - REM &lN8NG PRES &URE SOUNDARY 5_ ~ MAXIMUM RT, = SIPF [ ~ ~

=== LOWEST ~~ SYSTEM MYDRO-E SERVICE U TEMPERATURE _.~ . ~. MEATUPr COOLDOUWN'* : 3400 ~ -MEATW' = I E. m bl E h 5000LDOWN* = 3000 E c = m

i*

{ 1000 o C _ l 1 ass l see ~ , _ MINIMUM PRESSURE ]j TEMPERATURE FOR: lE 2

CRITICAL OFERATION s

-~ 5 _-~ OF CORE -~

- 9 eof 64RITICAL E

4W ~- OPERATION 5 OF M E E - aanvana na PRESSURE __._- _:-:::FOR SOC OPERATION ,- = -- - e_-_ o i o ies, are zoo me soo soo

F SNotCATED REACTOR COOLANT TEMPERATURE Te 1

FIGURE 3.4 2c ReactorCootent System Pressure Temperature Limitations for up to 40 Years of Full Power Operation N ST. LUCIE - UNIT 1 3/4 4-23c Amendment No. [ f a L{ F G-ff V l

3/4 UMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 4 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Limiting Conditions for Operation and ACTION requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for each specification. 3.0.2 Adherence to the requirements of the Limiting Condition for Operation and/or associated ACTION within the specified time interval shall constitute compliance with the specification. In the event the limiting Condition for Operation is restored prior to expiration of the specified time interval, completion of the ACTION statement is not required. 3.0.3 In the event a Limiting Condition for Operation and/or associatad l ACTION requirements cannot be satisfied because of circumstances in excess of those addressed in the specification, the facility shall be placed in at least HOT STANDBY within 6 hours, at least HOT SHUTDOWN within the following 6 hours and at least COLD SHUTDOWN within the subsequent 24 hours unless l corrective measures are completed that permit operation under the permissible ACTION statements for the specified time interval as measured from initial discovery or until the reactor is placed in a MODE in which the specification is not applicable. Exceptions tc these requirements shall be stated in the individual specifications. f l 3.t. 4 Entry into an OPERATIONAL NODE or other specified applicability condi-l tion shall not be made unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the ACTION state- ^ ments unless otherwise excepted. This provision shall not prevent passage through OPERATIONAL MODES as required to comply with ACTION statements. 3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power sourcs is inoperable, it may be considered OPEPABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system (s), subsystem (s), train (s), component (s) and device (s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfied, the unit shall be placed in at least HOT STANDBY within 6 hours, HOT SHUTDOWN within the following 6 hours, and at least . COLD SHUTDOWN within the subsequent 24 hours. l This specification is not applicable in MODE 5 or 6. SURVEILLANCE REQUIREMENTS l 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. l ST. LUCIE - UNIT 1 3/4 0-1 Amendment No. 40 l FQ 12 R A m

~. 7,' -e 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)_ SAFETY INJECTION TANKS LIMITING CONDITION FOR OPERATI0rl 3.5.1 Each reactor coolant system safety injection tank shall be OPERABLE with: a. The isolation valve open, b. Between 1090 and 1170 cubic feet of borated water, A minimum baron concentration of 172'O PPM, and c. d. A nitrogen cover-pressure of between 200 and 250 psig. 1 3 APPLICABILITY: MODES 1, 2 and 3.* ACTION: With one safety injection tank inoperable, except as a result a. / _: of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour or be in HOT SHUTDOWN within the next 8 hours. b. With one safety injection tank inoperable due~to the isolation valve being closed, either immediately open the isolation valve or be in HOT STANDBY within one hour and be in HOT SHUTDOWN within the next 8 hours. l SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE: At least once per 12 hours b'y: a. 1. Verifying the water level and nitrogen cover-pressure in the tanks, and 4 2. Verifying that each safety injection tank isolation valve is open.

With pressurizer pressure > 1750 psia.

f.l'bf /M b ST. LUCIE - UNIT 1 3/4 5-1

1,. 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE: Two physically independent circuits between t$e offsite trans-a. mission network and the onsite Class 1E distribution system, and b. Two separate and independent diesel g4nerator sets each with: 1. Engine-mounted fuel tanks containing a minimum of 152 gallons of fuel, 2. A separate fuel storage system containing a minimum of 16,450 gallons of fuel, and (

3..

A separate fuel transfer pump. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With either an offsite circuit or diesel generator set of the a. above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirements 4.8.1.1.1.a and 4.8.1.1.2.a.4 within one hour and at least once per 8 hours thereafter; restore at least two offsite circuits and two diesel generator sets to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. b. With one offsite circuit and one diesel generator set of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirements 4.8.1.1.1.a and 4.8.1.1.2.a.4' within one hour and at least once per 8 hours thereafter; restore at least one of the inoperable sources to OPERABLE status within 12 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 F%. l'2 8 9 C ST. LUCIE - UNIT 1 3/4 8-1 I

.i ELECTRICAL POWER SYSTEMS ACTION'(Continued) hours. Restore at least two offsite circuits and two diesel generator. sets to OPERABLE status within 72 hours from the time of initial loss or be in at least HOT STANDBY within the next S hours and in COLD SHUTOOWN within the following 30 hours. c. With two of the above required offsite A.C. circuits inoperable, demonstrate the OPERABILITY of two diesel generator sets by perfonning Surveillance Requirement 4.8.1.1.2.a.4 within one hour and at least once per 8 hours thereafter, unless the diesel generator sets are already operating; restore at least one of the inoperable offsite sources to OPERABLE status within 24 hours or be in at least HOT STANDBY within the next 6 hours. With only one offsite source restored, restore at least two offsite circuits to OPERABLE status within 72 hours from time of initial loss or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. d. With two of the above required diesei generator sets in-operable, demonstrate the OPERABILITY of two offsite A.C.

I c*rcuits by perfonning Surveillance Requirement 4.8.1.1.1.a

( ~, within one hour and at least once per 8 hours thereafter;..... restore at least one of the inoperable diesel generator sets to OPERABLE status within 2 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. Restore at least twc diesel generator sets to OPERABLE status within 72 hours from time of initial-loss or be in at least HOT STANDBY within the next 6 hours l and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS j 4.8.1.1.1 Two physically independent circuits between the offsita transmission network and the onsite Class lE distribution systea : hall be detennined OPERABLE at least once per 24 hours by verifying correct breaker alignments and indicated power availability. l l l /48- ~ p.59D ST. LUCIE - UNIT 1 3/4 8-2 u

,1 '.4.2 Initici Corde; sate Pump Start With System Deprcosuri::cd. e NOTE Section 8.2 can be performed using the IC Condensate Pump as the initial pump. However, Section 8.4 or 8.5 must be performed prior to pump start to supply the IC pump with electrical power.

1. heure normal system valve alignment has been completed as per Section 8.1.

~

2. Check hotwell level to be equal to or greater than normal operating level.

3. Check the lutwell makeup regulator and sprays to be in service and an adequeta supply of umter available from the Condensato Storage Tank and/or the SGBTF Monitor Storage Tanks.

4. heure the TCU System is in service and lined up to the Condansate Pump vith greetar than 12 GPM flow.

5. Line up ~ the backup seal unter supply to the Condensate Pumps by performing the following:

A. heure transfer pump suction and discharge valves are open. B. heure V-12558 (Makeup spray / seal unter supply) is open. C. heure the individual seal unter supply valves are open at each pumpt Y-12242 (IA Condensata Pump) V-12245 (IB Condensate Pump) Y-12590 (1C Condensate Pump)

6. Ensure V-9218. (Condensate Pump / Steam Generator fill) is open to allow filling and pressurization of the feeduster sections of piping.

7. Close the discharge valve on the condensate' pump to be started, then reopen the discharge valve just.enough to crack it off the sea t.

i

8. Verify the pump casing and suction strainer vents are open to the Condenser.

9. Reduce the main condensate recire regulator controller setpoint to 1000 GPM.

e pig a te IL W h mim

,-.u 1_<__THEQBY_QE_NQQLE88_EQWE8_EL@NI_QEEB@IlgNg_E(Q1QS[_@NQ PAGE 29 18 lHEBdQQyN@dlCS + ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY 7 QL / COii ANSWER 5.01 (1.00) CR,(a) - 420,000scf; 26,000 scf(b); 140 scf(c); 1,320 scf (d) SL,(a) - 448,000stf; 52,500 scf (b); 1100stf (c) ; 1,166 scf (d). REFERENCE CR lesson " Fundamentals of Natural Circulation"; CR, ROT 3-14, p2 SL,0NDP 120037, p 9. K 302 03/05/85 O2 00 05 00 07 -0.429 -0.429 302 08/18/86 335 11/17/86 ANSWER 5.02 (1.00) (a) REFERENCE CR, OP-203 Rev. 47, p 20. SL, OP-30124 Rev. 29, p 15; SL, OP-30125 Rev 15, p 4.; SL, LT 307, pp 44,31 K 302 03/05/85 03 00 01 06 10 +0.800 +0.800 302 08/18/86 ANSWER 5.03 (1.00) (b) REFERENCE FPC, CR3, HTFF/Thermo, p 82.; SL, PSTHTFF, Ch2, p45, LO12. DPC, OC, T,FFLHT, p 150. 3/O A1.01 (2.9/2.9) 269 8/19/85 12 00 01 03 16 +0.875 +0.875

f " e_T,0 98Y_9E_NgC6[$8_EgWEB_E(@N1_gEgB9IlgN _E6 pips _9NQ PAGE 30 g 1 ISEBd9DYN8DICS ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 5.04 (1.00) (c) REFERENCE OC, OP 1106/01, p 10.; BK,GP-03, p 19.; SL, OP 2200050, p 5.; CR3, pow, sys. ops., pp 22-23.; BK, 20-2-C4, p 37.; SL, LT 307, p41 & LO2. SL, LT 501, p41 L LO36; 62/O A4.03 (2.8/2.9) 269 8/19/85 10 02 03 01 16 +0.375 +0.375 325 5/19/86 06 O2 00 00 08 +0.500 +0.417 302 8/18/86 335 11/17/86 ANSWER 5.05 (1.00) (c) REFERENCE SL, PSTHTFF, HT p 43 & LO 4. ANSWER 5.06 (1.00) (a) REFERENCE SL, PSRT, p 8-11. ANSWER 5.07 (1.00) (d) REFERENCE Westinghouse Reactor Phystis. Sect. I-5, MTC and power defect. DPC, FNRE; SL, RP, Sect. 7.6, 7.7.; SL, PSRT, p 12-2, LO4.

f^ ' gtI_l,HEQBy_QE_NQCLE@B_EQWEB_EL@NI_QB[B@llgN t_ELQ1pS _@NQ PAGE 31 t IHEBdQQyN@dlCS ~ ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 5.08 (1.00) a. More b. More REFERENCE SL, PSRT, p 7-20, LO 16. KOO1/OOO, K5.26(3.3,3.6) o ANSWER 5.09 (.50) True REFERENCE SL, PSRT, pp 9-8,11.; LO If,4,6b. ANSWER 5.10 (1.00) 1. Increasing feedwater f1'ow rate. 2. Sealing of the bottom drain holes by feedwater on an increasing level, i REFERENCE SL, PSTHTFF, Ch4, p54, LO13.; SL, PSTHTFF, chl, LO15. l ANSWER 5.11 (1.00) 1. Low RCS flow 2. Variable high power 3. Local power density 4. Thermal margin low pressure r 5. Asymetric steam generator trip REFERENCE SL, PSTHTFF, ch3, p45, LO3. l Y

OF NUCLEAR _PQWER_ PLANT _QPERATigNt_FLUlQS _AND PAGE 32 i}:g_lHEORYIhERdQDYNAdlCS t ANSWERS -- ST. LUCIE 1L2 -86/11/17-LAWYER, SANDY ANSWER 5.12 - ( 1. 00) Bottom of the reactor core to the top of the steam generator tube sheet. REFERENCE SL, LT 823, p 2 L LO5. ANSWER 5.13 (.50) Peak linear heat rate REFERENCE SL, UILU2 TS, pp 2-1. ANSWER 5.14 (1.00) A gamma is completely asbsorbed by an orbital electron, the electron is ejected from the atom, causing the detector gases to ionize. REFERENCE CR, NETBNC, p 8.2-3; CR, OB 1.99.; SL, LT 410, p 6, LO 1. l ANSWER 5.15 (1.00) Post LOCA hydrogen generation due to corrosion. REFERENCE SL, TS, p B 3/4 6-4. SL, FSAR, chap. 6, p 6.2-69. b ( i

%* e_JdEQBY_QE_ NUCLE 68_PQWEB_E(@NI_QEEB@llgNt_E(UlgS _@NQ PAGE 33 t ISEgdggyN@dlCS ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 5.16 (2.00) 1. a. Reactor (1.0) b. Turbine c. RCP 2. a. It ensures maximum flow for initial decay heat removal at the instant 0.5) ( the reactor is tripped. b. It removes unnecessary operator reliance on automatic protective devices or features (challenges to safety systems). (0.5) REFERENCE SL, LT202, p32, LO12 & 13. ANSWER 5.17 (1.00) Polyethylene (poly, hydrogeneous material) (0.25) The neutrons being detected leaked from the core as fast neutrons and must be thermalized before detection to take advantage of the relatively higher U235 thermal fission cross section. (0.75) REFERENCE SL, TT403, pp 10 & 11, LO1 & 3. ANSWER 5.18 (1.00) U238. (0.25) Though the microscopic fission cross section for U238 is relatively small the large quantity that exists in PSL fuels results in a significant value of macroscopic fission cross section for fast neutrons. (0.75) REFERENCE SL, PSRT, pp 3-7,8, LO6,11.

THEQRY_QF_ NUCLEAR _PQWER_ PLANT _QPERATIQNt_FLUlDS _AND PAGE 34 5-e_ihE60QDYN@dlGS t ANSWERS -- ST. LUCIE IL2 -86/11/17-LAWYER, SANDY ANSWER 3.17 (1.50) A ~~Because of the flywheel, the RCP will continue to rotate due to their relatively-large angular momentum until about /250 seconds af ter trip. mome'tum of the rotor will be too small to B At that time, the angular n offset the resistance,of the pump bearings and the impeller will stop rotating. Loop resistance increases sharply at the point of rotor lockup causing core flow to decrease suddenly. C It eventually stabilizes at about 600 seconds and f ull natural circulation flow is established. REFERENCE SL, LT 823, p 7. ANSWER 5.20 (1.50) During cooldown the inner wall becomes the most limiting location. The 4 inner wall experiences more gamma heating and neutron flux embrittlement from power operations than does the outer wall. This reduces the allowable n t ensi ti es. ( d 44 4,M.4.,,../A2 n 4" g g g,4 i r 1 REFERENCE SL, LT 203, p 26. ANSWER 5.21 (1.00) f The new element will have increased in atomic number by one and the mass number will remain the same as the original element. REFERENCE t CR, NETRO, p 11.2-1; SL, NETRO, p 11.2-1. ANSWER 5.22 (1.00) l i No, it won't.(.25) Delayed neutrons behave as a source themselves. When a l subtri ti c al reactor has sufficient reactivity, the subtritical l multiplication of neutrons becomes significant. The large number of generations associated with this multiplication effectively holds up the decay rate.(.25) The negative SUR becomes > -1/3 dpm. (i. e. less negative-l decays slower) (0.5) L

I Sz,; THEORY OF NUCLEAR' POWER PLANT OPERATION _FLUlQSt_@NQ PAGE 35 g (* IHERdODYN@dlCS ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY REFERENCE NETRO, Ch 6.; SL, PSRT, p 8-34, LO 9. AMSWER 5.23 (1.00) See attached figure 1145C. REFERENCE SL, PSTHTFF, Ch3, p42, LO5. ANSWER 5.24 (2.00) See attached figure 1147. grading; (0.2ea) 1. Th/Tc 2. Tsat 3. secondary arrows (2) 4. primary arrow (1) 5. temperature drop / length greatest at Th & Tc (2) 6. primary curve form 7. secondary curve form 8. Tc close to but above Tsat. REFERENCE GL, PSTHTFF, p58, LO9.

S e_IHEORY OF NUCLEAR PQWER_ PLANT _QPERATigNt_ELUlDS _AND PAGE 36 t t lhERdDDY_N@dlCS ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 5.25 (3.00) a. Using figure C1, boron worth = 9.60 +or-O.02 pcm/ ppm. (0.5) % delta k/k = 10E-3 (delta,k/k)/(pcm) x (pcm/ ppm) =0.0096 % (delta k/k)/(ppm) (0.5)

b. 30%/ (1%/mi n) = 30 min.

30 mi.',utes is fast with respect to xenon changes using figure Al reactivity = 1320-(-940) = -380 pcm (0.5) using figure A6 (HZP is the only curve provided) 1253-380 = 873 pcm 873 pcm = 34(+or-2) inches on group 5 or 116(+or-2) inches on group 4 7000$ WOO 03h g first M hours from -2593 pcm4 o t c. xenon concentration increases for the 4 '"^"+

?? ;n (0.25) absat 3270 pcm, a difference of 1 00

/600 (0.25) so dilute C.9+ ppm /CD (0.25) }L7 r'".t p r 'pp.. - 7C. s,w xenon then decrease back to(the original (-MWr power ) pcm in 20 hours. So borate back)NHr6 pm (0.25) REFERENCE SL, PSRT, Ch 12, LO 1,2&3.; SL, PSRT, Ch 4, LO9 L10.; SL, AP 10140 R3. SL, PSRT. o 4026. Q 6._ LDO W /94 W / w s10.G W /660 h/1. 6 /aiu/e s /47 e ANSWER 5.26 (1.00) Ye=(L-U)/(L+U) where L is the lower excore flux (0.5) and U is the upper excore flux ASI becomes more positive. (0.5) REFERENCE SL, U2 TS, p 1-1.

6.g_PL@N1_SYSIEDS_DESIGNt_CQNIBQ(t_@ND_lNSIBudENI@llQN PAGE 37 ANSWERS -- ST. LUCIE 1L2 -86/11/17-LAWYER, SANDY ANSWER 6.01 (1.00) (c) REFERENCE SL, Lecture outline RPS, figure 7.2.21; SL, LT404, p32, LO2. ANSWER 6.02 (1.00) (b) REFERENCE ST Lucie SD117 "AFW", pp 9; CWD 87708-326; LT 412, p9, LO7. 061/000; K4.07(3.1/3.3) ANSWER 6.03 (1.00) C REFERENCE ST. Lucie SD13 "CVCS", pp 36; SL, LT205, p20. 004/010; K6.13(2.1/2.4) ANSWER 6.04 (1.00) (b) REFERENCE SL, lecture outline #46, ppi,2,4. ANSWER 6.05 (1.00) C REFERENCE ST Lucie SD145 "120VAC and 125VDC", pp 12/13 or SL, LT 503(504), p10, LO 2 063/000; K4.02(2.9/3.2)

6fc_P(ANI_SYSIEMS_DESIGUt_CONIB06t AND INSTRUMENTATION PAGE 38 ANSWERS -- ST. LUCIE IL2 -86/11/17-LAWYER, SANDY ANSWER 6.06 (2.00) a.'both b. unit I c. unit 2 d. unit 1 REFERENCE SL, lecture 47, pp2L3, difference analysis, p34. ANSWER 6.07 (2.00) a. 4,

normal, 4,

slow, b..CCW, stay the same, 2,

4. REFERENCE SL, SDO, p5; SL, book 7, pp SD29-rev.0 0.9. ANSWER 6.08 (1.50) 1) Letdown Heat Exchanger (+.25 ea for any 6) 2) Sample Heat Exchanger { 3) Shutdown Heat Exchanger 4) Spent Fuel Pool Heat Exchanger 5) RCP Seal Coolers 6) HPSI Pump Seal Cooler l 7) LPSI Pump Seal Cool er l REFERENCE l ST. Lucie SD40 "CCW System", pp 25 008/000; K1.02(3.3/3.4) ANSWER 6.09 (2.00) a. The li quid discharge valve is closed b. The blowdown valves and the sample valves are closed c. None d. The surge tank vent is valved from the atmosphere to the chemical drain tank I L

6:e_ PLANT _SY@TEMS_DESIGNt_CQNTRQLt_AND_lNgTRUMENTATiQN PAGE 39 e ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY g REFERENCE SL, SD 37; SL, LT410, pp12,18,20, LD 6. ANSWER 6.10 (1.75) -Minimum letdown at -1.1% deviation (4 /-.5% on setpoints) -First standby charging pump starts at -2.5% dev. -Second -4.2% dev. -Low level alarm at -5% dev. -Back up start signal to standby charging pumps at -5% dev. -All heaters off at 27% level -Lo-Lo Level alarm at 27% level (+.2 for action, +.05 for setpoint ea) REFERENCE ST Lucie SD9 "PZR pressure, relief and level control", pp 54-56 SL, LT 206, Transparency Fig 34A. 011/000; K1.01(3.6/3.9) and A2.03(3.8/3.9) ANSWER 6.11 (1.00) a) No Indication (c l ear / whi te ) b) Red I c) Blue d) Amber REFERENCE St Lucie SD5 "CEDS", pp 27/28; SL, LT405, p27, LD6. 001/000; K4.01(3.5/3.8) ANSWER 6.12 (.50) yes ANSWER 6.13 (3.00) a. Subchannel deviation alarm, high power channel trip, TM/LP alarm, DNBR alarm. b. SUR trip to the RPS,~SUR enable 10E-4% zero mode bypass.1% power. c. Input to RRS for reactor vs turbine power, input to CPCs for calculation of ASI, input to core barrel movement monitor. .1

r 6c;_Pg8NJ_SySIEUS_QESJQN _CQNIBQL _8NQ_lNSIBUDEN1811gN PAGE 40 3 i ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 6.14 (2.00)

1) Alignment keyway (0.04%)

2) Between hot leg discharge nozzles and upper core barrel outlets (nozzle bypass flow [O.74%3)

3) Between baffle plates and core barrel (core shroud leakage [0.26%3)

4) Around inserts in guide thimble tubes in the fuel assemblies (CEA guide tube bypass flow [2.07%3)

REFERENCE NA NCRODP 88.1, "RCS-Reactor-Vessel / Core Construction" Westinghouse PWR Systems Manual "RCS", pp 2.1-39; SL, LT 203, p24, LO6. ST Lucie SD2 "Rx Vessel Internals", Fig 32 002/000; K6.13(2.3/2.8) ANSWER 6.15 (1.75) Their are two electro-hydraulic operated valves per feed line (+.5) They are operated in fast speed in accident conditions by two Hydraulic (N2) accumulators (+.5). In normal ops (slow speed) they use a pneumatic pump (+.5) A spool valve, solenoid air operated determines speed (+.25) REFERENCE ST Lucie SD112 " Condensate and Feedwater", pp 18; SL, LT301, ppb,9, LO5. f 059/000; K4.19(3.2/3.4) ANSWER 6.16 (2.50)

e. reactor cavity filtration system, unit 1 (1.0) b.

it has a higher flow capacity than the fuel pool an shutdown cooling purification system. (250 gpm)[/L ph, (0.5) c. suction - from the refueling cavit (near th reactor vessel) (1.0) discharge - back to the cavity via a line common to the fuel pool purification piping to the cavity REFERENCE SL, LT 208, pp16,17, LO1.

PAGE 41 ..se_PL@NI_@Y@ led @_QE@lGN _CQNIBQ6t_GNQ_lN@lBydENI@llgN 6 t ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 6.17 (1.00) A heated thermocouple's output is compared with an unheated thermoccuple's output.(+.3) With no liquid to remove the heat, the temperature difference becomes large, creating a large voltage output (+.7) REFERENCE ST Lucie QSPDS Handout, pp 16; SL, LT407, p21. 017/020;K4.01(3.4/3.7) ANSWER 6.18 (1.00) Header pressure is 100 psi below the opposite steam generator or auxiliary feedwater header pressure. REFERENCE SL, LT 412 r2, p12. ANSWER 6.19 (2.00) Pressurized nitrogen is inserted into the hoist box by hose, replacing the cooling water. The cooling water flows out the bottom into the fuel pool. This gas can then be vented through a scintillation counter after a soak period has been completed. Cflow paths (0.5 ea); fluids (0.25 ea); detection (0.5)] REFERENCE SL, LT 208 r2, p59, LOS. l ANSWER 6.20 (1.00) 1. Allow for system pressurization to be controlled from the pump discharge valve. 2. Aid in valve opening ease once the pump is started. REFERENCE SL, OP 1-700020 r16, p 33; SL, LT301, LO2a.

4 7.J+-PRQGEQURgG_ _NQRMAL _AQNQRMAL,_EMgRQgNQY_ANQ PAGE 42 3 RhDJQ6QQJC@6_CQNIBQL ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 7.01 (1.00) (c) - (No chloride monitor listed among symptoms) REFERENCE SL, OP-1-610030 ANSWER 7.02 (1.00) (c) REFERENCE SL, OP-1-12OO20, ppi,2. ANSWER 7.03 (1.00) (b) You need 4 to go over 1750 psig. This is a requirement for going above 275 psig. (Note - d is referenced to going >250 degF, but you can't go over 1725 psig without Tavg >250 degF without exceeding the 350 degF deltaT limit between the PZR and Tavg. REFERENCE SL, OP2-30121 ppi-5. ANSWER 7.04 (1.00) 1 (d) l REFERENCE SL, OP-2-163OO24, p4. ANSWER 7.05 (1.00) (b) REFERENCE-SL, HP-2 r5, p 16.

c -Zac_ERQQEQURES_ _NQRMAlt_AQNQRMAlt_EMgRGENQY_ANQ PAGE 43 BE91QLQGlC@6_CQNIBQL 7' ' ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY s ANSWER 7.06 (1.00) (d) REFERENCE SL, 1-EOP-04, p6. ANSWER 7.07 (1.00) (a) REFERENCE SL, 1-EOP-03, p21. ANSWER 7.08 (1.00) (c) REFERENCE SL, ONOP 2-310031 r3, pl. ANSWER 7.09 (1.00) a) Unit 1 (+.5 ea) b) Unit 1 REFERENCE STLucie OP 1/2-0030127, pp 1, 7; pp2,10. 002/020; PWG-12(3.7/3.7) 4 ANSWER 7.10 (.50) False REFERENCE SL, ONOP 1-110030 r12, sect 5.4.2a, p7

.Z-e_PBgCEggBES_ _NgBD8L _9DNgBD963_EDESGENCy_9Ng PAGE 44 2 S' B69196gGIC06_CgNJBg6 ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 7.11 (.50) True REFERENCE SL, HP-2, p17. ANSWER 7.12 (2.50) 1. Place reheater control system in manual, then close TCVs.

2. Open startup transformer breakers.

3. Reduce Tavg to reference setpoint (Tref =532 degF) by manual operation of the atmospheric steam dump valves.

4. Isol ate S/G blowdown.

5. Verify IC steam driven AFW pump has started and has established flow to the S/Gs.

If AFW pumps have started due to the auto start feature, manual control can be taken after the auto actions are completed. REFERENCE SL, ONOP 1-30140 r29, p 4. ANSWER 7.13 (1.50) 1. entry nto an airborne radiation area =or> 25*/. MPC 2. wori 3signments involving irradiated fuel

3. work assignments involving equipment or surfaces contaminated to levels

> 10,000 DPM/100cm squared. REFERENCE SL, HP-1, pl.

a 'Z:a_P8QQEQUBES_;_NQ8d@bt_@BNQ80G(t_EdE8@QNQY_@NQ PAGE 45 S' 869196001G66_QQN18QL ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ' ANSWER 7.14 (2.00) 1. containment air particulate monitor 2. containment radioactive gas monitor 3. componnent cooling liquid monitor 4. condenser air ejector gas monitor 5. steem generator liquid sample monitor 6. plant vent-radiation monitor 7. containment area radiat.on monitors 8. high l evel, pressure or temperature i'n the quench tank 9. high temperature reactor coolant relief or safety valve discharge line

10. low level in' volume control tank 11.high level reactor coolant drain tank 12.high level containment sump

13. low pressurizer level 14.high level component cooling water surge tank

15. safety relief valve (s) open alarm -H11 16.high SI loop header pressure REFERENCE SL, ONOP 1-0120031, r10, p2.

ANSWER 7.15 (2.50) 1) Stop withdrawal and insert CEAs to 500 pcm below critical condition 2) (Recheck ECC)(not required as statement in question may preclude) 3) Recheck boron concentration by chemistry sample 4) Verify CEA position 5) Verify agreement between NI channels 6) Notify reactor engineer Cany 5 at 0.5 each] REFERENCE ST Lucie OP 0030126, pp 1/2; SL, 1-0030122, r28, p2 001/010; A2.07(3.6/4.2) e

r a e Z:.t_P8QQEQUBES_;_NQBd@(t_@BNQBd@6t_Ed[BGENQY_@NQ PAGE 46 S' 569196QGlG86_QQNI@Q( ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY A ANSWER 7.16 (1.50) 1) Turbine tripped (+.3 ea) 2) Generato. OCBs open 3) Exciter Field Breaker open j 4) Electrical Auxiliaries transferred to S/U Xfrmrs 5) At least 1 DC bus energized REFERENCE ST Lucie EDP-1, pp 4, step 2 EPE-OO7; PWG-11(4.0/4.0) ANSWER 7.17 (1.50) 1. All clearances have been properly released. 2. All tags have been removed and valves, switches, etc. are in their required positions. 3. The system has been tested to the extent that it is evaluated as safe to be returned to service. REFERENCE SL, OP 10122 r21, p2. ANSWER 7.18 (1.50) 1. After each refueling. 2. The conditions used in the ECC calculation are questionable and/or unreliable due to a lack of steady operation as determined by the NPS. 3. An excessive reactivity anomaly, which could affect this approach to c r i t i c a,11 ty, has existed since the last time at which critica111ty was achieved. (An excessive reactivity anoraly is defined in Reg. Guide 1.16 and STS-6.9.1.B.d). l l REFERENCE SL, OP 2-30126 rl, p2.; SL, OP 30221. l

Z:(_PBgCE9UBES_;_NQBd@62_8BNQBU661_EdgBGENCY_8Np PAGE 47 3' BG91969GJC96_CgNIBQL ANSWERS -- ST. LUCIE IL2 -86/11/17-LAWYER, SANDY ANSWER 7.19 (2.00) 1. the steam supply to the turbine seals 2. air in-leakage to the condenser 3. the deltaT of the circulating water across the condenser 4. the status of the circulating water pump 5. the circulating water box prime 6. the steam jet air ejector operation 7. the SJAE loop seal B. the condition of feedwater heater alternate dump valves REFERENCE SL, ONOP 2-610031 ro, p2. ANSWER 7.20 (1.50) Auto - Runback to 60% on loss of one MFW pump Immed - Ensure S/G 1evels can be maintained with availabile MFW or reduce steam demand until levels can be maintained If runback occurs, ensure reactor power is matched with turbine power REFERENCE SL, EOP 1-700040, p3. / ANSWER 7.21 (1.50)

c. prevents bowing of the rotor b.

prevents seal damage due to pulling in air and dirt across the glands

c. minimizes water intrusion into the turbine REFERENCE SL, OP 2-30124 r17, ppi,2.

ANSWER 7.22 (1.00) Since saturation Temperature for the RCS safeties is < 700 deg F, this would represent a superheat condition in the RCS which could only occur with core uncovery (+1.0)

a Zat_P8QGE9UBES_;_NO8d@6t_@BNOBd@(t_EDEBQENgy_@NQ PAGE 48 Be9106091Cet_CgN18QL ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY REFERENCE CEN-152, pp 5-77 for LOCA discussion EPE-074; EK1.02(4.6/4.8) ANSWER 7.23 (1.00) To preheat the auxiliary spray. REFERENCE SL, EOP<2-120040 r4, p7. l' i I ~ i f h-I I I i I l i

f~ e PAGE-49 ja,ze_0Qd1Ni@l8@llyE_P8gGEQUBE@g_QQNQlligN@t_@NQ_(ldll@llQNS ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY- -ANSWER B.01 (1.00) (c) REFERENCE SL, TS-2, p 1-7,2-9,6-12,4-9. PWG-5(TS) (2.9/3.9) ANSWER B.02 (1.00) (c) REFERENCE SL, TS, pp 3-2,4,5. 15/20; PWG-5(2.8/3.9) ANSWER 8.03 (1.00) (a) REFERENCE SL, TS2, p 9-1. 34/0; PWG-5(2.8/3.7) ANSWER 8.04 (1.00) (c) REFERENCE CR, EM-207 Rev. 16, p 5; VG, 10CFR20.403, (2) and (4). ANSWER 8.05 (1.00) (d) REFERENCE SL, TS1, p 3/4 0-1

PAGE 50 Hyt_@DdlNI@IB@llyE_P8QCEQUBE@t_CQNQlligN@g_@NQ_(ldlI@llgNS ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY 64/50; PWG-5(3.1/4.1) ANSWER 8.06 (1.00) (b) REFERENCE SL, TS1, p 3/4 7-9. ANSWER B.07 (1.00) (a) REFERENCE SL, TS2, p 3/4 7-10. ANSWER B.08 (1.00) (d) REFERENCE SL, TS2, p 3/4 5-1.~ ANSWER 8.09 (2.00) a. true b. true i c. false d. false l REFERENCE SL, AP 10432 r24. l 1 l L

7 = 8.. ADMINISTRATIVE PROCEDURES _CQNQlTlQNS _ANQ_LlMITATlQNS PAGE 51 t t ..,s. ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 8.10 (2.00) a. 1. Revi ew the uni t's Tech Specs. (1.5) 2. Review the unit's EOPs. 3. Review the unit's night order, equipment out of service log, CCO log, and specific station log for the previous seven dayu. 4. Complete a minimum 8 hour watch. 5. Pass an oral exam on the specific unit. b. Less than four months have elapsed since the person last worked on the unit. (0.5) REFERENCE SL, AP-OOO5720 PWG-23; (2.8/3.5) ANSWER 8.11 (2.00)

a. Restore Tavg to =or> 515 degF within 15 minutes.

b. Be in hot standby within the next 15 minutes. REFERENCE SL, TS1,2, pp 3/4 1-7,6. ANSWER 8.12 (1.50) 1. reactor control operator's log 2. equipment out of service log 3. night order book 4. turbine operator log 5. nuclear operator log REFERENCE SL, AP 10120, pB. ANSWER 8.13 (1.50) a. The responsible Foreman or an Electrical Department Supervisor. [0.5ea] b. One month [0.53 k

v = t4_ ADMINISTRATIVE PROCEDURES _CQNQlTigNQt_ANQ_LlMlTATlQNQ PAGE 52 8 t ,s. ' ANSWERS -- ST. LUCIE IL2 -86/11/17-LAWYER, SANDY REFERENCE St. Lucie.AP 0010135 PWG-14(Tagging / Clearances) (3.6/4.0) ANSWER 8.14 (1.50) 1. The intent of the procedure is not altered.

2. The changes are approved by 2 members of plant management, one holding a SRO license on the affected unit.

3. The change is documented, reviewed by FRG, and approved by the Plant Manager within 14 days.

ANSWER 8.15 (2.00) The temperature of both the primary and secondary coolants in the steam generators (0.5) shall be > 70 degF (0.5) when the pressure of either coolant in the steam generator is > 200 psi. (0.5). All modes.(0.5) REFERENCE SL, U1TS, p3/4 7-13. ANSWER 8.16 .(2.00) 1. An individual should not be permitted to work more than 16 hours straight, excluding shift turnover time. 2. An i ndi vi dual should not be permitted to work more than 16 hours in any 24 hour period, nor more than 24 hours in any 48 hour period, nor more t than 72 hours in any 7 day period, all excluding shift turnover time.

3. A break of at least 8 hours should be allowed between work periods, including shift turnover time.

4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

REFERENCE SL, AP 10119, r8, p3. a i I l l i

7 ~ Brt_0DdlNi@lB@llVE_PBQQEDUBE@t_QQND111QN@t_@@D_(ldlI@llQN@ PAGE 53 . :r, ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 8.17 (1.50)

1. Engine mounted fuel _ tanks (0.3) containing > 152 gallons of fuel ( O'. 2 )

2. Fuel storage system (0.3) containing >16,450 gall ons of fuel.0.2) ( 3. Fuel transfer pump (0.5) REFERENCE SL, U1TS, p 3/4 8-1. ANSWER 8.18 (2.00) a. If the person being relieved must leave their assigned station for a period of less than two hours. (0.5) b. 1. status of the control board (1.5) 2. off normal conditions 3. tests in progress REFERENCE SL, AP 0010120, p12. PWG-23 d (2. 8/3. 5) ANSWER 8.19 (2.00) a. Yes - As long as continous physical contact is maintained. [1.03 b. 1. Return to service of equipment where functional testing is required to prove operability of the system or component. CO.53 2. Cases of significant radiation exposure any room or area where there exist radiation levels >1000 mr/hr. [0.53 REFERENCE St. Lucie AP 0010124 p. 2, 3.2.1.3 PWG-14(Tagging / Clearances) (3.6/4.0) PWG-13(Valve Lineup Verification) (3.7/4.0) I,

w f g PAGE 59, Br#_0DyJNJSJB91JyE_BBggEQUBES3_QQNgllJgNS2_9Ng_6]DJJ811gNS s. * * -ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY 9 ANSWER 8.20 (2.00) 1. Leakage (except controlled leakage). into closed systems, such as pump . seal or valve packing leaks that are captured, and conducted to a sump or collecting tank. 2. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary leakage. REFERENCE SL, UlTS, p1-4. 4 l = -,,

(- .i T I e-2 2' A 5 fig '/ 4-.- 'A-1 Fig B s T d n, / t t I Fig C s l ~A NS W E Rb l=cg.a rc I I LI 5~ \\ _____.__.______._.___,_._._,.__,.,__,__._____..___.._l

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/ U. S. NUCLEAR REGULATORY COMMISSION ([()[) REACTOR OPERATOR LICENSE EXAMINATION ~ FACILITY:- _gTt_LUCIg_1kg___________ REACTOR TYPE:- _PWR-gg__________________ DATE ADMINISTERED: _g6/11/1Z________________ _LAWygR _gANpy___________ EXAMINER: 2 CANDIDATE: 'INSIBygIlgNg_Ig_g@Np199IEi Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses af ter 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 six (6) hours after the examination starts. % OF CATEGORY % OF CANDIDATE'S CATEGORY __Y0 lye _ _19186 ___gCgBE___ _y@(yg__ ______________g81gggBy_____________ _29299 _ _2Ez99 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW _I2ses__ _29199 ________ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS 2.1 o o _9fr@@"__ _2?z99. ________ 3. INSTRUMENTS AND CONTROLS _29299__ 2Ez99 ________ 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL // Sv0 1;;tsi__ Totals Final Grade All work done on this examination is my own. I have neither given nor received aid. Candidate's Signature s l

~ Cs, NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS o 4 During the administration of this examination the following rules apply: 1. Cheating on the examination means an automatic denial 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 gnly 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 eagh section of the answer sheet. 8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a ngw page, write gnly gn gng sidg 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 thrgg 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 cnly if they are commonly used in facility litetatute.

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. l

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. j

e a d P

Y '

18. When you complete your examination, you shall a.

Assemble your examination as follows: (1) Exam questions on top. (2) Exam aids - figures, tables, etc. (3) Answer pages including figures which are part of the answer. b. Turn in your copy of the examination and all pages used to answer the examination questions. c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions. t 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. i

1 l z.._'B BI Ng1 EL E g_QE _ N9G L E 98_ E99E B _ EL 9NI_ QE E B 911 gN PAGE 2 i

v,ISEBDQpVNSDIGga_SE91_IB9NSEg8,9ND_ELUlp_ELgW

( DUESTION 1.01 (1.00) Which one of the following gases are NOT limited by Unit 1 Tech Specs in the gas storage tanks? c. hydrogen b. nitrogen c. oxygen d. xenon QUESTION 1.02 (1.00) Which one of the following sources can potentially introduce the largest (in standard cubic f eet) amount of non-condensible gas into the RCS? c. Zirc-water reaction. b. Safety injection tanks. c. Pressurizer vapor space. d. 100% failed fuel. (***** CATEGORY 01 CONTINUED ON NEXT PAGE

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/ c_ /

' 'l __EBJNCJELEg_9E_NgCLE98_EgyEB_EL@NI_9EEB91]QN PAGE 3 2 .,IUEBdggyNedJgg,_egeI_IBeNSEEB_8ND_ELylp_ELQW e QUESTION 1.03 (1.00) Which one of the f ollowing statements is CORRECT concerning the paralleling of electrical systems? o Although it is desirable to have speed and phase position matched, it is much more important to have voltages matched. b. If voltages are not matched at the time the synchronizing switch is closed, there will be VAR flow from the lower voltage source to the higher one. c. If the incoming machine is at synchronous speed but out of phase with the running bus when the breaker is c1csed, heavy currents will flow to either accelerate or retard the incoming machine. d. If the incoming machine is in phase but slightly faster than synchronous speed when paralleled, the system will tend to speed up the system to synchronous speed, e. If the resistances are not matched at the time the synchronizing switch is closed, heavy currents will flow to tend to speed up the incoming machine to synchronous speed. QUESTION 1.04 (1.00) Which one of the following correctly describes the response of core delta T if the RCS coolant flow rate is reduced while the steam system is controlling to maintain 80% electrical output? Unit I has been operating at 80% of full power, steady state, for 10 days. All control rods are fully withdrawn (ARD). a. Delta T will remain the same since the turbine / generator output power has not changed. b. Delta T will remain the same but nuclear power will increase to provide the same megawatt thermal output. c. Delta T will increase but nuclear power remains the same to provide the same megawatt thermal output. d. Delta T will increase and nuclear power must increase to provide more steam flow to the turbine. (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****) i b_ /

[ ' I z _ _f BI NGI EL E S_9E _ NUg(E 88_ E9 WEB _EL @NI_gEg B911gN PAGE 4 i '.IBEBdQQyN9diggi_SE@l_JB9NSEEB_8Ng_E6Ulg_E(gW QUESTION 1.05 (1.00) Initially, one centrifugal charging pump is in operation when a second centrifugal charging pump in parallel with the first pump is also put into operation. Which statement below correctly describes the effect on system volumetric flow rate and system head loss 7 a) Higher flow rate, higher head loss b) Same flow rate, higher head loss c) Higher flow rate, same head loss d) Same flow rate, same head loss QUESTION 1.06 (1.00) Which one of the following will cause plant efficiency to increase? a. Total S/G blowdown is changed from 30 gpm to 40 gpm. b. Steam quality changes from 99.7% to 99.9%. c. Level increase to higher than normal in a feedwater heater. d. Absolute condenser pressure changes from 1.0 psi to 1.5 psi. QUESTION 1.07 (1.00) Which one of the curves on the attached figure 1172 correctly represents the xenon concentration for the given power history? QUESTION 1.08 (1.00) Of the following, which must the main condensor remove the most heat from to condense? (assume steam is of equal quality)

a. one pound of steam at O psia b.

one pound of steam at 300 psia c. two pounds of steam at 600 psia d. two pounds of steam at 1200 psia (***** CATEGORY 01 CONTINUED ON NEXT PAGE

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PAGE 5 Iz__EBJNCJE(ES_gE_NgCLE98_EggEB_E(@NI_DEEGOIJgN i .IUEBdggyN9DICS _UE91_Ig@NSEEB_9N9_ELylp_E(gg i QUESTION 1.09 (1.50) For the changes listed below (treat each one independently) indicate whether the moderator temperature coefficient will become MORE NEGATIVE, LESS NEGATIVE or have NO EFFECT. (Assume all other parameters are constant) e) Neutron flux peak shifts radially inward from the edge of the core, b) Boron concentration decreases 100 ppm while core is at MOL. c) Increased number of burnable poisons are inserted into the core. QUESTION 1.10 (.50) A general rule is of ten stated " doubling the count rate halves the margin to criticality". This is mathematically stated by the equation: CR1/CR2 = (1-Keff2)/ (1-Keff1) Is the following statement True or False? "Both Keff1 and Keff2 must be less than one in order for this to be true". QUESTION 1.11 (1.50) Indicate whether the following will cause the Upper-Lower summer output to become more positive or less positive (i. e. indicate direction of change) a. Power increase with power defect compensated for by dilution only. b. Power increase with power defect compensated for by rod withdrawal only. c. Buildup of xenon in the top portion of the core. i QUESTION 1.12 (1.00) The driving force for subcooled natural circulation flow (steady state) at 4 St. Lucie is about 26 feet. Between what two points in the RCS is this measured? i.e. Answer in the form "from the top / bottom of component A to the top / bot of component B". i i l (***** CATEGORY 01 CONTINUED ON NEXT PAGE

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I

'12__EBJNCJELES_QE_NUCL[98_EO ER_EL NT_9EEB91]QN PAGE I[ 2 .IBEBDQQyNOd]CS _DE81_IB8NSEEB_9Np_ELUlp_ELQW 2 QUESTION 1.13 (.50) Which of the three unit 2 reactor saf ety limits is NOT specified as a safety limit on unit !? (Numerical value not required.) QUESTION 1.14 (1.50) List the three main power producing isotopes in the core at end of life end indicate their approximate contribution ( i n

/.)

to power. QUESTION 1.15 (2.00) gkg manhkED of What is the PREFERRED sequence for the tripping d the to or THREE components referred to in step 5.1.1 (RCP, Rx, Turb.) the event of a rapidily dropping level in the RCP lower oil reservoir? What are the two reasons for this sequence being preferred? See figure 1149. QUESTION 1.16 (1.00) Describe the changes that occur in the atomic number and mass number of an atom when it decays by negative beta emission. Remember the atomic number is the number of protons and the mass number is the number of neutrons plus protons. QUESTION 1.17 (1.00) The reactor is made to be subtritical by a very small amount of reactivity (less than the value of beta). Will the resultant stable negative startup rate approach -1/3 dpm? Explain. QUESTION 1.18 (1.00) Explain the two effects that result from decreasing RCS flow (at constant power) which cause a decreasing Critical Heat Flux Ratio. Ensure your cnswer addresses both CHFR and thermal hydraulic considerations. (***** CATEGORY 01 CONTINUED ON NEXT PAGE

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r 'iz_JEB1NCIE(ES_QE_NUCLEQ8_EQWE8_E(@N1_QEg8@llQN PAGE 7 s .ISE8dQQyN@dlG$t_dE@l_18@NSEE8_@NQ_E(UlQ_E(QS QUESTION 1.19 (1.50) Indicate whether the viscosity of each of the following increases or decreases with INCREASING temperature. Also, explain why they each change. a. water (l i qui d ) b. steam (gas) QUESTION 1.20 (2.00) Describe HOW and WHY the following will respond to a loss of natural circulation flow following a reactor trip from 100% equillibrium conditions. c) RCS wide range temperature difference (Delta T) b) Relationship between Tcold wide range and S/G pressure QUESTION 1.21 (1.00) a) What is the most significant method of xenon removal while at LOW power levels? b) What happens to samarium concentration for the first week after an increase in power level to 100% from 50% ? (i.e. increase, decrease, or remains the same). QUESTION 1.22 (1.00) Draw and label the ideal and real Rankine cycle curves for a FW or condensate PUMP on the attached figure 1145C. To aid you in better understanding the question, example figures 1145ALB have been provided. On these are drawn the TURBINE portion of i deal ( 1-2) and real (1-2' ) Rankine cycles on both T-S and Mollier(h-s) diagrams. These ar somewhat exaggerated diagrams to more clearly show the difference between the real and the ideal TURBINE cycles. (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

'It_JEBING1ELES_9E_NQCLEOB_EQWE6_ELONI_QEEB@llOUt PAGE O .ISEBdQQYN901QSt_UEGl_lBONSE[6_@NQ_E(ylQ_E(QW QUESTION 1.23 (2.00) Sketch the primary (RCS) and secondary temperature profiles for a Utube S/G (at 100% power) which has a height of approximately L/2 (ie the tube length is L) on the attached figure 1147. Label the endpoints of the primary curve Th and Tc. Indicate by arrows, the direction of fluid flow on EACH curve. Label the horizontal axis at 0, L/2 and L. Show the relation of Tsat to Tc and Th. QUESTION 1.24 (3.00) St Lucie unit 2 has been operating at a steady 100% of full i power for 7 days with all of the CEAs fully withdrawn from the core..The burnup is 5000 EFPH on cycle 3. Answer a, b, and c below using cny of the provided figures and tables. Show your work and/or how you errived at your answer. See figures 1156 A-L. a. What is the value of boron worth in (% delta k/k)/ ppm and in pcm/ ppm. (1.0) b. The reactor power level is now reduced to 70% of full rated power at a rate of 1 % per minute by inserting rods (programmed bank motion). What is the rod position when the power change ic complete? (1.0) c. You are to maintain this 70% of full power for the first 20 hours after the power level change. You do not wish to move the control rods. Explain what change will be required to the boron concentration to compensate for xenon changes. Give aumerical values. Neglect any effect due to samarium poisoning and show calculations. (1.0) (***** END OF CATEGORY 01

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2. PLANT DESIGN _lNC(yDlyG_S8EETY_QND_ EMERGENCY _@X@TEd$ PAGE 9 QUESTION 2.01 (1.00) Select the one INCORRECT statement concerning the intake cooling water system (ICW). c. The power supply for pump 1C is the AB bus, which normally is lined up to receive power from the B network. b. Upon loss of offsite power, bearing lube water for the ICW pumps will NOT be interrupted because of the backup supply from the domestic water system, c. Upon loss of offsite power, if all three ICW pumps are available for starting, pump 1C is not started to avoid overloading the diesel generators. d. All three ICW pumps receive an auto start signal upon SIAS. QUESTION 2.02 (1.00) Which one of the following statements correctly describes how to reset the MECHANICAL overspeed on the turbine driven AFW pump? a. It must be reset locally, after driving the limitorque to the open position, to relatch the linkage, b. It must be reset locally by using a lever to relatch the linkage. c. It will reset automatically as turbine speed decreases below a pre-determined setpoint. d. It may be reset l oc al l y, but can also be reset from a switch on RTGB 102 in the control room. (***** CATEGORY O2 CONTINUED ON NEXT PAGE

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2 . PLANT _pgglgN_1NCLUDINg_ggEgly_9Np_EDEBGENCy_SySIEDS PAGE 10 QUESTION 2.03 (1.00) Select the CORRECT statement concerning the instrument air system. a. .On loss of instrument air, the backup air compressor will start at approximately 85 psig. b. At about 80 psig decreasing, the cross-connect capability from unit 1 to unit 2 is lost. c. If the backup compressor automatically starts, it will automatically stop when air pressure is restored. d. Following a blackout, the air compressors must be locally reset on both units before being restarted. QUESTION 2.04 (1.00) The reactor cavity cooling system consists of two full-capacity fans with: (select one of the following) a. the operating requirement (ONOP 2000030) to be at =or< 50% power with the loss of one reactor-cavity cooling fan. b. the fan in standby started automatically on a CIAS. c. the fan in standby started automatically after a 10 second delay on LOW flow in the operating fan d. the fan in operation restarted automatically after a loss of off-site power as demanded by the D/G shutdown sequencer. QUESTION 2.05 (1.00) Which one of the f ollowing describes the purpose of the suction stabilizers j (dampeners) associated with the charging pumps? a. Prevent excessive pulsation levels in the piping downstream of i the charging pumps. i b. Prevent overpressure of the suction side of the charging pumps. j! c. Minimize system losses due to acceleration head and assure that sufficient NPSH is available. l d. Provide an isolation signal for the appropriate charging pump i if suction side pressure oscillations become too large. (***** CATEGORY O2 CONTINUED ON NEXT PAGE *****) i 4

q. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY _@Y@TEMS PAGE 11 QUESTION 2.06 (1.00) Which one of the f ollowing correctly describes the normal lineup of the 125 VDC swing Bus? a. The swing bus AB is powered from the A-side train in UNIT 1. b. The C train i s powered from either of the A or B buses via the swing bus AB in UNIT 1. c. The swing bus AB is powered from the A-side train in UNIT 2. d. The swing bus AB is supplied by either a battery charger or a battery backup in UNIT 2. QUESTION 2.07 (1.00) The pressurizer system design is intended tor (select the correct statement) a. compensate for volume changes in the RCS for design transients of a 10% power / minute ramp or a 5% power step. b. provide suf ficient steam volume to prevent the water level from reaching the relief valve nozzles f ollowing a reactor trip. c. provide a small enough water volume to minimize the pressure buildup in the containment following a LOCA. d. provide sufficient water level to prevent draining the pressurizer f ollowing a load reject incident. QUESTION 2.08 (1.00) The shutdown cooling heat exchangers are used to remove heat during cooldowns (select the correct statement) a. only if the pressure in the pressurizer is =or< 1500 psia and the RCS temperature is =or< 500 degF. b. only if the CCW inlet temperature i s =or< 55 degF. c. with the cooldown rate controlled by throttling the SDC return valves to the LPS1 headers. d. with the cooldown rate controlled by throttling the LPSI flow control valves which are in series with the SDC heat exchangers. I (***** CATEGORY O2 CONTINUED ON NEXT PAGE

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2. PLANT _DEg]GN_]NCLUp]NG_gAgETy_ANp_gMgRggNgy_SygTEMS PAGE 12 QUESTION 2.09 (1.00) Which one of the f ollowing statements regarding the 120 volt instrument and vital AC systems is correct? a. The normal source of 120 VAC vital is from 480 VAC MCC 1AB via step down and regulating SOLA transformers to the static switch and transfer switch to vital AC panel number 1A. b. Unit 1 has two vital AC buses, while unit 2 has only one vital AC bus. c. Both units 1 and 2 normally utilize two 125 VDC buses to supply power to static inverters that feed eight 120 VAC instrument buses. d. The maintenance bypass transformers for providing alternate power to the 120 VAC instrument buses actually consist of two transformers, one to lower the voltage from 480 VAC to 120 VAC and one to stabilize and regulate the voltage. QUESTION 2.10 (1.50) Indicate whether the following statements regarding the main steam system cpply to UNIT 1, UNIT 2 or BOTH UNITS. c) The atmospheric steam dump isolation valves can be remotely operated from the control room. b) A check valve downstream of the MSIV is utilized to prevent backflow of steam from the other S/G if a steam break were to occur upstream. c )' 8 Safety Valves, divided into two groups that will lift at different pressures, are located on each steam line upstream of the MSIV. QUESTION 2.11 (1.00) Indicate to which Unit (s) the following descriptions of RCP seal injection cpply. c) The Regenerative Heat Exchanger inlet is interlocked with the Seal Injection Isolation MOV. b) During Back-up Seal Injection operations, two charging pumps are needed (***** CATEGORY O2 CONTINUED ON NEXT PAGE

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'2. PLANT DESIGN INCLUDING SAFETY _AND_EMERGENQY_@YG1gMG PAGE 13 QUESTION 2.12 (1.75) For each of the components identified by the upper case letters A thru H on 4 figure 1190, choose the correct component from column B below and write its column:B number next to its identifying letter on your answer sheet. The first item i s completed f or you. 2 Column A Column B A 5 1 Recirculating i mpel l er B ______ 2 Auxiliary impeller C ______ 3 Integral heat exchanger D ______ 4 Mechanical seals E ______ 5 Cooling water outlet F ______ 6 Seal injection inlet l G ______ 7 Control bleedoff H ______ 8 Cooling water i nlet QUESTION 2.13 (3.00) For each of the functions listed in a, b, and c below, match the affected valve (s), 1,2,3,and/or4 of the main turbine. Assume that the valve i position limiter is at'100%. I c. valves closed by the overspeed (not backup 1. throttle valves overspeed) protection controller (OPC) 2. governor valves b. valves closed by the overspeed trip i mechanism 3. reheat stop valves i ^ c. valves opened when the turbine is latched 4. interceptor valve QUESTION 2.14 (1.50) Upon loss of a unit 2 SUPS inverter, the off normal operating procedure requires you to check the reflash module RA-RAB-4 to determine which SUPS is in alarm. e. Where is RA-RAD-4 located? (What wall of the cable spreading room) b. If you are unable to gain access to the cable spreading room, which inverter does this indicate has failed? 'c. Which switch / button and what position (depress, up, down, on, etc.) (figure 1105) would you use to restore power to the bus? (***** CATEGORY O2 CONTINUED ON NEXT PAGE *****) ? ..-~n_-,, ,,.,---,_n.. -,,,,,.-,_r,,,-n,_.,, ..--,,n,--,,-,_

2___ELON1_DESl@N_lNCLUDlG@_SQEEly_QNQ_EDE8GENQ1_Sy@ led @ PAGE 14 ~ QUESTION 2.15 (2.00) Describe the 4 flow paths within the reactor vessel which BYPASS the fuel rods. QUESTION 2.16 (1.00) Why do the UNIT 1 Containment Spray Pumps require Seal Water Heat Exchangers, while the UNIT 2 Containment Spray Pumps do not? QUESTION 2.17 (1.75) Describe the two operational modes of the UNIT 2 Main Feedwater Isol ati on Valves. Include a description of the motive force for the valves, number of valves per feedline, their response in both normal and accident conditions and the manner or method in which speed is controlled. QUESTION 2.18 (2.50) In addition to f uel pool purification of the refueling cavity, and shutdown cooling purification, one unit has an additional filtration system to keep the cavity water clear. a. Name the system and unit. (1.0) b. What design feature allows it to maintain clarity? (0.5) c. From where does it take a suction and to where does it discharge?(1.0) QUESTION 2.19 (1.00) What are two purposes of the quench tank? (***** CATEGORY O2 CONTINUED ON NEXT PAGE *****)

2 PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 15

) DUESTION 2.20 (2.50) Sealing between the nuclear reactor vessel head flanges is provided in the oystem design. a. What control room instrumentation can be used to alert the operator of a failure in the sealing? Consider two situations separ-stely: 1) the l failure of the inner seal and 2) the failure of both seals. (1.0) I b. How is the amount of leakage from the RCS from between the flanges 4 determined? (1.0) c. If there is a leakage from between the seals, the leakage is of what type? (unidentified, identified, etc.) (0.5) 4 T QUESTION 2.21 (1.50) Describe the difference in the operation of the diesel oil transfer system for UNIT 1 and UNIT 2 when a demand signal for the transfer pumps to start is received. (The control switches are in AUTD). Include auto start signal ] cnd all auto actions from start to stop. i I .I t i (***** END C CATEGORY 02

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i

.3 __JNSIBgDENIS_9ND_CQNJgg(S PAGE 16 1 QUESTION 3.01 (1.00) Which one of the statements below, regarding the circulating water system is INCORRECT? a. When a circulating pump is started, its corresponding discharge valve automatically opens to 30% and then fully opens 15 minutes l ater if the pump is still running. b. In order to start circ water pump 1A1, the discharge valve for circ water pump 2A2 must either be shut or fully open with circ pump 2A2 running. c. If a circ water pump is started with its discharge tunnel already being supplied by the other common circ pump, then it takes only five minutes for the second circ pump's discharge valve to open. d. If lubricating water flow to an idle circulating pump is low (less than 8 gpm), the pump cannot be started. QUESTION 3.02 (1.00) Which one of the following reactor trips DOES NOT receive an input from the core protection calculators? a. Thermal margin / low pressure b. Local power density c. High rate of change of power d. Variable sw(r power A89L (***** CATEGORY 03 CONTINUED ON NEXT PAGE

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3.

INSTRUMENTS AND CONTROLS PAGE 17 s e i QUESTION 3.03 (1.00) Which one of the f ollowing statements is CORRECT with respect to the unit 2 incore instrumentation? 4 a. One of the purposes of the intere instrumentation system is to provide l an accurate source range neutron detection system for use during reactor startups. b. There are more than 100 incore instrumentation (ICI) detector i assemblies. l C. The heated junction thermocouple (HJTC) system measures the reactor coolant liquid inventory above the fuel alignment plate. d. In each of the ICI detector assemblies there are four self powered rhodium neutron detectors which measure the neutron flux distribution t ) above the fuel alignment plate. J f QUESTION 3.04 (1.00) i The reactor coolant pump seal tube leak alarm is activated: (select one of the following) by a high deltaT between the RC at the inlet and at the outlet of the e. shaft seal heat exchanger, b. by a high deltaT between the CCW at the inlet and at the outlet of the shaft seal heat exchanger. c. if there is a high RC temperature at the outlet of the shaft seal heat exchanger and if a 60 second delay has occurred since the actuation of the high temperature signal. d. If the seal cooler CCW outlet valve is closed. } 1 i i l I i i i I ( I (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****) i 4 ,v,- ye,- ,,,_,.,_rw----_7. ,,--,-,ww-y-_,--% ,.,m.,,3 -,m.m,-.%,w-,

}.

' INSTRUMENT @_AND_ CONTROLS PAGE 18 i . QUESTION 3.05 (1.00) i Which one of the f ollowing statements correctly. describes the operation and control of the main feedwater pumps? a. If both main feedwater pumps were in operation with the total feedwater flowrate at 40*/. o f full power flowrate and if one of the two operating condensate pumps tripped, then one feedwater pump should trip. CI e'b b. If the suction pressure for an operating main feedwater pump has ~~ fallen to 300 psig and a five second delay has occurred, the feedwater pump snould trip. c. If the flowrate of an operating main feedwater pump has reached the LO-LO setpoint and a =or) 10 second delay has occurred, the feedwater pump should trip. d. If the lube oil pressure of an operating main feedwater pump has dropped to 6 psig and a =or> 10 second del ay has occurred, the feedwater pump should trip. s QUESTION 3.06 (1.00) Which one of the statements below CORRECTLY describes the ef f ect of the condenser vacuum interlock on the Steam Bypass Control System? a. If ALL M/A stations are in AUTO when vacuum is regained, then the Condenser Vacuum Reset button must be depressed to remove the interlock. b. ONLY if the Master Integrated Controller is in Manual, is it required to depress the Condenser Vacuum Reset button to remove the interlock. c. It makes no difference if the M/A stations are in Manual or Auto, when the condenser vacuum is regained, the interlock is removed automatically. l d. If ANY of the M/A stations are in manual when vacuum is regained, i then the Condenser Vacuum Reset button must be depressed to remove the interlock. i I 1 i f (***** CATEGORY 03 CONTINUED ON NEXT PAGE

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PAGE 19 3:__JNSJBUDENI@_OND_CgNJBgL@ QUESTION 3.07 (1.00) Which one of the f ollowing is used as an input to the Steam Generator Level Control System when power is less than 157.? a. Nuclear Power b. Feed Flow / Steam Flow Mismatch c. S/G Downtomer Level d. Steam Flow Generated Level Program QUESTION 3.08 (1.00) As it applies to the Core Protection Calculator, which one of the following describes Thermal Power? a. Average That - Highest Tcold b. Average Thot - Average Tcold c. Highest Thot - Highest Tcold d. Highest That - Lowest Tcold e. Highest That - Average Tcold QUESTION 3.09 (1.00) Indicate for each of the following statements whether they apply to the Control Element Drive Mechanism System on UNIT 1, UNIT 2 or BOTH UNITS. I a) During a withdrawal sequence, when the lift coil energizes, it exerts a downward magnetic force on the anti-ejection gripper armatures, allowing the lifting motion to take place, b) The CEA Withdrawal Prohibit (CWP) may be bypassed by depressing a pushbutton on the control panel for the CEAs. I i OUESTION 3.10 (.50) I Answer TRUE or FALSE to the following statement regarding the ESFAS measurement cabinets. 1 c) If a condition which caused a Trip Bistable to trip has cleared, then ) the lighted Trip Reset Pushbutton will no longer be illuminated. 1 4 f l (***** CATEGORY 03 CONTINUED ON NEXT PAGE

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l

3:_.INSIBUDENIS_9ND_CONIBDLS PAGE 20 QUESTION 3.11 (2.50) Answer the f ollowing question concerning the intake cooling water (ICW) pumps by filling in the blanks. dWY a. The three ICW pumps are centrifugal pumps each with a capacity of _____ gpm (+or-10%) with a/hischarge pressure of _____ psig (+or-10%) Muy b. Upon loss of off site power, the system is automatically restarted and loaded onto the emergency diesel generators. If all three ICW pumps are available, _____ pumps are started. The interruption in ICW pump operation should be less than (give approximate time). During oper ati on in which the ICW pump motors are powered from the emergency diesel generators, the bearing lube water supply is from _____. QUESTION 3.12 (1.25) Pressurizer pressure is 2270 psig decreasing and Pzr level is minus 4.0% from program and increasing. Fill in the tabl e below with open, closed, on, off or min as appropriate. Assume that the reactor is at 100% of full power, CVCS controllers are in automatic and charging pump #2 and #3 are the first and second backup pumps respectively. Spray Prop Backup Letdown CP CP CP valve (s) Htrs Htrs Valve (s)

1
2
3 on/ min on QUESTION 3.13 (1.00)

Indicate what type of detector is used in the following excore instruments: a) Unit 1 Wide range Logarithmic Safety Channel b) Unit 2 Linear Safety Channel c) Unit 2 Logarithmic Startup Channel (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

PAGE 21 3, ' INSTRUMENTS _AND_CQNTRQLp QUESTION 3.14 (2.00) What automatic actions (other than alarms) occur, if any, when the f ollowing process radiation monitors exceed their setpoints? Consider each of the f our monitors separately. a. Liquid discharge monitor b. Steam generator blowdown monitor c. Letdown process monitor d. Component cooling water monitor QUESTION 3.15 (2.00) The qualified safety parameter display system (DSPDS) determines three saturation margin monitoring (SMM) values, a. List tne three margins and the associated temperature sensors that are utilized. (1.5) b. What signal is used to provide the saturation temperature? (0.5) QUESTION 3.16 (2.00) For unit I there are 3 HPSI pumps. a. What is the design pressure and flowrate for a HPSI pump? b. What is the primary water supply for the HPSI pumps and what is or the available volume of water required by T.S.? l OUESTION 3.17 (1.50) l l List the 4 inputs to a Reactor Regulating System Cabinet and indicate if any differences in the inputs from UNIT 1 and UNIT 2 exist. (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****) l I

.3:__,1NSIRUMENIS_OND_CQNIBQLS PAGE 22 QUESTION 3.18 (1.75) With the reactor at 30% power, all controllers in AUTO, heaters and sprays off and one charging pump running, the pressurizer level starts to decrease from its setpoint. List the changes in the CVCS and any alarm / protective functions that occur as pressurizer l evel decreases until a TM/LP trip occurs. Give the applicable setpoints and note any differences between UNIT 1 and UNIT 2. (Assume no operator action) QUESTION 3.19 (1.00) Indicate the color that will be displayed on the UNIT 1 CEA Core Mimic display for each of the following situations: a) Shutdown CEA in its operating band b) Regulating CEA is at its Upper Electrical Limit (UEL) c) Shutdown CEA is at 120 inches d) Regulating CEA is dropped QUESTION 3.20 (1.50) Describe how the UNIT 1 Wide-Range Logarithmic Safety Channel controls the indicating range that is supplied by the instrument. Include in your discussion any indications that inform the operator of what scale is in effect. i QUESTION 3.21 (3.00) a) What is the purpose of the Power Trip Test Interlock? b) What three trips are automatically bypassed by the RPS? c) How is the Zero Power Mode Bypass initiated and when is this bypass automatically removed? QUESTION 3.22 (1.00) Describe how the Heated Junction Thermocouple (HJTC) System detects a collapsed liquid level above the core. (***** END OF CATEGORY 03

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4 PBQCEQUggg_;_NgBDO(1_gggggDO(2_gDggggNgy_ gyp PAGE 23 2_2:809196pGIC06_CgNIBg6 QUESTION 4.01 (1.00) Which one of the following is correctly stated regarding a permissible dose to an operator (w/o form NRC-4) in a restricted area as specified in j 10CFR2O? c. Under non-accident conditions, the operator is permitted to receive no more than 7 1/2 rems per calendar quarter to each hand and to each foot. b. Under non-accident conditions, the operator is permitted to receive no more than 1 1/4 rems of beta per calendar quarter to the lens of the eye. c. Under accident or emergency conditions, the operator is permitted to receive up to 25 rem once in a lifetime exposure. d. Under accident or emergency conditions, the operator is permitted to receive up to 100 rem once in a lifetime exposure. QUESTION 4.02 (1.00) Which one of the following " Radiation Area" definitions" means the same as that given in HP-2, "FP&L health physics manual"? a. any area where the dose rate exceeds five mrem /hr or where, in any j five consecutive day period, exceeds 100 mrem /hr at any time. b. any accessible area where a major portion of the body could exceed a dose of five mrem in any one hour, or in any five consecutive days a dose in excess of 100 mrem. c. any accessible area where any portion of the body could exceed a dose rate of five mrem /hr or where, in any five consecutive day period, l could exceed a dose rate of 100 mrem /hr at any time. l l d. any area where the dose rate to any portion of the body could exceed a dose of five mrem in any one hour, or in any five consecutive days a dose in excess of 100 mrem. l t l l (***** CATEGORY 04 CONTINUED ON NEXT PAGE

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l l L

'42_ _f B9CE DUBE S_;_UQBUS62_9BNQB D862_ E Dg BGENCy_ OND PAGE 24

BBDID6gGJC86_CQNIBQL QUESTION 4.03 (1.00)

If a steam generator tube rupture occurs on Unit 1 and if all RCPs are stopped, RCP restart criteria CANNOT be met if: (choose one) a. the CCW has been lost for four minutes. b. the RCS is 30 degF subcooled. c. the pressurizer level is 40%. d. the unaffected steam generator level is 30% wide range. QUESTION 4.04 (1.00) The unit I hydrogen recombiner should always be placed in service when the hydrogen concentration in containment is in which one of the following ranges? a. O.5% to 3.5% b. 0.5% to 4.5% c. 1.5% to 3.5% d. 1.5% to 4.5% e. O.0% to 4.0% QUESTION 4.05 (1.00) Which one of the f ollowing locations is where the "B" RCO reports to on a Control Room Evacuation due to inhabitability? a. Remote Shutdown Panel b. Electrical Equipment Room, Reactor Auxiliary Building l c. Turbine Operating Level d. LPSI Pump Room i t (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

42_ _ PB gg E QUBE S_;_NQBd862_8 BNQBU862_EDEggg dCy_ @NQ PAGE 25 B9D1969GJC96_CgNIgg6 QUESTION 4.06 (1.00) Which one of the following is the RCP trip strategy in EDP-5(Excess Steam Demand), assuming CCW is maintained to the pumps, RCP operating limits are maintained and Pressurizer pressure falls to < 1300 psia? a. Trip all-RCPs b. Trip one RCP in each loop c. Trip the two RCPs associated with the faulted S/G d. Trip one RCP in the loop associated with the faulted S/G e. Leave all four RCPs running QUESTION 4.07 (2.50) According to procedure 2-30127, " reactor plant cooldown - hot standby to cold shutdown" at unit 2; a. What would be the control status and position of the following (2.0) valves when taking the pressurizer solid? (manual or auto) and (open, closed or throttled) 1. pressurizer level control valves LCV-2110P and LCV-21100 2. letdown pressure control valve b. Below what temperature may the pressurizer be taken solid? (0.5) QUESTION 4.08 (1.00) Indicate whether each of the following statements regarding cooldown of the reactor plant are applicable to UNIT 1, UNIT 2 or BOTH UNITS. a) The shutdown cooling system (SDC) shall NOT be placed in service until the RCS pressure is < 265 psia and the temperature is < 325 degF b) When the RCS temperature is < 500 degF and RCS pressure is < 1500 psig rack in the breakers and close the SI Tank discharge valves. Rack the I breakers out again once the valves are closed. t QUESTION 4.09 (.50) Is the following statement TRUE or FALSE? If at 100% of full power on unit 1, a CEA has dropped into the core, the operator should immediately commence emergency boration in order to reduce power to =or< 50% within 1 hour. (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

4 __TBgCEQgBES_ _NgBd863_8BNQBD861_EdEBGENCY_8ND PAGE 26

809196gG1c06_CgNIBQL DUESTION 4.10

(.50) Is the following statement TRUE or FALSE? An EXCLUSION AREA is defined in St Lucie plant procedures as ...any area specifically barricaded and locked to prevent unauthorized entry and conspicuously posted as an exclusion area (in addition to any other required postings)". QUESTION 4.11 (1.50) If, during refueling operations, an accident which resulted in damage to a NEW fuel element occurred, what is the ; 1) immediate automatic action and

2) five immediate operator actions according to procedure 2-1600030,

" Accidents involving new or spent fuel"? Assume the accident occurred inside containment. L QUESTd'ON 4.12 (2.50) Five.of the ten immediate operator action steps on a complete loss of off-site' electrical power are listed below. State the remaining five. 1. Trip Turbine and reactor manually 2. Ensure all CEAs are fully inserted and reactor trip breakers are open 3. Ensure turbine valves are closed 4. Ensure generator exciter supply: breaker and generator breakers are open

5. Ensure that diesel generators hkve started and are feeding only emergency buses QUESTION 4.13 (2.00)

I fIntheunit 1 control room, sixteen positive indications of leakage of , coolant from the RCS to containment or to other systems are provided by , equipment which permits continuous monitoring of certain plant parameters ,End the activity of other systems. List eight of these; ie, eight different types of equipment, which may alarm and indicate when excessive leakage is present. 1 l (***** CATEGORY 04 CONTINUED ON NEXT PAGE

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PAGE 27

4:_ PB9CEQUBES_;_N9BDOL _9pNgBD96,_EggBQggCy_9ND 1

B99196991C96_CQNIBQL QUESTION 4.14 (2.50)

If it appears that critical conditions are going to be achieved 600 pcm LESS THAN the calculated ECC, what five actions, verifications and notifications are required as stated in OP 0030126, "ECC and ICRR"? QUESTION 4.15 (2.00) If a UNIT 2 Blackout occurs, what 8 loads on the emergency buses are not tripped? (Similar loads like load centers or group A pumps are considered as the same load) QUESTION 4.16 (1.50) What five substeps constitute verification that plant electrical power requirements are satisfied in EOP-1? QUESTION 4.17 (1.50) What are the 5 symptoms that a SG Tube Rupture has occurred as listed in the Entry Conditions of EOP-4 (SGTR)? QUESTION 4.18 (2.00) While operating at 100% of full power, St Lucie unit 2 experiences a slow decrease in the condenser vacuum. List eight things that could be checked to determine the cause of the decrease in the condenser vacuum. QUESTION 4.19 (1.50) Assume unit 1 is operating at 100% power when a main feedwater pump trips. List the expected automatic actions AND your immediate actions assuming the transient does NOT cause a reactor trip. l (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

4t__PBQGEQUBES_ _NQSd@(t_@BNQBd@(t_EDEBQENgy_QNQ PAGE 28 8091960GlG0(_QQNIBQL DUESTION 4.20 (1.50) Certain limits and precautions are addressed i n the unit 2 operating procedure 2-30124, " Turbine startup". State the reason for each of the following, a. Gland steam should be placed in service after the turbine is on the turning gear. b. Gland steam should be placed in service bef ore a vacuum is drawn. c. Steam header drain valves must be open below 20% load. DUESTION 4.21 (1.00) Why are Core Exit Thermocouple temperatures > 700 degrees F an almost certain indication of an uncovered core situation? e I o i (***** END OF CATEGORY 04

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

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saass et i ST. LUCIE mtIT 1 c OFF-NOINAL OPERATING PROCRDtRE NO. 1-0120034, REVISION 17 REACTOR C001 ANT PIMP - 0FF-MORMAL OPERATION 1 4.0 SDiPICMS : (continued) 4.7 Reactor and turbine trip as indicated by annunciator D-8, j. " Turbine-Reactor Trip." l

5. 0 INSTRUCTIONS :

I l 5.1 Immediate Automatic Actions: 1. If the resetor is critical when a RCP trips or is tripped, a j reactor and~ turbine trip will occuE 5.2 Immediate Operator Actions: 1. If either of the following conditions are observed: Valid full scale bearing temperature indication 01 l Valid rapidly dropping or no indicated level in either the upper or lower oil reservoir. THEN Trip the reactor. AND Trip the af fected RCP. NOTE Bearing temperature and oil level abnorsalities will normally have other attendant alarms and/or indications associated with them which may confirm validity of alarm condition versus instrument failures. 2. If the reactor is critical and a RCP trips, refer to " Standard Post Trip Actions", (1-EOP-01). /R17 5.3 Subsequent Actions: 1. Refer to the following applicable section as appropriate from [ symptoms. A. Reactor Coolant Pump High Vibration Alarm: 1. Ensure valid alarm by checking: VBIS-01-1A1 VBIS-01-1A2 VBIS-01-131 VB1S-01-132 2. Compare and record affected pump readings with baseline i. readings. f { h 4 5' 0 t

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e 1 PIGURE C.$ E0L POST TRIP XENON OVERRIDE r INFORMATION ST. LUCIE 2 CYCLE 2 Approximate RCS Boron Concentration 300 PPM 200 PPM 100 PPM peg yc3 pg Xenon ( < 5 hours during startup -375 -390 -407 immediately following shutdown) HR HR g PCM PCM PCM POWER DEPECT 37./Hr - 48 - 51 - 54 HR HR HR PCM PCM PCM 20"./Hr -319 ~330 -358 VS HR HR HR ESCALATION RATE PCM PCM PCM -537 ER 30"./Er -479 ER -507 HR FCM PCM PCM 103 HR 207 gg 2 Pumps 299 gg BORON DILUTION 152 'HR - 3 Pumps 456 304

uP5 at Group 5 at Group 5 at ECC RECOMMENDED CIA CROUP HEIGHT

60, withdrawn 60" withdrawn 60" withdrawn i

Based o'n keeping the R critical @ vorst case Xenon, 37./Hr Escalation Rate, 3 Charging Pumps, +500D CM above PDIL Temperature IAW RRS Program.

- ASI control as per OP-0030123 may prove restrictive.

Referencesr 1) CE Technical Data for Cycle 2

2) Physics Curve Book Glossary, Boron Dilution Reactivity Equation.

E. J. Wunderlich. g i ',.,,s.. - v fig I/iG L ~ '

.~. ___-. s 100 , W h) id 80 4. v. .i. .: 'E. u q. s e W N y e. e.,es me o. ....====**** U b, s E g C. t W W W y W W M to to go see ese ses d, j u s %Q 40 Go 80 too 12.0 140 TIME ( hours) G UR E ll 72. c...-_n.,c_,,n_-

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t F 4 .-,x r T h l-2, A ) - 18s 6 "lM ~N 7 Wik p. i L, ,w-E s ,i g L

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q g ac u b -q _---- = -=% 'N n .A = c...... ..a..., 'O f Y Q -3 r N Z ,,l "'goy'c .i U 1+ I N \\\\\\ - . _-b / . sus. i p G i wo. ma.o [ \\ ) ( [ cIU m$*'cTea A: B: C: l D: E: F: G: H: -g1) Reciruciating Impeller (2) Auxiliary Impeller (3) Integral Heat Exchanger ( 81) Mechanical Seals (5) Cooling Water Outlet (b) Seal Injection Inlet (7) Control Bleedoff - EduRE //90 (8) Cooling Water Inlet n _ - - - - ~,. _ - - -___.,,y ,,m.. - _,, w,,,-,,_,

EBINCIE(ES_QE_NyC(E@B_EQWEB_E(@N1_QEEBGllgN PAGE 29 1: IeIMEgdQDyNQtlGS_ME@l_18@NSEE6_OND_E(ylD_E(QW u t I NSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY A b t/ ) ANSWER 1.01 (1.00) (b) i REFERENCE SL, U1TS, p 3/4 11-15. ANSWER 1.02 (1.00) CR,(a) - 420,000scf; 26,000 scf (b) ; 140 scf (c); 1,320 scf (d) SL,(a) - 448,000scf; 52,500 scf (b); 1100stf(c); 1,166 scf (d). I i-REFERENCE CR lesson " Fundamentals of Natural Circulation"; CR, ROT 3-14, p2 SL,0NOP 120037, p 9. K 302 03/05/85 O2 00 05 00 07 -0.429 -0.429 1 302 08/16/86 335 11/17/86 4 1 1 ANSWER 1.03 (1.00) 1 (c) REFERENCE I OC, OP 1106/01, p 10.; BK,GP-03, p 19.; SL, OP 2200050, p 5.; CR3, pow. sys. ops., pp 22-23.; BK, 20-2-C4, p 37.; SL, LT 307, p41 & LO2. SL, LT 501, p41 L LO36; ~ 62/O A4.03 (2.8/2.9) l 269 8/19/85 10 02 03 01 16 +0.375 +0.375 l 325 5/19/86 06 02 00 00 OO +0.500 +0.417 302 8/18/86 335 11/17/86 + ANSWER 1.04 (1.00) (C) i l I 1

it _EBINQlELEQ_QE_NUQLEQB_EQWEB_P(@N1_QEEg@llQN PAGE 30 i s e UIHF,JdQ Q YN@dlC S t _H E @l_18@NS EE 6_@N Q _E((llQ _E(Q W -I ANSWERS -- ST. LUCIE IL2 -86/11/17-LAWYER, SANDY REFERENCE -SL, PSTHTFF, HT p 43 & LO 4. ANSWER 1.05 (1.00) (a) REFERENCE. CNTO, " Thermal / Hydraulic Principles and Applications, II", pp 10-45/4B O06/050; K5.01(2.9/3.1) ANSWER 21.06. (1.00) f I (b) 5.. REFERENCE General Physics, Heat Transfer Thermodynamics and Fluid Flow, pp. 145 - 160. ST Lucie Thermo Handbook, Chapter 2d SL, PSTHTFF, Ch2, LO5. OO2/OOO-K5.01 (3.1/3.4) ANSWER 1.07 (1.00) 4 (c) REFERENCE SL, CNTO, pp 4-16/27. KOO1/OOO K5.13(317/4.0) t' ANSWER 1.08 (1.00) (c) REFERENCE steam tables f i n l I y e.- 1r-W-e-r----mm--1 T --ye'v'M--**-*==-'T e--=--r-W-vm TT--* 1v--+1+-w--' yee +--e- '--*y- -Pr- +h-- T c --1--rm

E81NCIELES_QE_ NUCLE 88_EQWE8_ELONI_QEEB@llgN PAGE 31 12b_eIHERMQQYN9MlCS,_HE81_IB@NSEEB_@ND_E(UlD_E(QW g j IANSWERS -- ST. LUCIE IL2 -86/11/17-LAWYER, SANDY l ANSWER 1.09 (1.50) 1 a) Less (+.5 ea) b) More c) More REFERENCE ST Lucie Reactor Physics, Section 7.5.1.2.2 SL, PSRT, Ch7, pp 7-20/27, LO14. 001/000; K5.26(3.3/3.6) ANSWER 1.10 (.50) j True REFERENCE SL, PSRT, pp 9-8,11.; LO if,4,6b. i ANSWER 1.11 (1.50) c) Less 1 b) More c) Less REFERENCE St. Lucie SD 4, pp 36 and Reactor Physics Supplementary Handout #2 015/020; K5.03 & K5.07(3.3/3.7) l ANSWER 1.12 (1.00) Bottom of the reactor core to the top of the steam generator tube sheet. REFERENCE SL, LT 823, p 2 & LOS, 1 i i r i t

1 __EBINGlELES_QE_UUCLEBB_EQWE8_E(@N1_QPEB@llgN PAGE 32 t viUE50QQYN@dlGS _UE61_18@NSEE8_@NQ_E(Q1Q_E(QW a t I ANShERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 1.13 (.50) Peak linear heat rate REFERENCE SL, Ul&U2 TS, pp 2-1. ANSWER 1.14 (1.50) U-235 40-50% (+.4 for isotope, +.1 for contribution to power in order) Pu-239 40-50% U-238 5-9% REFERENCE SON /WBN License Cert Trng, " Reactor Kinetics", pp 6 St Lucie Reactor Physics Section 7.6.7; SD 1, pp 33 001/000; K5.47 (2.9/3.4) / ANSWER 1.15 (2.00) 1. a. Reactor (1.0) b. Turbine c. RCP 2. a. It ensures maximum flow f or initial decay heat removal at the instant the reactor is tripped. (0.5) b. It removes unnecessary operator reliance on automatic protective devices or features (challenges to safety systems). (0.5) REFERENCE SL, LT202, p32, LO12 & 13. ANSWER 1.16 (1.00) The new element will have increased in atomic number by one and the mass number will remain the same as the original element. REFERENCE CR, NETRO, p 11.2-1; SL, NE1HO, p 11.2-1.

12__EBJNCIELES_QE_NyCLE88_EgWEB_EL8NI_gEEBOllgN PAGE 33 1

VIHE8DQDYN8dlCS _HE81_IB8NSEEB_8ND_ELylD_E6pW 3

I ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 1.17 (1.00) No, it won ' t. (. 25) Delayed neutrons behave as a source themselves. When a subcritical reactor has sufficient reactivity, the subtritical multiplication of neutrons becomes significant. The large number of generations associated with this multiplication effectively holds up the decay rate.(.25) The negative SUR becomes > -1/3 dpm. (i. e. less negative-decays slower) (0.5) REFERENCE NETRO, Ch 6.; SL, PSRT, p B-34, LO 9. ANSWER 1.18 (1.00) Lower flow at the same power l evel resul ts,in a larger delta T(+.25); CHF Ratio is the ratio of CHF to Actual Heat _ Fl ux'i at a speci f i c location in the core (+.25). The decrease in flow resuts in less stripping action to remove bubbles forming at nucleation sites on the cladding and therefore ~ e steam film could form at the lower flow rates.(+.5) REFERENCE SON /WBN HTFF ST Lucie Thermo Handout, Ch 2, Section E, Part 2.40 SL, PSTHTFF, Ch3, Boiling Heat Transfer, p43, LO4. 003/000; K5.01(3.3/3.9 ) ANSWER 1.19 (1.50) c. decreases (0.25) b. increases (0.25) As temperature increases, the viscosity of liquids and gases varies (1.00) in opposite directions. In l i qui ds, increased molecular vibration caused by rising temperature tends to weaken the attraction between adjacent molecules, reducing the viscosity of the liquid. In gases, however, molecular attraction is very weak. Molecular vibration, increasing with temperature, results in more collisions and interference between molecules moving past each other. The viscosity of gases increases with temperature. REFERENCE SL, PSTHTFF, p 14, LO 9.

m 1 __EBINQlELE S _QE _NyCLE OB _EgWE B _P(@N1_QPE 8@llgN PAGE 34 i 4'. THERMODYNAMICS _HEQ1_TR@NSEER_ONQ_E691Q_E(QW t 8 ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 1.20 (2.00) a) Delta T increases (+0.7) as That increases due to boiling and Tcold remains relatively constant (+0.3) b) Tcold will not follow Psteam (+0.7) as Pstm decreases due to boil off in the S/G while Tcold will remain relatively constant (+0.3) i REFERENCE General Physics, HT & FF, pp 356/7 SL, PSTHTFF, Ch4, pp60-63, LO12 EPE-017; EK1.01(4.4/4.6) i ANSWER 1.21 (1.00) a) Xenon decay [+.5 ea] b) Decreases REFERENCE SL, PSRT, Chapt 4. i ANSWER 1.22 (1.00) See attached figure 1145C. REFERENCE SL, PSTHTFF, Ch3, p42, LOS. I I l ANSWER 1.23 (2.00) See attached figure 1147. l-l grading; (0.2ea) 1. Th/Tc 2. Tsat 3. secondary arrows (2) 4. primary arrow (1)

5. temperature drop / length greatest at Th & Tc (2) 6.

primary curve form 7. secondary curve form 8. Tc close to but above Tsat.

PAGE 25 1___EBINCIELE@_QE_NyCLEQB_EQWE8_E(@N1_gEESQllgN t

v1HEgdQQYNQylGS _HEQl_lB@NSEEB_@NQ_E(Qlp_E(QW t

ANSEERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY REFERENCE SL, PSTHTFF, p 58, LO9. ANSWER 1.24 (3.00) 9.60 +or- 0.02 pcm/ ppm. (0.5) a. Using figure C1, boron worth = 10E-3 (delta k/k)/(pcm) x (pcm/ ppm) % delta k/k = =0.0096 % (delta k/k)/(ppm) (0.5)

b. 30*/./ ( 17./mi n ) = 30 min.

30 minutes is fast with respect to xenon changes using figure Al reactivity = 1320-(-940) = -380 pcm (0.5) using figure A6 (HZP is the only curve provided) 1253-380 = 873 pcm A73 Ocm = 34 ( + or-2) inches on group 5 or 116(+or-2) inches on group 4 0.5) 8 4100 g c. xenon concentration increases for the first M hours f rom -2593 pcm to 4

i;_t 2270 pcm, a difference of

' ut i?' pcm (0.25)

^^. M O M /4 0 0 (0.25) so dilute 4,7 7 p ;.- '" i ; : r ',_ p..

70.5 '^;r ^ 2! p e r- /00 (O.25) xenon then decreases back todthe original 6499'. p ower ) pcm in 20 hours. 8 (0.25) So borate bacQ74rJP ppm 1V/67 REFERENCE SL, PSRT, Ch 12, LO 1,2L3.; SL, PSRT, Ch 4, LO9 L10.; SL, AP 10140 R3. SL, PSRT, p 4026, 06. %OO W l').5 & W = %0.S too W9 4 W& = /67 W

m 2. PLANT DESIGN _lNGLUDlNG_EAFETY_AND_EMERQENQY_GY@TEMS PAGE 36 4,. ANSWERS -- ST. LUCIE 162 -86/11/17-LAWYER, SANDY i ANSWER 2.01 (1.00) (b) REFERENCE SL, SD 165. I ANSWER 2.O2 (1.00) (b) REFERENCE I ST Lucie SD117 "AFW", pp 9; CWD B7709-326; LT 412, p 9, LD7. 061/000; K4.07(3.1/3.3) j i l ANSWER 2.03 (1.00) (a) REFERENCE i SL, lecture outline 85, p 5. i ANSWER 2.04 (1.00) (d) REFERENCE SL, primary systems, pp SD2-Rev 1-7, 1-8.; SL, LT 602, pli, LD3. I e l ANSWER 2.05 (1.00) 1 c f } REFERENCE j ST. Lucie SD13 "CVCS", pp 36; SL, LT205, p20. i t 004/010; K6.13(2.1/2.4) f k l 1 r --- - * -.

v.--m44 y.,

.,.e-.-,r,----..e.,,..,-.,v---..-,.-.-%, -,,,y,.,-w. g.www--,-me. --e.---

2___PL@N1_Q[@l@N_ LNG (UQ1NQ_S@Egly_6NQ_Ed(RGENCY_SYSIEd5 PAGE 37 AN WERD -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 2.06 (1.00) C REFERENCE ST Lucie SD145 "120VAC and 125VDC", pp 12/13; SL, LT 503(504), p10, LO2. 063/000; K4.02(2.'9/3.2) ANSWER 2.07 (1.00) (c) REFERENCE SL, unit 1/2 lesson plans and system descriptions, book i of 2, p i. q SL, LT206, pp6,7, LO1. ANSWER 2.08 (1.00) (c) REFERENCE SL, Primary Systems, book 2, SD24 rl, p 20; SL, LT 207, pp20,21, LO10. ANSWER 2.09 (1.00) (d) REFERENCE SL,~LP 33, pp 2-5; SL, LT 503/504, PB, LO2. ANSWER 2.10 (1.50) e) Unit 2 (+.5 ea) b) Unit 1 c) Both REFERENCE ST Lucie SD104 " Main and Extraction Steam", pp 11-19 039/000; K1.01(3.1/3.2), K1.02(3.3/3.3) & K4.06(3.3/3.6)

A 6 m ~-+ * ~ -L "b--* -+A-2t__E60N1_QESIGN_lNC(yglNQ_EGEEly_@NQ_EdEBGENCY_SYSIEd@ PAGE 38 .e. 86/11/17-LAWYER, SANDY i ANSWERS -- ST. LUCIE lb2 6 ANSWER 2.11 (1.00) Y& i a) Wa++-T' (+.5 ea) b) Both Units REFERENCE St Lucie SDB "RCP", pp 17-19 004/000; K1.03(3.3/3.6) ANSWER 2.12 (1.75) B 6 C 7 i. D 8 E 3 F 4 4 G 1 H 2 REFERENCE j SL, SD 7 figure 8; SL, LT 202, p50, LOS. ANSWER 2.13 (3.00) (1.0)

a. 2,4 (1.0) b.

1,2,3,4 (1.0) c. 2,3,4 REFERENCE 3 j SL, OP 2-30124, pp7,10,11. i ANSWER 2.14 (1.50) i i a. Northwest wall b. Fire and Security

c. manual bypass switch in " alternate to load" t

i REFERENCE i SL, OP 970031 r3, p3.; SL, LT 503/504, fig 38. 3 ___ _., -. _ _. _ _ _., _ _ _ _ _ _ _. _, _. ~.,... _,. _ _. _.

2:__PL9N]_Dggl@N_JNCLgD]Ng_g3Egly_gND_gDgggENCy_gy@lEUp PAGE 39 ) a

e ANSWERS -- ST. LUC 1E 1&2

-86/11/17-LAWYER, SANDY ANSWER 2.15 (2.00)

1) Alignment keyway (0.04%)

2) Between hot leg discharge nozzles and upper core barrel outlets (nozzle bypass flow [0.74%3)

3) Between baffle plates and core barre 7 (core shroud leakage CO.26%3)

4) Around inserts in guide thimble tubes in the fuel assemblies (CEA guide tube bypass flow [2.07%3)

REFERENCE NA NCRODP 88.1, "RCS-Reactor Vessel / Core Construction" Westinghouse PWR Systems Manual "RCS", pp 2.1-39; SL, LT 203, p24, LO6. ST Lucie SD2 "Rx Vessel Internals", Fig 32 002/000; K6.13(2.3/2.8) ANSWER 2.16 (1.00) The Recirculation Flow in Unit 2's CS Pumps is much higher (150 vs 50 gpm) and is able to cool the seals without outside cooling (+1.0) l REFERENCE St. Lucie SD24 " Safety injection and CNTMT Heat Removal Systems", pp 21 SL, LT207, p21. 026/000; K1.02(4.1/4.1) ANSWER 2.17 (1.75) The;r are two electro-hydraulic operated valves per feed line (+.5) They are operated in fast speed in accident conditions by two Hydraulic (N2) accumulators (+.5). In normal ops (slow speed) they use a pneumatic pumpt+.5) A spool valve, solenoid air operated determines speed (+.25) f REFERENCE ST Lucie SD112 " Condensate and Feedwater", pp 18; SL, LT301, ppb,9, LD5. 059/000; K4.19(3.2/3.4) r i I l 1

2 __P(GUl_DESlGN_lNC(yDlNG_SOEEly_QND_EMEBGENCY_Sy@lEMS PAGE 40 , ANSWERS -- ST. LUCIE 162 -86/11/17-LAWYER, SANDY ANSWER 2.18 (2.50) a. reactor cavity filtration system, unit 1 (1.0) d ggytdown cooling b. it has a higher flow capacity than he fuel po purification system. (250 gpmS( d d C re), (0.5) c. suction - f rom the ref ueling cavi (near the reactor vessel) (1.0) discharge - back to the cavity via a line common to the fuel pool purification piping to the cavity REFERENCE SL, LT 208, ppl6,17, LO1. ANSWER 2.19 (1.00) c. To receive any discharge from the pressurizer safety and relief valves (and thereby prevent the release to containment). b. To collect discharge from miscellaneous reliefs inside containment. REFERENCE SL, SD 41, p 2; SL, LT 206, p39, LO9. ANSWER 2.20 (2.50) a. 1)A line from the annulus is equipped with a pressure transducer and l transmitter which provides an alarm. (0.75) 2)The containment air monitor can be used to watch for failure of both O-ring seals in conjunction with the above alarm. (0.25) b.'The 3/4 inch line from the annulus can be valved to the RCDT and the volume, or level, in the drain tank observed. (Or any method of I4 performing an RCS leakage calculation if its adequately described. eg, the valve can be opened to reduce the pressure to that of the RCDT and then closed. The l ength of time for the pressure to reach the alarm value can be observed. +1TO b c. identified leakage (0.5) l REFERENCE SONGS, TS 3.4.5.2; SL, LPLSD 2; SL, LT203, p9, LOS I i I L

2 __P69NI_DEglgN_JNCLUDJNg_g6BEly_9ND_EDEgggNCy_Syg]EUS PAGE 41 , ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 2.21 )

rup...-ta 20 E" For UNIT 1,

wh-a single tank low evel is received, ;t: solenoid valve opens and xfer pump starts until high level is reached [+.753 For' UNIT 2, either tank low level will cause BOTH tank solenoid valves to open and the appropriate pump to start. EACH tank's solenoid valve shuts at a high level and the pump stops when BOTH are filled.[+.753 REFERENCE SL, LT 501, p24 LD11 064/000; K1.03(3.64/4.0) l l

._.~._- _ 3._lNElRQU(NI@_QND_QQNIRQLS - PAGE 42 t j r. ab' ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 3.01 (1.00) (b) (to start 1A1, IB1 must meet these conditions) REFERENCE 4-SL, SD 123, pp 17-24. 4 i f i ANSWER 3.O2 (1.00) l' (c) REFERENCE SL, Lecture outline RPS, figure 7.2.21; SL, LT404, p32, LO2. i I ANSWER 3.03 (1.00) 1 (c) l REFERENCE j SL, LP&SD, Sect 35, p 1.9B 1.9B-20; SL, LT407, p21, LOS. 1 i } ANSWER 3.04 (1.00) { (b) } REFERENCE SL,' Primary systems, RCP, p SDB-Rev.1-8; SL, LT202, p8, LO2. i i ANSWER 3.05 (1.00) i (d) g o4 1 i REFERENCE SL, SD 33, p 22. k 4 ---eve-- --,,--.-.v,,e-,w,.-,,,-v,..,,-3,-, v-yewe ,-,-e ~- - - t,-.r.--. ---,,,--..,--ww.--,, --.+--.w-- r., +e

3t-_lNS18UDENI@,6ND_CQNIBQLS PAGE 43 k j ,A SWERS -- ST. LUCIE lb2 -86/11/17-LAWYER, SANDY l 1 ANSWER 3.06 (1.00) j d REFERENCE ST Lucie SD108 "SBCS", pp 18; SL, LT406, p33. 041/020; K1.06(2.6/2.9) ANSWER 3.07 (1.00) c J REFERENCE ST Lucie SD11 "S/G Water Level Control", pp 21; SL, LT408, p18, LO3. 035/010; K4.01(3.6/3.8) i j ANSWER 3.08 (1.00) e o j REFERENCE 4 ST Lucie SD62 "RPS", pp 36; SL, LT404, p33. i l 012/000; K6.07(2.9/3.2) i i l { ANSWER 3.09 (1.00) c) Unit 1 b) Unit 2 i [ REFERENCE j ST Lucie SD5 "CEDS", pp 9, 29; SL, LT405, pp9,23, Lust,10. 001/000; K4.07(3.7/3.0), K1.03(3.4/3.6) i I i I 1 I f 1 i

Ic__INSI6UDEN1@_QNQ_GQNIBQL@ PAGE 44 . ~. , ANSWERS -- ST. LUC 1E ik2 -86/11/17-LAWYER, SANDY ANSWER 3.10 (.50) o) False REFERENCE ST Lucie SD20 "ESFAS", pp 10/11; SL, LT401, p8, LO6. 013/000; K6.03(2.4/2.9) & PWG-1(3.0/4.0) ANSWER 3.11 (2.50) + (1.0) c. 14,500 +or-10*/. H1*lV e 51, i &7. b. 2 (1.5) 10 to 40 sec. the discharge of the ICW pumps REFERENCE SL, Intake cooling water system, SD 165, p O 0-9. ANSWER 3.12 (1.25) Spray valve - closed; BU htrs - off; letdown - ming CPM 2 -on; CPM 3 -on (0.25 ea) REFERENCE SL, ONOP 2-120035 r7, p 2. ANSWER 3.13 (1.00) c) Fission Chamber (+.33 ea) b) Uncompensated Ion Chamber c) BF3 Proportional Counter REFERENCE STL SD 4, "Excore NIS", pp 56/73 SL, LT403, pp12,32,39, LO1,2. 015/0001 K6.01(2.9/3.2)

3c__1NS16QUEN15_QND_QQNI6QLQ PAGE 45 ..s. ANSWERS -- ST. LUCIE 162 -86/11/17-LAWYER, SANDY i ~ ANSWER 3.14 (2.00)

c. The liquid discharge valve is closed l

b. The blowdown valves and the sample valves are closed c. None d. The surge tank vent is valved from the atmosphere to the chemical drain tank REFERENCE j SL, SD 37; SL, LT410, pp12,18,20, LD 6. i f ANSWER 3.15 (2.00) i }

o. RCS saturation margin - max of RTDs in the hot and cold legs (1.5) l Upper head saturation margin - max of the top three UHJTCs CET saturation margin - max CET i

'b. Pressurizer pressure (0.5) l REFERENCE SL, Computer Monitoring Systems QSPDS, p 1-18; SL, LT407, p20, LO3. ANSWER 3.16 (2.00) c. 1100 psig (+or-100) and 350 gpm (+or-30) (1.0) 3 1 See figure A1206. b. The refueling water tank, RWT, which has a TS requirement of 401,800 gal. (1.0) i REFERENCE i SL, SD 4; SL, LT207, pp14,16, LO4. I 1 l l ANSWER 3.17 (1.50) i j Cold Leg Temperature (+.3 en response) Hot Leg Temperature 3 i Turbine First Stage Pressure Nuclear Power Unit i uses 2 RTD cold leg inputs per loop, Unit 2 has only 1 per loop i T I i i +

-3. INSTRUMENTS AND CONTROLS PAGE 46 , ANSWER $ -- ST. LUCIE IL2 -86/11/17-LAWYER, SANDY REFERENCE ST Lucie SD 15 "RRS", pp 5; SL, LT402, pp4,5, LO3. 001/000; K1.04(3.2/3.4) & K1.05(4.5/4.4) ANSWER 3.18 (1.75) -Minimum letdown'at -1.1% deviation (+/- .5% on setpoints) -First standby charging pump starts at -2.5% dev. -Second -4.2% dev. -Low level alarm at -5% dev. -Back up start signal to standby charging pumps at -5% dev. -All heaters off at 27% level -Lo-Lo Level alarm at 27% level (+.2 for action, +.05 for setpoint ea) REFERENCE ST Lucie SD9 "PZR pressure, relief and l evel control", pp 54-56 SL, LT 206, Transparency Fig 34A. 011/000; K1.01(3.6/3.9) and A2.03(3.8/3.9) ANSWER 3.19 (1.00) c) No Indication (clear / white) b) Red c) Blue d) Amber REFERENCE St Lucie SDS "CED5", pp 27/28; SL, LT405, p27, LO6. 001/000; K4.01(3.5/3.8) ANSWER 3.20 (1.50) A Range control circuit energizes an output relay (+.5) when it senses < 1000 cps (+.25) to select the extended range output (+.25). A red lamp above the % power meter illuminates in the extended range (+.5) (Note: The opposite of the above for wide range selection will be also allowed) REFERENCE ST Lucie SD4 "Excore N1s", pp 13/14, 17; SL, LT403, p16. 015/000; K6.01(2.9/3.2)

3. INSlRUMEN1S_QND_CONIROLS PAGE 47 ANSWERB -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 3.21 (3.00) a) Ensure the operator does not deliberately or inadvertantly defeat parts of the protection system by switch misalignment (+1.0) b) High SUR; Loss of Load; Local Power Density (+.33 ea) c) Must turn 4 keylock switches located on each RPS panel (+.7) and is bypassed above.1% [.5% Unit 2] (+.3) REFERENCE St. Lucie SD 62, pp 31/32; SL, LT404, pp 28,29, LD5,6,7. 1 ANSWER 3.22 (1.00) A heated thermoccuple's output is compared with an unheated thermocouple's output.(+.3) With no liquid to remove the heat, the temperature difference becomes large, creating a large voltage output (+.7) 1 REFERENCE ST Lucie QSPDS Handout, pp 16; SL, LT407, p21. 017/020;K4.01(3.4/3.7) i i 1 J 4 1 J 4 J

gg__880GEgyBES_;_UQBd@(t_@@NOBd@(t_EMEBGENQY_@NQ PAGE 49 8@Q1QLQGlGQ(_QQNIBQ( I ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY-a l ANSWER 4.01 (1.00) (b) I REFERENCE-4 10CRF20.101 R 1/1/86, p 250. t ANSWER 4.02 (1.00) (b) REFERENCE SL, HP-2 r5, p 16. i i ) ANSWER 4.03 (1.00) (d) t REFERENCE SL, 1-EOP-04, p6. ANSWER 4.04 (1.00) 4 (a) i l REFERENCE i i SL, 1-EOP-03, p21. i - l l ANSWER 4.05 (1.00) C REFERENCE r ST Lucie EP 0030141; SL, ONOP 30135, p6. PWG-11(EOP Immediate Actions) (4.3/4.4) l' l

4:__B8QQEDUBES_;_NOBd@(t_QBNQBdQ6t_QUEBGENQY_@NQ PAGE 49 ,$6DIOLOGICAL CONTROL 8 ANSWERS -- ST. LUCIE 1&2 -86/11/17-LAWYER, SANDY ANSWER 4.06 (1.00) b REFERENCE ST Lucie EDP-5, Steps 7-9 EPE-074; EK3.04(3.9/4.2) ANSWER 4.07 (2.50) open (2.0) a. 1. manual 2. auto - throttled b. 200 degF (0.5) REFERENCE SL, OP 2-30127 r15, p13. ANSWER 4.09 (1.00) a) Unit 1 (+.5 ea) b) Unit 1 REFERENCE STLucie OP 1/2-0030127, pp 1, 7; pp2,10. 002/020; PWG-12(3.7/3.7) ANSWER 4.09 (.50) False REFERENCE SL, ONOP 1-110030 r12, sect 5.4.2a, p7 ANSWER 4.10 (.50) True

ft__P8QGEQQBE@_;_NQ6dQLg_QBNQQdQ(g_Ed[QQ[NGY_QNQ PAGE 50 .. 89DigLQQlqQL_GQN16QL i ANSWERS -- ST. LUCIE IL2 -86/11/17-LAWYER, SANDY REFERENCE SL, HP-2, p17. ANSWER 4.11 (1.50)

1) (f or damage to new f uel) none (0.25) 2)

a. inform control room personnel of the accident (1.25) b. sound the containment evacuation alarm c. stop 2-HVE-BA and 2-HVE-8B (containment purge fans) if running d. verify I-FCV-25-1 through I-FCV-25-6 (containment purge valves) have closed e. evacuate the containment and check for personnel contamination REFERENCE SL, ONOP 2-1600030 r2, p2. ANSWER 4.12 (2.50) 1. Place reheater control system in manual, then close TCVs. 2. Open startup transformer breakers. 3. Reduce Tavg to reference setpoint (Tref =532 degF) by manual operation of the atmospheric steam dump valves. 4. Isolate S/G blowdown. 5. Verify 1C steam driven AFW pump has started and has established flow to the S/Gs. If AFW pumps have started due to the auto start feature, manual control can be taken after the auto actions are completed. REFERENCE SL, ONOP 1-30140 r29, p 4. L

4t__PQDGEDyBES_ _NOQdQ(t_QQNQQUQ(t_[U(QQgNGY_QND PAGE 51 . 86DIOLOGICAL CONTROL

ANSWERS -- ST. LUCIE 102

-86/11/17-LAWYER, SANDY ANSWER 4.13 (2.00) 1. containment air particulate monitor 2. containment radioactive gas monitor 3. componnent cooling liquid monitor 4. condenser air ejector gas monitor 5. steam generator liquid sample monitor 6. plant vent radiation monitor 7. containment area radiation monitors 8. high level, pressure or temperature in the quench tank 9. high temperature reactor coolant relief or safety valve discharge line

10. low level in volume control tank 11.high level reactor coolant drain tank 12.high level containment sump

13. l ow pressuri z er level 14.high level component cooling water surge tank

15. safety relief valve (s) open alarm -H11 16.high Si loop header pressure REFERENCE SL, ONOP 1-0120031, r10, p2.

ANSWER 4.14 (2.50) 1) Stop withdrawal and insert CEAs to 500 pcm below critical condition 2) (Recheck ECC)(not required as statement in question may preclude) 3) Recheck boron concentration by chemistry cample 4) Verify CEA position 5) Verify agreement between N1 channels 6) Notify reactor engineer Cany 5 at 0.5 each3 REFERENCE ST Lucie DP 0030126, pp 1/2; SL, 1-0030122, r 2 8, p2 001/010 A2.07(3.6/4.2)

St__PBOGLUVOCS_:_NQQUQ(t,QQNQQdQ(t,[dg6Q[NGY,QNQ PAGE 52 .sB00196091GOL_QQNISQL kANSWERS -- ST. LUCIE IL2 -86/11/17-LAWYER, SANDY ANSWER 4.15 (2.00) 1) HPS1 Pumps (+.25 ea) 2) SI Motor Operated Valves 3) Emergency Lighting 4) Class ! Emergency Power Panels 5) Diesel Oil Transfer Pumps 6) "A" RCP oil lift pumps 7) Sups Power Inverter 8) HVAC Valves and Dampers REFERENCE ST Lucio EP 0030140, rio, p3. 062/000; K3.01(3.5/3.9) 4 ANSWER 4.16 (1.50) 1) Turbine tripped (+.3 na) 2) Generator OCDs open 3) Exciter Field Dreaker open 4) Electrical Auxiliaries transferred to S/U Xfrmrs 5) At least 1 DC bus energized 4 REFERENCE ST Lucio EOP-1, pp 4, step 2 EPE-OO73 PWG-11(4.0/4.0) I ANSWER 4.17 (1.50) 1) Condenser Air Ejector Rad Monitor Alarm (+.3 ea) 2) S/G Dlowdown 3) Main Steam Line 4) Hi activity in a S/g per sample 5) Increasing S/G 1evel REFERENCE ST Lucie EOP-4, ppt l EPE-0303 PWG-10(4.5/4.5) l l

r 4t_.P6QQEQUBQQ_ _NQQUG(t_QQNQQUQ(t_QUQ6QENQY,0NQ PAGE $3 .S00196991G0(_QQN16QL AANSW'ERS -- ST. LUCIE IL2 -86/11/17-LAWYER, SANDY ANSWER 4.10 (2.00) 1. the steam supply to the turbine seals 2. air in-leakage to the condenser 3. the deltaT of the circulating water across the condenser 4. the status of the circulating water pump 5. the circulating water box prime 6. the steam jet air ejector operation 7. the SJAE loop sea! 8. the condition of feedwater heater alternate dump valves REFERENCE SL, ONOP 2-610031 ro, p2. ANSWER 4.19 (1.50) Auto - Rumback to 60*/. on loss of one MFW pump 1mmed - Ensure S/G 1evels can be maintained with availabile MFW or reduce st'eam demand until levels can be maintained If runback occurs, ensure reactor power is matched with turbine power REFERENCE SL, EOP 1-700040, p3. ANSWER 4.20 (1.50)

c. prevents bowing of the rotor

b. prevents seal damage due to pulling in air and dirt across the glands

c. minimizes water intrusion into the turbine REFERENCE SL, OP 2-30124 r17, ppi,2.

ANSWER 4.21 (1.00) Since saturation Temperature for the RCS safeties is < 700 dog F, this would represent a superheat condition in the RCS which could only occur with core uncovery (+1.0)

r 4t__BBQGEDUBES_:_UQBUG6t_OQUQBdQ(t_EDEBG(NGY_QND PAGE S4 .ff)DIOLOGICAL CONTROL 'ANSNERS -- ST. LUCIE 162 -86/11/17-LAWYER, SANDY REFERENCE CEN-152, pp S-77 for LOCA discussion EPE-074; EK1.02(4.6/4.0) r l I l l l l

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