ML20214T912

Exam Rept 50-255/OL-87-01 on 870504-08.Exam Results:Both Senior Operator Candidates Passed.Exam & Answer Key Encl

ML20214T912
Person / Time
Site:	Palisades
Issue date:	06/04/1987
From:	Defferding L, Gruel R, Upton J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20214T908	List: ML20214T906 ML20214T912
References
50-255-OL-87-01, 50-255-OL-87-1, NUDOCS 8706100477
Download: ML20214T912 (69)

Text

{{#Wiki_filter:r l U.S. NUCLEAR REGULATORY COMMISSION l REGION III Report No. 50-255/0L-87-01 Docket No. 50-255 License No. DPR-20 l Licensee: Consumers Power Company Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 Facility Name: Palisades Nuclear Plant I Examination Administered At: Midland, MI and Palisades Nuclear Plant Evamination Conducted: May 5, 6, 7, and 8, 1987 Examiners: Y ( Lp b_ b '9-N L. J. Defferding () Date N b, L1 @? I"'/ N R. L. Gruel / Date fk4 L{ x b~W"O J. W. Upt6n U Date fkf $( b$ d't b~N~'Sl P. R. Sun ~derland p Date M [ Approved By:[T. M. Burdick, Chief, [:>~4(49 l l Date l Operator Licensing Section 1 l Examination Summary Examinations were administered on May 5-7,1987 (Report No.50-255/0L-87-01) to two senior operator candidates. Results: Both candidates passed the examinations. l l l l 8706100477 070604 PDH ADOCK 05000255 Y PDR

r-DETAILS 1. Examiners L. J. Defferding, PNL R. L. Gruel, PNL

• J. W. Upton, PNL P. R. Sunderland, NRC, Region III
• Chief Examiner 2.

Exit Meet _i_ng n At the conclusion of the site visit, the examiners met with representatives of the plant staff to discuss the results of the examinations. The results were combined with the results of the Requalification Examination (see Report No. 50-255/0 L-87-02). Personnel present at the meeting included: R. A. Fenech, CPCo, Operations Superintendent R. M. Rice, CPCo, Operations Manager J. G. Lewis, CPCo, Technical Director W. G. Merwin, CPCo, Training Administrator C. S. Kozup, CPCo, Technical Engineer E. A. Feury, CPCo, Supervisory Instructor R. B. Heimseth, CPCo, Supervisory Instructor L. A. Schmiedeknecht, CPCo, Supervisory Instructor E. R. Swanson, NRC, Senior Resident Inspector L. J. Defferding, Batelle, Examiner J. W. Upton, Batelle, Examiner R. L. Gruel, Batelle, Examiner P. R. Sunderland, NRC, RIII Examiner The examiners made the following observations concerning your training program: a. Generic Weaknesses The examinees were weak in understanding the theoretical background for system operation for components and component failures. The examinees were unsure as to personnel assignments when the j control room was unaccessible. b. Generic Strengths The candidates exhibited (in the simulator) good training and knowledge in the handling of the plant in response to instrument failures and in response to accident conditions. 2

e c. Simulator The simulator exhibited the following problems: Malfunction MS-11 (Turbine Bypass Malfunction) did not work. Boration and Dilution modelling appeared rough. 3. Examinations Review Based on comments provided to the candidates during the examination and as a result of discussions with the facility staff, several modifications were made to the examinations and are noted in the enclosed answer keys. The Attachment to this report is a copy of the facility comments and the resolutions.

Attachment:

As stated 3

w ATTACHMENT Question: 7.08 Comment: This question requires memorization of a resource assessment tree that is available for use during a complex casualty. It does not fall under the category of an immediate action and goes beyond what we expect an operator to recall from memory. For a question of this type, the reference material should have been furnished 'and the question worded to have the operator use the reference material to arrive at the proper resource tree and determine from plant conditions what the proper equipment available should be used. Recommendation: In this case, without proper reference material, allow additional answers in Part b. for supplying borated water to the PCS. Safety injection tanks - approximately 200 1 50 psi l Boric acid pumps - approximately 100 1 20 psi SIRW tank gravity feed - approximately 30 psi l

Reference:

E0P 9.0, Functional Recovery. Resolution: This question does not require memorization of a resource assessment tree. l The facility recommends allowing addition answers for Part b. Part b. can be answered correctly as long as the candidate knows that the HPSI, LPSI, and containment spray pumps can be used to supply borated water to the PCS. We feel that this knowledge should be possessed by a candidate and we do not agree that this knowledge is only gained from memorization of a resource l assessment tree. However, the facility's recommendation does identify an l additional correct answer to Part b.; that being the use of the boric acid l pumps. As the question specifically requested flow paths using pumps, the safety injection tanks and SIRW tank gravity feed will not be added to the key. The answer key is modified to accept the boric acid pumps as an additional correct answer. f I L

r Attachment 2 .3 ( . Question: 8.03 Comment: This question calls for almost total recall of 10 CFR 50.73. Need to memorize Code of Federal Regulations is excessive. The question asks when a Licensee Event Report (LER) is required, and the events in the multiple choice questions were pulled directly from 10 CFR 50.73 with a couple of words changed to make three of the four parts incorrect. Practically speaking, when an event occurs at Palisades that calls for an LER, we utilize all of our reference material, including 10 CFR, Administrative Procedures, Nuclear Licensing Department, and do not depend on memorization. Recommendation: Delete this question as being beyond the scope of operator knowledge without the use of appropriate reference material, as this is a decision that does not require immediate action (i.e., LERs must be submitted within 30 days).

Reference:

Code of Federal Regulations, Section 50.73. Resolution: This question was written so as not to require recall or memorization of a portion of 10 CFR 50. The question did not require a listing of those conditions that require a LER. With an understanding of that portion of 10 CFR 50, a candidate could arrive at the correct answer. The question remains in the examination. j 4 i 1 ,.-----,.~n

7 )* f.p glg p-e.. / j-

p. - yu ran p t

, y %; t .o

1. :,.;

, y i fMe bi i b.ah' hs bd' d I U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: PALISADES REACTOR TYPE: PWR-CE DATE ADMINISTERED: 87/05/05 EXAMINER: UPTON/DEFFERDING/ GRUEL CANDIDATE: ANSWER KEY - Fu.,; _ INSTRUCTIONS TO CANDIDATE: Use separate pr.per for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70: in each category and a final grade of at least 80t. Examination papers will be picked up six (6) hours after the examination starts. OF CATEGORY : OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY .5 25.00 25.00 5. THEORY OF NUCLEAR POWEP. PLANT OPERATION, FLUIDS, AND THERMODYNAMICS S 25.00 25.90 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION 24 .2 78.00 25.96 7. PROCEDURES - NORMAL, ABNORMAL, l / EMERGENCY AND RADIOLOGICAL CONTROL 25.00 25 96 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS .00 Totals Final Grace All work done on this examination is my own. I have neither given nor received aid. Ulididate's Signature k

w1 ~ w NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply: 1. Cheating on the examination means an automatic dental of your application and could result in more severe penalties. 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating. 3. Use black ink or dark pencil only to facilitate legible reproductions. 4. Print your name in the blank provided on the cover sheet of the examination. 5. Fill in the date on the cover sheet of the examination (if necessary). 6. Use only the paper provided for answers. 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet. 8. Consecutively number each answer sheet, write "End of Category _" as, appropriate, start each category on a new page, write only on one sice of the paper, and write "Last Page" on tne last answer sneet. 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 cown on your desk or table.

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

13. The point value for each cuestion 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, ANS*4ER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANS'4ER ELANK.

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

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

i 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. 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. 4 e i 8 e

y 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 2 THERMODYNAMICS QUESTION 5.01 (2.50) Plutonium-239 is produced in the core of the Palisades nuclear reactor. a. DESCRIBE the 3-step sequence of nuclear-reaction events that produces the Pu-239. (1.0) b. WAT impact does the buildup of Pu-239 have on the effective beta of the core? (0.5) c. WAT impact does the buildup of Pu-239 have on the fuel temperature coefficient (FTC) of the core? WY? (1.0) QUESTION 5.02 (1.00) If the condenser vacuum changed from 10 to 20 in. of Hg, then the turbine back pressure would (1.0) (a. increase by a factor of ten (10). (b. decrease by a factor of two (2). (c. increase by 4.91 psi (d. decrease by 10 psi QUESTION 5.03 (1.00) For each of the radioactive decays indicated below, SPECIFY whether the emitted particle (or wave / ray) is a NEUTRON, PROTON, BETA-PARTICLE (either beta-negative 'or beta-positive), ALPHA-PARTICLE, or GAMMA-RAY CNLY. a. U-231 decays to Th-230 (0.25) j b. Kr-87 (excited) decays to Kr-86 (0.25) c. Xe-136 (excited) decays to Xe-136 (stable) (0.25) d. tritium decays to helium-3. (0.25) \\ j (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) l

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 3 THERMODYNAMICS 1 QUESTION 5.04 (1.50) After a spent-fuel assembly had been in the spent-fuel pool for one year, it was surveyed and it was determined that the dose rate at one foot away was 50,000 R/hr. One year later (after two years in the pool), the dose rate at the same location was found to be 5,000 R/hr. CALCULATE the effective half life, t-1/2, of the fuel assembly. (1.5) QUESTION 5.05 (1.00) Following a reactor trip from sustained operation at 100% power, the power (neutron flux) level drops immediately to about (1.0) (a.) 6% because about 94% of the neutrons are prompt neutrons. (b.) 6% because about 0.4 to 0.5% of the neutrons are delayed i neutrons. (c.) 99.5 to 99.6% because about 0.4 to 0.5% of the neutrens are delayed neutrons. (d.) 99.5 to 99.6% because 99.5 to 99.6% of the' neutrons are prcmpt neutrons, i i G 5 e (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

l +. 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 4 THERMODYNAMICS i QUESTION 5.06 (3.00) Section 3.1.3 of the Palisades Tech-Specs, " Minimum conditions for l Criticality," states, "a b c) When the primary coolant temperature is below the minimum temperature specified in "a)" above, the reactor shall be subcritical by an amount equal to or greater than the potential reactivity insertion due to depressurization." a. Consider a depressurization event caused by a failed, stuck open primary safety valve. If the primary-coolant pressure war initially 2100 psia and if the primary-coolant temperature was 500 degrees F before and after depressurization, WHAT would be the maximum change in the primary-coolant pressure? (1.0) b. The following information is known about the PCS. The PCS volume is 10,300 cubic feet not including the PZR. The density of water at 350 degrees F/2100 psia is 58.0 lbm/ cubic foot. The density of water at 500 degrees F/2100 psia is l 50.0 ltm/ cubic foot. WHAT would be the density change of the primary coolant due to the 1 =ediate depressurization event described in "a."? (1.0) c. If the reactivity INSERTION due to depressurization (as referred to in the Tech-Specs) was 0.1t delta rno, WHAT would be the pressure coefficient of reactivity for the nuclear reactor? SPECIFY magnitude AND sign. (1.0) 1 9 ("""** CATEGORY 05 CONTINUED ON NEXT PAGE *""*") i

, 3.. 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS PAGE 5 QUESTION 5.07 (1.00) In the Palisades nuclear reactor core, Gedolina (Gd-203) is used. as a burnable poison because (1.0) (a.) it has a high resonance absorption peak and thereby provides a negative component to the MTC. (b.) it is readily manufactured as complete fuel pin replacements and thereby provides a lower Linear Heat Rate in a fuel assembly (for a given power level). (c.) it has high absorption cross section and thereby has burned s out by the end of the cycle effectively increasing the length of a cycle. 1 (d.) it has a high resonance absorption peak and therefore can be used in fuel assemblies with relatively lower neutron flux. QUESTION 5.08 (1.00) As cere age increases during a cycle in the Palisades nuclear reactor, the integral rod worth at 100t full power of a re;ulating CEA located near the center of the core (1.0) (a.) increases due to the fact that the CEA is operating in a re; ion of higher neutron flux. (b.) increases due to the fact that te:ritrature of the CEA is higher. (c.)decreasesduetothefactthatthetemperatureoftheCEA is higher. (d.) decreases due *.o the fact that the boric-acid concentration in the core is less. i QUESTION 5.09 (1.50) Equilibrium xenon reactivity dces not change as much for a lot power change at a high power level as it does for a power change of 10 at a low power level. EXPLAIN. (1.5) (==" CATEGORY 05 CONTINUED ON NEXT PAGE *"") y7 --t-~ ~wm -*-----e'-- 7 -'t e --M9 e--' * - - '- - * ' 1r

• e*-

w eT

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 6 THERMODYNAMICS QUESTION 5.10 (2.00) The Palisades power plant is operating at 100% of full power with all rods out (ARO). The age of the core is 8000 MWD /MTU. The boron concentration is equal to the " predicted boron concentration" for this reactor condition. It is necessary to insert the CEAs in the manual sequential (MS) mode until Group 4 is at 40 inches. A change in the boron concentration will be used to maintain 100% power. Use the Palisades Technical Data Book as necessary. DETERMINE the number of PMW gallons required. Clearly OUTLINE your steps. (2.0) QUESTION 5.11 (1.00) During accident conditions, the following information is available: FZR pressure = 1000 psia Hottest CET te=perature = 500 degrees F a. WHAT is the temperature subcooled margin (SCM)? (0.5) b. WHAT is the pressure SCM? (0,5) OUESTION 5.12 (3.00) j For each of the following, STATE the condition of the noted fluid. a. A leak exists in the steam generator steam space while the plant is at 100% power. STATE the temperature AND the degree of subcooling/ quality / degree of superheat of the exit fluid. (1.5) b. The regenerative heat exchanger inlet and outlet tempera-tures (letdown) are 538 degrees F and 240 degrees F, j respectively. The inlet temperature (charging) is 110 degrees F. STATEtheoutlettemperature(charging) of the regenerative heat exchanger. (1.5) (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

q r a 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 7 ~~~ THERMODYNAMICS QUESTION 5.13 (3.50) Included with this examination is the Characteristic Curve figure for the Primary Coolant Pump (PCP). a. DEFINE the term " pump runout." WHERE on the figure does pump runout occur? (1.0) b. The figure shows the recommended NPSH. 1. If the water entered the PCP at 360 degrees F, WHAT would be the minimum PCP suction pressure in psia required to meet the NPSH recommendation? (1.0) 2. According to SOP-1, " Primary Coolant System," can the PCP be placed in service with this PCS 4 pressure? (0.5) c. The PCP is operating such that its parameters fall on the indicated head curve at the point corresponding to a water flowrate of 70,000 gpm. If the temperature of the water was raised, HOW would the operating point shift? EXPLAIN your answer. (1.0) QUESTION 5.14 (1.00) l The term "RT-NDT" is that value of temperature (1.0) (a.) above which a metal behaves in a purely brittle fashion. (b.) above which the reactor vessel (at the beltline) should not be operated. (c.) above which non-destructive tests (NDT) have not been conducted. (d.) above which a metal behaves in a purely ductile fashion. i I L I i I (***** CATEGORY 05 C0itTINUED Oil llEXT PAGE *****) . _. = . -. _. -, ~. - -

=. - - ,>c PAllSADES PLANT W a 1 PRIMARY COOLANT PUMP CilAR ACTERISTIC CURVE G l} O -80 e Total Efficiency f Head, 4'i'.','l .70 l ft. t-i ;. g. l ' -60 ~ n 400 : Head l t w . Recommended -200.NPSH -50 ... II Efficiency, i? 1 ~ MiniNP t 1. O ! Q 300 100 ! -40 g } n 1 2

.o.

l 2 200 30 d. j

Brake, w

. 4g' h) 3 - Ez 100 -10,00) -20 i-aI BilP @ SP. GR. 1.0' i Va 1g: 0" - 5,000 -10 i R :: %f o. 0 -0 ~ ,i 0 20 40~ 60 80 100 120 z 1000 Gallons per Minute i ~ .m .~ 1

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 8 THERMODYliAMICS QUESTION 5.15 (1.00) The term " critical heat flux" refers to that heat flux between a fuel pin and the bulk of the primary coolant (1,0) (a.) at which the heat-transfer mechanism changes between natural convection and nucleate boiling. (b.) at which the heat-transfer mechanism changes between nucleate i boiling and partial film boiling. (c.) at which DNBR would equal 1.3. (d.) which is 77t of that which would cause clad failure. 4 1 4 l i i i l l l (***** END OF CATEGORY 05 *****) J

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 9 QUESTION 6.01 (1.00) When operating in the Manual Individual (MI) mode, LIST the three ~ (3) control rod interlocks which are NOT bypassed? (1.0) QUESTION 6.02 (1.50) With the Emegency Diesel Generator No. I controls in automatic, WHAT three (3) conditions would generate signals to automatically start the. diesel? (1.5) QUESTION 6.03 (1.00) STATE the design bases for the size of the Volume control Tank. (1.0) CUESTION 6.04 (1.00) During a large break LOCA when the SIRW tank level reaches the RAS setooint, WHAT design feature ensures an uninterrupted suction flow path to the safeguard pumps? (1.0) (*==** CATEGORY 06CONTINUEDONNEXTPAGE*****)

i 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 10 1 l QUESTION 6.05 (2.00) For each of the following conditions (., b., and c.), LIST those actuation signals (1. through 6. that should have triggered. Consider each condition separately. Each condi-tion may)have for its answer no, one, or several actuation signal (s. (2.0) 1. SIAS 2. CSAS 3. Auto Containment Isolation 4. MSIS vs. MSIV 5. MS 6. AFAS a. A steam-11ne break has occurred in containment and 1 containment pressure = 7 psig containment radiation = background i S/G levels = 60% and 40% PZR pressure = 1800 psia SIRWT level = 801 l S/G pressure = 680 and 580 psia a b. A small-break LOCA has occurred and 4 i containment pressure = 2 psig containment radiation = 6 R/hr --->10Rnew i' S/G 1evels = 65% and 65% I . PZR pressure = 1800 psia SIRWT level = 50% i S/G pressure = 700 and 700 psia i c. A feedwater problem has occurred and i containment pressure = 1 psig } containment radiation = background S/G 1evels = 60% and 31% PZR pressure = 2200 psia SIRWT level = 80% 1 j S/G pressure = 720 and 650 psia i j QUESTION 6.06 (3.00) STATE six (6) of the seven (7) automatic responses which occur in the CVCS system when a Safety Injection Signal is generated 4 with standby power available. (3.0) [ I l (***** CATEGORY 06CONTINUEDONNEXTPAGE*****)

o 6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 11 QUESTION 6.07 (2.00) During power operation, an air line to valve CV-1359 breaks. CV-1359 can be used to isolate the noncritical service water

header, a.

WILL the valve fall OPEN, CLOSED, or "AS IS"? (0,5) b. 1. WHAT immediate action is required? 1.0) 2. WHY is this immediate action necessary? 0.5) QUESTION 6.08 (2.00) a. During abnormally-high containment pressure conditions, WILL the indicated Steam Generator pressure and Pressurizer pressure be EQUAL 10, GREATER THAN or LESS THAN actual? PROVIDE a rationale for your answer. (1.0) b. During abnonnally-high containment temperature conditions, WILL the indicated Steam Generator level and Pressurizer level be EQUAL TO GREATER THAN, or LESS THAN actual? PROVIDE a rationale for your answer. (1.0) QUESTION 6.09 (1.50) LIST the three (3) loads that can be directly cooled from service water during a loss of CCW. (1.5) QUESTION 6.10 (2.00) a. If the "HIGH POWER RATE CHANNEL PRE-TRIP" alarm was activated by the RPS, WHAT two (2) other control signals / trips should have been activated? (1.0) b. If the " RATE TRIP CHANNEL BYPASSED" alarm was activated by the RPS, LIST the two (2) signals / trips, either of which should have been the cause. (1.0) (***** CATEGORY 06CONTINUEDONNEXTPAGE*****)

6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 12 QUESTION 6.11 (1.00) WHICH of the following is NOT a function of the excore NI start-up channels? To provide (1.0) (a.) core-powerindicationsfromonecountpersecondto10**5 counts per second (b.) core-power signal to rod control up to 10**-45 power (c.) high SUR alarm at 1.5 dpa (d.) core-power signal to audio countrate amplifier for use during refueling QUESTION 6.12 (2.50) WHAT is the significance of the following colors that are used in the critical Function Monitoring System? (2.5) a. blue b. magenta c. green d. yellow e. white QUESTION 6.13 (2.00) a. DESCRIBE the interlocks between the reactor-side tilt machine and the refueling machine. (1.0) b. DESCRIBE WHY both main transfer winches are not activated to manually transfer fuel and control rods between the containment and the fuel building when the transfer carriage is out of service. (1.0) i (***** CATEGORY 06 CONTIllUED ON NEXT PAGE *****)

s 6. PLANT SYSTEMS DESIGN. CONTROL, AND INSTRUMENTATION PAGE 13 QUESTION 6.14 (2.50) The preferred AC bus Y20 or D20 supplies power to various loads. a. WHAT is the normal supply for the preferred AC bus Y20? (0.5) b. If the normal supply became unavailable, HOW would power be supplied to the preferred AC bus Y207 (1.0) I c. If offsite power was lost, WHAT two (2) independent power sources could be used to supply the preferred AC bus Y20? (1.0) i I (***** EllD OF CATEGORY 06 *****) i l

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 14 RADIOLOGICAL CONTROL QUESTION 7.01 (1.50) ANSWER the following parts of this question related to Precautions and Limitations regarding plant operation above 10% power. ) a. TRUE or FALSE. A turbine backpressure of 3" HgA is acceptable. (0.5) b. Chemistry Department should be informed of WHAT type of power change? (0.5) c. T-avg should exceed WHAT value when reactor power is greater than 90%7 (0.5) QUESTION 7.02 (5.00) The plant is operating at 100% power when a reactor trip occurs: a. WHAT actions should be taken in the event all full length control rods are not fully inserted? (1.5) b. What actions should be taken if Bus 1A,1B, or IE has not transferred to start-up power? (1.0) c. If forced circulation cannot be maintained, HOW would the condition of natural circulation be verified? (1.5) d. If containment isolation and containment spray should have occurred and did not, HOW would they be initiated / established? (1.0) l l (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

2 7. ' PROCEDURES - NORMAL ABNORMAL. EMERGENCY AND PAGE 15-RADIOLOGICAL CONTROL QUESTION 7.03 (1.50) STATE whether the start of each of the following operations would-tend to INCREASE or DECREASE void size (if one exists in the reactorvessel): a. Pressurizer spray operation b. Pressurizer heater operation c. Reactor vessel head venting QUESTION 7.04 (2.00) STATE whether continued operation is allowed per Technical Specification 3.1.5, Primary Coolant System Leakage Limits, for each of the following: a. 0.5 gpm leakage through cold leg weld b. 0.8 gpm steam generator tube leak c. 2 gpa leakage from an unknown source d. 3 gpm leakage from a valve stem seal QUESTION 7.05 (1.00) During operation at 35% power, WHICH one of the following situations is NOT allowable beyond a two-hour period? (1.0) a. loss of one primary coolant pump b. an inoperable secondary system safety valve l c. a closed safety injection tank isolation valve d. two auxiliary feedwater pumps in manual for testing QUESTION 7.06 (1.00) If a visible sighting of a tornado was reported, WHAT immediate l actions should be taken? (1.0) (***** CATEGORY 07CONTINUEDONNEXTPAGE*****) )

e e 7. PROCEDURES - NORMAL. ABNORMAL EMERGENCY AND PAGE 16 RADIOLOGICAL CONTROL t QUESTION 7.07 (2.50) If power was lost to instrument AC bus YO1, WHAT immediate actions should be taken? Why? (2.5) QUESTION 7.08 (5.00) 1 The Functional Recovery Procedure, E0P 9, Attachment A, provides guidance for reactivity control. If CR0s cannot be inserted or driven in, two methods of boron addition are specified. a. Regarding boron addition using the CVCS, 1. By WHAT means are the charging pumps supplied borated water if the boric acid pumps are unavailable? (1.0) I 2. LIST the three (3) flowpaths that are available to supply borated water from the charging pumps to the PCS. (1.0) b. LIST the three (3) flowpaths (pumps and PCS injectio'n sites) l for supplying borated water to the PCS if the charging pumps j are unavailable AND the PCS pressure limitations of each. (3.0) i QUESTION 7.09 (1.00) j As referred to in ONP 25.2, " Alternate Safe Shutdown Procedure," ] LIST the four (4) sets of items that the operators take with them i when evacuating the control room? (1.0) I 4 l QUESTION 7.10 (2.00) i If a fuel handling accident occurred in the auxiliary building fuel handling area, WHAT four (4) immediate actions should be taken? (2.0) i (***** CATEGORY 07 CONTIHUED ON NEXT PAGE *****) -,.----~.,m--,---, <,w-, - - - ..,-n-, n-.,-,--., ,-n,,- -n-.-...,-+w-<~--wo-r.,---,-,w

o 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 17 RADIOLOGICAL CONTROL QUESTION 7.11 (1.50) Plant cooldown is proceeding from Hot Shutdown to Cold Shutdown. a. Low Temperature Over-Pressure Protection (LTOP) must be operable under either of WHAT two (2) conditions? (1.0) b. WHAT constraints are placed on the HPSI pumps when LTOP is in service? (0.5) J w .I l (*****ENDOFCATEGORY07*****) ,.-.n.. e

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 18 QUESTION 8.01 (1.50) From the list of conditions beJow SELECT that set (for example; 2.', 4., 8., and 9.) which is the definition of " Hot Standby Condition" for the Palisades plant. (1.5) 1. The primary coolant has a boron concentration equal to the shutdown boron concentration. i 2. The neutron-flux logarithmic-rance channel instrumentation indicates greater than 10**-4% of rated power. 3. T-avg is less than 210 degrees F. 4. The primary coolant has a boron concentration equal to the refueling boron concentration. 5. T-avg is greater than 525 degrees F. 6. The neutron-flux power-range instrumentation indicates less than 2 of rated power. 7. The reactor is critical. 8. Any of the control rods are withdrawn. 9. The nuclear reactor is suberitical by an amount greater than or ecual to the margin specified in Technical Specifications 3.10.

10. All full-length control r:ds are fully inserted except for the i

single, highest-worth control rod which is fully withdrawn. t 6 (***** CATEGORY 08CONTINUEDONNEXTPAGE**===)

l .e-0 8. ADMINISTRATIVE PROCEDURES, CON 0!TIONS, AND LIMITATIONS PAGE 19 4 l l ) QUESTION 8.02 (2.00) Included with this examination is a copy of Figure 2-3 from the Palisades Tech-Specs, Section 2.1, " Safety Limits-Reactor Core." a. If the Primary Coolant System (PCS) pressure was 2100 psia, I i INDICATE on Figure 2-3 the region of acceptable operation. (0.5) b. WHAT is the objective or basis for this safety limit? (0.75) l c. Section 3.1.1 of the Palisades Tech-Specs specifies that { the nuclear-reactor vessel flowrate, with four (4) primary coolant pumps operating, shall be 126.9 x 10"6 lbm/h or 1 greater, when corrected to 532 degrees F. If the vessel 1 flowrate drcpped below 126.9 x 10"6 lbm/h, EXPLAIN WHAT I change shculd be made to the temperature limits of Figure 2-3. (0.75) ) i t L i I i 6 j s l i i i i I i ( i (""* CATEGORY 08 CONTINUED ON NEXT PAGE '"")

PALISADES QUESTION 8.02 May 5, 1987 = ses ,\\ N \\ s M8k l~8MSA .-shyhy i x \\.\\'w x \\ i ~ NNj x N N 40 SO 100 110 ' stacca Powan-% cP 2ssoMw Ruster Care Safety Limits Palluder Figure 4 Pump Operaties Testsial specif utless I-3 I*b) 1 1

e l 8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 20 QUESTION 8.03 (1.00) SPECIFY the letter designation of the correct response. According to the Code of Federal Regulationsthe holder of an operating license for 10 CFR 50 l lant shall submit an LER (Licensee Event Report) for any event of the type described below. (1.0) (a.)Anytoxic-gasreleasewithintheSiteBoundary--OR--any l toxic-gas release in the Unrestricted Area that exceeded l by two times the limiting combined MPC when averaged over a time period of one hour. (b.) Any 11guld effluent release that exceeded by two times the limiting combined MPC at the point of entry into the receiving water (i.e., Unrestricted Area) for all radio-nuclides except tritium and dissolved noble gases, when averaged over a time period of one hour. (c.) Any sequence / combination of causes or conditions that caused at least one independent train or channel to become inoperable in multiple systems or two independent trains or channels to become inoperable in a single system designed tot 1. shutdown the reactor and maintain it in a safe shutdown condition --OR-- 2. remove residual heat --OR-- 3. control the release of radioactive material --OR-- 4. mitigate the consequences of an accident. (d.)Thecompletionofanynuclearplantshutdown,includingashutdown 1. required by Technical Specifications. 2. for maintenance / repair. 3. for refueling. l (* *

• CATEGORY 08 CONTINUED ON NEXT PAGE * **)

- _ = _ - - z 8. ADNINISTRATIVE PROCEDURES. CONDITIONS. AND LINITATIONS FME 21 l l L QUESTION 8.04 (2.00) Consider that at Palisades a condition existed that exceeded the Limiting Conditions for Operation as specified in the Palisades Tech. Specs. This condition was entered at 0930 (9:30an) hours. The associated ACTION requirements called for one requirement to be completed in 12 hours and there were no special exceptions associated with noncompliance. It is known that the ACTION requirement would take 2 hours of work to complete. (2.0) a. If, at 1530 (3:30 ps), work on the ACTION requirement had 3 not been started and corrective measures allowed work on i the ACTION recuirement to start, WAT additional actions l (if any) woulc be required by Tech. Specs? i i b. If, at 2000 (8:00 pe), work on the ACTION requirement had not been started and corrective measures allowed work on the ACTION requirement to start, WAT additional actions (ifany)wouldberequiredbyTech. Specs.7 c. If,at2130(9:30 ps),workontheACTIONrequirementhad not been started and corrective measures allowed work on the ACTION requirement to start, WHAT additional actions (if any) would be required by Tech. Specs.7 QUESTION 8.05 (1.00) According to the Palisades Tech. Specs., Section 3.1 " Primary Coolant Systems" (PCS),(one set of criteria for the start ofPCP)isPCScold-legte 1 a primary coolant pump 1. than or equal to 250 deg F --AND-- Pzr water volume is l ~2.~ than or equal to 700 cubic feet --0R-- secondary water TempWature in each S/G is _3._ than 70 deg F above PCS cold-leg temperatures. (1.0) greater, greater, greater j greater, greater, less l less, less, greater less, less, less i l i I (***** CATEGORY 08CONTINUEDONNEXTPAGE*****) l

l .C 8 ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS .PAGE 22 (j ,/ l QUESTION 8.06 (2.00) Consider that at the Palisades nuclear power plant, a heatup is progressing at 40 degrees F/h. The Primary Coolant System (PCS) pressure is 1400 psig. a. SPECIFY the PCS temperature range which is required by Palisades Tech-Specs, Section 3.1.2, "Heatup and Cooldown Rates." (Section3.1.2ofTech-SpecsreferstoFigure3-1 which is provided.) (0.5) b. Figure 3-1 refers to a fluence of 1.8 x 10"19 nyt. WAT is " fluence" in this situation and WAT changes must be made before the stated fluence limit is reached? (1.5). QUESTION 8.07 (1.00) According to the Palisades Tech-Specs, Section 3.1.3, " Minimum t Conditions for Criticality," the nuclear reactor can be taken critical if the primary coolant temperature is at any value 1. degrees F -AND-low-power physics test are 2. iiiiiducTa'd. (1.0) .)))between371and525,being below 371, being between 371 and 525, NOT being .) below 371, NOT being ) I t t i (""' CATEGORY 08 CONTINUED ON NEXT PAGE *"") l

1 ./ E.- w - m 3-I f* I g I 3> O f 4#, 2600- : - - - i. - - - i - - : - - - t - - - l - - !.- l. - l - - - l. -- - ). - - - i - - -l- - - -l- - -: -

- - : -.-:- -- -:- - - -:- - -:- - - l-2400-.

- -- t -- - : ---: - --l---t ---l - - -t ---r -,

- -:- - - -:- - - :- - - i.- - - ? - - <

2200-.--.---.-- s-- s-- c --'--.-- - p .:- -- :- - - : - - : - -- :- - : - --.: -- - -- -Q. -- P. / l-IR l l 60 F/HR R 2000-E s 1800-. --.---.--. -- _.c--.---.--,. - -,. 0 /Il 0 f/NR g-U l600-. - -,.--,.--,. - -, - - -..-.--.--.--.--.--.--.--r --.--,--.--r---r--r-R I400- : - - - { - - { - - - i - - - ! - - - : - - - ! - - i - - - i - - - ! - - - ! - - :- - - ' - - -l- - - -l- - - -l - - -l - - -l- - - -:- - - -: - - -: g E 4 l- ) 00' F /.HR : l': .'0 R / I I R 1200- .~ p o = s. S I000- ---.---.- -.--.---'---*.---'.---'--'---s.- m. l G B00-- o -. ~ - 600 400 200- ; - - - - - - - - ! - - - L. I---;---

---l--

0- t---4-- e t- -t ---t 4 g-g- ,....,..................,....,.........',........r...,....t-'---t-----F---:--t--n...?->> ,....i....,....,....,........,.....,....,...., o ga 5 7 I I I I 2 2 2 2 3 3 3 3 4 4 4 4 5 5 5 5 6

• • I O

5 0 2 5 7 0 2 5 7 0 2 5 7 0 2 5 '7 0 2 5 7 0 pn 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 g i = 3 U TEMPERATURE DECREES F oi

m. Te O

qag -e J .o 3 Palisades Plant Pressure /Temperat r gLimits for lleat p N for Fluence to 1.8 x 10 nwt l ) l I Ff-

e 3-1 6

-- I

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 23 i QUESTION 8.08 (2.50) According to the Palisades Tech-Specs, Section 3.1.4, " Maximum Primary Plant Coolant Radioactivity," the specific activity of the primary coolant shall be limited to 1. ( 1.0 micro Ct/gm dose equivalent I-131 AND 2. ( 100/E micro C1/gm. a. WHAT is the meaning of " micro C1/gm dose equivalent I-131"? (0.5) b. Limit "2." is concerned with WHAT radionuclides? WAT is "E"7 (1.0) c. If limit "2." was exceeded, Tech-Specs requires that the plant should be shutdown with T-avg less than 500 degrees F within 6 hours. WHAT is the significance of 500 degrees F being used here as part of the specifications? (1.0) QUESTION B.09 (2.00) As s::ecified in the Administrative Procedure, " Processing Werk Requests / Work Orders," a control operator has generated a work recuest by filling out a VR/WO ferm. Cate;orize each of the following statements as TRUE or FALSE. The Shift Supervisor shall assign a priority nu:-ber to the a. work request. I (0.5) b. If the Operations Planner determines the WR/WO to be unacceptable, he will return the WR/WO to the Shift Su;ervisor. (0,5) A Shift Supervisor shall review the WR/WO if it is deter-c. mined to be an Emergency Maintenance: review by a Shift Supervisor is not required if it is determined to be an Urgent Maintenance. (0.5) d. If the removal of ecuipment from service for maintenance places the plant in an LCO condition, the Shift Supervisor shall net release the equipment. (0.5) (""* CATEGORY 08 CONTINUED ON NEXT PAGE ""*)

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 24 QUESTION 8.10 (2.50) You have received 1000 mrem of whole-body occupational dose in the first quarter of this year and 300 arem in the second quarter-of this year. Your cumulative dose to date is 22 rem. You are a healthy male who turned 24 on the first of the year. a. According to the Palisades administrative dose limits, HOW much additional whole-body occupational dose can you receive this second calendar quarter? SPECIFY any assumptions pertinent to your answer. (1.0) b. Based on the whole-body lifetime dose limits as set by 10CFR20, WHAT is the whole-body dose limit that you can receive this year? SPECIFY any assumptions pertinent to your answer. (1.5) QUESTION 8.11 (1.50) According to the Palisades Tech-Specs, Section 3.10.2, the LCO is 0.6% reactivity maximum for any control rod in the core at rated power and 1.2% reactivity maximum for any rod in the core at zero power. a. WHAT event analyzed in the safety analysis produces this LC07 (0.5) b. WHY does a specific control rod have an integrated rod worth that is greater at zero power than when inserted at 100% power? (1.0) QUESTION 8.12 (2.00) According to Palisades Technical Specification 3.2.2(c), the combined content of the two Concentrated Boric Acid Storage Tanks (CBASTs) should be at least 118 inches of 6-1/4 to 10% l by weight boric acid solution. Standing Order No. 28, Rev.1, March 5, 1985 has placed a different operational limit on the CBASTs. a. WHAT is the different limit to which CPCo has committed itself (to the NRC)? Under WHAT power plant conditions does the different limit apply? (1.0)- b. WHAT is the concern that has generated the modified limit? (1.0)

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 25 QUESTION 8.13 (2.00) According to Standing Order No. 54 concerning the Technical Specification on Fire Rated and Fire Protection Assemblies, an " inoperable" cable tray enclosure requires one of two actions. LIST the two actions. (2.0) QUESTION 8.14 (2.00) Standing Order 54 concerning the Technical Specification on Minimum Shift Crew Ccmposition provides the following table. Nurber of Individuals Required Power Operation, Hot Standby, Cold Shutdown, Position Hot Shutdown Refueling Shutdown SS 1 1 SE or SRO 1 c. RO a. 1 A0 b. d. STA 1 Ncne COMPLETE the table giving the number of individuals for a., b., c., and d. (2.0) e t a J (""" END OF CATEGORY 08 "=a) ("""""""= END OF EXAMINATION "==========)

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 26 THERMODYNAMICS ANSWERS -- PALISADES -87/05/05-UPTON, J. ANSWER 5.01 (2.50) a. U-238 + n = U-239 U-239 = beta + Np-239 (24 min) Np-239 = beta + Pu-239 (56 hr) [+0.33 for each reaction, +1.0 maximum] b. Pu-239 reduces beta-eff (because the beta for thermal fissioning of Pu-239 is about 0.002) [+0.5] c. Because Pu-239 has a neutron-absorption-fission peak just above thermal energy, it adds a positive component to the FTC. [+1.0] REFERENCE 1. Palisades: Nuclear Operator Training, " Reactor Theory (PQ)," Theoretical Concepts (PQAO), Lesson Plan Outline Objective 4.45,

p. 32.

2. Palisades: Nuclear Operator Training, " Reactor Theory (PQ)," Theoretical Concepts (PQAO), SH-PQAO, p. 36. ANSWER 5.02 (1.00) (b.) [+1.0] REFERENCE 1. Palisades: Applied Reactor Heat Transfer and Fluid Flow, Section 4.7, p. 23. 191006k111 ...(KA'S) 4 / 'k l .c'. I} ( u u,

k. #=J/

d e4 I. .. ) ( /, j 'y' 'u.)

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, ANO PAGE 27 THERMODYNAMICS ANSWERS -- PALISADES -87/05/05-UPTON,J. ANSWER 5.03 (1.00) a. alpha particle b. neutron c. gamma-ray only d. beta particle [+0.25 each] REFERENCE 1. Palisades: Nuclear Operator Training, " Reactor' Theory (PQ)," Theoretical Concepts (PQAO), Objective 4.1, p. 8. ANSWER 5.04 (1.50) A = A(o) e**-0.693t/t-1/2 [+0.5] in A(o)/A = 0.693t/t-1/2 (0.693)(1 yr) t-1/2 = --------------- In 50,000/5,000 = (0.693)/2.30 = 0.30 years [+1.0; full credit for 0.2 to 0.4 years] REFERENCE 1. Palisades: Nuclear Operator Training, " Reactor Theory (PQ)," Theoretical Concepts (PQAO), Objective 4.2, pp. 8 through 11. ANSWER 5.05 (1.00) (b.) [+1.0] REFERENCE 1. Palisades: Nuclear Operator Training, " Reactor Theory (PO)," Theoretical Concepts (PQAO), Objectives 4.12 and 4.13, pp. 13 through 20.

5-5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS,- AND PAGE 28 THERMODYNAMICS ANSWERS -- PALISADES -87/05/05-UPTON, J. ANSWER 5.06 (3.00) a. p1 = 2100 psia p2 = 681 p]sia (saturation pressure for 500 degrees F) [+0.5 delta p = -1419 psi [+0.5] b. rho if = 50.0 lbm/ cubic foot v 2f = 0.02043 cubic foot /lbm [+0.5] rho 2f = 48.95 lbm/ cubic foot delta rho f = 1.05 lbm/ cubic foot [+0.5] c. delta k/k = +0.1% = +0.001 delta k/k/ delta p = +0.001/-1419 = -7.05 x 10**-7 [+0.5 for the magnitude, +0.5forthesign) REFERENCE 1. Palisades: Technical Specifications, Section 3.1.3, " Minimum Conditions for Criticality," pp. 3-12 and 3-13. 2. Palisades: Nuclear Operator Training, " Applied Reactor Heat Transfer and Fluid Flow (PR)," Lesson Plan Outline, Sections 4.31, 4.32 and 6.3, pp. 5 and 95. 193003K102 192004K108 ...(KA'S) ANSWER 5.07 (1.00) (c.) [+1.0] REFERENCE 1. Palisades: Nuclear Operator Training, " Reactor Theory (PQ)," Control Poisons and Fission Poison Products (PQBO), Objectives 4.13 and 4.14, pp. 10 and 11.

~~ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 29 THERMODYNAMICS ANSWERS -- PALISADES -87/05/05-UPTON, J. ANSWER 5.08 (1.00) (a.) [+1.0] REFERENCE 1. Palisades: Nuclear Operator Training, " Reactor Theory (PQ)," Theoretical Concepts (PQBO), Objectives 4.8, pp. 8 and 9. ANSWER 5.09 (1.50) The production of Xe-135 is dependent on the flux or power level because the production is from fission fragments [+0.5]. The removal of Xe-135 is by burnout and by decay. The burnout of Xe-135 is power dependent while the decay term is not [+0.5]. As the power level increases, the burnout term becomes more dominant in Xe-135 removal and the condition is approached where a power-level change would equally affect production and removal producing no change in the equilibrium Xe-concentration [+0.5]. REFERENCE 1. Pelisades: Nuclear Operator Training, " Reactor. Theory (PQ)," Control Poisons and Fission Poison Products (PQBO), Cbjective 4.27, 4.28, 4.29, 4.30 and 4.35, pp.19 through 23. 2. Palisades: Technical Data Beck, " Equilibrium Xenon Versus Reactor Power," Figure 2.1, Rev. 2.

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 30 THERHODYNAMICS ANSWERS -- PALISADES -87/05/05-UPTON,J. ANSWER 5.10 (2.00) Using Figure 6.1, the initial boron concentration is 320 ppe. Using Figure 5.1, the delta-rho is 0.54%. Using Figure 4.1, the reciprocal boron worth is 97 pps/% delta-rho. Therefore, delta-ppe = (97)(0.54) = 52.4 ppa. Using Figure 8.1, gallons / delta-ppe = 180. Therefore, answer = (180)(52.4) = 9430 gal. 4 1 (Using equation on Figure 8.2, answer = 10,300 gal) 5.77 x 10 in 1/f i [+0.33 for each step] REFERENCE 1. Palisades: Technical Data Book, Dated 5/12/84 Figures 4.1, 5.1, 6.1, 8.1, and 8.2. 2. Palisades: Nuclear Operator Training, " Reactor Theory (PQ)," Control Poisons and Fission Product Poisons (PQBO), Objectives 4.17, 4.18, 4.20, and 4.22, pp. 12 through'15. ANSWER 5.11 (1.00) a. 544.6 - 500 = 44.6 degrees F [+0. 5] b. 1000 - 680.9 = 319.1 psia [+0.5] REFERENCE 1. Palisades: Nuclear Operator Training, " Applied Reactor Heat Transfer and Fluid Flow (PR)," SH-PRA0, pp. 35 and 36. 193008K115 ...(KA'S) N

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 31 THERMODYNAMICS ANSWERS -- PALISADES -87/05/05-UPTON, J. ANSWER 5.12 (3.00) Comment: The starting pressure for this calculation can range from 570 to 790 psia. a. p = 690 psia (saturated) h = 1202 8TU/lbm (saturated steam) delta h = 0 [+0.5] P-exit = 15 psi T-exit is approximately 320 degrees F [+0.5] 108 degrees F superheat [+0.5] b. EdeltaT=$deltaT [+0.5] OR delta T charging - delta T letdown ($ letdown /E charging) E letdown = 40 gpm [+0.25] Echarging=44gpm [+0.25] delta T charging = (538 - 240) (40/44) = 298 x 0.91 = 271 degrees F j T = 110 + 271 = 381 degrees F [+0.5] l ~ REFERENCE 1. Palisades: Nuclear Operator Training, " Applied Reactor Heat Transfer and Fluid Flow (PR)," SH-PRA0, Objectives 4.35, 4.37, and 4.48, pp. 45 through 49 and 68.

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 32 THERMODYNAMICS ANSWERS -- PALISADES -87/05/05-UPTON, J. ANSWER 5.13 (3.50) a. " Pump runout" is the term used to describe the operation of a centrifugal pump when it is pumping at minimum head and maximum flowrate (and low NPSH and max amps) [+0.5]. It is indicated by the far-right in the figure [+0.5]. b. 1. NPSH = 100 ft H 0 2 = 43.4 psia sat. press. (360 degrees F) = 153.0 psia hence, min. press. = 196.4 psia [+1.0]. 2. no, SOP-1 requires 250 psia [+0.5] When the PCS temperature is increased, the PCS water density c. is decreased. The decreased density results in the frictional losses being decreased. This means that the operating point would move to the ri ht on the curve providing less head and more flowrate. [+1.0 REFERENCE 1. Palisades: Nuclear Operator Training, "Applie'd Reactor Heat Transfer and Fluid Flow (PR)," SH-PRAO, pp.123 through 133 and Figure 10. 191004K112 ...(KA'S) ANSWER 5.14 (1.00) (d.) [+1.0] REFERENCE 1. Palisades: Nuclear Operator Training, " Materials Science (MSCI)," Objectives 4.9, 4.10, and 4.11, SH-MSCI, Rev. 1, pp. 14 through 17 and Figure MSCI-4. 193010K102 ...(KA'S) l J

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 33 THERMODYNAMICS ANSWERS -- PALISADES -87/05/05-UPTON, J. ANSWER 5.15 (1.00) (b.) [+1.0) REFERENCE 1. Palisades: Nuclear Operator Training, "Appiled Reactor Heat Transfer and Fluid Flow (PR)," SH-PRAO, pp. 50 through 52. 193008K106 ...(KA'S) e O i

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 34 ANSWERS -- PALISADES -87/05/05-UPTON, J. ANSWER 6.01 (1.00) ~ upper electrical limit lower electrical limit Rod Withdrawal Prohibit (RWP) [+0.33 each] REFERENCE 1. Palisades: Nuclear Operator Training, Advanced Systems Training, "RX Reg. and Rod Control (PNLB)", SH-PNLB, p. 28. 001000K408 ...(KA'S) ANSWER 6.02 (1.50) 1. turbine trip 2. bus IC undervoltage 3. S/U transformer undervoltage 4. bus ID undervolt. age [Any three (3) +0.5 each, +1.5 maximum] REFERENCE 1. Palisades: Nuclear Operator Training, Advanced Systems Training, " Diesel Generators (PNHB)", Lesson Plan Outline, Objectives 4.13, p. 19. ANSWER 6.03 (1.00) The Volume Control Tank is designed such that (with level in the normal control band) the tank can accommodate a zero to full power increase without diversion [+0.5], and can com zero power decrease without requiring makeup [pensate for a full to +0.5]. REFERENCE 1. Palisades: Nuclear Operator Training, Advanced Systems Training, PCS Auxiliary and Containment (PNK), "CVCS (PNKA)", SH-PNKA,

p. 21.

004020K601 ...(KA'S)

W 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 35 ANSWERS -- PALISADES -87/05/05-UPTON,J. ANSWER 6.04 (1.00) The containment sump valves start to open (one minute) before the SIRW outlet valves fully close --OR-- the actions of these valves overlap. [+1.0] REFERENCE 1. Palisades: Nuclear Operator Training, Advanced Systems Training, EngineeredSafeguardsSystems(PNM),"SafetyInjection(PNMA)", SH-PNMA, p. 25. 006000K409 ...(KA'S) ANSWER 6.05 (2.00) I Comment: MSIS - such an actuation signal does not exist at Palisades. MSIVs do, of course, exist. Hence, the 2 alternate answers to "a.". The answer to "b." is changed to reflect the new setpoint of 10 R. a. SIAS, CSAS, Auto Containment Isolation, MSIS (1., 2., 3., 4.) --0R-- (1.,2.',3.) [+1.00] b. None [+0.5] c. None [+0.5] REFERENCE 1. Palisades: Nuclear Operator Training, Advanced Systems Training, Engineered Safeguards Systems (PNM), " Safety . Injection (PNMA)", LP-PNMA, pp. 16 and 17; " Containment Spray (PNBM)", SH-PNMB, p. 23; " Containment Building (PNMF)",SH-PNMF,p.14. 2. Palisades: Nuclear Operator Training, Advanced Systems Training, Secondary Plant Steam Systems (PND), " Main Steam (PNDB)", SH-PNDB, p.11; " Auxiliary Feedwater (PHEB)",LP-PHEB,p.8. Ol2000A301 ...(KA'S)

7 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 36 ANSWERS -- PALISADES -87/05/05-UPTON, J. i ANSWER 6.06 (3.00) 1. Boric Acid Pumps start (P56A and B). 2. CoolantChargingPumpsstart(P55A,BandC). 3. Boric Acid Gravity Feed Valves open (MOV-2169 and -2170). 1 4. Boric Acid Pumped Feed Stop Valve (MOV-2140) opens. l* 5. VCT Outlet Valve (MOV-2087) closes. 6. Concentrated Boric Acid Tanks' Recirc V'alves (CV-2130 and ) -2136) close. 7. Boric Acid Makeup Stop Valve (CV-2155) closes. [+0.5 each, +3.0 maximum] REFERENCE j 1. Palisades: Nuclear Operator Trainin PCS Auxiliary and Containment (FNK)g, Advanced Systems Training, "CVCS (PNKA)", Objective 4.24, SH-FNKA, p. 48. ANSWER 6.07 (2.00) a. CLOSED (Air is required to cpen the valve) [+0.5] b. 1. If noncritical header is lost for greater than 10 secs [+0.5)thentriptheplant[+0.5] l 2. To prevent overheating of generator exciter (and subsequent failure of exciter diodes) [+0.5] REFERENCE i 1. Palisades: SH-FNAA, ...(KA'S) pp. 15 and 16. 00062EK303 i

j 6. PLANT SYSTENS DESIGN. CONTROL, AND INSTRUNENTATION PAGE 37 I ANSWERS -- PALISADES -87/05/05-UPTON,J. ) ANSWER 6.08 (2.00) a. The indicated pressures will be LESS THAN the actual pressure j [+0.5]. PZR and S/G pressure instruments read relative to containment pressure, therefore, as containment pressure increases, the indicated PZR and S/G pressures decrease [+0.5]. b. The indicated levels will be GREATER THAN the actual levels [+0.5]. The reference leg would be less dense resulting in i 1, less delta Ps and thus greater indicated levels [+0.5]. ) REFERENCE 1. Palisades: SH-PNKE, p. 26 and 27. l 191002K108 ' 191002K111 ...(KA'S) i l l ANSWER 6.09 (1.50) Comment: Due to the wording of the question in which " loa'ds" was I used instead of " pumps or types of pumps," three alternate' answers are acceptable. An incorrect load I or pump will result in less than full credit. 1. HPSI 1. engineered safety pumps and 2. LPSI --OR-- 2. SDC Hx 3. Containment Spray Pump --0R-- engineered safety pumps [+1.5 for either] i l PEFERENCE 1 ...(KA'S}p.40. 1. Palisades: SH-PNAB 1 00026EA103 i' ANSWER 6.10 (2.00) 4 Comment: The reference lists both RUP and AUP. The ARP a. RWP l+0.75 lists only the RWP. The point count was adjusted j AWP +0.25,- as shown b. Power-Range Safety Channel > 15%

+0.5; Wide-Range Log Channel ( 10**-4%

0.5 + 1 l REFERENCE 1. Palisades: Nuclear Operator Training, Advanced Systems l Training, RX Nonttoring and Protection Systems (PNN), " Nuclear Instrumentation (PNNA)", Lesson Plan Outline, i Rev. 2, LP-PNNA, pp. 30 and 31. 012000K603 ...(KA'S)

l 6. PLANT SYSTEMS DESIG*, CONTROL, AND INSTRUMENTATION PAGE 38 ANSWERS -- PALISADES -87/05/05-UPTON, J. ANSWER 6.11 (1.00) (b.) [+1.0] REFERENCE 1. Palisades: Nuclear Operator Training, Advanced Systems Training, RX Monitoring and Protection Systems (PNN), " Nuclear Instrumentation (PNNA)", Lesson Plan Outline, Rev. 2, SH-PNNA, Objective 4.7. ANSWER 6.12 (2.50) a. failed, bad, or nonessential b. danger, immediate action --OR-- alarm condition l c. passive, off, or closed d. caution --0R-- alarm condition [ e. Intermediate or throttled [+0.5eachpart] i REFERENCE 1. Palisades: PNOC, Objective 4.02. ANSWER 6.13 (2.00) a. 1. The reactor-side tilt machine cannot be rotated from vertical to horizontal if the refueling machine is in the tilt machine zone. [+0.5] 2. The refueling machine cannot enter tilt zone unless tilt machine is vertical. [+0.5] b. One winch is driven to tow the carriage while the other winch freewheels to pay out cable. [+1.0] REFERENCE 1. Palisades: PNEQ. 034000K402 ...(KA'S) i

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 39 ANSWERS -- PALISADES -87/05/05-UPTON, J. ANSWER 6.14 (2.50) a. 125 VDC Bus No. 2 [+0.25] --OR-- inverter No. 2 l [+0.5 for either] b. by (manual) transfer of the bypass regulator --0R-- by connecting Y01 AC instrument bust [+1.0 for either] l 1 c. 1. 125 VDC battery 2. D/G-1 3. D/G-2 i [+0.5 each, +1.0 maximum] REFERENCE 1. Palisades: PNIC, Objectives 4.14 and 4.15, Figure PNIC-1. i 1 4 .I

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 40 RADIOLOGICAL CONTROL l ANSWERS -- PALISADES -87/05/05-UPTON, J. 'I ANSWER 7.01 (1.50) Comments: Part "a." is deleted because the word acceptable is not sufficiently clear. Part "c." is deleted because the j question does not state whether the condensate or the purification demineralizer is to be considered. Part "e." J was changed during the exam to reflect the changes in the procedure. a. False (below 7 mils is normal, 14 alls requires trip) [+0.5] b. True (maximum allowed is 4.3" HgA) [+0.5] c. True (below 40 psi is acceptable) [+0.5] d. 15% of rated thermal power [+0.25] within a one-hour period [+0.25] e. 562.8 degrees F [+0.5] --OR-- 543.5 degrees F REFERENCE 1. Palisades: SOP 8, Main Turbine and Generating Systems, Sections g 5.0.e and 5.0.v, pp. 2 through 4 of 61, Revision 16. 1 2. Palisades: 50P 11, Condensate System, Section 5.0.n, p. 4 j of 27, Revision 4. 1 j 3. Palisades: GOP 6, Power Level Change, Sections 6.1.6 and 6.1.9, Revision 2. 045000A101 ...(KA'S) i 4 i s -.

s. 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 41 RADIOLOGICAL CONTROL ANSWERS -- PALISADES -87/05/05-UPTON, J. ANSWER 7.02 (5.00) Comment: The answer to part "c." was changed because E0P-1 lists k 3 ftens while E0P-8 lists 5 items to be checked to verify natural circulation. Push both [+0.25] reactor trip push buttons [+0.25] a. Open CR0 clutch power feeder breakers [+0.25] Set all CR0 clutch power toggle switches to CLUTCH OFF [+0.25] Commence emergency boration [+0.5] b. Attempt manual transfer [+0.5] Close both NSIVs [+0.5] c. Core delta T less than 50 degrees F CETs 25 degrees F subcooled I Loop T-H within 15 degrees F of CETs loop TC's constant or decreasing ] CETs constant or decreasing [+0.5 each, +1.5 maximum] Containment Isolation is initiated by[ pushing either or both d. HIGH RADIATION INITIATE push button +0.5] j . Containment spray is initiated by opening containment spray valves [+0.25] and starting containment spray pumps [+0.25] REFERENCE 1. Palisades: E0P 1.0, Standard Post Trip Actions, Section 3.0, Steps 4, 5.d, 11, 13, and 14, pp. 2, 5, and 7 of 8, ,t Revision 0. 00029EK312 ...(KA'S) i ANSWER 7.03 (1.50) a. Increase b. decrease c. decrease [+0.5 each] REFERENCE 1. Palisades: E0P 8.0, Loss of Forced Circulation Recovery, Steps 55 through 59, pp. 11 and 12 of 15, Revison 0. 00074EK102 ...(KA'S)

.~ 7. PROCEDURES - NORMAL, ABNORMAL. EMERGENCY AND PAGE 42 RADIOLOGICAL CONTROL ANSWERS -- PALISADES -87/05/05-UPTON, J. ANSWER 7.04 (2.00) Comment: Part "a." is accepted as a correct answer seeing as SOP-1 l does not allow operation with less than 4 PCPs. a. allowed l b. not allowed c. not allowed d. allowed [+0.5each] REFERENCE 1. Palisades: Technical Specifications 3.1.5, Primary Coolant System Leakage Limits, pp. 3 through 21, Amendment 95. 002020SGA8 ...(KA'S) ANSWER 7.05 (1.00) (a.) --OR-- (c.) [+1.0] REFERENCE 1. Palisades: Technical Specifications, Sections 3.1.1.c (Table 2.3.1), 3.1.7.c, 3.3.2.a, and 3.5.2.b. 002020SGA8 ...(KA'S) ANSWER 7.06 (1.00) Comment: In the answer, step 3.2 could be supplied as part of the { immediate actions, but it is not required. 1. Start diesel generators [+0.5] 2. Announce conditions [+0.25] and start assembly of plant personnel in access control [+0.25]. REFERENCE 1. Palisades: ONP 12, Acts of Nature, Section 3.1, p. 1 of 3, Revision 11. 062000SGA7 ...(KA'S)

r r 7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 43 RADIOLOGICAL CONTROL ANSWERS -- PALISADES -87/05/05-UPTON,J. ANSWER 7.07 (2.50) Actions - Trip reactor [+0.5]. Isolate letdown (close CV-2001) [+0.5]. l Close PCP controlled bleedoff containment isolation valves (CV-2083 and CV-2099) [+0.5] Open PCP controlled bleedoff relief stop valve (CV-2191) [+0.5]. Reason - To contain primary coolant discharge via the drain tank, due to loss of VCT level and other indications, due to loss of cooling-pond pumps, any]of the reasons used for emergency boration [+0.5 for any REFERENCE l 1. Palisades: ONP 24.5, Loss of Instrument AC Bus YO1, p.1 of 3, Revision 12. 000057EK03 ...(KA'S) ANSWER 7.08 (5.00) Gravity feed [+0.4]F.+0.3].from either the boric acid tanks [+0.3] a. 1. or from the SIRWT 2. Normal charging [+0.4] HPSI [+0.3] j auxiliary spray [+0.3] j i b. 1. HPSI pumps [+0.4] using either cold leg [+0.3] or hot leg

+0. 3, injection.

PCS pressure must be less than 1250 psia _ 0.3 (1200 to 1300 psia acceptable). 4 + 2. Containment spray pumps [+0.4] using LPSI cold leg injection { [+0.3]. PCS pressure must be less than 250 psia [+0.3] (200 to300psiaacceptable). 3. LPSI pumps using LPSI cold leg injection [+0.4]. PCS pressure 4 must be less than 170 psia [+0.3] (150 to 200 psia acceptable). 9 REFERENCE 1. Palisades: E0P 9.0, Functional Recovery, Attachment A. 001000K405 ...(KA'S)

r 7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 44 RADIOLOGICAL CONTROL ANSWERS -- PALISADES -87/05/05-UPTON, J. ANSWER 7.09 (1.00) 1. radios 2. vital area door keys 3. locked valve keys 4. emergency flashlights I [+0.25each] REFERENCE 1. Palisades: ONP 25.2, Alternate Safe Shutdown Procedure, Section 4.2, p. 2 of 16, Revision 0. 0000075GA6 ...(KA'S) ANSWER 7.10 (2.00) 1. notify the control room and evacuate fuel handling area 2. ensure fuel handling area charcoal filter is in operation (by placing HS-1894 to " Refuel" position) 3. trip the fuel handling area supply fan (V-7) 4. trip the fuel handling area fans V-69, 70A, 70B (by placing HS-1893 to l "EmergencyOff") [+0.5each; item"1."canbesplitintotwoimmediateactions] REFERENCE 1. Palisades: ONP 11.2, Fuel Handling Accident, Section 3.2, p. 1 of 2, Revision 0. 00036EK303 ...(KA'S)

r- .o o 7. PROCEDURES - NORMAL, A8 NORMAL, EMERGENCY AND PAGE 45 RADIOLOGICAL CONTROL ANSWERS -- PALISADES -87/05/05-UPTON, J. ANSWER 7.11 (1.50) a. 1. PCS less than 300 degrees F (250 degrees F per Technical Specifications) [+0.5] shutdown coolin 2. are open [+0.5]g isolation valves (MO-3015 and MO-3016) b. A maximum of one HPSI pump is allowed to be operable [+0.5] REFERENCE 1. Palisades: SOP 1, PCS, Section 4.0.q and w, p. 4 of 45, Revision 16. 2. Palisades: Technical Spe:tfications, 3.1.8 and 3.3.2.g. 010000K503 ...(KA'S) s l l

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 46 ANSWERS -- PALISADES -87/05/05-UPTON,J. ANSWER 8.01 (1.50) 5., 6., and 8. [+0.5each] REFERENCE 1. Palisades: " Technical Specifications," Section 1.1, p. 1-1. 002020SGK5 ...(KA'S) ANSWER 8.02 (2.00) a. below the 2100 psia parameter line [+0.5] b. to maintain the integrity of the fuel cladding --OR-- to prevent the release of significant amounts of fission products to the ' primary coolant --OR-- to maintain the DNER greater than 1.3 [+0.75 for any version] c. The temperature limits should be reduced prcportionately to the deficiency in the vessel flowrate (1 degree F per 1% in flowrate). [+0.75] REFERENCE 1. Palisades: Technical Specifications, Section 2.1, " Safety Limits-Reactor Core," pp. 2-1 and 2-13. 2. Palisades: Technical Specifications, Section 3.1, " Primary Coolant System," p. 3-Ib. 0020205GK5 ...(KA'S) l

/ 8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 47 ANSWERS -- PALISADES -87/05/05-UPTON,J. ANSWER 8.03 (1.00) (b.) [+1.0] REFERENCE 1. Generic: Code of Federal Regulations, Section 50.73(a), " Licensee Event Report System, (a) Reportable Events," January 1, 1985, pp. 458 and 459. 2. Palisades: Technical Specifications, Section 1.4, " Miscellaneous Definitions, Reportable Event," p. 1-5. 068000SGK3 ...(KA'S) ANSWER 8.04 (2.00) Coment: It was agreed that an answer of "none" is acceptable for part "b." and then the details should be supplied in part "c.". a. none [+0.5] l b. none [+0.5] c. Tech. Specs. Section 3.0.3 applies with the actions listed in "b". [+0.5; +1.0 for detailing the additional actions, if they are not listedinpart"b".] By 2230 hours action shall have been initiated to place the unit in a condition in which the Specification does not apply [+0.25] by placing it, as applicable, in: 1. at least HOT STANDBY within the next 6 hours [+0.25] 2. at least HOT SHUTDOWN within the following 6 hours [+0.25], and 3. at least COLD SHUTDOWN within the subsequent 24 hours [+0.25]. REFERENCE 1. Palisades: Technical Specifications, Section 3.0, " Limiting Conditions for Operation", p. 3-1. 000000SGA8 ...(KA'S)

( 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 48 ANSWERS -- PALISADES -87/05/05-UPTON, J. ANSWER 8.05 (1.00) (d.) [+1.0] REFERENCE 1. Palisades: Technical Specifications, Section 3.1, " Primary Coolant Systems,", p. 3-Ic. 003000K614 ...(KA'S) ANSWER 8.06 (2.00) a. PCS temperature should be above 375 degrees F '[+0.5]. b. Fluence here is the fast neutron flux integrated over time to which the reactor vessel is exposed. --OR-- Fluence here is fast neutron dose or exposure to which the reactor vessel is exposed. [+1.0] Before the fluence exceeds the limit in the figure, the heatup and cooldown curves should be updated [+0.5]. REFERENCE 1. Palisades: Technical Specifications, Section 3.1.2, "Heatup and Cooldown Rates," pp. 3-4 and 3-9. 002020SGK5 ...(KA'S) ANSWER 8.07 (1.00) (a.) [+1.0] REFERENCE 1. Palisades: Technical Specifications, Section 3.1.3, " Minimum Conditions for Criticality," p. 3-12. 002020SGA8 ...(KA'S) ~

c-8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 49 ANSWERS -- PALISADES -87/05/05-UPTON, J. t ANSWER 8.08 (2.50) a. Dose equivalent I-131 shall be that concentration of I-131 which alone would produce the same thyroid dose as the quantity and isotopic mixture of the iodine isotopes actually present. [+0.5] b. Limit "2." is concerned with radioactive isotopes other than todines [+0.25] which have half-lives greater than 15 minutes [+0.25]; E is an average of the disintegration energies [+0.5]. c. 500 degrees F is used because the saturation pressure associated with 500 degrees F is below the lift pressure of the atmospheric steam-relief valves of the S/Gs. --OR-- This would prevent a release to the atmosphere in the event of a S/G tube rupture. [+1.0 for either] REFERENCE 1. Palisades: Technical Specifications, Section 3.1.4, " Maximum Primary Plant Coolant Radioactivity," pp. 3-17 and 3-18. 2. Palisades: Technical Specifications, Section 1.4, " Miscellaneous Definitions, p. 1-4. 002020SGA8 ...(KA'S) t_ i ANSWER 8.09 (2.00) a. False b. True l c. False d. False [+0.5each] REFERENCE 1. Palisades: Administrative Procedure, " Processing Work i Requests / Work Orders," Proc. No. 5.01, pp. 6 through 16. 0000PWGA32 ...(KA'S) i i

8-ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 50 ANSWERS -- PALISADES -87/05/05-UPTON,J. ANSWER 8.10 (2.50) a. If you had a completed NRC Form 4 on file, the limit is 3000 mrem per quarter; so, you can receive an additional 2700 mrem (full credit will be given if either the control or alert levels, 2500 j and 2000 mres, respectively, are used) [+0.5].

1. ~

b. If you have a NRC Form 4, you can receive 3 rem per huarter or } 12 rem per year [+0.5]. However, you can only receive 5 (24-18) or 30 rem cumulative dose, so your dose limit would be 8 rem this year [+0.5]. REFERENCE 1. Palisades: Administrative Procedure, " Radiation Dostmetry," Proc. No. 7.04, Revision 6, pp. 3 and 4. 006000K601 ...(KA'S) ANSWER 8.11 (1.50) a. A rod-ejection accident. [+0.5] j b. One rod fully withdrawn with the other rods fully inserted has i a greater rod worth due to the neutron flux being higher locally relative to the rest of the core. [+1.0] REFERENCE 1. Palisades: Technical Specifications, Section 3.10.2. 2. Palisades: Nuclear Operator Training, " Reactor Theory (PQ)," Poison and Fission Poison Products (PQBO), Objectives 4.10, 4.11 and 4.12, pp. 9 and 10. i 1 1 i E

f \\ n. 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 51 ANSWERS -- PALISADES -87/05/05-UPTON, J. i ANSWER 8.12 (2.00) a. Both CBASTs will be maintained at or above 118 inches [+0.5] whenever the reactor is critical [+0.5]. (Ifeitherlevel drops below 118 inches, then action step 3.2.3(b) would become applicable.) b. The concern is that if one D/G were inoperable concurrent with the-loss of off-site power, the required amount of boric acid may not be available automatically unless the level of T-53A is always maintained above 118 inches. [+1.0] REFERENCE 1. Palisades: Standing Orders, " Palisades Plant-Operability of Concentrated Boric Acid Tanks,' Standing Order No. 28, Rev.1 March 5, 1985. 00059EK102 ...(KA'S) ANSWER 8.13 (2.00) 1. Establish a continuous fire watch on at least one side within one hour. 2. Verify the operability of fire detectors on at least one side and establish an hourly fire inspection. [+1.0each] REFERENCE 1. Palisades: Standing Orders, " Palisades Plant-Supplemental Technical Specifications," Standing Ort'tr No. 54, Rev. 5, January 13, 1987, p. 10. l 086000K403 ...(KA'S) l tt I

.y 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AN9 LIMITATIONS PAGE 52 ANSWERS -- PALISADES -87/05/05-UPTON, J. ANSWER 8.14 (2.00) a. 2 b. 2 C. none d. 2 -[+0.5each] REFERENCE 1. Palisades: Standing Orders, " Palisades Plant-Supplemental Technical Specifications," Standing Order No. $4', Rev. 5, January 13, 1987, p. 28. 0000PWGA23 ...(KA'S) 4

y,. EQUATION FORMULA AND PARAMETER SHEET Where mg = m2 ~ (density)i(velocity)3(area)1 = (density)2(velocity)2(area)2 i KE = "{2PE = mgh PE + KE +P V g 3 = PE +KE +P Y22 where V = specific g g 2 2 volume P = pressure Q=Ec(T -Tin) Q=UA(T,y,-Tstm) O " "(h -h ) p out l 2 N ~ #) m = (B - a) P = P,10(SUR)(t) P = P e /T SUR = 26.06 T= t o T p p A,ff delta K = (K,ff_1) CR (1.K,ffg) = cR (1-Keff2) CR=S/(1-K,ff) g 2 (1-K,ff3) (1-K,ff) x 100'. A'If = 0.08 sec,3 M = (1-Keff2) K SCM = eff decay constant = In (2), 0.693 1 = A e-(decay constant)x(t) A 1 t 0 1/2 1/2 Water Parameters Miscellaneous Conversions 10 1 gallen = 8.345 lbs 1 Curie = 3.7 x 10 dps ~ 1 gallen = 3.78 liters 1 kg = 2.21 lbs 3 3 1 ft = 7.48 gallons I hp = 2.54 x 10 Btu /hr 3 6 Density = 62.4 lb /ft 1 MW = 3.41 x 10 8tu/hr 3 Density = 1 gm/cm 1 Btu = 778 ft-lbf Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters2 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 ft-lbm/lbf-sec 1 ft H O = 0.4335 lbf/in.2 2 ~

PALISADES TECHNICAL DATA BOOK FIGURE 41, REV 21 CYCLE 7 HZP RECIPROCAL BORON WORTH VS BURNUP no-i i I i i i i A 'l 8 l k \\ l 1 105- .i i j I \\ n i Q. l i l <= x i j l 'j iOO-m i 1 i i i i-t 5 i l 5 g g3 5 l t i = l e 3 ^. C ~ E: i Pg go. i

'l e

..:::r:::. . REVEWED BY s.. g g A g 3o g 33 REACTOR M EZR 2.*' b c Mb_/m <./ REACTOR thChtERhc.h SUPERNTENCthT l I l d0-0 2 4 6 8 10 12 00RNUP - GWD/WTd CONSUWERS 70wr.R CCWPW atAcron EschttRNC/ PAuSADES GCPaekeeo REActon ENostER cacup 02/27/86

{ u j PALISADES TECHNICAL DATA BOOK FIGURE 5.1. REV 21 CYCLE 7 INTEGRAL ROD WORTH i 24 I, i i l i i i

1. 0 -

e l l t t, i REVEWED BY c i 4 M o .i?...- W r. o8 i asc:cac AEa Cn. / / t l'M A., /EbM f og 0 AEACICR ENC;hEIRJ[ ' ' ~ ~ SUPERATENDENT

i 4

~ E i i T. p 5, f a C } 5 0 s-1 8 \\ o l g N + i ~ i 5 5 0 5 .k.. C. W . h l t -- 0 4- ^ l .4. j i --.. ~..... g s e 0 2 t i l l W 0 0-l 60 a0 100 120 140 CR4 0 20 40 GR3 80 100 120 132 INCHES 41TrtDRAWN ROD POSiilON CONSUWERS POWER COWPANY REACTOR ENGNEDNC/ PAUSADES CCPaek=ed REACTOR ENGhEG CROUP 02/2I/86 4--.e.- u-y y

r

s..

.e l i PALISADES TECHNICAL DATA BOOK FIGURE 61. REV 2 CYCLE 7 , 1%y s :,,e,.., BRE01CTED BORON CONCENTRATION vs p.N . Mf, ". BURNUP (HFP. ARO. E00ll. XENON) 1300 _r ....... _L _.. 1200 .r...-..,....... - 1100-- .. ~ -. _... u 1000 2 900---- - - - r.- - .... -.. _ ~. ~.. ~. - -.,,-. n -. c e C. a...... .i s.,- + =. cgi4L ~ ~ l . ' '. MM z 800

a. r. r r

cs is ... _ = I'; 7 0 0 -- --~' 1 a .U Z C 600 . N.. v 1 o C 500-- r:....- t 400 .r ...._-.u _.,4 . s. u... ,u 300-m , y ~.,.,.: ~ 4 W . p"o,- BY -.= a .m

,=.,

u r ,. W.k JL $n. 100 3 p g: PT. ACTOR u..... x.u n./_vd/L sif. ......~. ~ --.. M ~.. 100 ._4........ at>dron tucintigma y _. _ Q.. -~. suPDunroccur 0 6 6 -1 0 1 2 3 4 5 6 7 8 9 10 11 12 EXPOSURE GWD/WTU C0esstadUt$ POWDt CotePANY REAcr0R DeGIIEDHpee/ PAUSADO CCPeekerd poctom Deeptat omew 02/27/M CONTROLLFr) mov

4-t Tigure 8.1, Rav 0 4 Hor F-3 7 T B GAu.ms N P=1t. pF ( .e s a. { g't.

). m - i=c.:.tu-fy::.:.t___

1 :. i l Mf

o l

.__l:=:.. l.

l g. g .;.g gi_j i ..r:.=

l

.. :t. 1_@ - (==. l.,::h 5:;. +

W: l- _rl:=* 4 - ,h . l: i 4=- :Fg l -'_@ i:Y 5.E r M-lN il-f" Y:U: l-

• 3-isl5i. l.Wl3-T'l l lM.tl" l

. =. _ =. _.. 2. ._.:__.......___...c... , :._n :_ ---i W-'.

.: n: _. ;.......

. s, f tab.,i = 9.: - -{ a-

1 i

i,l. .l \\t,

. s.- W. i. _ i.:=-.- D 6.cl,r

.:.t 2

c. -

yM P.~2'.'i y.

l3l-,W ;:

f.;

pag g g Q - -($.g ll, g.,y g,g LM ' td PCS \\e9:r f . l _.=_ : 2 :.. l.. t:. :- ...[. l_. l =.=== L.. \\, W,. .s l. ...\\_..... ._.l..=..

._s:.I". :L_. l:. (_.. I~_.;,. -

._. _-..= . :. : : i... .n 2 . =. V - .. _. _ _... ;. ::. /..: _ :_ :...

.:. _..=.. _ M._...

T

..__.t ..._a=.___. .=.;:te :. .1 .- fr =:::= :I: r; :=l .:.L _t _ _ _ {:==.=j:. ;.r. F 2:1 r J. ? .m

.- i _.._ I ; __.. -

N. = : l:.:.: t :=.1- =:= J :. y. - _ {.= g' _... =_!.. . __= =:.; N -- = r.i. l.. _ _ ( _.._. _ _ = _ _... _ .6.- w m 4

"". ::- 5

. :E.1 '.N s en 3.:.Ei:G 4

1!-

-ik!. be -:.--.-...:*-'":-.L_- ; S:

_ r. :::.

--er --J 25 -

.:2:+

... =s. :.* . m. := p.

=. r.s

=:_

.r. r . =.. = = -:=.:.r=:==:.r._z ur e: - _.=.f.~.. . =. - -._- =-

m=

r_. : 4: .=-==:.;.--.-.. 3 + =:::.r=. -a

==- ~ : ::=: =- e.-r e u t .. _. = = 2 _s .....a,.: _ _ = .. u. _..==_a--*.==: r-8: _ _- _ r-.: :

== c =. =._ ..a. :.

=..:-

__. :.r

_.=.---.==..:. :.:

tm.- ..r

==r

=

=::

=. ci - - - ' ===- ::.. - .=.: _. t...=.=_ =:. :..: : : *.=.======= :== =.. r : _:.=: _.:n._.. =: ; n..:=. _=s . i.. :. .... = =. =.=_=__==r.._- .. r.:.-

r..r.::

~_. L.= t - = - .~... -.~.-. =. -

-..... c_.::- r-.

... r-

. = =., - . =. -. =_ .. g._. -... ...g_... = a=. g _-....=...u....=- ..w

._ (

.._.__...-......3 . =. ___ .p _ _ l. g, _... _. 4... l .l i

1. u, _ _ _ t...=.J

- _m- -.:: =- : =.-. l-. i. I. I:.\\. 4...l.

_:._ __... a..c _l-

_- _2.._... r_=. _=, _ _._ : ;.. u.= __= a t p e = -- = n.=.::..__ _.. = q 5_.=._; =.. =t g -..

r. =. p: =_. 3.. ;. l i-g.=._.....p--,

p.... _- =.:.:~_. t =. _ p__= :==...r = =n' =- " <,_. _ "= : 2

. =.-j _.

. i=- s g ._-:= c l.v ac m ._:[ _ 2 a.+ o = i-- l_r.t l "- c. -- j. t ==== + -- = i -

== T - ~.'=== ' ~ ~==" E I ~~ ' r

u..:.

ii----_.._..==--c----.

=;u--- - ::---

e4

a. 1

....._==..f..-...--._- -..- d.. _=..... . l.. u_ _c s y et d ~ b d' -- R7# t* -E ~ ' U3.=~J I : l'.W "": I I \\ =I= !+3 'r ~~ 9 :-5 "~= 4:~E - -._=t--l'"5 4 ': ~9 *--! g g i _. 6 .:.se: rw '-- _;=;c-te =2=m = i - LA as-:

-U s=-w==E==

. : t=+m.-E=4.1 --__ -~ -- :lij:F- =: 8 I

==t-

1. 1

==E :'; ._!= z.1 -I=.E:..-EL.r.1 s:M -=-;t+#- F. . _ _ =., __ _=_=. : r =_=. o --..i g .'..<..::.;,. I..: =_w. t;_==::=-_=.._ u _A _, _. s L_ _.\\_., i - - r._. c

y. :

-- _T :=:.l..Mi?%-- JiEMi sh:'E5:Mi~ l %= *%= o _ ftEE:J Ld_ t- -l V - ~ \\._ w.=:- _.:-- r J.___4._ lr_.::. 8,- g.i ....._._. r_.C. T .p.=_.; _;._/. r ...t. ZI .,, ;. y

===.==..= __. 7

_m =__ p m.==

.:r _._g==. =_a g. _ -. :r== r=_==_ c-.

-- r====_. g: --g.g=r. f _ _. _ _ =... - =.:.a=_=_-=.

. _==

_. a,..._ _ - 6: . f; ...._._=:. _--=_;=--L C,=

==.=

O es;:::= :- = g, . :.z_=1 - =.. i _ : 5.==== ;__ _--g=.=_=.=:_:__=_..- .=..-r=_. - = g-. EE p-===5 :. . _ b. - z=_

==

=

==..,:=.. 2 = :.- .-.--l._ .==_ ".r .te.r. - . _:..:.. q:..EE=. =.=&._. r_., __ _..

-:=..

4 .o

=._ --

-;. -gr.c .a:=-.- - =--. __ _

== _ g.:. N . = : : - - .. =:::

-

2 .=: =_:j,

===._=_=E-::==.i._. _._4.s..

.r_.3Z_ E_F,_i:W'-'-"___.;::.

= =.. _ _.. -.. _... _ =.. -. - -=. _. 4 =...s.... n..5 g

i... _

..~... _.. _ m =.- ._=== m .m.- ...a f _....g.. 4.

s. p.

=11 g.. 10 =...p. e .6 e ,,,i. e. .i.;i.. r~.i.. 4 m 4 Pg-. q.w-s., \\ ~ l %.s ' .- S i Rt'nc.cG Q l. ( i om ~Ur 6 4 \\ I .m a.

,m.e i

4. Km ns,:e

(< I f,. - Figura 8.2, Pag 2 1 ef 2, Rsv 0 FORMULA SMEET I. Boron Addition .( A. OT 5 77 X 10 in (B.A.T.k. PPM-Pc(Initial) V Gal. B.A. = (B.A.T.k. PPM-PC(Final) B. COLDV Gal. B.A. = 8.h6 X 10 in (B.A.T.k. PPM-PC(Initial) (B.A.T.k. PPM-PC(Final) C. V Gal. B.A. for Gal. of Water Desired PPM = to Berate X increase desired PPM, increase B.A.T.k. PPM II. Dilution i A* HOT k 5 77 X 10 in (PC Tnitial) V Gal. PMW = (PC Final) I COLD V Gal. PMW = 8.h3 X 10 in (PC Initial) (PC Final) III. Blend Ratio B.A.T.k. PPM - 1 = for Gal. PMW PC PPM 1 Gal. B.A. 59/iTHED bY M M [ IID, gecter Engineer i l /1 "/' fbl. I i % 3cisup.:m:2re.eut I l ~4- .s,.:. . >/s-;.

n .o Figure 8.2, Page 2 of 2, Rev 0 IV. Mixing Water and Concentrated B. A. A. : Final Concentration = ((Initial Gal. X Initial Cene.) 4 Initial Gal. + Gal. H O Added) 2 ~ = (Initial Gal X Initial Cone. ) dT - Initial Gal. Desired Cene. V. Mixing 2 Tanks of Different Concentrations. cene. Of Ta.d "A" X Gal. n. "A")+(Cene. Or n. "B" X Gal. n. A. Final Cone. = (Gal. Tk. "A" + Gal. Tk. "B") B. Gal. C g f besired= Gd. Of water te a rste X Desired m Increase PFM Of Cene. S.A. - FPM Final PFM Increue VI. To Predict Or Deter:mine Evap. Botte=s Concentration Gal. Of Peed, Ineresse in Bettes Cene. vap. Concentrate X To Evap. Cone. Of Feed To Evap. Volune \\ '.. VII. Pressure, Te=perature Volu=e, Of A Gas flz- { s P,V P,V .1 c 2 T 1 2 P = Abselute pressure i V = volu=e T = Te=p. #F.ankine ( F + he0) . :.. 7, v. z. REVIEWED BY ~s m d m chi f d-P.? f(eact:r ti:Cr.:ar h $3 + <== Tid.:it::1 5. !;;.t'. r;;3t I \\ l t e y _}}