Text

Forwards Exam Rept 50-369/OL-86-01 for Units 1 & 2 on 860310,summary of Exam Results,Written Exam Questions & Answer Key & NRC Comments on Written Exam.W/O Rept.Table of Exam Results Withheld (Ref 10CFR2.790)
	ML20211B244
Person / Time
Site:	McGuire, Mcguire
Issue date:	05/27/1986
From:	Brownlee V; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Tucker H; DUKE POWER CO.
Shared Package
ML20211B250	List: ML20211B244; ML20211B268;
References
	NUDOCS 8606110547
	Download: ML20211B244 (100)
	v • d • e

{{#Wiki_filter:, Willik) a' I May 27, 1986 Ouke Power Company ATTN: Mr. H. B. Tucker, Vice Presider.t Nuclear Froduction Department 422 South Church Street Charlotte, NC-28242 Gentlemen:

SUBJECT:

MCGUIRE EXAMINATION REPORT 369/0L-86-01 The NRC administered examinations on March 10, 1986, to employees of your company who had applied for licenses to operate the McGuire Nuclear Station. At the j conclusion of the written examination, a copy of the exam was left with your staff; at the conclusion of-the site visit, preliminary findings on the operating examinations were discussed with those members of your staff identified in the Examination Report, Enclosure 1. A table summarizing the examination results for each examined individual is provided as Enclosure 2. Copies of the written examination questions and answer key are included in this report as Enclosure 3. A copy of your staff's comments on the written exam is included as Enclosure 4. In accordance with 10 CFR 2.790(a), a copy of this letter and Enclosures 1, 3 and 4 will be placed in NRC's Public Document Room. is exempt from public disclosure pursuant to 10 CFR 2.790(a) and will not be sent to the Public Docu. Tent Room. Should you have any questions concerning this letter, please contact us. Sincerely, (Original signed by VLBrownlee) Virgil L. Brownlee, Chief Reactor Projects Branch 3 Division of Reactor Projects

Enclosures:

1. Examination Report 50-369/0L-86-01

2. Table of Examination Results (Official Use Only-Privacy ActInformation) 4

3. R0/SR0 Exam Questions and Answer Key 4.

Facility Coments on Written Exam i cc w/encls: (Seepage 2) 8606110547 860527 PDR ADOCK 05000369 [h 1 y 1 1

4 O Duke Power Company 2 May 27, 1986 cc w/encls 1 & 2: T. L. McConnell, Station Manager cc w/encls 1, 2, 3 & 4: S. Frye, Director, Operator Training bec w/encls 1, 2, 3 & 4: Senior Resident Inspector bec w/ encl 1: Project Manager, NRR State of North Carolina bec w/ enc 1 2: J. Lanning, Management Assistant, OLB:DHFT:NRR bcc w/encls 1 & 3, & 4: Operator Licensing Branch, DHFT:NRR Document Control Desk $1 i RII RII RI R.II RII gJ CC ro CAJu ian VP nciera TPeebles 5/N /86 5/4'/86 5/21/85 5yf/86 5/ /86 t.

e bne/osure 3 (loh U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: MCGUIRE 1&2 REACTOR TYPE: PWR-WEC4 DATE ADMINISTERED: 86/03/10 EXAMINER: CASTO,C b _ _ _'_ j _u_'y k_ E _(g */_ _ _ _ _ _ _._ _ APPLICANT: INSTRUCTIONS TO APPLICANT: Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheett. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts. % OF CATEGORY % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY ___ y _"_ ______ 3410~0 _'5.00[____ 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, y..),, HEAT TRANSFER AND FLUID FLOW 2A40 '5.00 ~ ________ 2. PLANT DESIGN INCLUDING SAFETY 'k7 3 3&rtTO ________['S.00 ________ 3. INSTRUMENTS AND CONTROLS

30. 00/d 25.00

________ 4. PROCEDURES - NORMAL, ABNORMAL, et EMERGENCY AND RADIOLOGICAL CONTROL 0 ftH N O V TOTALS FINAL GRADE,________ All work done on this examination i', my own. I have neither given not received aid. ~~~~~~~~~~~~~~ EPPL CEUT 5~55GUATURE I -t

e 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 2 --- isEER557AERICE-sEAi isissEEE Es5 FE5i5 FE5s l QUESTION 1.01 (1.50) For each of the conditions stated below explain the response of a positive displacement pump volumetric flow rate (refer to fi3vre 1.1). O. Doubling the pump speed b. Throttlin3 down on the pump discharge valve

c. Increasing pump internal friction losses QUESTION 1.02 (1.50)

During performance of an emergency boration while at power, how AND why are the following parameters effected? (assume no control rod movement) .a. Subcooline b. OP delta T setpoint c. Control Rod Worth QUESTION 1.03 (1.00) If Bank D control roos where positioned at core midplane and subsequently. driven further into the core, describe the effect on Delta I. QUESTION 1.04 (.75) During a reactor startup in a subcritical condition the first reactivity addition caused the 1/M plot to decrease from 1.0 to 0.625. The second reactivity addition caused the 1/M plot to decrease from 0.625 to 0.33. Which reactivity addition was larger, the first or the second? ~ QUESTION 1.05 (1.00) Explain why subcooling in the Reactor Coolant System Hot Les is neccessary during natural circulation. (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****) l

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 3 --- isEER56isEsiEs-sEsi'iEEssEEE Es5 FEUi5 EE5s QUESTION 1.06 (2.00) Answer the following in regard to the Reactor Vessel Level Instrumentation: a. The measured differential pressure is pressure compensated during both subcooled and saturated conditions. List the specific parameterd used for BOTH of these conditions. Cl.03 b. What is the purpose of the RTDs installed on the impulse lines? CO.53

c. For the Dynamic Head Range a reduction in differential pressure compared to the nominal operating differential pressure is an indication that Reactor Coolant conditions have changed (assuming no NC pump trip), HOW have Reactor Coolant canditions changed?

CO.53 OUESTION 1.07 (1.00) For ECC celculations how is xenon worth equated to ppm equivalent boron worth? How does this relationship affect the determination of adequate shutdown margin? GUESTION 1.08 (1.00) Considerin3 ONLY flux hardening effects,is differential baron worth more or less negative from BOL to EOL? WHY? CUESTION 1.09 (1.00) ~ Explain how decreasing Reactor Coolant system flow (with power held constant) will result in a decreasin3 DNBR. (m**** CATEGORY 01 CONTINUED ON NEXT PAGE ***xx)

1. PRIWCIPLES OF NUCLEAR POWER PLANT OPERATIONr PAGE 4 --- isEEs56isisics-sEAi iEAssFEE As5 FEUi6 FE6s QUESTION 1.10 (1.75) At 30% power a NC pump is inadvertently tripped. Assume control rods in canval, all other systems in automatic and no operator / protective actions occur. Indicate the effects on the following: (increases / decreases /RTS) affected loop i unaffected loop I steam generator level-I steam generator steamin3 rate-I Delta T-I steam pressure at turbine inlet QUESTION 1.11 (1.00) Which of the following statements describes a condition occuring in a fuel assembly containing a control bank rod that has just dropped from a 100% power quilibrium condition?

o. The xenon concentration begins to decrease b.

The samarium concentration begins to decrease c. Beta effective begins to decrease d. The DNBR begins to decrease OUESTION 1.12 (1.00) Which of the following statements describes the relationship beween integral and differential rod worth? a. Integral rod worth (at any location) is the slope of the differential rod worth curve at that position. b. Integral rod worth (at any location) is the total area under the differential rod worth curve from the end of the rod to that location.

c. There is no relationship between intergral and differential rod worth.

d. Inte3ral rod worth (at any location) is the square of the differential rod worth at that location. (xxxxx CATEGORY 01 CONTINUED ON NEXT PAGE xxxxx)

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 5 TEEEU665U555C5I~UE5T TE5UEFER 5U6~FL656 FL6U ~ ~ ~~~~ OUESTION 1.13 (1.00) The fuel maneuvering limits are required following a refueling outage to prevent undue stresses to the: a. fuel of the new fuel assemblies b. cladding of the new fuel assemblies c. fuel of irradiated fuel assemblies d. claddin3 of irradiated fuel assemblies GUESTION 1.14 (1.00) The most serious problem with recching the critical beat flux is caused by a. the poor thermal conductivity of steam b. the blockage of flow through the core when steam bubble formation becomes significant c. the displacement of boron from the core as steam bubble formation becomes significant d. the high pressure surges in the Reactor Coolant System caused by steam bubble formation QUESTION 1.15 (1.00) The reactor is at 80% power with a core delta T of 48 degrees F and.e mass flow rate of 100% when a station blackout occurs. Natural circulation is established and core delta T stablizes at 40 degrees F. If decay heat is approximately 2% of full power, what is the mass flow rate (% of full flow)? a. 1.9% b. 2.1%

c. 3.0%

d. 3.4% (***** CATEGORY 01 CONTINUED ON NEXT PAGE

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i

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 6 --- isEss557sisiEs-REAi iEEssEEE Es5 FE5i5 EE5s QUESTION 1.16 (1.00) Which of the following describes the changes to the steam that occur between the inlet and outlet of a real (not ideal) turbine? a. Enthalpy decreases, entropy decreases, quality decrease. b. Enthalpy decreases, entropy increases, quality decreases.

c. Enthalpy constant, entropy decreases, quality decreases.

d. Enthalpy increases, entropy increases, quality increases. QUESTION 1.17 (1.00) Which of the following would cause an inadvertent dilution accident? a. Overfillin3 a S/G while in hot standby b. A regenerative heat exchanger leak c. Valving in a demineralizer that was not saturated d. A VCT lo-lo level resulting in the FWST being used for charging GUESTION 1.18 (1.50) a. True or False: Ouring cold plant conditions, you would expect the COLD calibrated PZR level instrument to indicate HIGHER than the HOT calibrated level instrument. [0.53 103 which c$uld b. Give two different conditions involving the reference result in a false high level indication on the PZR level instrument. E1.03 (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION. PAGE 7 --- TAEER557sARIEs-sEAi inAssiEE As5 EEUi5 FE60 GUESTION 1.19 (1.50) A reactor is taken critical with ::enon concentration at zero. Power is raised to 50% at 5%/ min. A trip occurs as power reaches 50%. Use the following choices to describe how :<enon concentration will be trending. Increasir. Decreasing Near equilibrium a. one hour after the trip { b. four hours after the trip the reactor has been restarted and power has reached 25%. c. 12 hours after the trip. GUESTION 1.20 (1.00) With the turbine DEH control in ' turbine manual

the operator inadvertently depresses the

'GV' increase and 'GV fast

pushbuttons while at 80% load.

For each of the following state whether the initial effect will be increase / decrease /RTS: a. main steam (sm) system flow b. Tsve c. steam generator level "~ d. feodwater flow GUESTION 1.21 (2.00) The reactor is critical at 10,000 cps when a S/G PORV fails open. (Assuming no rod motion, and no reactor trip): a. Is the final Tave higher or lower than the initial Tave?Why? b. Is the final power level above or below the PGAH?Why? = (***** CATEGORY 01 CONTINUED ON NEXT PAGE

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1. PRINCIPLES OF NUCLEAR POWER FLANT OPERATION, PAGE 8 --- iAERR657sAsiEs-AEsi isissFEE Es5 FEUi5 FE6E GUESTION 1.22 (1.50) a. What is the Subcooling Margin (SCM) of the Reactor Coolant System (NC) if the following conditions exist? Th= 580 deg F Pressurizer pressure = 2185 psi 3 Tc= 520 des F Steam Generator pressure = 850 psis b. Which one of the following would result in the smallest SCH: (briefly explain voor choice, assume identical NC pressures for each case) 1. SCM during a controlled natural circulation conditions immediately followin3 a trip due to loss of flow.

2. SCM from continued operation at 10% power.

3. SCM produced when all NC pumps are operated at normal no-load conditions after e:: tended shutdown. QUESTION 1.23 (1.50) a. What is a delayed neutron? (0.5) b. Why are delayed neutrons important? (0.5) c. What happens (and why) to the percentage of delayed neutrons over core life? (0.5) GUESTION 1.24 (1.50) Define the following terms: a. Axial Flux Difference (0.5) b. Reactivity (0.5) c. Total Power Defect (0.5) (***** END OF CATEGORY 01

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2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 9 QUESTION 2.01 (2.00)

e. The Auxiliary Feedwater System (CA) has discharse check valve temperature sensors installed. Specifically where in the flow path are they installed AND what two hazardous condition s might they detect?

b. List the CA system suction flowpaths in order of preference. QUESTION 2.02 (2.00) For the Residual Heat Removal System (ND) answer the follin3

e. What conditions must be established to allow manual opening of NI-184, 185 (containment sump suction valves).

b. Durins solid plant operations what hazard may result from positionin3 the letdown flow control valve to automatic and starting an ND pump? QUESTION 2.03 (.50) Durin3 P ant operation at power a low pressurizer level signal of "17% is l received, with the aid of figure 45.1 outline the response of the Chemical cnd Volume Control System (NV) to this event. (identify any valves which reposition) GUESTION 2.04 (1.50)

e. For each of the following state whether the Diesel Generator (EGA) will or will not start with its control in automatic!

1. 86N lockout present and 2/3 UV on 4160v bus

2. 86S lockout present and a LOCA

3. Jacket water temperature high and a 2/3 UV on 4160v. bus 4.

Lube oil pressure low (1PSA/1PSB) and a LOCA b. Blackout load sequencing is in progress when the sequencer reset push-button is depressed, how will this affect the blackout loadin3? GUESTION 2.05 (1.00) List four (4) sources of water to the containment sump lower compartment under accident conditions. (***** CATEGORY 02 CONTINUED ON NEXT PAGE

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2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 10 GUESTION 2.06 (.50) Under emergency operat in the Containment Spray system has operated by an Sp signal and has been automatically secured, WHAT signal (s) would automatically restart an NS pump under these conditions? OUESTION 2.07 (1.00) What provisions have been made for the Condenser Circulating Water (RC) system to prevent water hammer in the event all operating RC pumps trip? OUESTION 2.08 1.00) Concerning the Annu.us Ventilation (VE) system: a. True/ False. When operating in the recirculation mode the filter train is bypassed. b. True/ False. While operating in MANUAL the automatic recirculation mode controls (i.e. CPCS) are bypassed. QUESTION 2.09 (2.50) For the Nuclear Service Water (RN) system answer the following:

a. The containment ventilation units receive their cooling water supply from the

'A' train pumps, what plant condition necessitates this arrangement? Explain El.03 b. Refer to figures 53.1 thru 53.4, which figure correctly deplicts the RN system alignment with a unit Ss signal present? CO.53 c. In which position do NC pump motor cooler outlet valves fail AND what action (s) restores them to their normal mode? C1.03 GUESTION 2.10 (.50) During which particular phase of NI system operation is the swing check valve installed in the FWST supply line most likely to close? (***** CATEGORY 02 CONTINUED ON NEXT PAGE

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2, PLANT DESIGN INCLUDING SAFE 1Y AND EMERGENCY SYSTEMS PAGE 11 QUESTION 2.11 (1.50) Three valves are installed in the line between ND Train B and the NI pumps, explain how these valves are arranged in the flowpath AND state the basis for this arrangement. QUESTION 2.12 (.50) An NI system start signal is present, however,only one NI pump has started, how are the NI pumps protected from runout conditions? QUESTION 2.13 (1.00) The makeup water to the Reactor Coolant System provided from the SSF controls is supplied by; a. the NV system positive displacement pump b. the train A NV system centrifugal pump c. a SSF dedicated positive displacement pump d. a SSF dedicated centrifugal charging pump OUESTION 2.14 (1.00) Which of the following conditions will result in a reactor trip? a. Low flow on 2/3 detectors in 1/4 reactor coolant loops when >P7 and <P8.

b. Low flow on 2/3 detectors in 1/4 reactor coolant loops when

>P8.,, c. Low flow on 1/3 detectors in 4/4 reactor coolant loops when >P7 and <P8. d. Low flow on 1/3 detectors in 4/4 reactor coolant loops when >P8. QUESTION 2.15 (2.00) List all protection si nals which will automatically initiate the Safety 3 Injection System. Include logic and setpoints. (***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 12 GUESTION 2.16 (1.00) List four (4) conditions necessary for the Standby Diesel Generator feeder breaker to close automatically. QUESTION 2.17 (2.00)

c. What supplies the backup motive force for the low pressure protection system should the Instrument Air system fail?

CO.53

b. At what temperature is the RCS low temperature interlock satisfied durin3 cooldown?

CO.53

c. What operator action is required during the cooldown to enable the Low Protection System below 300 des F?

E0.53 d. What components are actuated to provide for low pressure protection to to the RCS during MODE 5? E0.53 OUESTICN 2.18 (2.50) a. What TPREE input contacts (signals) must be closed to automatically start the Containment Air Return and Hydrogen Skimmer fans after the 10 rairute time delay? [1.53 b.. State TWO reasons why the operation of these fans are necessary during a LOCA inside containment? [1.03 QUESTION 2.19 (1.00) Which of the following will cause the automatic closure of the UHI discharge isolation valves?

a. There are no automatic closure signals-

b. Luw nitrogen pressure in surge tank

c. Low water level in accumulator d.

Membrane leakage alarm (xxxxx CATEGORY 02 CONTINUED ON NEXT PAGE

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~ n 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 13 QUESTION 2.20 (1.00) Which of the following malfunctions would cause a pressurizer level indication of 0%? a. dp cell diaphragm rupture b. Reference les rupture c. Impulse line rupture

d. Equalizin3 valve leakage 00ESTION 2.21 (1.50)

/ Other than reducing containment pressurer list the THREE functions of the Ice Condenser system that are accomplished by the sodium-tetraborate solution produced by meltdown of the ice. QUESTION 2.22 (2.50) Concerning the Safe Shutdown Facility (SSF):

a. List five rooms which constitute the SSF.

6. What system (s) supply electrical power to both the security system and SSF IRCs? c. State the basis for having a subbank of pressuricer heaters powered from the SSF. l (***** END OF CATEGORY 02 xxxxx)

3. INSTRUMENTS AND CONTROLS PAGE 14 OVESTION 3.01 (2.00) a. An instrument air (VI) leak has occurred upstream of the Auxiliary Building header isolation, what VI system automatic actions will result from continuous air header pressure decrease? [1.03 b. In response to part a. above, the operator dispatches someone to start D/G 1A, would the alignment of this D/G air supply to the VI header be done? (choose one) [1.03 1. Automatically 2. With a manual valve 3. By installing jumpers OUESTION 3.02 (1.00) i The Component Cooling Water Reactor Building Non-Essential Supply Header Isolation Valves (KC-230,KC-220) will automatically shut on; a. a Sp si3nal b. a Ss signal c. a St signal d. a HI-HI flow signal throug'n the applicable valve QUESTION 3.03 (1.00) Which of the following is a correct statement concerning the source range audio count rate circuit? a. If the control room audio count rate is lost due to a detector f a,i l u r e, then the containment audio count rate is lost at the same time, b. If the control room audio count rate is lost due to a detector failure, the audio count rate can be restored by a selector switch behind the audio count rate instrument cabinet back panel. c. If the control room audio count rate is lost due to a detector failure, the audio count rate can be restored by a selector switch on the front of the audio count rate panel but than the containment audio count rate indication will be lost. d. If the control room audio count rate is lost due to an amplifier failure, the control room audio count rate will be lost until the.implifier is repaired. (***** CATEGORY 03 CONTINUED ON NEXT PAGE

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30 ? INSTRUMENTS AND CONTROLS PAGE 15 OVESTION -3.04 (1.00) If_the turbine has just been latched for a plant startup. Placing the OPC Key Switch in the TEST posttion will; a. trip the governor valves only 'b. trip the governor and intercept valves c. trip-the throttle valves only d. trip the throttle and intercept valves QUESTION 3.05 (2.50)

a. Describe 3 ways the 120VAC Vital Instruments can be supplied power from the 600 VAC emergency busses and indicate which is the NORMAL (preferred) supply.

C1.53

b. With the plant operating at 100% power, Vital Instrument Panel EKVA supply feeder. breaker trips open, would you expect the reactor trip breakers to open? Briefly explain. State ANY assumptions.

C1.03 0VCSTION 3.06 (1.00) a. Which section/ component of the Rod Control system enables the control rods to react proportionally to a change in HC temperature? CO.53 b, which section/ component of the Rod Control system balances CO.53 ' Reactor / Turbine pouer in the event of a Turbine runback? 00ESTION 3.07 (2.00) For the following Process Radiation Mointors, state the type of RADIATION detected, type of DCTECTOR. and protective FUNCTION (if any): 1._ EMF 32 steam generator blowdown demin outlet

2. EMF 36 unit vent gas

3. EMF 43 control room vent intake

(***** CATEGORY 03 CONTINUED ON NEXT PAGE

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i l l

K ________________'AND CONTROLS 3. INSTRUMENTS PAGE 16 QUESTION 3.08 (1.")) For the Digital Rod Positan Indication system (DRPI) answer the following

e. Specifically, how is a Data Failure A(orb) on a particular control ad identified?

CO.53 b. How many Central Control Units (CCU) must be operating for full accuracy operation? [0.53

c..How - is a CCU which has been manually or automatically disconnected identified on the control board display panel?

CO.53 QUESTION 3.09 '(1.50) Answer the following regarding the Reactor Protection system TRUE/ FALSE:

a. In order to generate a ' Turbine Trip'-Reactor Trip signal, 2/3 low auto-stop oil pressure and 4/4 throttle valve closure signals are required.

b..A General Warning al a r ra would be received upon 1/2 ' Train in Test' alarms.

c. P-14 (S/C high level) actuates a turbine trip and feedwater isolation only.

OUCSTION 3.10 (1.00) Answer the following with regard to the Reactor Trip Breakers (RTB) and their controls: a. TRUE/ FALSE. Depressin3 and holding both "feedwater isolation reset train 1A' ar.d ... train 1B' pushbuttons while the RTBs are being opened will prevent a feedwater isolation. b. TRUE/ FALSE. The RTB closing springs charge when the breaker is racked to the ' TEST' position and discharges when the breaker is racked to the ' DISC' position. (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

= 3. INSTRUMENTS AND CONTROLS PAGE 17 GUESTION 3.11 (2.00) For the Steam Dump Control system answer the follouing: a. Refer to figure 78.1, what parameter is each of the indicators on the S/G A PORV controller displaying? CO.53 b. The main steam header pressure auto / man control station has AUTO-SET PT-MAN postions provided, specifically what function is/are performed in each of these three postions? CO.753 c. In the Tavs mode a 10% step loss of load signal is present (no reactor trip occurs /C-9 is satisfied), Bank 2 condenser dump valves fail to open Tava-Tref deviation is increasing, which of the following would be the next initial action: CO.753 (1) Bank 3 valves open (2) S/G safeties open (3) S/G PORVs open (4) no other valves would open 00ESTION 3.12 (1.00) Which of the following does the GT delta T protection circuit prevent from exc9eding? a. Power density b.'DNB c. total core power d. redistribution QUESTION 3.13 (1.50)

c. What condition (s) automatically isolate the fire protection system containment isolation valves (1RF821A Unit-1, 1RF823A Unit-2)?

CO.53

b. List four general types of fire protection status alarms.

[1.03 (mmmmm CATEGORY 03 CONTINUED ON NEXT PAGE mammm)

3. INSTRUMENT 3 AND CONTROLS PAGE 18 00ESTION 3.14 (1.50) Refer to figures 82.1, 2* a. What is the purpose of the Rate Mode Selector Switch on the Power Range A drawer? b. What automatic actions (if any) would occur as a result of the loss of detector volt alarm on the Power Range A drawer? c. State the purpose of the gain switch on the Power Range B drawer. QUESTION 3.15 (.75) For the 250v DC Auxiliary Power system distribution center 1DP list the normaltalternate and backup power supply. QUESTION 3.16 (.75) List the 3 process lines which close upon a main steam isolation signal. QUESTION 3.17 (.50) Which 2 Main Feedwater Pump (MFP) trips are provided to protect the MFP from a loss on Net Positive Svetion Head? OUESTION 3.18 (1.00) While operatin3 on the feed regulatory bypass valve controller the power range channel N41 fails low, assuming a zero level error how would t.he bypass valve control respond? (i.e. open, close, remain the same) (***** CATEGORY 03 CONTINUED ON NEXT PAGE

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_ _ _ _ = _ _ _ _ _........ - - 3. INSTRUMENTS AND CONTROLS PAGE 19 QUESTION 3.19 (1.50) a. For each of the following state if the condition WOULD or WOULD NOT result in a turbine runback signal: [1.03 1. 1/4 OP delta T alarm 2. PCB 8 and PCB 11 open 3. 60% impulse pressure and 1A MFP trips 4. stator water pressure 15 psi below normal and >10% impulse pressure for > 45 seconds b. State the difference between an automatic and manual turbine runback signal (i.e. method by which the turbine is runback) CO.53 QUESTION 3.20 (1.00) During normal NCP operation how many of the 5 indicating lights at the local NCP maintoring system are energized? GUESTION 3.21 (1.00) For the Auxiliary Feedwater (CA) system answer the following: a. Which systems / processes automatically isolate on a CA pump auto start signal? b. Once started and with the discharge valves operating at maximum flow how is control of their position regained? c. How is control of the CA pump recire valves regained after an avt6 start? GUESTION 3.22 (1.00) Concering the NCP oil lift pumps (OLP) answer the following: (refer to figure 91.1) a. Specifically what NCP conditions must exist to automatically shutdown the OLP? E0.53 b. TRUE/ FALSE. An NCP-OLP will automatically start when the NCP is <100% speed and the safety breaker is open. [0.53 (***** CATEGORY 03 CONTINUED ON NEXT PAGE

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_I__ _f_ _______________b_ A 20 ~GUESTION 3.23 (.50) What provisions have.been installed to allow for renergiration of the C-heater elements in the event of a loss of 1LXG? (describe special alignments and source of power). QUESTION .3.24 (1.50) List three different conditions that 6.11 automatically close the Main Steam Isolation valves. i (***** END OF' CATEGORY 03 zuumm)

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 21 RdDi5E55i5AE 55sTR5E---------------------~~~ ~~~~ QUESTION 4.01 (1.00) A mainfeed pump turbine trip test should not be performed unless the unit load is less than (select the maximum allowable) a. 10% b. 15% c. 50% d. 65% QUESTION 4.02 (1.00) When draining the cold les accumulators, the water is stored in the a. containment sump b. refuelin3 cavity c. fueling water stora3e tank d. reactor coolant drain tank QUESTION 4.03 (1.00) Which of the following conditions would require all NC pumps to be tripped during a valid safety injection? a. If an ND pump is running and the NC system subcooling is 10 des F b. If an NI pump is running and the NC system subcoolins is 10 de3 F. c. If flow is verified from an CA pump and NC system subcooling is <0 des F d. If flow is verified from an NI pump and NC system subcooling is <0 des F (***** CATEGORY 04 CONTINUED ON NEXT PAGE

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4. PROCEDURES - NORMALr ADNORMAL, EMERGENCY AND PAGE 22 ~ '~~~~~~~~~~~~~~~~~~~~~~~ ~~~~ d6 UL 5EUIL 66UTR L R -QUESTION 4.04 (1.00) If the.following colors appeared on the control room CSF status trec display, which color coded path has the hi hest priority? 3

a. RED b.

ORANGE c. YELLOW d. GREEN QUESTION-4.05 (1.00) If the following CSFs were all displayed orange, which one has priority?

o. Heat Sink b.

Subcriticality c. Integrity d. Inventory OUESTION 4.06 (1.00) If you receive no whole body exposure for the first 7 weeks of a calendar quarter, then you may receive up to ____ during the 8th week without exceeding the-normal whole body administrative exposure limit. c. 100 arem

b. 500 mrem c.

800 mrem d. 1000 mrem (***** CATEGORY 04 CONTINUED ON NEXT PAGE

- - - - )

n 40 PROCEDURES . NORMAL, ABNORMAL, EMERGENCY AND PAGE 23 ~ ~~~~~~~~~~~~~~~~~~~~~~~~ ~~~~ d656L6656dL C6NTR6L R QUESTION 4.07 (1.00) Which of the followin3 statements regarding-access keys to Extra High Radiation Areas is correct? a.' Extra High Radiation Area keys shall be issued to HP personnel only, during non-emergency conditons. b. Extra High Radiation Area keys are issued on a daily bases and are only transferable to your shift relief.

c. The Extra High Radiation Area key locker includes keys for Radio 3raphic Exposure Devices.

d. To be issued an Extra High Radiation Area key, a signed statement for issue approval by an HP supervisor must be documented on your Daily Exposure Time Record. QUESTION 4.08 (1 00) Which of the following conditions would warrant an emergency boration of the Reactor Coolant System? a. 'Lo Insertion Limit' alarm during Mode 1 operations. b. One control rod stuck fully out on a reactor trip.

c. A stuck open pressurizer PORV during Mode 1 operations.

d. Less than 2000 ppm boron in the coolant during Mode 6 operations.

QUESTION 4.09 (2.00) 'HcCuire Limitations and Precautions, OP/0/A/6100/08 states the following: 'All shutdown banks must be at the fully withdrawn position whenever positive reactivity is being inserted by baron or Xenon concentration changes, reactor coolant temperature changes, or motion of control banks." State the 2 exceptions to this precaution. (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

.:._u."= .c' 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 24 ~~~~ 56EUL65 UAL 6UUTRUL'~~~~~~~~~~~~~~~~~~~~~~~ ~ R QUESTION 4.10 (1.00) During a response to NC system leakage within the capacity of both NV pumps AP/1/A/5500/10, there is one manual Safety Injection and one manual Reactor Trip requirement. State under what condition (s) each of these is required. QUESTION 4.11 (1.00) Concerning the Emergency Boration AP/1/A/5500/38 procedure: (fill-in-the-blank)

a. A time delay of up to ____(a range of) minutes can be expected before indication of negative reactivity insertion is obtainable on core instrumentation.

b. TRUE/ FALSE. To equali=e Pressuriner baron concentration the operator places Pressuriner Heater Control Groups in manual AND closes the supply breaker, sprays operate to control pressure. QUESTION 4.12 (1.00) Which of the following is a symptom of a LOSS OF LETDOWN FLOW according to AP/1/A/5500/12, Loss of Letdown, Charging or Seal Injection? a. Letdown heat exchanger outlet high temperature alarm.

b. Letdown heat exchanger outlet high pressure alarm.

c. Regenerative heat exchanger letdown high temperature alarm. d. Increasing VCT level. (***** CATEGORY 04 CONTINUED ON NEXT PAGE xxxxx) l

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 25 ~~~~~~~~ ~~~~~~~~~~~~~~~ ~~~~ d656L655EdL"66UTRUL R QUESTION 4.13 (1.00) While performing steps in EP/1/A/5000/09 Loss of All AC Power, an SI signal cay be present, what ACTION with regard to the SI signal must be taken AND why must this action be taken (once power is restored to 1 ETA or 1ETB)?

a. No action is necessary as the SI signal has no affect.

b. Place SI in TEST to prevent an overpressure transient on the NCS.

c. Reset the SI to permit the D/Gs to energize the buses.

d. Reset the SI to permit manual loading of components onto the buses.

QUESTION 4.14 (1.00) Which of the actions correctly describes the sequence for removing a CF pump from HOLD followins CF isolation on a Rx trip and lo-Tave? a. Reset hold, reset isolation

b. Reset isolation, match %feedwater-% hold si nals, reset hold 3

c. Reset hold, reset isolation, match %feedwater-% hold signals d. Reset isolation, reset hold, match %feedwater-% hold signals QUESTION 4.15 (1.00) Select the malfunction which lists" Place CRD Selector in manual AND control AFD within Tech Spec limits' as an immediate action step, accordins.to AP/1/A/550/14 Rod Contal Malfunctions. a. Failure of a Control Rod Bank to move in Automatic b. Continous Insertion / Withdrawal of a Control Bank

c. Dropped Control Rod

d. Control Rod Misalignment

(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

4. PROCEDURES - NORMAL, ADNORMAL, EMERGENCY AND PAGE 26 ~~~~~~~~~~~~~~~ ~ ~~~~ A5i5t55i5AL 55UTR5L R QUESTION 4.16 (1.00) The Steam Generator tube rupture emergency procedure EP/1/A/5000/04, uses two terms associated wi'th the Steam Generators " Ruptured' and " Faulted *, EXPLAIN the bases of the term " Faulted' and give the parameter (s) used to determine if a Steam Generator is " Faulted *. QUESTION 4.17 (1.00) With a loss of power to 1 ETA NO automatic actions occur on the board, the Diesel Generator is running, WHAT are your immediate actions to restore power and load 1 ETA with the Diesel Generator? DUESTION 4.18 (1.50) Other than the Condenser Vacuum indication, LIST three (3) symptoms of a loss of Condenser Vacuum event per AP/1/A/5500/23. QUESTION 4.19 (1.00) After resetting a CF isolation signal HOW LONG must the operator wait before attempting to open the CF isolation valve? EXPLAIN. QUESTION 4.20 (1.00) Given the following conditions is it allowable to open 1NV-92A (NC pump seal bypass return header isolation)? YES/NO. NCS pressure 400psis No. 1 seal leakoff valve open No. 1 seal leakoff less than 1 spm Seal injection flow to each NC pump > 6 3pm No. 1 seal leakoff temperature 200 deg. F QUESTION 4.21 (1.00) The unit startup procedure cautions the operator not to exceed 1955 psis in NC system prior to Steam Generator pressure of greater than 585 psis. WHAT is the basis for this caution? (*xxxx CATEGORY 04 CONTINUED ON NEXT PAGE *****)

= 4. PROCEDURES - NORMAL, ADNORMAL, EMERGENCY AND PAGE 27 ~~~~E5656L6G565L'6UUTRUL'" ~~~~~~~~~~~~~~~ ~~~~~ QUESTION 4.22 (.50) During a reactor startup the Shutdown Banks are being withdrawn, all banks are out however the operator ascertains that there are NO Rod Position Indicators operable for a control rod, WHAT immediate action (s) should be taken? QUESTION 4.23 (1.00) While operating the CA system with its suction supply from the main condenser hotwell the operator finds the hotwell level is 2' 5' below normal. What ACTION (S) should be taken with regard to the CA system AND why is/are the action (s) necessary?' QUESTION 4.24 (1.00) [ NOTE: The terms ' guideline A,B,C' are used as typical e:<amples of EOPs3 An operator is performing Emer3ency Procedure Guideline A, when symptoms appear requirin3 transition to guideline B. While performing guideline B, the operator finds it necessary to enter guideline C. After completion of the actions in guideline C WHICH procedure would be re-entered? Cassume all guidelines end with transition words ' Return to Guideline and Step in Effect'. QUESTION 4.25 (1.00) While proceeding down the left-hand column of an emergency procedure-the operator moves to the right-hand column for contingency instructions for a particular step. The operator finds the contingency action not successful what COLUMN and STEP should the operator proceed to? (***** CATEGORY 04 CONTINUED ON NEXT PAGE

- - - - )

o 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 28 ~~~~~~~~~~~~~~~~~~~~~~~~ ~~~~RAU UL65 UAL UUUTRUL QUESTION 4.26 (1.00) Select at what point the SI systems should be aligned for cold leg recireviation based upon FWST level *

c. FWST level low alarm b.

It is done automatically c. 50% level d. 3% level GUESTION 4.27 (2.00) LIST the four (4) possible alternate actions that can be taken if during a response to Nuclear Power Generation /ATHS the Turbine had not automatically tripped. QUESTION 4.28 (1.00) If the Subcriticality Critical Safety Function indicates a dashed path, which of the following actions is required? a. Go immediately to the referenced procedure. b. Go to the referenced procedure as time permits. c. Monitor other status trees and if no higher priority condi-tion exists, then So to referenced procedure. d. Monitor other status trees and if no higher priority condi-tion exists, then go to referenced procedure as time permits. (***** END OF CATEGORY 04 x****) (************* END OF EXAMINATION xxxxxxxx*******)

~ ~ m g zr p u s u.x u - - out)/(Energy in) 2 ,o og s o V,t + 1/2 at 2 J g = mc A = A,e ** KE = 1/2 av a = (Vf - 1 )/t A = 14 3 'PE = ogn Vf = V, + at

= a/t 1=

an2/t1/2 = 0.693/t1/2 1/2'N

M /*> M 2

t W = v :P nD A= [(g/2 I*III) 1 S I * '3I '" m = V**Ao -Ex I*I' Q.=ph o Q = aCpat 6 = UA A T I = I e"* c ! = I, 10~^/ M Pwr = W ah f TVL = 1.3/v 10 "#III HVL = -0.693/u 8 p =,:e /T t SUR = 26.06/T SCR = 5/(1 - Edf) CR, = 5/(1 - Egf,) g fj) = CR II ~ " #f2) SUR = 26e/t* + (s - e)T s CR (1 - K j 2 M = 1/(1 - Kgf) = CR /CR, T = (s*/s) + [(s - e)f fe] j T = s/(e - s) M = (1 - Kg f,)/(1 - Kgfj) T = (a - e)/(ie) SDM = ( -Kgf)/Kgf /K t= = 10 seconds e = (Kgf-1)/Kg f = aKgf df I = 0.1 seconds *I gf (1 + IT)] e = ((t*/(T Kgf)] + [s / Ijj=1d2,2 2 d P = (seV)/(3 x 1010) Id gd jj 22 2 I = eN R/hr = (0.5 CE)/d (meters) R/hr = 6 CE/d2 (f,,g) Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lem. 1 curie = 3.7 x 1010dps 1 ga;. = 3.78 liters I kg = 2.21 lba 3 1 ft+ = 7.48 gal. I hp = 2.54 x 10 8tu/nr Density = 62.4 lbg/ft3 1 av = 3.41 x 106 Stu/hr Density = 1 ge/cr lin = 2.54 cm Heat of vaporization = 970 Sto/lom

F = 9/5'C + 32 Heat of fusion = 144 Btu /lbe

'C = 5/9 (*F-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf 1 ft. H O = 0.4335 lbf/in. 2 e = 2.718 \\-. = :- - -. . = =.

i yeeums.gpfm 1athe'py. Ste/ID tit'opy. Dtx/* s F gae.gy,tufth b '- Press. Temp

tege, Eve, 3:eem Cstit Loop Steem Celer toep tesem Caere Steem pose F

9 ele g As A A s, s, aj, og e, i v s s 3.0886 32.018 OA1602 3302A 3302.4 0.00 1975.5 1075.5 0 2.1872 2.88 72 e 1021.3 mass 6 &le 35.023 0.01602 2945.5 2945 5 3 03 1973 3 1976.8 0 0061 2.1705 2.1766 SSB 3022.3 gle e.15 45.453 0.01602 20043 2004 7 13 50 I M 7.9 1081.4 0 0271 2.1140 2.1411 1930 1925.7 e.15 E20 $3.160 0 01603 15M.3 15M 3 21.22 IM35 1984.7 00422 2.0778 2.1160 2122 1028 3 gao Eso 64 484 0 01604 10393 10393 32.54 1057.1 10893 O M41 2 0168 2.0809 32.54 1032 0 e.30 SAO 72.869 0.01606 792.0 792.1 40 92 1052A 1093J 0.0799 1.9762 2.0M2 40.92 1034.7 eat 3.5 79.586 0 01607 641 5 641.5 47.62 1048 6 1096.3 0 0925 1.9446 2.0370 4742 1036.9 El s.4 85.218 0 01609 540.0 640.1 53.25 1045 5 10903 0 1028 1.9186 2.0215 5324 10MJ e.6 .r v'my a 4 00. < s.91610 .466.81.. -4664 4 ; r SLIO.1043 7,11003 ;0.3...,1,996(i 2 A33 o 48.10 4048.3... 43.7 1 GA 94.38 0.01611 411.67 41149 62.39 1040.3 1102.6 0.1117 13775 1.9970 6239 10413 cA ' g.9 98.24 OA1612 368.41 368 43 66.24 1038.1 1104.3 0.1264 14606 1.9870 0624 1042.9 E9 1.0 101.74 0.01414 333.59 333 40 6913 1036.1 1105A 0.13M 13455 1.9781 00J3 1944.1 1A SA IM.07 0.01623 17334 173.76 94.03 1922.1 1816.2 0.1750 1.7450 1.9200 94A3 10512 SA 3.0 141.47 0.01630 110 71 11833 10p.42 1013.2 1122.6 0.2009 1AS$4 1 564 109 41 1056.7 SA 4.0 152.96 0.01636 90 63 90 64 120A2 3006 4 1127J 0.2199 1A428 1A626 120.90 1060.2 4.0 S.0 162 24 0.01641 73.515 73.53 130 20 1000.9 1131.1 0.2349 14094 13443 130.18 1063.1 SA 4A 170 05 0.01645 61.967 61.98 ISS 03 996.2 1134.2 0.2474 1.5820 13294 1MAI 1065.4' SA FA 176 84 0.01649 63 6M 5345 144.83 992.1 1136 9 0.2581 1.5587 1A168 14431 1067.4 7A S.O 182 86 0.01653 47.328 47J5 150.57 988.5 1139.3 0 2676 1.5384 1A060 15034 1089.2 ED 9.0 188.27 0.01654 42.385 42 40 1M.30 985.1 1141.4 0.2760 1.5234 1.7964 15628 1070A 9.L 80 193.21 0.01659 38.404 38 42 161.26 982.1 1143.3 0.2836 1.5043 1.7879 16123 1072 2 39 14.696 212.00 0.01672 N.782 2630 180.17 970.3 1150.5 0.3121 14447 1J568 180.12 1077.6 14.896 15 213 03 0.01673 26.274 26.29 181.21 969.7 1150.9 0.3137 1A415 1.7552 181.16 1877.9 15 30 227.96 0.01683 20.070 20.0h7 196 27 960.1 1156.3 0.3358 IJ962 1.7320 19621 8082A 30 30 250.34 0.01701 13.7266 13 744 218.9 945.2 1164.1 0.3682 1.3313 1A995 2142 1 3 7.9 30 40 267.25 0 01715 10 4794 10.497 236.1 933.6 1169A 0.3921 1.2844 1A765 236 0 1092.1 de 50 281.02 0.01727 8.4967 8.514 250.2, 923.9 1174.1 0.4112 1.2474 J.6686 250.1 1095.3 50 80 292.7) 0A1738 7.l M 2 7.174 M2.2 915.4 1177.6 0.4273 1.2167 1A440 262A 1088.0 90 70 302.93 0.01748 6.1875 6205 272.7 907A 1180 6 0 4411 1.1905 1A316 272.5 1100.2 70 i 80 322.04 0.01757 5 4536 5 471 232.1

900.9 1183.1 0.4534 1.1675 1A208 281.9 1102.1 80 l

90 320.28 0 01766 4A777 4A95 2901 894.6 1185.3 0.4643 1.1470 1All3 290A 1103.7 90 100 327A2 0.01774 4.4133 4.431 298.5 088.6 1187.2 0.4743 1.1384 1A027 298.2 1105.2 See 120 341.27 0.01789 3.7097 3.728 312.6 877A 1190 4 0.4919 1.0960 1.5879 312.2 1107.5 120 240 353 04 001803 3.2010 3 219 325.0 868.0 1193 0 0.5071 1.0681 1.5752 324A 1109.6 140 nec 363 % 0 0;S15 2A155 2A34 336.1 859.0 1195.1 0.5206 1.0435 13641 335A 1111.2 See 380 373 00 0.01827 2.5129 2.531 346.2 850.7 1196.9 0.5328 1A715 1.5543 345A 1112.5 380 300 35140 0 01839 2.2689 2.287 355A S42 2 1198.3 0.5438 1.0016 1.5454 354A 1113.7 30 250 40097 0.01865 1A245 13432 376.1 825.0 1201.1 0.M79 0 9585 1.5264 375 3 1115A 350 Boo 4t? 3b 0 01889 1.5235 3.5427 394 0 808.9 1202.9 0.5882 #1.9223 1.5105 392A 1117.2 300 350 411.73 0.01913 1.3064 1.3255 409.8 7942 12040 0 4055 0 8909 1A968 408A 1818 ! 550 400 444 60 0.0193 1.14162 1.1610 424.2 780 4 1204.6 0.6217 0 8630 1.4847 422J 1112 7 400 1 450 4M 2B 0 0195 1.01224 1.0318 437J M7.5 1204.8 04360 02378 IA738 435J 1118.9 450 500 467 01 0 0198 0 90787 0 9276 449.5 755.1 12047 0.6490 0.8148 1A639 447.7 1118 2 900 950 476 94 00199 0 82183 0 8412 460.9 743.3 1204 3 06611 03936 1A547 458.9 1118 6 560 400 48523 0 0201 014962 0.7698 4713 732.0 1203 7 0.6723 0 7738 1.4461 469A 1116.2 000 703 .503 08 0 0205 0.63505 0 6556 491.6 710.2 1201A 06928 03377 1A304 488.9 1116A 700 833 514 21 0 0209 0.54809 0.M90 509.8 689.6 1199 4 01111 03051 1.4163 5063 1115.2 000 900 531.95 0 0212 0 4796S 05009 526 7 669 7 1196 4 0 7279 0.6753 1A032 5232 1113.0 900 1000 5 **.5B 0.0216 0 42435 0 4460 542.6 f 50 4 !!92.9 0 7434 0.6476 13910 5306 1110.4 1000 1100 555 2d 0.0720 0.37863 0 4006 557.5 631.5 11891 0 7578 0 6216 1.3794 553.1 1107.5 1300 1230 l H7.19 0 0223 0 34013 0.362b 571.9 613 0 1144 8 01714 0.5969 1.3683 566 9 1104.3 1200 1803 u S77 42 0 0227 0 30722 0.3299 585.6 594.6 1880 2 0.7843 0 5733 1.3577 580.1 1100 9 1300 i 1 1400 557 07 0 0731 0.27871 0 3018 598 8 576 5 1175.3 03966 0 5507 ~ 1.3474 b92.9 1037.1 1400 l 3500 596 20 0 0235 025372 0.2772 611 3 5584 1170 1 0 8055 0 5285 1.3373 6052 1093.1 1500 2000 635 80 0 02",7 016706 0.1883 672.1 466.2 1138.3 0 8625 0 4256 1.7581 6624 10G56 2000 l 2500 66d 11 0 0266 01020ft 01307 7313 361.6 1093 3 C 9139 0 3206 1.2345 118.5 1032.9 2500 4 8000 695 33 0 0343 0 050/3 0.0850 301 8 218.4 1070 3 0 9728 0.1891 1.1619 782 5 973.1 3000 32982 70147 0OS0S 0 0 0508 906 0 0 906 0 1.0612 0 1.0612 8753 875.9 3708.2 i TABLE A.3 PROPERTIES OF SATURATED STEAM AND SATURATED I WATER (PRESSURE) A.4

Volume.C/le Eathelpy.Cd/lb tnies,,, gi,ji, r 'y' tener

Eve, sneem toter tver tieem weier t.e, e ee.

'7' y 9 e e N N 4 g n s a2 OASS59 am1602 3305 3305 -0.02 tonA lonA 0.0000 2.1Sn 2.1Sn 32 35 0.09991 eD1602 tus 2948 3.00 10n.S 10763 0.0061 2.u06 2.u67 35 i 40 0.12163 001402 2446 2446 8 03 1071.0 1079.0 0.0162 2.1432 2.1594 40 45 0.14744 001602 2037.7 2037.8 13.04 1064.1 1081.2 0 0262 2.1164 2.1426 45 90 0.17796

A1402 1704.8 1704.8 18.05 1065.3 1083.4 0.0361 2.0901 2.1262 to l

40 0.2561 0A1603 1207A 1207.6 28 06 1059.7 1067.7 0.0%5 2.0391 2A946 60 t l 70 0.3629 OA1605 868.3 368 4 38 05 1054.0 1092.1 0.0745 1.9900 2.0645 70 00 0.5068 Obito? 633.3 633.3 48.04 1048.4 1096 4 0.0932 1.9426 2.0359 30 90 OA981 0.01610 448.1 468.1 88.02 1042.7 1100A 0.1115 1A970 2.0086 to.' 190 0A492 OA1613 350.4 350.4 68 00 1037.1 1105.1 0.1295 1A530 1.9825 100 Sie 3.2750 041617 265.4 265.4 77.98 1031.4 1109.3 0.1472 1A105 1.9577 110 130 SA927 OA1620 203.25 203.26 87.97 1025.5 1113.6 0.1646 1.7693 1.9339 130 130 2.2230 0A1625 157.32 157.33 97.96 1019A 1117A 0.1817 1.7295 1.9112 130 See 24092 041629 122.98 323.00 107.95 1014.0 1122.0 0.1985 1.6910 1A895 340 150 3.718 0.01634 97A5 97.07 117.95 1008.2 1126.1 0.2150 1.6536 1.8606 150 160 4.741 OA1640 77J7 77.29 127.96 1002.2 1130.2 0J313 3.6174 1A487 140 170 5.993 0.01645 62.04 62.06 137.97 996.2 1134.2 02473 1.5822 1A295 170 l 800 7.511 OA1651 50.21 50.22 148.00 990.2 1138.2 0.2631 1.5400 14111 130 190 9.340 0A1657 40.94 40.M 158.04 984.1 1142.1 0J787 1.5148 1.7934 190 300 11.526 OA1644 33.62 3344 168.09 977.9 1146.0 0.2940 1.4824 1.7764 300 310 14.123 0.01671 27A0 27A2 178.15 971.6 1149.7 0.3061 1.4509 1.7600 210 212 I4.696 OA1672 26.78 26.80 100.17 9703 1150.5 0.3121 1A447 1.7568 212 320 17.106 0.01678 23.13 23.15 188.23 965.2 1153.4 0.3241 1A201 1.7442 320 330 20.779 041685 19J64 19.381 19BJ3 958.7 1157.1 0.3308 1.3902 1.7290 230 340 24.968 OA1693 16.304 16.321 o 208.45 952.1 1160.6 0.3533 1.3409 1.7142 340 350 29325 0A1701 13A02 13.819 218.59 945.4 1164A 0J677 1.3323 1.7000 250 f i 360 35.427 0A1709 11.745 11.762 228.76 938.6 1167A 0.3819 1.3043 1.6062 300 370 41.856 0A1718 10.042 10.060 438.95 931.7 1170.6 0A000 1.2760 1.6729 270 300 49.200 OA1726 S.627 S.644 249.17 924.6 1173A OA098 1.2501 1.6599 300 390 57.550 0A1736 7A43 7A60 259.4 917.4 11763 0.4236 1.2238 14473 290 300 67.005 401745 6.448 6.466 269.7 910.0 1179.7 0.4372 1.1979 1.6351 300 310 77.67 OA1755 5.609 5.626 290.0 902.5 1182.5 0.4506 1.1726 1.6232 210 320 09.64 041766 4A96 4.914 290.4 094A 1185.2 E4640 1.1477 14116 320 340 117.99 OA1787 3.770 3.738 311.3 878A 1190.1 0.4902 1A990 1.5892 340 1 360 153.01 OA1811 2.939 2.957 332.3 862.1 1194.4 0.5161 1A517 ' 1.5678 360 300 195.73 0.01836 2.317 2J35 353.6 044.5 1198.0 0.5416 1A057 3.5473 300 400 247.26 0.01864 13444 1A630 375.1 325.9 1201.0 0.5667 0.9607 1.5274 400 420 308.78 0.01894 1.4808 1A997 396.9 306.2 1203.1 0.5915 0.9165 1.5000 420 440 381.54 0.01926 1.1976 1.2369 419.0 785A 1204.4 0.6161 02729 1A890 440 460 466.9 0.0196 0.9746 0.9942 441.5 763.2 1204.8 0.6405 0.8299 1.4704 450 480 566.2 0.0200 0.7972 0A172 464.5 739.6 1204.1 04648 0.7871 1.4516 400 500 480.9 0.0204 0.6545 0.6749 487.9 714.3 1202.2 OA090 0.7443 1.4333 500 520 812.5 0.0209 0.5386 0.5596 512.0 687A 1199.0 0.7133 0.7013 1.4146 820 540 962.8 0.0215 0.4437 0.4651 536.8 667.5 1194.3 0.7378 0.6677 1.3954 540 560 1133.4 0.0221 0.3651 0.3871 562A 625.3 1187.7 0.7625 0.6132 1.3757 560 580 1326.2 0.0228 0.2994 0.3222 589.1 549.9 1179.0 0.7876 0.5673 IJ550 SSO 600 1543.2 0.0236 0.2438 0.2675 617.1 550.6 1167.7 OA134 0.5196 1.3330 830 0 $20 1786.9 0 4247 0.1962 0.2208 646.9 506.3 1153.2 03403 0.4689 1.3092 820 640 2059 9 0A260 0.1543 0.1802 479.1 454.6 1133.7 0.8666 0.4134 1.2821 640 640 2365.7 0.0277 0.1166 0.1443 714.9 392.1 1107.0 0A995 0.3502 1.2498 650 640 2708.6 0.0304 0.0003 0.1112 758.5 310.1 1068.5 0.9365 0.2720 1.2006 Geo l 7C0 3094.3 0.0366 0.0386 0.0752 822.4' 172.7 995.2 0.9901 0.1490 1.1390 700 705.5 3208.2 0.0508 ~ 0 ~ -~ OA908 906.0 0 906.0 1A612 0 1.0612 705 i TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (TEMPERATURE) l A.3

Abeprop. U"8el". I Clee la. (el.tese) 300 300 300 400 600 000 700 000 000 8000 1500 1300 3300 1400 3600 e 00161 0 01M 0 0174 00186 0 7944 0 94 % 19726 11892 1.3000 14093 15160 lA7il 1.72b2 SA284 3.930s age 6 69 58 349 42 270 70 37b 49 121b 9 1790 3 18b18 1405 3 1430 1517.4 1578 9 I U 7.0 let? 6 1796 6 1738,A 0406J0) s 0.1292 02933 04362 0 M57 14590 1.5329 1344 1.63bI I6769 3Jlu 1.7517 1Jeb9 8Alta 1 A4 4 5A792 e 00161 0 0166 0 0174 00186 00704 0 7970 09072 1Al02 1.1078 12023 1 2948 1.30b8 1A757 1 % 47 1ADC 7e0 6 69 84 169 65 270 89 3M 61 487 93 IMIO 1345 6 1403 7 lebt 4 1514 4 IM94 1624.8 1640 7 17372 1794 3 003 CS) s 01291 0.2932 04360 0 %b5 06889 1.5090 IM73 1 6154 14540 16970 1733b I.7679 18035 18318 18617 ' A446 e 0041 00lu 00174 0 0186 0 0704 0 6774 0 7825 0.8759 O M31 10470 1.1289 12093 1.2825 13M9 I ese 6 70 11 169 88 271.07 37573 487A8 1273.1 IH92 1399.1 14b5 A 1511 4 IM69 IU27 3678 9 inb o !?92.9 5182.). 0.1290 0 293C 0 43be OMS 2 0648b 14M9 l.b444 1.5980 1A413 16807 1.71M 1 M22 IJBbl 18164 13464 e 00161 0 01 % 00174 00186 0C234 05869 068b4 07713 0 3504 09262 09998 10720 11430 1.2131 1.2825 l 300 6 70 37 170 10 271.26 3M 34 487A3 1260 6 1332 7 1394 4 1452.2 15Ce 5 1564 4 1620 6 16H.1 17M I U91.6 l 531AS) s 01790 0.2929 04357 0 M49 06881 1A6bt 1.1311 1.5822 1AM3 1 M 62 1.7033 1.7382 31713 1.8028 13329 e OA161 0 0166 0.0174 00186 00204 0 5137 0 6000 0684 0.7603 08295 OA966 0.9622 SM66 1.0901 3.M29 ' asse 6 70 63 170 33 271A4 3M 96 487.79 1249.3 1325.9 1389.6 1448 5 1504.4 I M I.9 1614 4 1675.3 1732.5 37903 ' 0 44.50) s 0.1389 0.2928 0.4355 0.M47 OM76 1A457 1.5149 1.56U IAIN 1.6530 1.6905 1.72 M l.7589 1.7905 3A207 e 00161 0 01M 00174 0.0185 0 0203 0 4531 05440 0618e 06865 0 7505 0 8121 0 8723 0.9313 09894 1.0468 1100 4 70 90 170.% 27143 376 08 487.M 1237.3 1318 8 1384 7 14441 1502 4 1559.4 1616 3 1673.5 1731.0 1789.C SM23) s 0.1269 02927 04353 0.5644 0.6872 1.4259 1.4996 1.M42 14000 1.6410 1.6787 1.7141 IJ475 1J793 1A097 e 00161 0 0166 0 0174 0 0185 0 0203 0 4016 0 4905 OM15 06250 06845 0 7418 C.7974 08519 0.9055 E9584 1300 & 71.16 170.78 27122 37620 48732 1224.2 1311.5 13791 1440 9 1449 4 ISM S 1614.2 16736 1729 4 1787A 0 67.19) s 0.1208 0.2926 0.4351 OM42 04448 1.4061 1A851 1.5415 13883 14298 1.M79 1.7035 8.7371 1.7691 1.7994 : e 0 01(,1 0 0166 00174 0 0185 0 0203 0.3176 0 4059 0 4712 0 5282 0 5809 0.6311 06794 07M2 0.7737 03195 I 34e0 a 71.6s 171.24 272.19 376 44 487.65 1194.1 12961 IN93 1433 2 1493 2 15518 1609.9 1660 0 17M.3 1785.C OS7A7) s 0.1287 02923 0.4348 03636 0 4859 1.3652 1ASM 1.5182 1.5670 1.6096 14484 1A845 1.7185 1.7508 1.7811 i e 0.0161 0.0166 0.0173 0.0185 0.0202 0.0236 0.3415 0 4032 04555 0.5031 0 5482 0 5915 0 8336 0.6748 0.7151 3600 6 72.21 171.69 27237 376 69 487.60 616.77 4279.4 1358 5 1425.2 1486 9 1546 6 4056 1664.3 17232 1782.3 i (GC4 87) s 0 1286 0.2921 0 4344 0 M31 0.68bl 0A129 1.4312 1.4968 1.5478 1.5916 1.6312 1.6678 1.7022 1.7344 1J657 e 0 0160 0.0165 0 0173 0A185 0 0202 0.0235 0J906 0 3500 0.3988 04426 04836 0.5229 RS609 0.5900 0 6743. 1800 a 72.73 IM.15 272.95 376.93 487M 615 58 1261.1 19472 1417.1 1480 6 1541.1 1601.2 16603 1720.1 IN93 521/IP) s 0.1284 02918 0.4341 0 5626 OAS*3 OA109 1A054 1A768 1.5302 1.5753 1.61H IA&28 14876 IJ204 3.7514 e 0 0100 0.0165 0 0173 0.0184 0.0201 0.0233 0.2488 0.3072 0.3534 0.3942 04320 E4880 R5027 0.5365 &5495> 3000 6 7326 172 60 27332 377.19 4A7.53 614 48 1240.9 1353 4 34087 1447.1 1536.2 1596.9 3657.0 1717.0 INF.1 - 53500) s 0 1263 0.2916 0 4337 O M23 0 6834 03091 1.3794 1.4578 1.5138 136C3 1.6014 14391 14743 IJ04 1J385 1 I e 0 0160 0.0165 0.0173 0 0184 0.0200 0.0230 0 1481 0.2293 02712 0.3068 0.3390 0 9692 0.3330 0.4259 OA525 3500 6 74.57 173 74 27427 SUA2 487.50 612.08 1876 1 1303 4 13861 1457.5 1522.9 1505.9 1447A 17002 3770.4 ' 458&11)s 0.1280 0.2910 0.4329 0.5609 0 6415 0.0048 1.3076 1Al29 IA7M 1.5269 1.5703 1A004 1A45dr 14796 3.7118-i e 0 0160 0.0165 0.0172 0 0183 0.0200 0.0228 0 0982 0 1755 0.2161 0.2484 0.2MO 0.3033 0.3282 0J522 0J753 3000 a 75 83 17t. 88 27522 37847 487.52 610.08 1060.5 1 M 7.0 13632 1440.2 1503A 1574A 1635 5 1701.4 17(1J. l 5 95.33) s 0.1277 029c4 0.4320 0.297 06796 0A009 1.1966 1.3692 1.4429 1A9M 1.S434 1M41 1421A I.GL61 1.64B8. e 0.0160 0 0165 0.0172 0.0183 0A199 0.0227 0.0335 0.1588 01987 02301 0.25M 0.2827 43055 0.3291 SJ510 3200 4 76 4 1M.3 2M6 3787 487.5 609 4 8003 1250 9 1353 4 1433.1 35033 1570.3 16343 16983 1761.2 (70$N) s 0 1276 0.2902 0.4317 04592 0 4708 0.7994 0.9708 IJS15 1.4300 1A866 1.5335 1.5749 1 AIM 1A4D 3J006 e 0 0160 0 0164 0.0172 0 0183 0 0199 0.0225 0.0307 0.1364 0 1764 0.2066 0 2326 0.2563 & 2754 0.2995 0319e 3500 a 77.2 176 0 276.2 3791 487.6 608 4 779 4 1224 6 13342 1422.2 1495 5 1 M 3.3 1429 2 1693 6 IM7.2 s 0.127s 02899 0 4312 0 5585 0 67U 0.7973 0.9508 1.3242 IA112 1.4709 1.5194 1.M18 1A002 14358 1.4691 e 0 0lH 0.0164 0.0172 0.0182 0.0198 0 0223 0.0287 0 1052 0.1463 0.1752 01994 0.2210 02411 0.2001 02783 4000 & 78.5 3U.2 377.1 379.8 487.7 406 5 763.0 1174.3 13114 3403C 1481.3 1M2.2 1619A 1685.7 17506 s 3 1271 0.2893 0.4304 0.5573 0 6760 0 7940 0.9343 12 44 1.3007 3.4461 1A976 1.5417 1.5812 14177 1A514 e 0 0159 0.0164 0 0171 0 0181 0.0196 0 0219 0.0M8 0.0591 0.1038 0.1312 0 1529 01718 eleno 0 2060 0.2203 S000 4 81 1 179 5 279 1 381.2 488.1 804 6 746 0 1042 9 1252.9 13(4 6 1452.1 M29.1 16039 1670.0 1737.4 l e 0.1265 02M1 0 4287 0.5550 0 6726 03880 0 9153 1.1593 1.3207 IA001 1A582 1.5061 laest 1.5863 34216 i 00159 0.0163 0 0170 C 0lbu 0 0195 0 0216 0.0256 ~ 0.0397 0.0757 0.1020 0.1221 0.1391 0.1544 0.!684 0.1817 l 6000 & 83 7 181.7 281.0 342 7 478 6 602 9 736 1 9451 1188 8 1323 6 1422.3 1505 9 1542 0 1654.2 17241 i e 0 1258 0.2670 0.4271 O M28 O M93 0 7826,0 9026 1A176 1.2615 IJ574 1.4229 1.4745 1.5194 13593 1596.2 e 0 0158 0.0163 0 0170 0 0100 0 0193 0 0713 0 0248 0.0334 0 0573 0 0SI A 0 1004 0.1160 0.1298 0 1424 0.1542 l M00 & 862 184 4 283 0 3s42 449 3 601 3 N93 901.8 1124.9 1281 7 1352 2 1482 6 15631 16386 1711 1 s n 1252 02059 04256 0 5607 0 M63 0 7/U 08926 10350 12055 1.3 D I l.3904 1.44v6 3.4938 1.53'5 15735$ TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE) (CONTINUED) A.6

Tempeestwo, F AbeIprose. l teattemp) 100 300 300 400 000 000 700 000 900 1000 1100 gtgo gygg g,go 3,go Clan la. e 00161 392 5 452.3 Sil A 571.5 631.1 000 7 3 6 88 00 1150 7 119b 7 1241 A latS 6 IBM I 1384 5 (101.74) o 0.1295 2.0t09 3.1152 2.1722 2.2237 32705 IJt44 e 0.0161 78 14 90 24 102.24 114 21 IM ll 198 08 150 01 261 M 173 86 185 78 897.70 300 62 321.53 333 45 6 4 GS 01 1148 6 1144 8 1241.3 1788 2 I H 5.9 13N 3 len 6 1443 7 ISM 7 1586 7 1639 6 1993 3 1744.0 1803 5 (162.24) s 01795 14716 3.9M9 1.9943 2.0MO 2 0932 2 136') 217M 2 2159 22521 3.24M tJlM 23503 2.3811 2A101 e 00161 SB 84 44 93 61 03 57.04 63 03 69 00 74 98 80 M 86 91 92 87 98 84 les to 110 76 116 72 10 4 68 07 1146 6 11937 1240 6 1287A 1335 5 1984 0 1433 4 1483 5 ISM 6 1586 6 1639 5 1893.3 1747.9 130 (192.21) s 01295 1.7928 13593 1.9173 1.9692 2 01M 2 0603 2.1011 21394 2 1757 2.2101 1.2430 22744 2.30M 2.3 e 00161 00lu 2989') 33 M3 37.985 41.986 45 978 49M4 $3 M6 $7.9M 61905 45 882 49A58 73 433 77307 26 4 68 04 168 09 11925 1239 9 12s7.3 3335 2 1M38 1433 2 14834 ISM S 15465 1639 4 1933.2 17473 1303 4 (213.08) s 01295 0.2940 1A134 1A720 1.9242 1A717 BA155 2.0M3 2ADM I1309 2.1653 2.1982 22297 22599 3.2890 e 00161 00lM 223M 25 426 36457 31.4M 34 465 37.458 40 447 43 435 44 420 49 405 52 JOB S$370 88.35

l 30 6

68 05 168 11 1191.4 1239.2 1286 9 1334.9 1383 5 1432 9 1483 2 1534.3 1546.3 1639.3 IM3.1 17473 1303 4 (227.96) s 01295 0.2940 1.7005 1A397 1A921 1A397 3.9836 2.0244 2.0628 2A991 2.1336 8.1665 3.1979 3.2282 2.25 e 0.0161 0 OlH I1.035 12 624 14.145 15 685 17.195 18699 to 199 Il 697 F3 IM 24 GB9 36.183 27A76 39.16 i l 40 6 68 10 16815 1186 6 1236 4 1205 0 1333 6 1382.5 1432.1 1482.5 1533.7 15858 1638 8 1992 7 1747.5 18 (267.25) e 0.1295 0 2940 14992 1.7408 14143 1A624 1.9065 1.M76 1.9860 2.0224 2.0569 3.0899 2.1224 2.1516 2. e 0.0161 0.OlM 7J57 8 354 9 400 10425 11.438 12 446 13A50 14 452 15.452 16A50 17A48 18.4 to 6 48 15 168 20 1881 6 1233.5 1283.2 1332.3 1381.5 1431.3 14813 1533.2 1585.3 16384 80 i (292.71) s 0.1296 0.2939 1A492 1.7134 1.7681 1A168 13612 1.9024 1.M10 1.9774 2A120 3.0450 2AMS 2.1058 2.13I i e 0.0l61 001H 0.0175 6.218 7Als 7.794 S.M0 9.319 10.075 10 829 11 581 12331 13ASI 13A29 14377 1 30 6 GS 21 les 24 269 74 1230.5 1291 3 1330.9 1300.5 1430.5 1481.1 1532 6 1564 9 1638 0 1882.0 1746A 1802.5 (312.04) s 0.1295 0.2939 0.4371 14790 1.7349 1.7842 1A289 1 8702 1.9089 1A454 1.9000 2A131 2A446 2.0750 3.1041 e 00161 0 0166 0 0175 4.935 S.588 4.216 6A33 7A43 0050 8 655 9258 9440 10A60 11A00 11 A59 100 6 6826 168 29 M977 1227.4 1279.3 1329 6 41379 5 1429.7 1480 4 1532.0 1584.4 1637.6 1991.6 1746.5 190 (327A2) s 0.1295 0.2939 0 4371 14516 1.7088 1.75M 1A036 13451 13839 1.9205 1A552 1.9003 2A199 2.0002 2A7M i e 0 0161 0 01 % 0 0175 4 0786 4.6341 S.1437 S ES31 6.1971 6 7006 7J060 7.7006 S.2119 8.7130 9J134 9.713 $20 A GS.31 168.33 M9 81 1224.1 1277.4 1328.1 1378 4 1428.8 14793 1531.4 1543.9 1637.1 ISS1J 17442 1802 (34127) o 0.1295 0.29N 04371 14206 1A472 1.7376 1.7529 1A246 1A635 1.9001 1A349 1A000 1A996 2.0300 2.000 e OC161 0 01H 00175 3 4661 3 95M 44119 44585 SJ995 S.7364 6.1709 6.6036 7A349 7AES2 7A946 S.323 140 6 68 37 148 38 M985 1220 8 1275.3 1326 8 1377.4 1428 0 1479.1 15308 1583 4 1636.7 1850 9 17453 180 (353 04) s 0 1295 0 2939 0 4370 1.6085 1.6686 1.71M 1.7;52 13071 13461 13828 1.9176 13508 1.9025 2Al29 2.0421 e 0.0161 0 0166 0 0175 30060 3 4413 3 0480 4.2420 4 6295 SA132 S.3945 S.7741 6.1522 6.5293 '6.9055 l 100 4 68 42 16442 26939 1217.4 1273.3 1825.4 1876 4 1427.2 1478 4 1530.3 1582.9 1636.3 1880.5 1745.6 1 l l (M3 55) s 0.1294 0 2934 0.4370 1.5906 14522 1.7039 1.7499 1.7919 1A310 13678 1.9027 1.9359 I AS76 1.9900 2 e 0 0161 0 0lM 00174 26474 30433 3.4093 3.7621 4.1084 4.4505 4.7907 S.1209 54657 5A014 6 1363 6 i 580 4 64 47 164 47 269 91 12138 1271.2 1324.0 1375.3 1426 3 1477.7 1529 7 1582.4 1635.9 18e02 17453 (173.041 s C l294 0.2ip38 0 4370 1 5743 1 6376 34900 1 7362 1.7784 1Al?6 1.Bi45 1A894 1A227 13545 1.9849 2A e 0 0161 0 0166 0 0174 23598 2.7247 3.0583 3.3783 S MIS 4.0008 4.3077 44128 4A165 53191 S.S200 200 a 68 52 164 51 M9 % 12101 1269.0 13226 1374.3 1425.5 1477.0 15291 1581.9 1635.4 1489 8 1745A (35140) s 0 1294 0 2935 0 4359 1.5593 14242 14776 1.7239 1.M63 13057 13426 1AFM 1.9109 1A427 3.9732 2 e 0 0161 0 0166 0 0174 0 0184 2.1504 24662 2 6872 2 9410 3 1909 3.4382 36837 3 9278 4.1709 4 4131 4.65 250 6 68 66 164 03 270 05 315.10 IM35 1319 0 1371.6 1423 4 1475 3 15274 1580 6 1634 4 1888 9 17442 1800 (430 97) s 0 1294 0 2937 04364 03H7 1.5951 1.6502 1.6976 1.7405 1.7801 1.8173 1A524 IA458 1 3177 1.9442 1.97 i e 0 0161 0 0165 0 3174 0 0186 1.7665 2.0044 2.2263 2A407 2 6509 2 8585 30643 3.2648 3 4721 367M 337 I 300 4 64 79 IM 74 27u14 375.15 1257.7 ISIS 2 1368 9 1421.3 1473 E 1526.2 1579 4 1633 3 lese 0 1743 4 17 l (417.35) s 0.1294 02937 0 4337 CSMS 1.5703 14274 14758 1.7192 1.7591 3.7964 13317 1A652 14972 3.9278 1 e 0 0161 00lM 00174 0 0186 1.4913 1.7028 1A970 2 0332 2 M52 2 4445 24219 2.79PA 23730 3.1471 3 350 & 08 92 1085 270 24 375 21 1251 5 III1.4 1366 2 14192 1471 8 1524 7 1578.2 1632.3 3687.1 17426 17 I (431.73) = 0 1293 0 2935 043G7 0 56M 1.5483 14077 8.6571 1.7009 1.7411 1.7787 1A141 13477 13795 1.9605 e 0 0161 0 0106 0 0174 0 0162 1 2841 1.4763 1.6490 1A151 1 9759 21339 2 2901 2.4450 2.9987 2.7515 2.9037, 400 a 69 05 16897 270 33 37527 12451 1337.4 1363 4 14170 1470 I 1523 3 15M.9 1631.2 1686 2 17 (444 60) 51293 02935 0 4365 0 56G3 1.5782 1.5901, 1.6406 1.6850 1 7255 1.7632 1.7988 1A325 13647 1.8955 1.925C e 0 0161 0 0106 0 0174 0 0186 0 9919 1.1584 13037 1.4397 15708 16992 1A256 1.9507 2.0746 2 1977 2.3 SCO h 09 32 1 % 19 270 51 375 38 12312 12991 13573 1417 7 14M 6 1520 3 1574 4 16291 lead 4 1740 3 1796 (457.Oll o 0 1292 0 2934 04354 05L60 14971 1 5595 1 6'23 165/8 1 6090 1 7371 1.7730 1.0069 14393 1.8702 lA9W i l TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE) A.5 l

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,,canr-n.,--,,,,,-

!n e d O! Y j I i s i l E E -a a li +: ! ' i I n i i I v l + h:1 a I s a D g= g + i Nd' :M

m. m 'ill f! lli

! c-I!!!i i ll ~ i i_, i s - l g'ii j ll l i l l= 1" l ) 5 .glg .l e, .g alsIm I s u b-a a 2 3 9@. -j s l i-a i! i a i I 09 . Ditz =

n [0 \\

1-
09 0-i

'09 l -[Hp = l 8 W l arvtston 2

l i d 4 i ll s : l! i t ' I ! I l l l 8 l 4 a! n i a CH :I = j -o+ I' M$!! l W l!!!al'I l!' l'ls! i j'j c.. i g

ll

n. l l

I lg g l i 1" = = t 8 8 si l aluI l I b 4;'! I e n 55 i gs

l

~ i n' I-a l 4 CH E CH> j . [His. C H F' 0 - + 1 CHla

0-LE

-[Hta CHP i l 8 W l l I

o i i i i j g i ll a i 4 I I I a qI i i I a 0-01 m: = ,i l "il i

g:

~ y-jii l ,) I!' i-ll ~ i rl i!!!i i 11_4 = .s l l .ll l. I i !ie 1 li l" 2. s I li n I i I alvula I a u a 85 I

j U

@E I. i g" E.:s a p I+. 0-50-':8 [H> 04x i g-g= g p~. I! Dy l 8 W REVISION 2

e l e I" g g g i il e L i l i li i li i n u I E I u + ,I 0Ni a a l; g* l 4- -oti = s .m 3 u ii -e ei 4i i .w l u s e to II. I. i I ii i I-,! 2 ..ii ls 11; < i ,l lli i i l: li l i i p4 I' I II aim in I s u , 355 -dg T T : ll M ~ -s p I I L Ei ? ?? i 8-a i! I 4 CH E -[H > . CH F' 0-I 0{x + + i -OR8 04: 048 0-s ) I W X \\ REVISION 2 i

-.~a -s - - - - - - - + - - - a .a 4 --w--- -aaa--.r-1a-m n.,n-----. I .s ( t E A l i t sl l I g s I d a, e l a.I ! i u i a $ I i l l l i.' t f. s m l! h 5 i 3 ~. 3 o Die \\ Y 4 e __._n..y -w -,_e-

_a e. 2, 1 ll lI

8 i i

i i l i eli ll 1 = y 0 $ I l n u 1 I i lE s s s' ll is S .c - ':~' l 5 f M I .g = g, 3-G i e g g b ~ = 2 g 2 -T i i is!I 9 = (O ) __.,,_.._,,_-_.,,,,,__,_._,,,,.,.,.-,-_,._.-,,_f,,__,,,,_.,w-, _w.,-,,

I O (- c ) g g s i E E y lg, j 8 5 a t i gg ll 1 i I 9 ! a s v.- I OO v = i lE 1 I g-i E ga a$a "4 : i. 3 w l ejul l! 8 ', [ h 1 l'l,0 i i .I I E qs s. / 8 O-l-<!! (3 = 1

a. s.. a.- v -M 1 ,1 n h e I.. I ag i 3 iI lg I ap e g l E !I if I .! I i 1 l4 isi li Elle 4 t i : , i si p i a a = 2 4 i II I u g i Il II e i S l I B E l i [g i 's 3 i = 2 RI t .5 .g l I. I! ~ 3 l h a_ l I m i I is 4 _ L_ q! .A x ib V I E l = 1 I 6 i

4. vu 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 29 --- isEER667sAsiEs-sEAi iEAssFEE Es6 FEUi6 FE6s ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 1.01 (1.50) (0.50 ea.) a. Flow rate doubles b. Flow rate remains constant i 77 t h e t er._ h g [ $ if /

c.~7b-b e.-- -E ta the 1me+ et REFERENCC M,cGuire op-ga-sps-thf-ff pg 32 K/A Component Pumps-PD (2.3/2.3)

-ANSWER 1.02 (1.50) es. increases due to decreasing Tave g g,f, y g n 0. ince==e 1 2v. cu aecreasing Tave c. decreases due to decreasin3 Tave and increasing boron concentration (.4 directioni.1 reason) REFERENCE McGuire op-me-cth-cP P3 66 (aab) op-me-rt-rco pg 41 K/A 000-024-EH1.01/1.02 (3.4/3.8;3.6/3.9) ANSWER 1 03 (1.00) Delta I becomes more positive due to the reduction of neutron flux relative to the top of the core. REFERENCE McGuire op-sc-eth-cp-pg36 K/A-001-000-K5.06 (3.3/4.0) 001-000-K5.10 (3.9/4.1) e

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 30 ~~- isEEs567sisics-REAi isissFEE As5 FEUi6 FE6s ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C t ANSWER 1.04 (.75) The first reactivity addition was larger than the second.CO.753 REFERENCE McGuire op-me-sps-rt-se pg 21 K/A 015-000-K5.05 (4.1/4.4). ANSWER 1.05 (1.00) There must be a complete flow path for circulation, a loss of subcooling could result in steam blockage in the RCS thereby causing an incomplete flow path from the heat source to the heat sink.[1.03. REFERENCE McGuire op ga-sps-thf-ht pg 27,28 K/A 002-000-5.15 (4.2/4.6) ANSWER 1.06 (2.00) a. subcooled-hot les temperature CO.53 saturated-wide range pressure CO.53 b. To correct the differential pressure measurement during elevated containment temperature conditions. [0.53

c. Voids have increased, level has decreased CO.53 REFERENCE McGuire op-mc-sps-ic-rvi pg 7,8,17 K/A 002-000-K6.03 (3.1/3.6)

ANSWER 1.07 (1.00) ppm equivalant boron worth is the ratio of Xenon concentration worth to overa3e differential boron worth.CO.53. If this boron equivalent plus present boron exceeds the pra determined for shutdown boron concentration, odequate SUM exist.[0 53. REFERENCE McGuire op-ac-sps-rt-rb pg 17 K/A 004-000-K5.19 (3.5/3.9)

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 31 --- isEss557sAsics-sisi isissFEE As5 FE5i5 FE5s ANSWERS -- MCGUIRE 182 -86/03/10-CASTO,C ANGWER 1.08 (1.00) Since baron is a 1/V absorber this shift in the neutron spectrum toward cPithermal neutron range results in the diff. boron worth becoming less negative C.53 - PU239 builds in faster early in core life so flux hardening occurs faster at BOL.C.53 REFERENCE McGuire op-me-rt-rco pg 34 K/A 004-000-K5.06 (3.0/3.6) ANSWER 1.09 (1.00) Lower flow at the same power level results in a larger diff. temperature through the channel. Tin decreases Tout' increases CHF decreases toward the top of the core CO.53 lower coolant velocities result in less stripping action which removes nucleate bubbles, a steam film can form at lower heat flux. CO.53 REFERENCE McGuire op-me-cth-cp pg 83 (5.4.d) K/a RCPS-000-5.01 (3.3)

hS w,' 7 h S'fbt. C o% $

^"U" a gsf g Y decreases. increases decreaseslincreases decreaseslincreases decreases (0.25 ea.) REFERENCE CCAF] K/A 000-015-EK 1.04 (2.9/3.1) ANSWER 1. (1.00) (/' I/// h 3.><

o -1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 32 --- isEEs559RAsiEs-sEAi isissFER As5 EEUi5 EE5E ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C REFERENCE McGuire Core performance ps 13 K/A 000-003-EK1.03 (3.5/3.8) ANSWER 1.12 (1.00) b. REFERENCE McGuire op-me-sps-rt-rco ps 37 K/A 001-000-K5.02 (2.9/3.4) ANSWER 1.13 (1.00) d. REFERENCE McGuire data book Sta. Dir. 3.1.2.6 sec. 1.3 K/A 001-sws-7 (3.6/4.1) ANSWER 1.14 (1.00) a. REFERENCE McGuire Core Per. pg 10 K/A 002-020-K5.03 (3.2/3.6) ANSWER 1.15 (1.00) c. REFERENCE MNS thermo sec 8 K/A 002-020-A4.02 (4.3/4.5) b.I i

l 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 33 ~~~~ UER5U6E 5k5E5,~U5IY~TRdA5F5R ds6~FLUf6~FL U ~ T ANSWERS -- MCGUIRE 182 -86/03/10-CASTO,C ANSWER 1.16 '1.00) b. REFERENCE McGuire op-ss-ht-2 pg 12 K/A 002-000-A4.02 (4.3/4.5) ANSWER 1.17 (1.00) c. REFERENCE McGuire core per. book K/A 004-000-A2.06 (4.2/4.3) ANSWER 1 18 (1.50) a. false CO.5]

b. Reference les drainin3 CO.5]

Elevated reference lea temperature CO.53 REFERENCE / t' 4 !! /* 'l {kwe[ NcGuire op-me ps-ipe K/A 010-000-K6.06 (2.3/2.4) ANSWER 1.19 (1.50)

c. increasin3 b.

decreasing

c. decreasing CO.5 ea.]

REFERENCE McGuire op-me-rt-rp P3 19,20 K/A 001-000-K5.41 (2.4/2 8) / 1

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 34 --- isEss557sAsiCi-REAi isAssFEE As5 FEUi5 FE5s ANSWERS -- MCGUIRE 1&2 -86/03/10-CAST 0rC ANSWER 1.20 (1.00) c. increase b. decrease c. increase d. increase REFERENCE McGuire sin malf 137 K/A 045-050-A2.10 (2.7/2.9) ANSWER 1.21 (2.00) final Tave is less than initial Tave CO.50] due to MTC adding reactivity 4 during cooldownCO.53 final power above POAH CO.50] positive reactivity places reactor on a SUR which results in heat additionCO.57. REFERENCE Westinshouse Rx physics sec. 1-5 DPC fundementals of Rx Eng. McGuire op-me-rt-rco ps2 obj. 2&3 K/A 039-000-K5.08 (3.6/3.6) ANSWER 1.22 (1.50)

c. Tsat 9 2200 psia = 649.5F SCM= 649.5-580= 69.5F C O.' 5 ]

b. 1 CO.001 Core delta T during natural circulation cooldown will approach full load delta T. That is greater than the two other cases. C0.53 i e

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 35 --- isEER557sisiCs-sEAi iEsssFEE As5 FEUi5 FE6s ANSWERS -- MCGUIRE 1&2 -86/03/10-CAST 0rt ANSWER 1.23 (1.50) a. A neutron born at some time (>1E-14 seconds) after fission (0.25 pts.) from the decay of fission fragments (0.25 pts.) (0.5) b. They allow control of the reactor (0.25 pts.) by increasing the average neutron lifetime (0.25 pts.) (0.5) c. Decreases (0.25 pts.) due to buildup of Plutonium (0.25 pts.) (0.5) REFERENCE Westinghouse Nuclear Training Operationse pp. I-3.4 & I-3.10 - 12 001/000-K5.47 (2.9/3.4) ANSWER 1.24 (1.50) a. Difference in normalized flux signals between the top and bottom halves of the core. (0 5) b. Fractional change in neutron population per Seneration OR fractional deviation from criticality. (0.5) c. The reactivity associated with soins from HZP to HFP. (0.5) REFERENCE VCS. TS, p. 1-1 and Westinghouse Nuclear Training Operations, pp. I-3.2 and I-5.26 001/000-K5.53 (2.8/3.4) ~ -K5.54 (2.8/3.1) -K5.49 (3.4/3.7) )

e t 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 36 ANSWERS -- MCCUIRE 142 -86/03/10-CASTO,C ANSWER 2,01 (2.00)

c. Located upsteam of the check valve CO.53 - suction overpressurization

- pump stegn binding E.25 ea.] ~7 b %/She4< (c y e /'t f. b. UST,CA cond. storage tk,Hotwellet4SW C.15 ea. 11stinsi.10 es. proper order] i REFERENCE cp-me-sps-sy-ca K/A 061-000-K1 01 (4.1/4.2) 061-000-K4.01 (3.9/4.2) 061-000-K1.05 (2.6/2.8) ANSWER 2.02 (2.00)

c. NS-1,18 closed and on of the followinst C.5 es. correct path 3 i

1. S' latched contacts closed 2. S' latched bypass pushbutton depressed

3. ND-4,19 closed

c. s/, 74, sa i a. ca

b. Can cause the NC system pressure to rhrr,:;- by 1^^r**

su auch me 8'*" in a water solid condition. E0.53 REFERENCE op-me-sps-sy-nd pg 8/10 K/A 005-000-K4.07 (3.2/3.7) 005-000-A2.02 (3.5/3.7) ANSWER 2.03 (.50) NV 1/NV 2 close and orifice isolation valves (457,458,and 459)close [.25 ea] REFERENCE McGuire op-me-sps-sy-nv pg 14 K/A 004-000-A3.2 (3.6/3.6) 004-010-A2.08 (3.5/3.7) i 9

o o 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 37 ANSWERS -- MCGUIRE 182 -86/03/10-CASTO,C ANSWER 2.04 (1.50) 0 1. will not [0.25 ea.] 2. will 3. will 4. will b. Prevent any other load groups from being applied CO.53 REFERENCE McGuire op-me-sps-el-eq a/b K/A 064-000-K4.02 (3.9/4.2) K4.10 (3.5/4.0) ANSWER 2.05 (1.00) FWST NCS breakuy(c/4/aN4 q, /'g & SIS - Ice melt g g REFERENCE n4g/&i McGuire op-me-sps-sy-ms pg 7 K/A025-000-K1.03 (3.2/3.0) ANSWER 2.06 (.50) CPCS >=.25 psis REFERENCE McGuire op-me-sps-sy-ns pg 9 K/A 026-000-A3.01 (4.3/4.5) ANSHER 2.07 (1.00) Vacuum breakers are installed and automatically open if all RC pumps trip REFERENCE McGuire op-ac-sps-sy-rc pg 16 K/A 075-000-A3.01 (2.1/2.1)

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 38 ANSWERS -- MCGUIRE 182 -86/03/10-CASTO,C ANSWER 2.08 (1.00)

e. False b.

True REFERENCE McGuire op-me-ent-ve pg 12 me-sys-ve-1 K/A 029-000-K1.05 (2.9/3.1) ANSWER 2.09

P' ( 2. 3 G r--(2. 3 )

c. Blackout CO.53-higher NPSH from LLI C0.25]

RV pumps have no power [0.253

b. 53.3 CO.53 L.t e s e-CC Y'/

1* c. ' W posI-fion' Ecaf3 E

3 rreretcr icuecs E0.53 REFERENCE HCGuire op-me-sps-sy-rn K/A 076-000-K4.06 (2.8/3.2)

K1.19 (3.6/3.7) K6.03 (1.9/2.0) ANSWER 2.10 (.50) i Recirculation phase REFERENCE McGuire op-me-sys-sp-nI pg 7 K/A 006-000-K6.06 (2.3/2.7) I ANSWER 2.11 (1.50) l Two in parallel [0.25] and one in series CO.253 l insures flowpathCO.253 and isolationEO.253 capabilities for failure of l oither A or 8 trainCO.53 REFERENCE j McGuire op-me-sys-sp-ni P3 7 l K/A 006-000-K4.18 (3.3/3.8) [ K6.06 (2.3/2.7) l I l i l l

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS 9 AGE 39 ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 2.12 (.50) Manually adjusted throttle valves installed in the discharge line limit flow thru one pump to < runout conditions. REFERENCE McGuire op-me-sys-sp-ni pg 8 K/A 006-050-K4.02 (4.1/4.3) ANSWER 2.13 -(1.00) c. REFERENCE MNS OP-MC-SYS-Sp-NI K/A 000-068-EK3.10 (3.9/4.2) ANSWER 2.14 (1.00) b. REFERENCE MNS OP-MC-SPS-SY-NC pg 29 K/A 012-000-K4.02 (3.9/4.3) ANSWER' 2.15 (2.00) 0 0 222 ea. 1. Hi containment pressure, 2/3, 1.0 psis (+-0.1) 2. Low pressuri=er pressure, 2/4, 1845 psis (+- 10.0 psis) 3. Low steamline pressure, 2/3 on 1/4 lines, 585 psis (+-5.0 psis) REFERENCE MNS OP-MC-SYS-SP-NI pg 15 K/A 006-000-K4.05-(4.3/4.4) l t

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 40 ANSWERS -- MCGUIRE 182 -86/03/1'0-CASTO,C ANSWER 2.16 (1.00) 0 0.25 ea. 1. 2/3 UV on 4160v E-bus

2. Load shed actuated 3.

DG > 95% speed

4. 06D reset REFERENCE HNS SDG LP p 4 K/A 064-000-K6.06 (2.2/2.5)

ANSWER 2.17 (2.00)

a. Nitrosen from the cold les accumulators

[0.53

b. 320 des F CO.53

c. Operator selection j. ys E0.53

d. Normal PZR PORV's 4/0 32 1

[0.53 REFERENCE HNS SD NC-1223.03 p 11 K/A-010-000-K4.03 (3.8/4.1) ANSWER 2.18 (2.50) Y '/ ' 0 a. 1. Sp signal L /4/M/O [

2. >0.25 psis from CPCS 3

Ee missive from 5e3vencer74d*/ CO.5 ea.] l b. 1. To ensure rapid return of upper containment air to the lower contain-ment. r I 2. To assure adequate mixing of containment atmosphere to pevent excessive H2 buildup. [0.5 ea.] REFERENCE MNS PSM VOL 1 MC-SYS-VX pp 1,2a K/A 103-000-K1.08 (3.6/3.8) l i

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 41 ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 2.19 (1.00) c. REFERENCE Tech Specs K/A 006-000-K4.09 (3.8/4.1) ANSWER 2.20 (1.00) c. REFERENCE MNS MC-IC-ILE-5 Component pressure transmitters (2.4/2.5) ANSWER 2.21 (1.50) 1. Retain Iodine

2. Absorbs neutrons 3.

Serves as cooling medium REFERENCE MNS OP-MC-SPS-SY-NY pp 2,7 K/A 025-000-PWGt35 (3.4/3.6) s ANSWER 2.22 ?"42.5^)(l.il 9,/' O pf

s. 0/ N m; Electrical room; battery roomienNtrul resiii;shn rd equip==nt, room

[0.25 ea.]

b. 208/120 v ac Eskss3;250/125v dc [1DC3 [0.5 ea.3 c.

[ Heaters may be necessary 10 hrs following event to] insure steam bubble stays in pressurizer and not in reactor vessel [0.253 due to excessive cooldown [0.253 REFERINCE McGuire op-me-cp-ad K/A 000-068-EM 2.01 (3.9/4.0) EK 3.09 (3.9/4.4) EA 1.10 (3.7/3.9)

3. INSTRUMENTS AND CONTROLS PAGE 42 ANSWERS - MCGUIRE 1&2 -86/03/10-CAST 0rC 4 ANSWER 3.01 (2.00) a. CBase and standby 1 load] p jjg go c 1VS-1 opens at 80 psis CO.5] "Te /77 7,p.sM h, standby 2 starts and loads CO.5] Sad -f4/r

U b.

3 E1.0] Cl Y, f, yL REFERENCE-McGuire AP/1?A/5500/22 K/A 070-000-K4.02 (3.2/3.5) ANSWER 3.02 (1.00) a. REFERENCE MNS OP_MC_SPS_SY_KC p. 11 K/A~008-000-K1.02'(3.3/3.4) f ANSWER 3.03 (1.00) a. i REFERENCE MNS PSM MC-FC-ENI-4 K/A 015-020-A3.01 (2.6/2.7) ANSWER 3.04 (1.00) b.. l ~ REFERENCE MNS PSM MC-IC-DEH 'K/A 045-000-K4.13 (2.6/2.8) p 1 i l l i L i (- E

e 3. INSTRUMENTS AND; CONTROLS PAGE 43' ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 3.05 (2.50)

c. Any three required

[1.53 1. Battery charger to inverters to bus. PREFERRED SUPPLY rc y N

2. Rattar-y-tc inver t r tu m s. Ys 71e M S & A t /d /ucy.e 3.

600VAC to standby battery charger-to inverters to bus. 4. ower to 600 N r.;ei i.e W h eb to M7 C3.4 es. with 0.3 for proper PREFERRED supply] b. No 00.43 Only one channel of 8/S will trip EO.63. E1.03 REFERENCE MNS PSM Vol 2 MC-SYS-EPG MC-SYS-EPL-1 K/A 062-000-K4.09 (2.4/2.9) ANSWER 3.06 (1.00)

a. Pulser CO.53 b.

Power Mismatch circuit E0.53 REFERENCE MNS OP-MC-SPS-IC-IRE K/A 001-000-K4.03 (3.5/3.8) ANSWER 3.07 (2.00) 1..camma, scintillation,close s/s blowdown Heat exchs. inlet and demin outlet

2. beta, scintillation and GM, close WG 160 3.

beta, scintillation, close air intake E.2ea], 0.2 ea.3, E.2 ea] radiation,

detector, action REFERENCE MNS MC-IC-RM-2 K/A 073-000-K1.01 (3.6/3.9)

K4.01 (4.0/4.3) K6.01 (2.2/2.4) t i

r-9 s 3. INSTRUMENTS AND CONTROLS PAGE 44 ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 3.08 (1.50)

a. The seneral warning LED for the rod with data in error will be flashing EO.53 b.

1 E0.53 c. CCU failure light will illuminate for the particular unit E0.53 REFERENCE 1 HNS OP-MC-SPS-IC-EDA ps 6 K/a 014-000-A1.02 (3.2/3.6) ANSWER 3.09 (1.50) i

s. false EO.53 b.. false EO.53 c.

false CO.53 REFERENCE .MNS OP-MC-SPS-IC-IPE K/A 012-000-K4.06 (3.2/3.5) ANSWER 3.10 (1.00)

a. true EO.53 b.

false E0.53 REFERENCE MNS OP/1/A/6150/08 enclosure 4.4 pg 2 MNS OP/1/A/6150/08 enclosure. 4.6 PS 2,4 K/A 001-000-K6.03 (3.7/4.2) a 9 9 e e e E

i 3. INSTRUMENTS AND CON.TROLS PAGE 45 ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 3.11 (2.00) (4 pt A E0.253

c. rish side-*+==

lina

==e-"-- left ide - manual loader output CO.25] b. Auto - steam pressure is controlled to maintain setpoint Set'Pt - chanses output to maintain set pt in auto Man - output controlled manually CO.25ea.] c.(M) (0.75) REFERENCE MNS OP-SPS-IC-IDE K/A 041-020-K6.03 (2.7/2 9) A4/03 (2.4/2.5) 035-010-A4.01 (3.7/3.6) ANSWER 3.12 (1.00) b. REFERENCE MNS OP-MC-CTH-CP K/A 012-000-K5.01 (3.3/3.8) [U.9) 0,3 . ANSWER 3.13 -{1.5?) , j]V a. St signal # :: LOOA E0.53 Ib

b. 1..deluse ve pressure 2.

sprinkle alarm check valves 3. manual is lation valves 4. fire dohrs open E0.25 ea.] REFERENCE MNS MCSD 0133-03 ps 2 K/A 086-000-A1.05 (2.9/3.1) A4.02 (3.5/3.5) l l l l i

~ 3. INSTRUMENTS AND CONTROLS PAGE 46 ANSWERS -- MCGUIRE 1&2 -86/03/10-CAST 0rC-ANSWER 3.14 (1.50) a. resets the lock-in feature of the +/- rate trip bistables E0.53 b. none [0.53 c.. Adjust sain of summing level amplifier to calibrate the power ranse channel to the power output determined by the secondary calorimetric. [0.53 REFERENCE MNS MC-IC-ENB-16 K/A 015-000-K6.03 (2.6/2.9) A2.01 (3.5/3.9) A4.02 (3.9/3.9) ANSWER 3.15 (.75) normal - charger 1DP alternate - char 3er 1DS backup - battery 1DP E0.25 ea.] I REFERENCE MNS OP-MC-SPS-ELE ps 7 K/A 063-000-K4.02 (2.9/3.2) -ANSWER 3.16 (.75) MSIVs, 'iSIV bypasses, main steam line PORVs E0.25 ea.] REFERE6CE MNS OP-MC-SPS-SY-SM K/A 039-000-K4.05 (3.7/3.7) ANSWER 3.17 (.50) all 3 condensate booster pumps tripped MFP suction pressure low E0.25 ea.] REFERENCE MNS OP-MC-SPS-SYCM .K/A 059-000-K4.16 (3.1/3.2) l ~

3. INSTRUMENTS AND CONTROLS PAGE 47 ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 3.18 (1.00) remains the same REFERENCE MNS MC-IC-IFE-1 K/A 035-010-A3.01 (4.0/3.9) ANSWER 3.19 ( T HiW H @ I a. 1. would not

2. would not 3.

would I hp, h [/, h$7 f, v, /. V 6 [0.25 es.3 4. would not b. auto - runback ad 0 OM man - runback - ernor valves e 200%/ min CO.53 REFERENCE MNS MC-IC-DEH-13 K/A 045-000-K4.12 (3.3/3.6) ANSWER 3.20 M re07 (c. rvhtageggunderfrequency} 3 - { cont 1 powerr und 4' Y il REFERENC n HNS OP-NC-SPS-CH-NCP .K/A 003-000-A4.06 (2.9/2.9) ANSWER 3.21 (1.00)

a. S/G blowdown S/G sample CA recirc valves CO.2 ea.]

b. depress reset pushbuttons I & II c.

depress reset pushbuttons I & II REFERENCE MNS OP-MC-SPS-Sy-CA K/A 061-000-K4.03 (3.1/3.4)

-3. INSTRUMENTS AND CONTROLS PAGE 48 ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 3.22 (1.00)

s. '100% pump speed or safety breaker open E0.25 ea.]

b. false CO.5] REFERENCE MNS MC-CMP-NCP-12 K/A 003-000-K4.03 (2.9/3.4) ANSWER 3.23 [FM .5^1 0 kirk-keyfknterlockt al ernate s urcegreaker from 1LXF REFERENCE MNS MC-IC-ILE-4 K/A PZR PCS K2.01 (3.0/3.4) ANSWER 3.24 (1.50) HI '!I Containment pressure. Low steamline pressure >P-11. Hihg rate of pressure decrease <P-11. REFERENCE MNS OP-M C-SPS-SY-SM K/A 039-000-K4.05 (3.7/3.7) ( I

4i PROCEDURES - NORMAL, ABNORMALr EMERGENCY AND PAGE 49 R 65dE6d5EEE~U6NTR6['~~~~~~~~~~~~~~~~~~~~~~~ ~~~~ ANSWERS -- MCGUIRE 182 -86/03/10-CASTO,C ANSWER 4.01 (1.00) c. REFERENCE MNS-OP /1/ A/6100/01 pp. 1-2 K/A 059-SWG-7 (3.0/3.4) ANSWER 4.02 (1.00) c. REFERENCE MNS OP/1/A/6200/09 enc 4.4 ps 1 K/A 006-000-K4.16 (2.6/3.0) ANSWER 4.03 (1.00) d. REFERENCE MNS EP/2/A/5000/01, foldout page K/A 003-000-A2.02 (3.7/3.9) ANSWER 4.04 (1.00) c. REFERENCE ) MNS EP/2/A/5000/10 p. 2 l K/A PWG 22 (4.3/4.3) ' ANSWER 4.05 (1.00) b. REFERENCE i MNS EP/2/A/5000/10 p.2 i K/A PNG-22 (4.3/4.3) l i l I

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 50 RA5i5L55i5AL 55sTR5L ~~~~ . ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 4.06 (1.00) c. REFERENCE MNS HP MANUAL P.2.1.-3 K/A PWG 15 (3.4/3.9) ANSWER 4.07 -(1.00) a. REFERENCE MNS HP MANUAL 2.5.5 KA/ PWG 15 (3.4/3.9) ANSWER 4.08 (1.00) d. REFERENCE MNS AP/1/A/5500/31, p.2. K/A 004-010-A2.07 (3.8/3.9) ANSWER 4.09 (2.00) 1. Reactor coolant temperature and boron concentration are being maihtained at the hot shutdown, xenon free condition. 2. The reactor coolant has been barated to the cold shutdown concentration and the plant is being cooled down. [1.0 ea.] REFERENCE MNS OP/0/A/6100/08, p. 28 K/A 004-010-A2.02 (3 8/3.9)

a ~ 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 51 ~~~~ 565UEUU56dE~d6UTRUE~~~~~~~~~~~~~~~~~~~~~~~~ R ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 4.10 (1.00) Pressuri=er level below 5% - SI Pressuri=er pressure approaching 1945 psis - reactor trip REFERENCE MNS AP/1/A/5500/10 p. 8 K/A 013-000-A4.03 (4.5/4.7) ANSWER 4.11 (1.00) a.3-5 Eminutes] E0.53 b. TRUE [0.53 REFERENCE MNS AP/1/A/5500/38 p. 4 K/A 000-024-EA2.06 (3.6/3.7) 000-024-EK3.02 (4.2/4.4) ANSWER 4.12 (1.00) 6. REFERENCE MNS AP/1/A/5500/12 p. 2 K/A 004-000-A2.07 (3.4/3.7) ANSWER 4.13 (1.00) d. REFERENCE MNS OP/1/A/6150/02A p. 3 K/A 003-000-A4.07 (2.6/2.6)

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 52

~~~~~~~~~~~"---

R 6 6L65 EdL E5NTR5L ~~~~ ANSWERS -- MCGUIRE 182 -86/03/10-CASTO,C ANSWER 4.14 (1.00) b. REFERENCE MNS OP/1/A/6250/01 p. 1 K/A 059-000-A4.11 (3.1/3.3) ANSWER 4.15 (1.00) d. REFERENCE MNS AP/1A/5500/14 K/A 000-005-SWG-11 (4.4/4.3) ANSWER 4.16 (1.00) Indicates a failure in the secondary pressure boundary,00.53 S/G steam pressure decreasina in a-crreontr ol-led manner-or-S/G. Japr esswi ed -EO. 25 ea. 3 ce y /*V' ~ REFERENCE Westinshouse Users Guide 6689B;1 p. 7 K/A 000-038-EA2.02 (4.5/4.8) ANSWER 4.17 (1.00) Open any pump breakers closed in on bus Turn on D/G cynchroscope Manually close IETA Emergency Breaker Load bus per enclosure (sequence) REFERENCE MNS AP/1/A/5500-07 p. 2 K/A 000-056-SWG-11 (4.5/4.6)

a,, 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 53 ~~~~ 5655LUU5UAU~EUUTRUL ~~~~~~~~~~~~~~~~~~~~~~~~ R ANSWERS -- MCGUIRE 182 -86/03/10-CASTO,C ANSWER 4.18 (1.50) ' Low Vacuum pre-trip alarm Main senerator load decreasing Loss of condensate flow Exhaust hood high temperature alar gf./'g,g Loss of RC pumps / flow g.c C0.5 ea./33 hh A f SA6 REFERENCE MNS AP/1/A/5500/23 K/A 000-051-SWG-10 (3.6/3.9) ANSWER 4.19 (1.00) 3 minutes CO.53 to allow the hydraulic /nitrosen emergency blow cccumulator to recharge E0.53 REFERENCE MNS OP/1/A/6250/01 p. 2 K/A 059-000-A4.11 (3.1/3.3) ANSWER 4.20 (1.00) Yes REFERENCE l MNS OP/1/A/6150/02A p. 3 K/A 003-000-A4.07 (2.6/2.6) l ANSWER 4.21 (1.00) This will cause a safety injection REFERENCE HNS OP/1/A/6100/01 p. 12 l K/A 010-000-SWG-7 (3.4/3.9) l l l l i l __,m.

o.? 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 54 ' ~~~~ A5i5E55 CAE 55UTR5E------------~~~--------- R ANSWER 3 -- MCGUIRE 182 -86/03/10-CASTO,C ANSWER 4.22. (.50) Open the Reactor Trip Breakers REFERENCE MNS OP/1/A/6100/01 p. 13 K/A 014-000-SWG-11 (3.9/4.2) ANSWER 4.23 (1.00) Break vacuum E0.253 limit system flow Eto 1400 spm3 E0.253 to provide minimum NPSH E0.5] REFERENCE MNS OP/1/A/6250/02 HK/A 061-000-SWG-7 (3.6/4.1) ANSWER 4.24 (1.00) .B' REFERENCE Westinghouse ERG suideline manual K/A PNG 22 (4.3/4.3) ANSWER 4.25 (1.00) Next step /substep left-hand column REFERENCE Westinshouse ERG manual K/A PWG-22 (4.3/4.3) ANSWER 4.26 (1.00) a.

o.. 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 55 ~~~~ 56 UL66565L 66NTR6L~~~~~~~~~~~~~~~~~~~~~~~~ R ANSWERS -- MCGUIRE 182 -86/03/10-CASTO,C REFERENCE HNS EP/1/A/5000/12.1 p. 2 K/A 000-074-EK3.11 (4.0/4.4) ANSWER 4.27 (2.00) Stop both DEH pumps Place turbine in manual and close GVs fast Locally trip turbine 6' Y ' / k' d CloseallS/Gstefa i lation valves M / }v/h % REFERENCE MNS EP/1/A/50 0/11.1 p. 2 K/A 000-029-EA1.13 (4.1/3.9) ANSWER 4.28 (1.00) c REFERENCE VCS, E0P-12.0, p. 4 Westinshouse ERG manual K/A PWG-22 (4.3/4.3) I k l I l I

r .e L AC.losu<c 3 (2ofh) U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: MCGUIRE 1&2 REACTOR TYPE: PWR-WEC4 DATE ADMINISTERED: 86/03/10 EXAMINER: CASTO,C _ 2 _4_5__k _(p_' ________ APPLICANT: INSTRUCTIONS TO APPLICANT: 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 passins grade requires at least 70% in each catesary and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts. % OF . CATEGORY % OF APPLICANT'S CATEGORY VALUE T SCORE VALUE CATEGORY _,p,,7_,_,,igTAL ________ 5. THEORY OF NUCLEAR POWER PLANT 44,00 I.00 5 OFERATION, FLUCDS, AND THERMODYNAMICS g.1, 46 19 te _397U0 ________ 6. PLANT SYSTEMS DESIGN, CONTROL, 25.00 AND INSTRUMENTATION _'S 00 ________ 7. PROCEDURES - NORMAL, ABNORMAL, 30.00 I____ EMERGENCY AND RADIOLOGICAL CONTROL 30.00 25.00 ________ 8. ADMINISTRATIVE PROCEDURES, _7'____ se CONDITIONS, AND LIMITATIONS l'F b 3,v l 140700 100.00 TOTALS FINAL GRADE 'All work done on this examination is my own. I have neither j sivon nor received aid. ~ ~~~~~~~~~~~~~~ EPPL5C5UT 5~5I5U5TURE t l l l l

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 2 QUESTION 5.01 (1.50) Durins performance of an emergency boration while at power, how AND why are the following parameters effected? (assume no control rod movement)

n. Subcoolins

b. OP delta T setpoint c.

Control Rod Worth QUESTION 5.02 (.75) During a reactor startup in a subcritical condition the first reactivity addition caused the 1/M plot to decrease from 1.0 to 0.625. The second reactivity. addition caused the 1/M plot to decrease from 0.625 to 0.33. Which reactivity addition was larger, the first or the second? QUESTION 5.03 (2.00) Answer the followins in regard to the Reactor Vessel Level Instrumentation: a. The measured differential pressure is pressure compensated during both subcooled and saturated conditions. List the specific parametensi used for GOTH of these' conditions. [1.03

b. What is the purpose of the RTDs installed on the impulse lines?

[0.53 c. For the Dynamic Head Range a reduction in differential pressure compared to the nominal operatins differential pressure is an indication that, Reactor Coolant conditions have changed (assumins no NC pump trip), HOW have Reactor Coolant conditions chan3ed? CO.53 QUESTION 5.04 (1.00) For ECC calculations how is xenon worth equated to ppm equivalent boron worth? How does this relationship affect the determination of adequate shutdown margin? (***** CATEGORY 05 CONTINUED ON NEXT PAGE

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5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 3 QUESTION 5.05 (1.75) At 30% power a NC pump is inadvertently tripped. Assume control rods in canual, all other systems in automatic and no operator / protective actions occur. Indicate the effects on the following: (increases / decreases /RTS) affected loop i unaffected loop I steam generator level-I steam generator steaming rate-l Delta T-I steam pressure at turbine inlet GUESTION 5.06 (1.00) The fuel maneuvering limits are required following a refueling outage to prevent undue stresses to thet a. fuel of the new fuel assemblies

b. claddin3 of the new fuel assemblies c.

fuel of irradiated fuel assemblies d. cladding of irradiated fuel assemblies GUESTION 5.07 (1.00) The reactor is at 80% power with a core delta T of 48 degrees F and a mass flow rate of 100% when a station blackout occurs. Natural cireviation is established and core delta T stablizes at 40 degrees F. If decay heat is approximately 2% of full power, what is the mass flow rate (% of full flow)? a. 1.9% b. 2.1% c. 3.0% d. 3.4% (***** CATEGORY 05 CONT 1NUED ON NEXT PAGE

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n,

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 4 QUESTION 5.08 (1.00) Which of the following would cause an inadvertent dilution accident?

a. Overfillin3 a S/G while in hot standby b.

A regenerative heat exchanser leak c. Valving in a demineralizer that was not saturated d. A VCT lo-lo level resulting in the FWST being used for chargins GUESTION 5.09 (1.50) a. True or False Durins cold plant conditions, you would expect the COLD calibrated PZR level instrument to indicate HIGHER than the HOT calibrated level instrument. [0.53 b. Give two different conditions involving the reference les which could result-in a false high level indication on the PZR level instrument. E1.03 GUESTION 5.10 (1.50) ,o reactor is taken critual Aith xenon concentration at zero. Power is ir aised to 50% at 5%/ min. A trip occurs as power reaches 50%. Use the f3110 wing choices to describd-how xenon concentration will be trending. Increasing Decreasing Near equilibrium a. one hour after the trip b. four hours after the trip the reactor has been restarted and power has reached 25%. c. 12 hours after the trip. l (***x* CATEGORY 05 CONTINUED ON NEXT PAGE

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[ l I L

5. . THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 5 ~~~U5RA557NA555-~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ T QUESTION 5.11-(1.50) -Define the following terms! a. A::tal Flux Dif ference (0.5) b. Reactivity-(0.5) c. Total Power Defect (0 5) QUESTION 5.12 (1.00) Explain why subcooling in.the Reactor Coolant System Hot Les is neccessary -during natural cirevlation. QUESTION 5.13 (2.00) Given-the following, calculate the required boron change to increase ' reactor power from 75% to 100% while maintaining constant rod position. Moderator-Temperature Coefficient -15 pcm/ degree Doppler-only Power Coefficient -12 pcm/% power Void Reactivity chan3e -25 pcm Xenon change -50 pcm Boron Coefficient - 9 pcm/ ppm QUESTION-5'.14 (1.00) Which of the following will cause the Fuel Temperature Coefficient (pcm -per-degree) to become less negative? a. Fuel temperature increase. b. Baron concentration decrease. i l c. Control rod insertion (at constant power). d. Core age increase. e (***** CATEGORY 05 CONTINUED ON NEXT PAGE unema) I s i i I e +,. --3 r-r- m--,.w.--,m-.- ,--._.r...w- ---.,..w, ,-v,.. .,., -. -. ~, - _,. - -.,,. - - -,..,

,--,e

I= 5.. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 6 [00ESTION 5.15 (1.00) Which of the following does NOT provide assurance that the heat flux hot channel limits are maintained? a. Axial power distribution is maintained within limits. b. Control rod banks are sequenced with proper overlap. c. Control rod insertion limits are maintained. d. The HTC is within its analyzed temperature range. QUESTION 5.16 (1.00) Which of the followins statements concerning delayed neutrons is correct? a. The magnitude of the EFFECTIVE delayed neutron fraction is greater at EOL than at BOL. b. When calculating reactor period (SUR), the delayed neutron term may be considered to be insignificant if the reactivity added is less than the EFFECTIVE delayed neutron fraction. c. The delayed neutron fraction is the ratio of the number of delayed neutrons produced to the total number of neutrons produced. d. The presence of delayed neutrons cause the average neutron generation time to decrease. (*xxxx CATEGORY 05 CONTINUED ON NEXT PAGE

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e 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 7 QUESTION 5.17 (2.00) Durin3 a reactor startup the intermediate ranse instruments were indicating 2E-11 amps when the source ranse instruments were indicating 5E+3 cps,

c. What should the intermediate range indication be when the source ranse indicates SE+4 cps:

[1.03 1. 7E-11 amps 2. 2E-10 amps 3. 1E-10 amps 4. SE-10 amps b. If the intermediate ranse was indication 7E-10 amps when the source ranse was indicating SE+3 cps (as described above)' [1.03 1. the intermediate ranSe is Probably over compensated 2. the intermediate range is probably under compensated 3. the source range has reached its maximum count rate capibility QUESTION 5.18 (1.00) For the modes of heat transfer deplicted in figure 37 list the specific mode represented in order as shown. NOTE: modes may not be in proper heat transfer order of occurance. QUESTION 5.19 (3.00)

a. Refer to fisure 38 ' step positive reactivity addition', what is causing the change in slope between region I and region II?

[1.03 b. At what position on the graph does the SUR equation become invalid?[1.03 c. A graph of a ' step negative reactivity addition rate' would be limited in region III to a fixed slope, exactly what would cause this rate limitation? [1.03 (***** CATEGORY 05 CONTINUED ON NEXT PAGE

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5. THEORY OF NUCLEAR POWER PLANT OPERATIONr FLUIDSr AND PAGE 8 GUESTION 5.20 (1.50) For the following, state whether the tensile stresses are maximum on the OUTER or INNER wall of the reactor pressure vessel. a. Pressure Stress (0.5)' b. Heatup Stress (due to delta T only) (0.5) c. Cooldown Stress (due to delta T only) (0.5) QUESTION 5.21 (1.00) Explain why the equilibrium (at power) value of samarium reactivity is independent of power level. QUESTION 5.22 (1.00) Which of the following equations used to perform a PWR heat balance calculation is correct? a.- Grx = M(s) Ch(s) - h(fw)3 + M(bd) Ch(bd) - h(fw)] + Grcp b. Grx = M(s) [ hts) - h(fw)] + M(bd) [h(bd) - h(fw)] - Grcp c. Orx = M(s) Ch(s) - h(fw)] - M(bd) Ch(bd) - h(fw)3 - Grcp d. Grx = M(s) [h(s) - h(fw)] - M(bd) [h(bd) - h(fw)3 + Grcp NOTE: Notation Key G = Power fw = Feedwater M = Mass Flow Rate rx = Reactor s = Steam bd = Blowdown h = Specific Enthalpy (***** END OF CATEGORY 05 xxxxx)

6.. ' PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 9 QUESTION 6.01 (2.00)

c. The Auxiliary Feedwater System (CA) has discharge check valve temperature sensors installed. Specifically where in the flow path are they installed AND what two hazardous condition s might they detect?

b. List the CA system suction flowpaths in order of preference. QUESTION 6.02 (2.50) Concernin3 the Safe Shutdown Facility (SSF): a. List the five (5) rooms which consitute the SSF. b. What system (s) supply electrical power to both the security system and SSF IRCs? c. State the basis for having a subbank of. pressurizer heaters powered from the SSF. QUESTION 6.03 (1.50) a. For each of the.following state whether the Diesel Generator (EGA) will or will not start with its control in automatic 1. 06N lockout present and 2/3 UV on 4160v bus 2. 86S lockout present and a LOCA 3. Jacket water temperature high and a 2/3 UV on 4160v bus 4. Lube oil pressure low (lPSA/1PSB) and a LOCA b. Blackout load sequencing is in pro 3ress when the sequencer reset push-button is depressed, how will this affect the blackout loading? (***** CATEGORY 06 CONTINUED ON NEXT PAGE

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i e

.6'. PLANT SYSTEMS DESIGNr CONT 80L, AND INSTRUMENTATION PAGE 10 QUESTION 6.04 (2.50) For the Nuclear Service Water (RN) system answer the following: a. The containment ventilation units receive their cooling water supply from the 'A' train pumps, what plant condition necessitates this arrangement? E:: plain El.03 b. Refer to figures 53.1 thru 53.4r which figure correctly deplicts the RN system alignment with a unit Ss signal present? E0.53 c..In which position do NC pump motor cooler outlet valves fail AND what l' action (s) restores them to their normal mode? [1.03 QUESTION 6.05 (1.00) The makeup water to the Reactor Coolant' System provided from the SSF controls is supplied by; a. the NV system positive displacement pump b. the train A NV system centrifugal pump c.na SSF dedicated positive displacement pump ~ 1 d. a SSF dedicated centrifu3a1 charging pump QUESTION 6.06 (1.00) The Component Coolin3 Water Reactor Building Non-Essential Supply Header Isolation Valves (KC-230rKC-228) will automatically shutHont a. a Sp signal

b..a Ss signal c.

a St signal d. a HI-HI flow signal through the applicable valve 1 (***** CATEGORY 06 CONTINUED ON NEXT PAGE xxxxx)

,s p

e / 6. PLANT SYSTEM 3 DESIGir CONTROL, AND INSTRUhENTATION PAGE 11 + QUESTION 6.07 (1.00$ Which of the f6110 wins conditions will result in a reactor trip?

c. Low flow on.2/3 detec' tors in 1/4 reactor coolant loops when >P7 and (PG.

b. Low flow on 2/3 de'toctors in 1/4 reactor coolant loops when >P8.

~

c. Low flow on 1/3 detectors in 4/4 reactor coolant loops when >P7 and <P8.

d. Low flow on 1/3, detectors in 4/4 reactor coolant loups when >P8.

QUESTION-6.00 (2.50) Describe'3 ways'the 120VAC Vital Instruments san be supplied power a. from the 600 VAC emersency busses and indicate which is the NORMAL (preferred) supply. E1.53 b. With the plant operatins at.-100%.powerr Vital Instrument Panel EKVA supply feeder breater t r i p s,, o p e n, would you expect the reactor trip breakers to oren? Briefly explain.' State ANY. assumptions. E1.03 QUESTION 6.0? (2.00) WhaU supplies the backup motive force for the low pressure protection a. sysf.em should the Instrument Air system fail? E0 53

b. Ats'what temperature is the NCS low temperature interlock satisfied during cooldown?

E0.53 Wh[t operator action is required'during the cooldown to enable the c. Low Protection System below 300 des F? CO.53

d. WhcT; components are actuated to provide for low pressure protection to to the NCS durins MODE 5?,

E0.53 (***** CATEGORY.co CCMTINUED ON NEXT PAGE *****) l e/ i Os I ^ 9 j

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 12 QUESTION 6.10 (1.00) Which of'the following malfunctions would cause a pressurizer level i indication of 0%? a. dp cell diaphragm rupture b. Reference les rupture

c. Impulse line rupture d.

Equalizins valve leakage QUESTION 6.11 (1.00)

c. Which section/ component of the Rod Control system enables the control rods to react proportionally to a change in NC temperature?

[0.5]

b. Which section/ component of the Rod Control system balances

[0.53 Reactor / Turbine power in the event of a Turbine runback? QUESTION 6.12 (2.00) For the following Process Radiation Mointors, state the type of RADIATION detecte'd, type of DETECTOR, and protective FUNCTION (if any) 1. EMF 32 steam generator blowdown demin outlet 2. EMF 36 unit vent gas 3. EMF 43 control room vent intake OUESTION 6.13 (1.50) Answer the following regarding the Reactor Protection system TRUE/FALSEt l a. In order to generate a ' Turbine Trip'-Reactor Trip signal, 2/3 low auto-stop oil pressure and 4/4 throttle valve closure si nals are required. 3 b. A General Warning alarm would be received upon 1/2 ' Train in Test' alarms. [ c. P-14 (S/G high level) actuates a turbine trip and feedwater isolation j only. l l (***** CATEGORY 06 CONTINUED ON NEXT PAGE

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1 l i I E

i e 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 13 GUESTION 6.14 (2.00) For the Steam Dump Control system answer the followinst

c. Refer to figure 78.1, what parameter is each of the indicators on the S/G A PORV controller displayins?

b. The main steam header pressure auto / man control station has AUTO-SET PT-MAN postions provided, specifically what function is/are performed in each of these three postions? c. In the Tavs mode a 10% step loss of load si3nal is present (no reactor trip occurs /C-9 is satisfied), Bank 2 condenser dump valves fail to open Tavs-Tref deviation is increasing, which of the followins would be the next initial action: (1) Bank 3 valves open (2) S/G safeties open (3) S/G PORVs open (4) no other valves would open GUESTION 6.15 (1.00) Which of the following does the OT delta T protection circuit prevent j from exceedins? a. Power density b. DNB c. total core power d. redistribution i i QUESTION 6.16 (1.50) a. What condition (s) automatically isolate the fire protection system containment isolation valves (1RF821A Unit-1, 1RF823A Unit-2)? E0.5]

b. List four seneral types of fire protection status alarms.

E1.0] (***** CATEGORY 06 CONTINUED ON NEXT PAGE

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v 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 14 QUESTION 6.17-(1.50)

c. For the following state if the condition WOULD or HOULD NOT result in a turbine runback signal

[1.03 1. 1/4 OP delta T alarm 2. PCB 0 and PCB 11 open

3. 60% impulse pressure and 1A MFP trips 4.

stator water pressure 15 psi below normal and >10% impulse pressure for > 45 seconds

b. State the difference between an automatic and manual turbine runback signal (i.e. method by which the turbine is runback)

CO.53 QUESTION 6.18 (1.00) li hts at the During normal NCP operation how many of the 5 indicatin3 3 local NCP maintoring system are enersi=ed? OUESTION 6.19 (1.00) Cor$cering the NCP oil lift pumps (OLP) answer the following: (refer to figure 91.1) a. Specifically what NCP conditions must exist to automatically shutdown the OLP? E0.53 b. TRUE/ FALSE. An NCP-OLP will automatically start when the NCP is <100% speed and the safety breaker is open. [0.53 QUESTION 6.20 (.50) What provisions have been installed to allow for renersi=ation of the C-heater elements in the event of a loss of 1LXG? (describe special alignments and source of power) l (***** END OF CATEGORY 06

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i i I i I

-s 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 15 ~~~~ d656E65EE5[~5UUTR5E-----------~~----------- R QUESTION 7.01 (1.00) A mainfeed pump turbine trip test should not be performed unless the unit load is less than (select the maximum allowable) a. 10% b. 15%-

c. 50%

d. 65% QUESTION 7.02 (1.00) When draining the cold les accumulators, the water is stored in thet

a. containment sump b.

refueling cavity c. fuelin3 water storage tank d. reactor coolant drain tank OUESTION 7.03 (1.00) Which of the following conditions would require all NC pumps to be tripped during a valid safety injection?

a. If an ND pump is running and the NC system subcooling is 10 des F.

b. If an NI pump is running and the NC system subcoolin3 is 10 des F'. c. If flow is verified from an CA pump and NC system subcooling is <0 des F d. If flow is verified from an NI pump and NC system subcooling is <0 des F (xxxxx CATEGORY 07 CONTINUED ON NEXT PAGE xxxxx)

s '7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 16 ~

~~~-

~~~~ 56 UL65 EdL 5UUTR5L R QUESTION 7.04 (1.00) If the following colors appeared on the control room CSF status tree display, which color coded path has the highest priority? a. RED

b. ORANGE c.-YELLOW d.

GREEN QUESTION 7.05 (1.00) If the following CSFs were all displayed oranger which one has priority?

e. Heat Sink b.

Suberiticality

c. Integrity d.

Inventory GUESTION' 7.06 -(1.00) If you receive no whole body exposure for the first 7 weeks of a calendar quarter, then you-may receive up to ____ during the 8th week without exceeding the normal whole body administrative exposure limit.

a. 100 mrem b.

500 mrem c. 800 mrem d. 1000 mrem (***** CATEGORY 07 CONTINUED ON NEXT PAGE

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1 m -7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 17 ~~~~~~~~~~~~~~~~~~~~~~~~ ~~~~ 5656E66565E~66UTRUL R QUESTION 7.07 (1.00) Which of the following statements regardins access keys to Extra High Radiation Areas is correct?

a. Extra High Radiation Area keys shall be issued to HP personnel only, during non-emergency conditons.

b. Extra High Radiation Area keys are issued on a daily bases and are only transferable to your shift relief. c. The Extra High Radiation Area key locker includes keys for Radiographic Exposure Devices.

d. To be issued an Extra High Radiation Area key, a signed statement for issue approval by an HP supervisor must be documented on your Daily Exposure Time Record.

QUESTION 7.08 (1.00) Which of the followins conditions would warrant an emergency baration of the Reactor Coolant System? a. "Lo Insertion Limit' alarm durins Mode 1 operations. b. One control rod stuck fully out on a reactor trip. c. A stuck open pressurizer PORV durins Mode 1 operations.

d. Less than 2000 ppm baron in the coolant durins Mode 6 operations.

QUESTION 7.09 (2.00) McGuire Limitations and Precautions, OP/0/A/6100/08 states the following: ' All shutdown bank s must be at the fully withdrawn position whenever positive reactivity is beins inserted by baron or Xenon concentration i chanses, reactor coolant temperature changes, or motion of control banks.' State the 2 exceptions to this precaution. l (***** CATEGORY 07 CONTINUED ON NEXT PAGE

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l t

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 18 ~~~~~~~~~~~~~~~~~~~~~~~~ ~~~~ 5656L66fCAL 66UTR6L R GUESTION 7.10 -(1.00) During a response to NC system leakage within the capacity of both NV pumps AP/1/A/5500/10, there is one manual Safety Injection and one manual Reactor Trip requirement. State under what condition (s) each of these is required. QUESTION 7.11 (1.00) Concernin3 the Emergency Boration AP/1/A/5500/38 proceduret (fill-in-the-blank)

a. A time delay of up to ____(a ranse of) minutes can be expected before indication of negative reactivity insertion is obtainable on core instrumentation.

b.-TRUE/ FALSE. To equalize Pressurizer boron concentration the operator places Pressurizer Hester Control Groups in manual AND closes the supply breaker, sprays operate to control pressure. QUESTION 7.12 (1.00) Which of the followins is a symptom of a LOSS OF LETDOWN FLOW according to AP/1/A/5500/12, Loss of Letdown, Chargins or Seal Injection? a.-Letdown heat exchanger outlet high temperature alarm.

b. Letdown heat exchanser outlet high pressure alarm.

1:.' Regenerative heat exchanSer letdown high temperature alarm.

d. Increasins VCT level.

(***** CATEGORY 07 CONTINUED ON NEXT PAGE

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r e 7. PROCEDURES - NORMAL, ADNORMAL, EMERGENCY AND PAGE 19 ~~~~~~~~~~~~~~~~~~~'~~~~ ~~~~ 5656L55iEAL E5 TR6L R QUESTION-7.13 (1.00) While performins steps in EP/1/A/5000/09 Loss of All AC Power, an SI signal cay be present, what ACTION with regard to the SI signal must be taken AND why mus.t this action be taken (once power is restored to 1 ETA or 1ETB)? a. No action is pecessary as the SI signal has no affect.

b. Place SI in iEST to prevent an overpressure transient on the NCS.

c. Reset the SI to permit the D/Gs to enersi=e the buses. d. Reset the CI to permit manual loading of components onto the buses. QUESTION 7.14 (1.00) Which of the actions correctly describes the sequence for removing a CF pump from HOLD following CF isolation on a Rx trip and lo-Tave? a. Reset hold, reset isolation b. Reset isolation, match %feedwater-% hold signals, reset hold

c.. Reset hold, reset isolation, match %feedwater-% hold signals d.

Reset isolation, reset hold, match %feedwater-% hold signals QUESTION 7.15 (1.00) Select the malfunction which lists " Place CRD Selector in manual AND control AFD within Tech Spec limits' as an immediate action step, according to AP/1/A/550/14 Rod Contal Malfunctions.

c. Failure of a Control Rod Bank to move in Automatic b.

Continous Insertion / Withdrawal of a Control Bank c. Dropped Control Rod d. Control Rod Misalignment 1 (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

.7. PROCEDURES - NORMAL,' ABNORMAL, EMERGENCY AND PAGE 20 ~ ~~"~~~~~~~~~~~~~~~~~~~~~ ~~~~ d656LUU5EAL EUNTRUL R QUESTION 7.16 (1.00) The Steam Generator tube rupture emergency procedure EP/1/A/5000/04, uses two terms associated with the Steam Generators ' Ruptured

and ' Faulted *,

EXPLAIN the bases of the term " Faulted' and give the parameter (s) used to determine if a Steam Generator is ' Faulted'. QUESTION 7.17 (1.00) With a loss of power to 1 ETA NO automatic actions occur on the board, the Diesel Generator is running, WHAT are your immediate actions to restore power and load 1 ETA with the Diesel Generator? QUESTION 7.18 (1.00) Other than the Condenser Vacuum indication, LIST three (3) symptoms of a loss of Condenser Vacuum event per AP/1/A/5500/23. QUESTION 7.19 (1.00) After resetting a CF isolation signal HOW LONG must the operator wait before attemptin3 to OPen the CF isolation valve? EXPLAIN. QUESTION 7.20 (.50) During a reactor startup the Shutdown Banks are being withdrawn, all banks are out however the operator ascertains that there are NO Rod Position Indicators operable for a control rod, WHAT immediate action (s) should be taken? QUESTION 7.21 (1.00) While operating the CA system with its suction supply from the main condenser hotwell the operator finds the hotwell level is 2' 5' below normal. What ACTION (S) should be taken with regard to the CA system AND why is/are the action (s) necessary? (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

v. e + 7.- PROCEDURES - NORMALr ABNORMAL, EMERGENCY AND PAGE 21 ~~~~ 5656L6656dL'UUUTRUL R QUESTION 7.22 (1.00) ENOTE: The terms '3videline ArBrC' are used as typical examples of E0Ps3 An operator is performing Emergency Procedure Guideline Ar when symptoms appear requiring transition to guideline B. While performing guideline Br 'the operator finds it necdssary to enter guideline C. After completion of the actions in guideline C WHICH procedure would be re-entered? [ assume all svidelines end with transition words ' Return to Guideline and Step in Effect'. QUESTION 7.23 (1.00) While proceeding down the left-hand column of an emergency procedure the operator moves to the right -hand column f or contingency instructions for a particular step. The operator finds the contingency action not successful what COLUMN and STEP should the operator proceed to? OUESTION 7.24 (1.00) Select at what point the SI systems should be aligned for cold les recirculation based upon FWST level

a. FWST level low alarm b.

It is done automatically c. 50% level d. 3% level QUESTION 7.25 (2.00) LIST the four (4) possible alternate actions that can be taken if during a response to Nuclear Power Generation /ATWS the Turbine had not cutomatically tripped. (m**** CATECORY 07 CONTINUED ON NEXT PAGE *****)

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 22 ~~~~ 5656666 65L CU TREL'~~~~~~~~~~~~~~~~~~~~~~~ ~ R QUESTION 7.26 (1 00) If the Suberiticality Critical Safety Function indicates a dashed path, which of the following actions is required? a. Go immediately to the referenced procedure. b. .Go to the referenced procedure as time permits, c. Monitor other status trees and if no higher priority condi-tion exists, then so to referenced procedure. d. Monitor other status trees and if no hisher priority enndi-tion exists, then so to referenced procedure as time permits. QUESTION 7.27 (1.50) Indicate whether (YES/NO) the following conditions violate Critical Safety Function (CSF) red path criteria.

s. Pressuri=er level of 5% and RVILS upper ranse 80%.

b. Total CA flow 400 spm with all S/G 1evels <5%. c. Containment pressure 20 psis. QUESTION 7.?9 (1.00) During refuelins the. crane operator observes a -200 pound variance in the initial reading on the Dillon Load Cell while movir.3 fuel. What are the operator's immediate action (s)? (m**** END OF CATEGORY 07 *****)

8. ADMINISTRATIVE PROCEDURES, CONDITIONSr AND LIMITATIONS PAGE 23 QUESTION 0.01 (1.00) Turbine overspeed protection is required by Technical Specifications because an overspeed condition could cause

e. turbine components to become missles which may penetrate the turbine casing, allowing higher than allowable off-site doses.

b. turbine components to become missles, which may damage safety-related equipment.

c. the reactor thermal power to exceed the limits in the Unit's license, d.

the reactor to 30 prompt critical. QUESTION 8.02 (1.00) When a fire supression Spray / Sprinkler System is declared inoperable for a portion that protects an area containing redundant safety-related equipment the required action is to a. commence a Unit shutdown for the applicable unit within one hour.

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

c. establish a continous fire watch with backup fire supression equipment in the affected area within one hour.

d. 109 ambient temperature readings for the affected area hourly. QUESTION 8.03 (1.00) If the Containment Purge System Noble Gas Activity Monitor (EMF-39) is declared inoperable (while in mode 1), then

o. no purging or venting can be done via this pathway, b.

two independent containment air samples must be analyzed and two two qualified people must verify the purge lineup to allow purging via this pathway. c. the flow rate must be verified at least once every 4 hours to allow purging via this pathway.

d. grab samples must be taken and analy:ed at least once every 12 hours to allow purging via this pathway.

(***** CATEGORY 00 CONTINUED ON NEXT PAGE

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8. ADMINISTRATIVE PROCEDURES, CONDITIONSr AND LIMITATIONS PAGE 24 QUESTION 8.04 (1.00) A quarterly surveillance requirement of Tech Specs may be extended up to _____ days'without declarin3 the component inoperable due to the surveillance testing not being performed.

c. 9 b.

23 c. 32

d. 41 QUESTION 8.05 (1.00)

Which of the following is the responsibility of the Shift Supervisor in regard to the use of operating procedures performed during the shift?

c. Ensures the Working Copy File has a sufficient number of unused copies.

b. Initiates all procedure changes required during the shift.

c. Reviews and approves all completed procedures.

d. Compares the Working Copy to the Control Copy to ensure all changes are entered prior to use.

QUESTION 8.06 (1.00) Information Stickers placed on the Main Control Boards are controlled by

a. an Information Sticker Losbook.

b. a section in the Work Request Sticker Logbook. c. a section in the White Ta3 Sticker Logbook. d. a section in the Red Tag Sticker Logbook. (mmmmm CATEGORY 08 CONTINUED ON NEXT PAGE mamma)

\\ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 25 QUESTION 8.07 (1.00) Entries made in the Operators Logbook concerning. equipment shared by both Units should be made in

c. the Unit 1 RO Losbook.

b. the Unit 2 RO Logbook.

c. both Unit 1 and Unit 2 R0 Logbooks.

d. the Common Unit Logbook. QUESTION 8.08 (1.00) The person responsible to maintain accountability of Operations personnel during an emergency plant condition requiring a Site Assembly is a. the Superintendent of Operations. b. the Shift Supervisor. c. the Station Manager. d. the Recovery Manager. QUESTION 0.09 (1.00) Temporary modifications must be identified with a tag when they are installed

a. for more than one shift.

.b. past a shift change. c. by a Work Request in lieu of a procedure. de on safety-related equipment. QUESTION 8 10 (1.50) From what three (3) sources can a working copy of a procedure be generated? (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****) ,mm..

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 26 QUESTION 8.11 (1.00) For steps in EP's,AP's,PT's and OP's inwhich an individual has a reason to believe a particular step does not have to be performed, WHO is authorized to make this decision and HOW is the decision documented? QUESTION 8.12 (1.00) To be qualified as an independent verifier for completion of procedural eteps, such as determinins valve / breaker position, at least one of two criteria must be satisfied for the individual. What are these TWO criteria? OUESTION 8.13 (1.00) How are items on the Routine Task List which could not be performed on the echeduled shift re-scheduled to ensure their completion? (address both Tech Spec and Non-Tech Spec related items) GUESTION 8.14 (1.00) A Shift Supervisor has been off-shift for a period of three weeks, upon return to shift status a Turnover Checklist must be completed, HOW does the SS re-familiarise with shift conditions (according to the Turnover Checklist)? 00ESTION 8.15 (2.00) With regard to the Tech Spec Action Item Lo3 book

c. How are ' Closed Entries' made easly recognizable 7 b.

State the three functions of the second licensed operator. QUESTION 8.16 (.50) l TRUE/ FALSE. For the Control Room Annnunciator Losbook, if power range channel N41 fails and is removed from service per Tech Specs, all [ cssociated annunciators and status lishts that illuminate as a result of the condition shall be loS3ed. (***** CATEGORY 08 CONTINUED ON NEXT PAGE

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i l l l [

U. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 27 QUESTION 8.17 (1.00) During implementation of the Emergency Plan the Site Emergency Coordinator cannot delegate certain authority. What authority can not be delegated? QUESTION 8.18 (.50) The effects of an earthquake have been felt (Horizontal acceleration >0.089 cnd Vertical acceleration >0.0530). What is/are the immediate action (s) cccording to the E plan implementing proedure RP/0/A/5700/07? QUESTION 8.19 (1.00) What TWO conditions determine the operability of the pressurizer while the plant is in Mode 17 QUESTION 8.20 (1 00) During Unit i startup with the reactor about 2% power the operator finds the PORV block valve is stuck open and incapable of closing. Which of the -following is a correct action? (Refer to Figure 142.1 attached)

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

b. Even if action b is satisfied you are NOT allowed to increase power into Mode 1 (block valve cannot be restored operable),

c. Since the block valve is incapable of closing, you must proceed to Hot Standby with in the next 6 hours and Cold Shutdown with in the fo,11owing 30 hours.

d. The PORV must be closed and power removed from the PORV solenoid valve. QUESTION 8.21 (1.00) According to Emergency Plan Implementing Procedurer Sta. Dir. 3.8.1, All individuals onsite at the time of an emergency shall be accounted for and the names of the missing individuals shall be identified within ______ cinutes of the start of an emergency requiring Site Assembly. (***** CATEGORY 00 CONTINUED ON NEXT PAGE

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. 8.- ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 20 QUESTION 8.22 (1.50) Answer-the followin3 TRUE/ FALSE! a. Authorized Temporary Deviations to RWP requirements do not apply to RWPs for other task, however, they DO apply to similar RWPs for the same task b. OF the respiratory devices in the control room, the Pressure Demand respirators are the only device which can be used in an IDLH (Immediately Dangerous to Life and Health) atmosphere. c. Rapins off, posting and activatin3 a flashing light (in an extra high high radiation area) will replace the requirement that locked doors be provided. QUESTION 8.23 (1.00) The process of determing an instruments behavior by visually comparing the indications to other independent instrument channels which measure the same parameter is defined in Tech Specs as at a. Channel Calibration b. Channel Check c. Channel Functional Test d. Channel Verification QUESTION 8.24 (1.50) Which of the followin3 conditions / actions require logging in the Unit ~ Supervisors Los Book? 1. Notification of STA of an abnormal situation. 2. The on-duty Control Room SRO has been relieved by the STA.

3. Removal of a key, for use in plant manipulationse from the key locker.

QUESTION 0.25 (1.50) What three conditions determine the operability of the Upper Head Injection Accummulator in Mode 17 (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****) l \\ m

if.. 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 29 GUESTION 8.26 (1.00) -Which of the following conditions require a SDN calculation (verification) to-be performed within 1 hour? o. A' boron concentration change of >20 ppm. b. Goins out of the AFD target band.

c. Detection of an inoperable control rod.

-d. Reactor startup commencins >10 hours after shutdown. QUESTION 8.27 (1.00) Tech Spec 3/4.2.5 DNB Parameters, gives limits for two DNB related parameters. Which of the followin3 choices contains those two parameters?

e. Tav3 and NC system flow.

b. Pressurizer pressure and NC system flow,

c. NC system flow and Nuclear Power.

d. Tavs and Pressurizer pressure.

QUESTION 8.28 (1.00)

a. A licensed SRO shall be in the Control Room complex, and perform the duties of Control Room SRO when either Unit is in Mode (s)

b. An STA shall be onsite and within _____ minutes of the Control Room when 3

either Unit is in Modes 1-4. l (***** END OF CATEGORY 08

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

f a na ..i t Cycle efficiency o (Net tork out)/(Energy in) 2 a e og s a V t

1/2 at i

o { = mc (E = 1/2 mv a=(Vf - t,)/t A = An A = A e'** 3 PE = mgn yf = V, + at

= e/t 1=

an2/t1/2 = 0.693/t1/2 2 1/2'"

M / S Y W = v :P nD A=

4 [(t1/2)

II I)

D AE = 931 am m = V,,Ao - T.x Q.= m,ah I"Ieo Q = mCpat Q = UAa T I = I e'"* n I = I, 10'*/U ' Pwr = W ah f TVL = 1.3/u P = P',10 "#III 8 HVL = -0.693/u t/T p,p o SUR = 26.06/T SCR = S/(1 - K,ff) CR, = S/(1 - K,ffx) SUR = 26e/t* + (s - o)T s CR (1 - K,ffj) = CR (I ~ "eff2) j 2 T = (t*/s) + [(a - sy Io] M = 1/(1 - K,ff) = CR /CR, j T = s/(f. - s) M = (1 - K,ffo)/(I - K,ffj) T = (8 - e)/(Is) SDM = ( - K,ff)/K,ff a = (K,ff-1)/K,ff = aK,ff/K,ff t= = 10 seconds I = 0.1 seconds' o = [(t*/(T K,ff)] + [s,ff (1 + IT)] / Idl1"Id l 2,2 2 I P = (reV)/(3 x 1010) Id gd jj 22 d I = eN R/hr = (0.5 CE)/d (meters) R/hr = 6 CE/d2 (f,,g) Water Parameters Miscellaneous Conversions I gal. = 8.345 lbm. I curie = 3.7 x 1010aps l 1 ga;. = 3.78 liters 1 kg = 2.21 lbm I ft+ = 7.48 gal. I hp = 2.54 x 103 Stu/hr Density = 62.4 lbg/f t3 1 nw = 3.41 x 106 Btu /hr l Density = 1 gm/cW lin = 2.54 cm l Heat of vaporization = 970 Btu /lom 'F = 9/5'C + 32 l Heat of fusion = 144 Stu/lbm

C = 5/9 ('F-32) 1 Atm = 14.7 psi = 29.9 in. Hg.

1 BTU = 778 ft-lbf I ft. H O = 0.4335 lbf/in. 2 e = 2.718

Volume, ft'/lb Enthelpy. StrAo Entropy. StuAt a F P Water Evap Steam Water Evap Steam Water Evop Steam 8 A A A s, s, a, e 't og 's t g s at 0.08459 0.01602 3305 3305 -0.02 1075.5 1075.5 0.0000 2.1873 2.1873 32 35 0.09991 0.01602 2948 2948 3.00 1073.8 1076.8 0.006) 2.1706 2.1767 35 40 0.12163 0 01602 2446 2446 8 03 1071.0 1079.0 0.0162 2.1432 2.1594 40 45 0.14744 0.01602 2037.7 2037.8 13.04 1068.1 1081.2 0 0262 2.1164 2.1426 45 80 0.17795 0.01602 1704.8 1704.8 18 05 1065.3 1083.4 0.0361 2.0901 2.1262 50 60 0.2561 0.01603 1207.6 1207.6 28.06 1059.7 1087.7 0.0 % 5 2.0391 2.0946 60 70 0.3629 0.01605 868 3 868 4 38.05 1054.0 1092.1 0.0745 1.9900 2.0645 70 80 0.5068 0.01607 633.3 633.3 48.04 1048.4 1096.4 0.0932 1.9426 2.0359 30 80 0.6981 0.01610 468.1 468.1 58.02 1042.7 1100.8 0.1115 1.8970 2.0086 60 100 0.9492 0.01613 350.4 350.4 68 00 1037.1 1105.1 0.1295 1.8530 1.9825 300 110 1.2750 0.01617 265.4 265.4 77.98 1031.4 1109.3 0.1472 1.8105 1.9577 110 130 1.6927 0.01620 203.25 203.26 87.97 1025.6 1113.6 0.1646 1.7693 1.9339 120 130 2.2230 0.01625 157.32 157.33 97.96 1019.8 1117.8 0.1817 1.7295 1.9112 130 140 2.8892 0.01629 122.98 123.00 107.95 1014.0 1122.0 0.1985 1.6910 1.8895 140 150 3.718 0.01634 97.05 97.07 117.95 1008.2 1126.1 0.2150 1.6536 1.8686 150 l 160 4.741 0.01640 77.27 7729 127.96 1002.2 1130.2 0.2313 1.6174 1.8487 160 170 5.993 0.01645 62.04 62.06 137.97 996.2 1134.2 0.2473 1.5822 1.8295 170 180 7.511 0.01651 50.21 50.22 148.00 990.2 1138.2 0.2631 1.5480 1.8111 180 180 9J40 0.01657 40.94 40.96 158.04 984.1 1142.1 0.2787 1.5145 1.7934 100 200 11.526 0.01664 33.62 33.64 168.09 977.9 1146.0 0.2940 1.4824 1.7764 200 210 14.183 0.01671 27.80 27.82 178.15 971.6 1149.7 0.3091 1.4509 1.7600 210 212 14.696 0.01672 26.78 26.80 180.17 970.3 1150.5 0.3121 1.4447 1.7568 212 220 17.186 0.01678 23.13 23.15 188.23 965.2 1153.4 0.3241 1.4201 1.7442 220 230 20.779 0.01685 19.364 19.381 198.33 958.7 1157.1 0.3388 1.3902 1.7290 230 240 24.968 0.01693 16.304 16.321 208.45 952.1 1160.6 0.3533 1.3609 1.7142 240 250 29.825 0.01701 13.802 13.819 218.59 945.4 1164.0 0.3677 1.3323 1.7000 250 260 35.427 0.01709 11.745 11.762 228.76 938.6 1167.4 0.3819 1.3043 1.6862 260 270 41.856 0.01718 10.042 10.060 438.95 931.7 1170.6 0.3960 1.2769 1.6729 270 280 49.200 0.01726 8 627 8.644 249.17 924.6 1173.8 0.4098 1.2501 1.6599 200 290 57.550 0.01736 7.443 7.460 259.4 917.4 1176.8 0.4236 1.2238 1.6473 290 300 67.005 0.01745 6.448 6.466 269.7 910.0 1179.7 0.4372 1.1979 1.6351 300 310 77.67 0.01755 5.609 5.626 280.0 902.5 1182.5 0.4506 1.1726 1.6232 310 820 89.64 0.01766 4.896 4.914 290.4 394.8 1185.2 0.4640 1.1477 1.6116 320 840 117.99 0.01787 3.770 3.788 311.3 878.8 1190.1 0.4902 1.0990 1.5892 340 360 153.01 0.01811 2.939 2.957 332.3 862.1 1194.4 0.5161 1.0517 '1.5678 360 380 195.73 0.01836 2.317 2.335 353.6 844.5 1198.0 0.5416 1.0057 1.5473 380 400 247.26 0.01864 1.8444 1.8630 375.1 825.9 1201.0 0.5667 0.9607 1.5274 400 420 30S.78 0.01694 1.4808 1.4997 396.9 806.2 1203.1 0.5915 0.9165 1.5080 420 440 381.54 0.01926 1.1976 1.2169 419.0 785.4 1204.4 0.6161 0.8729 1.4890 440 l 460 466.9 0.0196 0.9746 0.9942 441.5 763.2 1204.8 0.6405 0.8299 1.4704 460 450 566.2 0.0200 0.7972 0.8172 464.5 739.6 1204.1 0.6648 0.7871 1.4516 480 500 680 9 0.0204 0.6545 0.6749 487.9 714.3 1202.2 0.6890 0.7443 1.4333 100 1 520 812.5 0.0209 0.5386 0.55 % 512.0 687.0 1199.0 0.7133 0.7013 1.4146 520 540 962.8 0.0215 0 4437 0 4651 536 8 657.5 1194.3 0.7378 0.6577 1.3954 540 5CO !!33.4 0.0221 0.3651 0.3871 562.4 625.3 1187.7 0.7625 0.6132 1.3757 560 550 1326.2 0.0228 0.2994 0.3222 589.1 589.9 1179.0 0.7876 0.5673 1.3550 580 l 1 600 1543.2 0.0236 0.2438 0.2675 617.1 550 6 1167.7 0.8134 0.5196 1.3330 600 l 620 1786.9 0.0247 0.1962 0.2208 646.9 506.3 1153.2 0.8403 0.4689 1.3092 620 ( 640 2059 9 0.0260 0.1543 0.1802 679.1 454.6 1133.7 0.8666 0.4134 1.2821 640 660 2365.7 0 0277 0.1166 0.1443 714.9 392.1 1107.0 0.8995 0.3502 1.2498 660 660 2708.6 0 0304 0.0808 0.1112 758 5 310.1 1068.5 0.9365 0.2720 1.2086 680 l 700 3094.3 0 0366 0.0386 0.0752 822.4 172.7 995.2 0.9901 0.1490 1.1390 700 705.5 3208 2 0.0508 0 0.0508 906.0 0 906 0 1.0612 0 1.0612 705.5 l TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED l WATER (TEMPERATURE) 1 A.3

9eleme ge/tti Enthalpy. BL;Ab EItropy. Sty /sts a F Emergy.Ch/Its P'"ne'- Press Temp water Evap Steam W ater tvep Steam Water tvep Steam Water Steam pole F pe o v v, g e h, s, s e, o h h g y e g er, 0.0686 32 018 0.01602 3302.4 3302.4 0.00 1076.5 1075 5 0 2 1872 2.1872 0 1021.3 0.0886 0.10 35.023 0 01602 2945.5 2945 5 3 03 10738 1076.8 0 0061 2.1705 2.1766 SA3 1022.3 0.10 0.15 4E453 0 01602 2004 7 2004 7 13.50 1067.9 1081 4 0 0271 2 1140 2 1411 13.50 1025.7 0.15 0.20 51160 0 01603 1526.3 1526 3 21 22 1063 5 1084 7 0 0422 2 0728 2.1160 2122 1028 3 0.20 0.30 64 484 0 01604 1039 7 10393 32.54 10b7.1 3029 7 0.0641 2.016S 2.0809 32.54 1032 0 0.30 0.40 72.869 0 01606 792.0 792.1 40 92 1052.4 1093.3 0.0799 1.9762 2.0562 40.92 10341 0.40 0.5 79.586 0 01607 641.5 641.5 47.62 1048 6 1096 3 0 0925 1.9446 2.0370 4742 1036 9 0.5 0.6 85.716 0 01609 540 0 5401 53 25 10455 1093 7 01028 1.9186 2.0215 53.24 1038.7 0.6 ..s '* 0;7 ^ '90 09. < 0 81610* 4466.81. 466.94 ,5810 '.1043 7.,1400 A 0.3., %1 8964i,. 2.0083,.48.10 jnO40.3. .s 0.7, 0.8 94.38 0.01611 411.67 411.69 62.39 1040.3 1102.6 01117 1.8775 1.9970 6239 1041.7 0.8 8.9 98.24 0.01612 368 41 368 43 66 24 1038.1 1104.3 0.1264 1A606 1.9870 66.24 1042.9 0.9 1.0 101.74 0.01614 333.59 333 60 69.73 1036.1 11058 0.1326 13455 1.9781 69.73 1044.1 1.0 3.0 126.07 0.01623 173.74 173.76 94.03 1022.1 1116 2 0.1750 1.7450 1.9200 94A3 1051A 2.0 3.0 14147 0 01630 118 71 118 73 109.42 1013.2 1122 6 0.2009 1.8854 1.8864 109 41 1056.7 3.0 4.0 152 96 0 01636 90 63 90.64 120.92 1006 4 1127.3 0.2199 1.6428 13626 120.93 1060.2 4.0 8.0 162 24 0.01641 73.515 73.53 130 20 1000.9 1131.1 0.2349 1.6094 13443 130.18 1063.1 SA 4.0 170.05 0.01645 61.967 61.98 138 03 996.2 1134.2 0.2474 1 5820 1A294 138D1 1065.4' 4A FA 176 84 0.01649 53 634 53.65 144.83 992.1 1136 9 02581 1.5587 1A168 144Al 1067.4 7.0 80 182 86 0.01653 47.328 47.35 150.87 988.5 1139 3 0 2676 1.5384 1A060 15034 1069.2 SA i 9.0 18827 0 01656 42.385 42 40 156.30 985.1 1841.4 0 2760 1.5204 1.7964 15628 1070.8 9.0 10 193.21 0.01659 38.404 38 42 161.26 982.1 1143.3 02836 1.5043 1.7879 161.23 1072J 10 14.696 212.00 0.01672 26 782 26 80 180 17 970.3 1150.5 0.3121 1.4447 1.7568 100 12 1077.6 14.696 15 213 03 0.01673 26.274 26.29 181.21 9691 1150.9 0 3137 1.4415 1.7552 181.16 1077.9 15 20 227.96 0.01683 20.070 20 067 196 27 960.1 1156.3 0.3358 1.3962 1.7320 19621 1082.0 to 30 250 34 0 01701 13 7266 13 744 218.9 945.2 1164.1 0 3682 1.3313 1.6995 218A 1087.9 30 40 267.25 0 01715 10 4794 10 497 236.1 933 6 1169.8 0.3921 1.2844 1.6765 236 0 1092.1 40 80 261.02 0.01727 8 4967 8 514 250.2, 923 9 1174.1 0 4112 1.2474 J.6585 250.1 1095.3 80 60 29231 0 01738 7.1562 7.174 262.2 915.4 1177.6 0.4273 1.2167 1.6440 242.0 1098.0 80 70 302.93 0.01748 6.1875 6205 272.7 907A 1180 6 0 4411 1.1905 1.6316 272.5 1100.2 70 80 312 04 0 01757 54536 5 471 232.t

900.9 1183 1 0.4534 1.1675 1.6208 281.9 1102.1 to 90 320 28 001766 4.8777 4 895 290 7 894 6 1185.3 0 4643 1.1470 1.6113 290.4 11033 to 100 327.82 0 01774 4.4133 4.431 238.5 888.6 1181.2 0 4743 1.1284 1.6027 298 2 1105.2 300 320 341.27 0 01789 3 7097 3 728 312 6 877A 1190 4 0 4919 1.0960 1.5879 312.2 1107.6 120 140 353 04 001803 3 2010 3 219 325 0 868 0 1893 0 0.5071 1.0681 1.5752 324 5 1109.6 140 I

160 363 55 0 01815 2.8155 2 834 336 1 859 0 1195.1 0 5205 1.0435 1.5641 335.5 1111.2 160 180 373 08 0 01827 2.5129 2.531 346.2 850 7 1196.9 0 5328 10215 1.5543 345.6 1112.5 180 200 35180 0 01839 2.2689 2.287 355.5 842.8 1198.3 05438 1.0016 1.5454 3542 11131 300 250 400 97 0 01865 1.8245 1.8432 3761 825 0 1201.1 0 5679 0 9585 1.5264 3753 1115.8 250 300 417 3b 001889 1.5233 1.5427 394 0 808.9 1702 9 0.5882 09223 1.5105 392.9 1117.2 300 350 42173 001913 1.3064 1.3255 409 8 7942 1204 0 0 6051 0 890a) 1.4968 404 6 1118 1 350 i 400 444 60 0 0193 1.14162 1.1610 424.2 7804 1204 6 0 6217 0 8630 1.4847 4223 11If 7 400 450 4t528 00195 1.01224 .l.0318 437.3 767.5 1204.8 06360 0 8378 1.4738 43hJ 1118.9 450 $20 of 7 01 00198 0 90787 0 9216 4495 755.1 1204 7 0 6490 0 8148 1.4439 4473 tilt 8 500 $50 47694 00199 0 82183 0 8418 460 9 743.3 1204 3 06611 0 7936 1.4547 45t.9 1118 6 $50 600 48620 0 0201 0 74962 03698 471.7 732.0 12037 0 6723 0 7738 1.4461 469 5 tile.2 600 703 ,502 03 0 0205 063505 0 6556 4916 710.2 1701 8 06928 0 7377 1.4304 488 9 1116 9 700 833 51821 0 0209 0 54809 0 5690 509 8 689 6 1193 4 0 7Ii1 0 7051 1.4163 506 7 1115.2 000 900 !)! 9) 0 0212 0 47968 0 5009 526 7 669 7 11 % 4 0 7279 0 6753 1.4032 523 2 1113 0 900 1000 544.Sh 00216 0 42435 0 4460 542.6 f 50 4 1192 9 0 7434 0 6476 1.3910 53*,6 II10 4 1000 1100 51L 2v 0.0720 0 37a(3 0 4005 557.5 631.5 1189 1 0 7573 0 6216 1.3794 513 I 1107.5 1100 3200 367.19 00223 0 34013 0 3625 571 9 613 0 1184 8 07714 05%9 1.3653 566 9 1804 3 1200 1900 L7142 00227 0 30722 0 3299 585 6 594 6 8180 2 0384) 05733 1.3577 580 1 1100 9 1300 14C0 $17 07 0 0731 0 27871 0 3018 598 8 576 5 1175 3 0 7966 0 5507 l.3474 b92 9 1037.1 1400 1500 5%20 0 0235 02h372 0 2772 6113 550 e i170 l 08015 0 ?283 1.3373 605 7 1093.1 1500 10*s 6 2000 2000 635 60 0 02's? O16766 0IFB3 672 1 466 2 1139 3 0 862t 04256 1.7881 6626 s 2500 66$ 11 0 02c.f 01020) 01307 731 7 3616 1093 3 C 9139 0 3206 82345 118 5 1032.9 2500 3000 695 33 0 0343 0 050/3 0 0850 801 8 218 4 1020 3 0 9728 01891 1.1619 7822 973.1 3000 3298 2 70147 0 0%08 0 0 050d 906 0 0 906 0 10612 0 10612 875 9 875 9 3708.2 TABLE A.3 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (PRESSURE) A.4

) Tempovetwo, F Abe pesos. (s to ) 100 200 300 400 900 000 700 000 900 1000 1100 1200 1300 1400 1500 e 00161 392 5 452.3 611.9 571.5 631.1 690 7 3 6 65 00 1150 2 11957 1241 8 1288 6 IBM I 1984 5 (101.74) s 0.1295 2 0h09 2.1152 21722 2.2237 2.2708 23144 e 0.0161 7s 14 90 24 102 24 114 21 126 15 138 08 150 01 161.94 173 86 185 78 197.70 200 62 221.53 233 45 5 h 68 01 114C 6 1144 8 1241.3 !?88 2 133b9 1384 3 1433 6 1483 7 1534 7 1586 7 1639 6 1693 3 17480 1803 5 (167 24) s 017v5 1 8716 1 9369 1.9943 2.0460 20932 213G7 2.1776 2 2159 2 2521 2.28 % 2.3194 2350) 2.3811 2.4101 e 0 0161 3884 44 93 51 03 57.04 63 03 69 00 74 98 to 94 86 91 9287 98 84 104 80 110 76 116 72 30 4 68 02 1146 6 1193 7 1240 6 120?.8 13355 1384 0 1433 4 1483 5 1534 6 1586 6 1639 5 1693 3 1747.9 1803 (19.'.21) s 01295 1 7928 1.8593 1.9173 1.9692 2 0166 2 0603 2.1011 213M 2 1757 2 2101 2 2430 22744 2.3046 2.33 e 0 0161 0 0166 29 89) 3393 37.985 41 966 45 978 49 964 53 946 57.926 61 905 65 882 69858 73 833 77.007 16 6 68 04 168 09 1892 5 1239 9 1287.3 1335 2 13835 1433 2 1483 4 1534 5 15865 1639 4 16932 17474 1803 4 (213.03) s 0 1295 0.2940 1.8134 18720 1 9242 1.9717 2.0155 2.0563 2.09 % 2.1309 2.1653 2.1982 22297 2.2599 2.2890 e 0 0161 00lu 223 % 25 428 28 457 St en 34 465 37.458 40 447 43 435 46 420 49 405 S2388 55.370 58.352 30 6 6805 16811 1198 4 1239.2 1286 9 1334 9 1383 5 1432 9 14a3 2 1534.3 15H.3 1639.3 1693.1 1747A 1803. (227.96) e 0.1295 0.2940 1.7805 1A397 1.8921 1.9397 1.90 % 2.0244 2.0628 2.0991 2.1336 2.1665 2.1979 2.2282 2 257 e 00161 00166 11 035 12 624 la165 15 685 17.195 18 699 20 199 21 697 23 194 24 689 26.183 27.676 29.1 40 6 68 10 168 15 1186 6 1236 4 1785 0 1333 6 1382.5 14321 1482.5 1533.7 1545 8 IH88 1992 7 1747.5 1803 0 (267.25) e 0.1295 0 2940 1.6992 1.7608 1 8143 1.8624 1.9065 1.9476 1.9860 2.0224 2.0569 2.0899 2.1224 2.1516 2.14 e 0.0161 0 0156 7.257 8354 9 400 10 425 11 435 12 446 13 450 14 452 15.452 14.450 17.448 14 445 19 441 60 6 68 15 165 20 !!81 6 1233 5 1243 2 3332 3 1381.5 1431 3 1481.8 15332 1585.3 1638 4 1692 4 1747.1 1802.8 (292.71) s 01295 02939 1.6492 1.7134 1.7681 1.8168 13612 1.9024 1.9410 1.9774 2.0120 2.0450 2.07H 2.1068 2.1359 e 0 0l61 0 0166 0 0175 6 218 7.018 '794 8 560 9 319 10 075 10 829 11 581 12.131 13 081 13 829 14.577 30 4 68 21 168 74 269 74 1230.5 1281 3 1330 9 13805 1430 5 1481.1 1532 6 1584.9 1638 0 1692.0 17468 1802.5 (312.04) s 0.1295 02939 0.4371 1.6790 1.7349 1.7842 14249 1 8702 1.9009 1.9454 1.9800 2.0131 2.0446 2.0750 2.1041 e 0 0161 0 0166 0 0175 4 935 5 588 6 216 6.833 7 443 B 050 B655 9.258 9 660 10 440 11.000 11.659 100 h 68 26 168 29 26977 1227.4 1279.3 1329 6 41379 5 1429 7 1480 4 1532.0 1564 4 1637.6 1691.6 1746.5 1802.2 (327.82) s 0.1295 0 2939 04371 1.6516 1.7088 1.7586 1.8036 1A451 18839 1.9205 1.9552 1.9683 2 Alt 9 2.0502 2.0794 e 0 0161 0 0166 0 0175 4 0786 4.6341 51637 5 6831 6 1929 6 7006 7.2060 7.7096 8 2119 8.7130 9.2134 9.7130 120 A es 31 168 33 26981 1224.1 1277.4 13281 1378 4 1478 8 1479 8 15314 1543.9 1637.1 1691.3 17442 1802.0 (341.27) s 0.1295 0 2939 0 4371 1.6286 1.6872 1.7376 1.7829 13246 1A635 1.9001 1.9349 1.9680 1.9996 2.0300 2.0592 i e 0 0161 0 0166 0 0175 3 4661 3 9526 4 4119 4 8585 S.2995 5.7364 61709 64036 7.0349 7.4652 7A946 8.3233 140 A 68 3' 168 38 269 85 1220 8 1275 3 1326 8 1377.4 1428 0 lef t i 1530 8 1543 4 1636 7 1990 9 1745 9 1801.7 i (353 04) s 0 1295 0 2939 0 4370 160$$ 1 6686 1.7196 1.7652 1 8071 1A461 1 8828 1.9176 1.950S 1.9825 2.0129 2.0421 e 0 0161 0 0166 0 0175 3 0060 34413 3 8480 4 2420 4 6295 5 0132 $3945 S.7741 6 1522 4 5293 '4 9055 7.2811 260 A 68 42 168 42 269 89 1217.4 1273 3 1325 4 1376 4 1427.2 1878 4 1530 3 1582 9 1636 3 1890.5 1745.6 1801.4 (363 55) e 0.1294 0 2938 0 4370 1.5906 1.6522 1.7039 1.7499 1.7919 1 8310 1A478 1.9027 1.9359 1.9676' l.9980 2 0273 e 0 0161 0 0166 0 0174 26474 3 0433 3 4093 3.7621 4.1064 4 4505 4.7907 S.1289 S 4657 53014 E1363 64704 180 4 68 47 16447 264 97 12138 1271 2 1324 0 1375 3 1426 3 1477.7 1529 7 1582 4 1635 9 1940 2 1785J 1801.2 l (373 Cal e Cl294 02638 04370 1 5743 1 6376 8.6900 1 7362 1.7784 1.8176 18345 1.8894 1.9227 1 9545 1.9849 2.014 e 0 0161 0 0166 0 0174 23598 2.7247 3.0583 3 3783 3 6915 4 0006 4 3077 4.6128 4.9165 S 2191 S.5209 SA2 200 6 68 12 It8 51 269 94 1210 1 1269 0 1322 6 1374 3 1425 5 1477.0 15291 1541.9 1635 4 1689 8 1745 0 1800 9 (351 60) e 01294 0 2938 0 4359 1.5593 1.6242 1.6716 1.7239 1.7663 1.8057 1.8426 18716 1.9109 1.9427 1.9732 2.002 e OC161 0 0166 0 0174 00186 2.1504 24662 2 6872 2 9410 3 1909 3 4382 3 6837 39278 4 1709 4 4131 4 6546 250 e 68 65 168 63 270 05 3/5 to 1263 5 1319 0 13716 1423 4 1475 3 1527 6 1580 6 1634 4 1644 9 1744 2 1800.2 (400 97) s C 1294 0 2937 04364 0 5567 1.5951 16502 1 6976 1.7405 1.7601 1 8173 18524 1.8d58 l.9177 1.9482 1.9776 e 00161 0 01E6 0 0174 0 0186 1.7665 2 0044 2 2263 2 4401 2 6509 2 5585 3 0643 3.2688 3 4721 3 6746 3 876 300 > 68 79 IM 74 27u te 375.15 1237 7 1315 2 1368 9 1428.3 1473 E 1526 2 1579 4 1633 3 1688 0 1743 4 1799 6 (417.35) s 01294 02937 0 4337 C5%5 1.5103 1.6274 16758 1.7192 !?591 f.7964 13317 1.9652 18972 1.9278 1.9572 e 0 0161 0 0166 0 0174 0 018C 14913 17028 1 9972 2 0332 2 2652 2 4445 2.6219 2.7980 2.9730 3.1471 3.3205 350 A C8 92 109 85 270 24 375 21 1251 5 1311 4 13M 2 1419 2 1471 6 1524 7 1578 2 1632 3 Ita?.I 1742 6 1798 9 (431.73)s 01293 0 29M 043G7 0 5664 1.5483 16077 16571 1.7009 1.7411 1.7787 1 8141 1 8417 13795 1.9a05 1.9400 e 00161 0 0lL6 0 0174 0 0162 1 2841 1 4761 16499 18151 1.9759 2.1339 2 2901 2 4450 2 5987 2.7515 2 903 400 a 69 05 168 97 270 33 375 27 1245 l 1307.4 13634 1417 0 14701 1523 3 1576 9 1631.2 1656 2 17419 17932 (444 60) : 51293 0293h 0 43M 0 5%3 1.5782 1 5901 16406 16850 1 7255 1 7612 1.7968 1.8325 lA647 1.8955 1.9250 e 00161 0 0166 0 0174 00186 09919 11584 13037 l.4397 15708 16932 88256 39507 2 0146 21977 23200 500 6 69 32 119 le 270 Sl 375 38 1231 2 12991 1357 7 1417 7 1466 6 1520 3 1574 4 16291 1644 4 1740 3 1796 (4LF.0llo 0 1297 0 2134 0 438.4 05t60 14971 1559) 16'2J 165/8 1 6990 17371 1.7730 18069 1A393 1 8702 lA908 1 TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE) A.5

Abe press. I!*Pv'il#'0. F C/sg in (ul. temp) 100 200 300 400 600 600 700 800 000 1000 1100 3200 1300 1800 1500 e 0 0161 0 01 % 00174 0 0186 0 7944 0 94 % 1 0726 18892 13008 14093 1.5160 16711 1.72b2 1 8284 1.9309 880 6 69 58 169 42 270 70 375 49 1215 9 1790 3 1351 8 14083 1463 0 1517 4 15719 1627.0 1682 6 1738 8 179h 6 (486.20) s 0.1292 0.2933 04h2 0 % 57 3 4590 3.5379 15844 163b3 I6769 3 71 % 1.7517 8.78b9 1 A184 38494 1.8792 e 0 0161 0 0166 0 0174 00186 0 0704 0 7928 09072 1.0102 1.1078 12023 1 7948 l.3858 1.47s7 1 % 47 1.6530 700 4 69 D4 169 65 270 89 37561 487 93 1781 0 134S t, 14037 14b9 4 1514 4 1%94 1624 8 IE07 17372 1794 3 (503 CS) e 01291 0.2932 04MO O % 55 06809 35090 1.% 73 1 6154 36b80 16970 17335 176M i8002 18318 18617 e 0 0161 0 0166 0 0174 0 0186 0 0704 0 6774 0 7875 0 8759 0 9631 1 0470 1 1289 12093 1782$ 13669 1.4446 800 & /0 11 169 88 271 07 375 73 487Ad 1771 1 13392 1399I I4SS A 1511 4 1%69 16227 167E 9 17h 0 1792 9 (518L). 0.1290 02930 0 43b8 0 % 52 0 6885 1 4869 1 5484 1.% 80 16413 1 6807 1.7175 17522 1.78bt 1 8164 1 8464 e 0 0161 0 0166 0 0174 0 0186 0C234 0 5869 0 6858 0 7713 0 8504 0 9262 0 9918 10720 11430 1 2131 1.2825 800 6 70 37 170 10 211.26 37584 487.83 1260 6 133?? 1394 4 14522 15CB S 1564 4 1620 6 1677 1 17341 1791 6 (531.95) s 0 1290 0 2929 0 4357 0. % 49 0 6881 1.4659 1.5311 1.5822 16263 1.6662 1.7033 1.7382 17713 16028 18329 e 0 0161 0 0166 0 0174 0 0186 0 0204 0$137 0 6080 0 6875 0 7603 0 8295 0 8966 0 % 22 1.0766 1.0901 1.1529 1000 6 70 63 170 33 271.44 375 96 487.79 1249 3 1325.9 1389 6 1448 5 1504 4 1561.9 1618 4 1675.3 1732 5 !?90 3 (544.58) s 0.1269 0 2928 0 4355 0 % 47 0 4876 1.4457 1.5149 1.5677 16126 16530 14905 1 7256 1.7589 1.7905 1.8207 e 00161 0 0166 0 0174 0 0185 0 0203 0 4511 0 5440 0 6188 06865 0 7505 0 8121 0 8723 0 9313 0 9894 1.0468 1100 6 70 90 170.56 271 63 376 08 447.75 1237.3 1318 8 1384 7 1444 7 1502 4 1559 4 1616 3 1673.5 1731.0 1789 0 (5%.23) s 0.1269 0.2927 0 4353 0 %A4 04872 1.4259 1.4996 1.5542 16000 1.6410 3.6787 1.7141 1.7475 1.7793 1A097 e 0 0161 0 0166 0 0174 0 0185 0 0203 0 4016 0 4905 0.5615 0 6250 0 6845 0 7418 C 7974 0 8519 0.90$$ 0 9584 3200 6 71.16 170.7 A 27122 376 20 487.72 1224 2 1311.5 1379.7 14:09 I449 4 1556 9 1614.2 1671.6 1729 4 1787.6 (567.19) s 0.1288 0.2926 0.4351 0 % 42 0 6868 1.4061 1.4851 1.5415 1.5883 16298 1 H79 1.7035 1.7371 1.7691 1.7996 e 0 01(,1 0 0166 0 0174 0 0125 0 0203 0.3176 0 4059 0 4712 0$282 0SBC9 0 6311 0 6794 0 7272 0.7737 0 8195 3400 6 71 48 17124 27219 376 44 48765 1194.1 12961 1369J 14332 1493 2 1551 8 1609 9 1668 0 1726 3 1785 0 (587.07)s 0.1287 02923 04M8 0.5636 0 6859 1.3652 1.4575 1.5182 1.5670 1.6CM 16484 1 6845 1.7185 1.7508 1.7815 e 0 0161 0 0166 0 0173 0 0185 0 0202 0 0236 0.3415 0 4032 0 4555 0.5031 0 5482 0 5915 0 6336 0 6748 0.7153 1600 4 72 21 171 69 272.57 376 69 487.60 616 77 J2794 1358 5 14252 1486 9 1546 6 1605 6 1664 3 1723 2 1782.3 (60487) s 01286 0 2921 04344 0 5631 0 68bt 0.8129 14312 1.4953 1.5478 1.5916 16312 1 6678 1.7022 1.7344 1.7657 e 0 0160 0 0165 0 0173 0 0185 0 0202 0 0235 0 2906 0 3500 0 3988 0 4426 0 4836 0 5229 0 M09 0 5940 0 6?43 1800 a 72.73 172.15 272.95 376 93 487.56 615 58 1261.1 1347.2 1417.1 1480 6 1541.1 1601.2 1660 7 1720.1 1779 7 (421.'32) s 0.1284 0.2918 0 4341 0 5626 0 68'3 0 8109 1.4054 1.4768 1.5302 1.5753 161% 1652A 16876 1.7204 1.7516 e 0 0160 0 0165 0 0173 0 0184 0 0201 0 0233 0.2488 0 3072 0 3534 0 3942 0 4320 0 4680 0.5027 0 5365 0.5695 2000 6 73 26 172 60 273 32 377.19 48753 614 48 1240 9 1353 4 1408 7 1447.1 1536 2 1596 9 1657.0 1787.0 1777.1 (635 80) s 01263 0 2916 0 4337 0 5621 0 68H 0.8091 1 3794 14578 1.5138 1.% 03 1.6014 1.6391 1 6743 1.7075 1.7389 e 0 0160 c.0165 0 0173 0 0184 0.0200 0 0230 0 1681 0 2293 0 7712 0.3068 0 3390 0 1692 0.3980 0 4259 0 4529 ' 2900 6 74 57 173 74 274 27 377 82 487.50 612 08 1176 7 1303 4 1346 7 1457.5 1522.9 1585 9 1647A,1709 2 1770 4 (664.11)s 0.1280 0 2910 0 4329 0 % 09 0 6815 0 8048 1.3076 1.4129 1.4766 1.5269 1.5703 14094 1.64 % 1.6796 1.7136 e 0 0160 0 0165 0 0172 0 0183 0 0200 0 0228 0 0982 0 1759 0 2161 0.2484 0.2770 0 3033 0 3282 0 3522 0.3753 3000 A 75 83 17t 68 275 22 378 47 487.52 610 08 1060 5 1267.0 1363.2 1440 2 15014 1574.8 16335 1701 4 17(1.8 (49L33) s 0 1277 0.29.4 0 4320 0 5597 0 6796 0 8009 1.3 % 6 1.3692 1.4429 1.4976 1.5434 1.5641 1.621' l.0561 1 6448 e 0 0160 0 0165 0 0172 0 0183 0 0199 0 0227 0.0335 0.1588 0 1987 02301 0 2576 0 2827 0.306% 0.3291 0.3510 3200 4 76 4 1753 2756 378 7 487.5 609 4 800 8 1250 9 1353 4 1433.1 15038 1570 3 1634A 16983 1761.2 005 C8) s C1276 0 2902 0 4317 0 5592 0 6768 0.7994 0 9708 1.3515 1.4300 1.4866 1.5335 1.5/49 1A126 1.6477 1.6806 e 0 0160 0 0154 0 0172 0 0183 0 0199 0 0225 0 0307 0.1364 0 1764 0 2066 0 2326 02%3 02784 0 2995 0 3198 3500 a 77.2 176 0 276 2 379I 487 6 6084 779 4 1724 6 1338 2 1422 2 1495 5 1%33 1629.2 1693 6 17b7.2 a 0.1274 0.2899 0 4312 0 5585 0 6777 0.7973 0 9508 1.3242 1.4112 1.4709 1.5194 1.5618 1.6002 1.635S 1.6691 e 0 0159 0 0164 0 0172 0 0182 0 0198 0 0223 0 0287 0 1052 0 1463 0 1712 0 1994 0 2210 0 2411 0.2601 0.2783 4000 4 7e.5 171.2 277 1 379 8 487.7 6065 763 0 1174.3 1311 6 1403 6 1481.3 1552 2 1619 8 1685.7 1750 4 s D1271 0 299.1 0.4304 05573 06760 0 7940 09M3 1.2754 1.3807 1.4461 1.4916 1.5417 1.5812 1.6177 1.8516 e O C159 0 0164 0 01?! 00181 0 01 % 0 0219 0 0268 0.0591 0 1038 0 1312 0 1529 0 1718 0 18*3 0 2050 0.2203 5000 4 Si l 179 5 279 I 381 2 488 1 604 6 746 0 1042 9 1752 9 13(4 6 1452 1 15291 16009 le10 0 1737.4 s 0.1765 0 2861 0 4261 0 5MO 0 6726 0 1880 0 9153 1.1593 1.3207 1.4001 1.4582 1.5061 1.f,481 1.5E 63 1A216 0 0159 0 0163 0 0170 C 0160 0 0195 0 0216 0 0256 0 0397 0 0757 0 1020 0 1221 0.1391 0 lM4 0 !684 0 1817 6000 4 83 7 181.7 281 0 362 7 #86 602 9 736 I 9451 1188 8 1323 6 1822 3 1505 9 1%20 16t4 2 1724 ? e 0 1258 0.2670 0 4271 0 H28 06693 0 7826,0 9026 10876 1.2615 1.35?4 1.4229 1.4743 1.5194 1 % 93 15 %.2 e 0 0158 0 0161 0 0110 0 0180 0 0193 0 0713 0 0248 0 03H 0 0573 0 03 t A 0 1004 0 1160 0 1296 0 1424 0.1542 7000 a 86 2 184 4 283 0 Sue 2 489 3 601 7 729 3 901 8 1124 9 1281 7 1392 2 1482 6 IM31 1639 6 171I I a 0 1252 0 2859 0 4256 0 5%C7 0 6163 0 7/77 0 8926 10h0 12055 1.3 D I 1 1904 14496 14938 153*$ l.5735 ~_ TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE) (CONTINUED) A.6

( I. ( h. g I IIITTIITIT1 i O O g o o e ITITITTITIl I v -, 0 m 1 O o O i O OO ('- l O nCoon o y 6 0" O' I

5.,

S

O'" O*O 0 0

'*L1t*-Ac*- f T T T.T T I T T T 1 1 ~-- K OO 0" O l 0 O l 0 0 c s 7 ^n n ",. -e I I I I I I-{ I.I I I l 1 .1 FIGURE 37 8 HEAT TRANSTER (HT) HODES OT 30! LING WATER ' oc-tur-uT-ta P'2-B-84

THERMO FOR NUC FWR PLT WRR ARE/pt(( N #/ff INANEI5FINY

OP-MC-SPS-RT-AK 50ptCab3r 20, 1984 RED /s) PCg2 21 of 24 0 I 4.0 RESPOIISE OF REACTOR TO REACTIVITY ADDITIOl65 i A. Step positive reactivity addition. I i l J b l .g i I 0 asyi. Q a{ 1 8 s4..p. Sm + p %w i o FIGURE 38 L se-e= -

p .I l E vi i = = 5 i ? I i 8 e i n s1 v I !Is G 3 2 e - = g-g l 3 E xdi :k:$:$[,,,,,,,,g'gii ' il ,is! I m ai,II; lli i iii I I i i i i ,llg!i:l" l $ l l l il i i l i i i li = = = s .ii aldi a v i asi I . h. 'I 9h. ll ,, 5 = n. et ~ 8 I 0-D ~ [}. I.* 0 % 01 +0-H8 gz 0- :: Dy 8 i i = v REVISION 2 l

2 I i -et s i s a B s s g i i = i a m li i 7 3 ! E g is l i W g i = a s i i ( +DE! l i E t n 5 3 n. ) in 9 9 5 di e q -[H 3 En " "l g ^. CHS -[Hf U 55l I n aan v i ~

l. ini

[11;l-l e 5 3 i lL l is i i 5 l lgl !E si"? l l l 11 i i i = = 8 8 3 11 j [ g ll ,,!I!!! 8 8 s 155 ~I f Ih 'I ~v l i ~ \\ cm C3 El g" i .a i. ei e n. a a I i -[Hta 4 -[Ht! -[H> 04 l CHl* [Ht' 0-J 0-$! -[Ht: + l 8 i i I A 1

1 iL s 1 N

l 9

7 3 2 W ) C EBI 6 J T. I l I C( E 1 II I T F O F6 A F ED D A E ET SU SS l 5 Y 2 RS 4 G 1 I A P S I I ER S R I LE N I A I CT R I C. I A C A A I R W S I I Y M T S I F A C E E I A l' e As e l 5" g A e ,h-7 y s , i a 4 E. s { I e F e l g E. A C e 'l 5, t / a A R y C T I i )I s > 2. E A I e 9x M I TRg 2I ?. A l v 2 E lA. I T e 6 y ~ > I I N Bg I I R' 'e 3 e iE e B 2 8 ePe S m. N 31 3 S tE ? oAe g E B M sI jt m 5 1 nNn,E S uB a S t B S A D I AG M A 5 A E S6CS i E I I S gCI 8a I I E 5 mI I C N E R s I bg2 l C/ B B vC S S Aa - B I I A sA A A L A U l A A l AmR i A - m l r t l a A A l u G I S I f o f B f l B I C S l T I I = f e f A ?Y E I U-o W W I a I S n B B E R F nS Fl S S D S s aA I e-S I S T =n CgC R S S S S ,~ ru rum e E S E S aa A, s A e pl tA I e W Pe E v 5 1 i u SN D l A o a. m M P nErCgA t W e I e W g e S C ,cs A I B gio S ASCC r R I CEE,erge A pSC i g E C R ~L l V EA M M El C S FS 2 I g 4 D M 5 A 1 3 S s 4 4 2 0 5 f ( t ) h h g 2l N e 2I O A P fR A l T TR m 1 T u 1 8 1 l A t 11 I h8 ~ e a f 2 ~ ~ A e S 4 e 2 3 ~ l ~ P r C W W R c SN S a p Is E f gI hN A il ,!ll!! ,ji 1 l' ilj ljd j;1

S e ~ 5 f E-r 8 b b i i"E 9 $ u s a n 8 i i f i I i l .2 + 2 8 2 a e 9 3iA 7 l ^ 0-1 3 ^m -(HE A "g g k, i!l i- .m g .cyg m aaa v S n l.II. 81 g gf' g ul I E l [ 1i i. i 2 i, -18 E2 l l 8 : 1 mn 1lll ini l l 1 il l i a

n. I s

a s <[l[aul,ag3-[v n I I g a u a v i ns I s T : [h I* .[H P a 5 a 5 5 M i! i! e = I

4. n.;s

.oe .m> .g .m .n, i E REVISION 2

i o i I i t f I \\ as l 1 9 i ll e 3 g a v-t =. y a gg 7 g ~ l sE I hE d l_ i 4 h 5l t ] j l { l m 5= ~ ~ E C K w J <3 x g a C w b l i \\ t I I s n,,.- -a a

O e M N m m 3 g 4 l3 ilt t 1 : 3 BI E e c 8 gI s a. - s_ = = sv ~ a i s E o-u gto. m = 1 I 3 'INE E ~ 3s b I s i aa.,la E g g w E I = = a. U s-1 gi 4 GI a% i-2 ( b t N I ~ =i g a e e i 13 I e e We l ~ t 2 E ~ 3 m E 'A U k M i.

s g"

g C m s 1 = a e 1 s \\!' .[ k s V l ii l 4I ll 85 MI 11

REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.4 All power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. ACTION: a. With one or more PORV(s) inoperable, within 1 hour either restore the PORV(s) to OPER.BLE status or close the associated block A valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the followir.g 30 hours. b. With one or more block valve (s) inoperable, within 1 hour either restore the block valve (s) to OPERABLE status or close the block valve (s) and remove power from the block valve (s) or close the PORV and remove power from its associated solenoid valve; otherwise, be in at least HOT STANOBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. c. The provisions of Specification 3.0.4 are not. applicable. SURVEILLANCE REQUIREMENTS 4.4.4.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demons *; rated OPERABLE at least once per 18 months by: a. Performance of a CHANNEL CALIBRATION, and b. Operating the valve through one complete cycle of full travel. 4.4.4.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with power removed in order to meet the requirements of ACTION a. in Specification 3.4.4. 4.4.4.3 The emergency power supply for the PORVs and block valves shall be demonstrated OPERABLE at least once per 18 months by: a. Manually transferring motive and control power from the normal to the emergency power supply, and b. Operating the valves through a complete cycle of full travel. FIGURE 142.1 McGUIRE - UNITS 1 and 2 3/4 4-10

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 30 ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 5.01 (1.50) a. increases due to decreasing Tave <c AN b. i- = " a e d= t-i t : r : : : i r., Tov = c. decreases due to decreasing Tave and increasing baron concentration (.4 directioni.1 reason) REFERENCE McGuire op-me-cth-cp pg 66 (aab) op-me-rt-rco pg 41 K/A 000-024-EK1.01/1.02 (3.4/3.833.6/3.9) ANSWER 5.02 (.75) The first reactivity addition was larger than the second.CO.753 REFERENCE McGuire op-me-sps-rt-sm pg 21 K/A 015-000-KS.05 (4.1/4.4). ANSWER 5.03 (2.00) 6. subcooled-hot les temperature E0.53 saturated-wide range pressure E0.53 b. To correct the differenti.al pressure measurement during elevated containment temperature conditions. [0.53 c. Voids have increased, level has decreased CO.53 l REFERENCE l McGuire op-me-sps-ic-rvi pg 7,8,17 l K/A 002-000-K6.03 (3.1/3.6) ANSWER 5.04 (1.00) ppm equivalant baron worth is the ratio pf Xenon concentration worth to average differential boron worth.CO.53.[If this baron equivalent plus present baron exceeds th( ppm determined for shutdown boron concentration, cdequate SDM exist.CO.53.Jec l l

e- -5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 31 ANSWERS -- MCGUIRE 182 -86/03/10-CASTO,C REFERENCE McGuire op-me-sps-rt-rb pg 17 K/A 004-000-K5.19 (3.5/3.9) ANSWER 5.05 (1.75) decreases: increases A TS wl N E 85 */MA decreasestincreases decreaseslincreases decreases (0.25 ea.) REFERENCE CCAF] K/A 000-015-EK 1.04 (2.9/3.1) ANSWER 5.06 (1.00) d. REFERENCE McGuire data book Sta. Dir. 3.1.2.6 sec. 1.3 K/A 001-sws-7 (3.6/4.1) ANSWER 5.07-(1.00) c. REFERENCE MNS'thermo sec 8 i i K/A 002-020-A4.02 (4.3/4.5) i I i l -,----------m v

5. THEORY OF NUCLEAR POWER-PLANT OPERATION, FLUIDSr AND PAGE 32 ANSWERS -- MCGUIRE 182 -86/03/10-CAST 0rC ANSWER 5.08 (1.00) c. REFERENCE McGuire core per. book K/A 004-000-A2.06 (4.2/4.3) ANSWER 5.09 (1.50)

c. false CO.5]

b. Reference les draining CO.53 Elevated reference les temperature CO.53 REFERENCE i

'McGuire op-me ps-ipe K/A 010-000-K6.06 (2.3/2.4) i ANSWER 5.10 (1.50) a. increasing

b. decreasins

c. decreasing E0.5 es.]

REFERENCE McGuire op-me-rt-rp ps 19,20 K/A 001-000-K5.41 (2.4/2.8). i L

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND Pact 33 ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 5.11 (1.50) c. Difference in normalized flux signals between the top and bottom halves of the core. (0.5) b. Fractional change in neutron population per generation OR fractional deviation from criticality. (0.5) c. The reactivity associated with going from HZP to HFP. (0.5) REFERENCE VCS, TS, p. 1-1 and Westinghouse Nuclear Training Operations, pp. I-3.2 and I-5.26 001/000-K5.53 (2.8/3.4) -K5.54 (2.8/3.1) -K5.49 (3.4/3.7) ANSWER 5.12 (1.00) There must be a complete flow path for circulation, a loss of subcooling could result in steam blockage in the RCS thereby causing an incomplete flow path from the heat source to the heat sink.C1.03. REFERENCE McGuire op-ga-sps-trif-ht pg 27,28 K/A 002-000-5.15 (4 2/4.6) I* ANSuER 5.13 (N -114 pcm (0.4) Tave 30.4 X O.25 X -15 = -300 pcm (0.4) Power: 25 X -12 = Void ; - 25 pcm Xenen: - 50 pcm Total -489 pcm (0.4) 54.3 ppm (52-56) (0.4) Boron: -489 / -9 = M /s/a/d .44,+F u...... REFERENCE Westinghouse Nuclear TraininS Operations, pp. I-5.27 - 5.36 001/000-KS.28 (3.5/3.8)

a 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS-AND PAGE 34 ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 5.14 (1.00) a REFERENCE NUS, Nuclear Energy Training - Reactor Operation, p. 9.2-5 ANSWER 5.15 (1.00) d REFERENCE McG, TS, P. B 2-4 ANSWER. 5.16-(1.00) C REFERENCE MNS TS p. B 2-4 K/A PNG 36 ANSWER 5.17 (2.00) a. 2 E1.03 b. 2 E1 03 REFERENCE McGuire Fund. of Rx Eng. Duke pg 269 K/A 001-010-K5.10 (2.9/3.6) ANSWER 5.10 (1.00) 1. convection EO.2 ea.] '2. nucleate bulk 3.-film

4. nucleate subcooled 5.

film

5. THEORY OF NUCLEAR POWER PLANT OPERATIOM, FLUIOS, AND PAGE 35 ANSWERS -- MCGUIRE id2 -86/03/10-CASTO,C REFERENCE McGuire oc-thf-ht-14 K/A 002-000-K5.01 (3.1/3.4) ANSWER -5.19 (3.00) a. In region I the power level rate of increase is starting to slow down due to the introduction of delayed neutrons E0.53 at first the short lived DNPs appear then the longer lived come in further slowing the rate of increase.CO.53

b. at the POAH E1.03 04 f ) T-c.

The rate of decrease in this area is dependent upon the decay of long lived DNPs and the rate of decrease i s c o n s t..a n t [1.03 REFERENCE McGuire op-me-sps-rt-rk pg 21 & 23 K/A 000-003-EK1.03 (3.5/3.8) 000-001-EK1.06 (4.0/4.2) 001 -000 -K5. 4 7 (2.9/3.4) ANSWER 5.20 (1.50) a. INNER (0.5) b. DUTER (0.5) c. INNER (0.5) REFERENCE NUS, Nuclear Energy Training - Plant Performance, pp. 10-1.8&9 McGuire op-me-ta pts 004/000-K5.09 (3.7/4.2) ANSWER 5.21 (1.00) cc

y. 2.v. o CM---

em_mm 4"- i t;ble icr+npa in s p+ei - both the production k{g{ pts). rate and removal rate are proportional to power level REFERENCE Westinghouse Nuclear Trinins Operations, p. I-5.77 McGuire op-me-rt-rco 001/000-K5.35 (2.1/2.3)

3 -5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 36 ANSWERS -- MCGUIRE 182 -86/03/10-CASTO,C ANSWER 5.22 (1.00) b REFERENCE General Physics, HTRFF MNS Thermo K/A 015-020-K5.11 (2.9/3.2) 015-000-A1.01 (3 5/3.8) t I l I i i s f i l ..n.....-..,,,, n-.-. _,.-.,_,.--.,-_._--.,,-.n.

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 37 ANSWERS -- MCGUIRE la2 -86/03/10-CASTO,C ANSWER 6.01 (2.00)

c. Located upsteam of the check valve E0.53 - suction overpressurination

- Pump steam binding C.25 ea.3 b. UST,CA cond. storage tk,Hotwell,NSW C.15 ea. listinsi.10 ea. Proper order] REFERENCE op-me-sps-sy-ca K/A 061-000-K1.01 (4.1/4.2) 061-000-K4.01 (3.9/4.2) 061-000-K1.05 (2.6/2.8) P

3 ANSWER 6.02 02r59)

C y 3 if s L L

c. D/G roum;CimsLitwoA roomeoattery roomecunLrul

.wum;.uo. md es.:ipment room CO.29 ea.] b. 208/120 v ac Eskss3;250/125v de E1DC3 CO.5 ea.3 c. Cheaters may be necessary 10 hrs following event to] insure steam bubble stays in pressurizer and not in reactor vessel [0.253 due to excessive cooldown [0.25] REFERENCE McGuire op-me-cp-ad K/A 000-068-EK 2.01 (3.9/4.0) EK 3.09 (3.9/4.4) EA 1.10 (3.7/3.9) l ANSWER 6.03 (1.50) a.1. will not E0.25 ea.] 2. will 3. will 4. will b. Prevent any other load groups from being applied CO.53 REFERENCE McGuire op-me-sps-el-eq a/b K/A 064-000-K4.02 (3.9/4.2) K4.10 (3.5/4.0) i

6. PLANT SYSTEhs DESIGN, CONTROL, AND INSTRUMENTATION PAGE 30 ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 6 04 (2.50) a. Blackout (0.53-~ higher NPSH from LLI CO.253 RV pumps have no power to.253 b. 53.3 CO.53 ti p$ td c# c. ' 9 iw puaition' Ceaf] E0 5J Y ' V# ofr ;t;-

t CO.5 M RdFERENCE MCGuire_op-me-sps-sy-rn K/A 076-000-K4.06 (2.8/3.2)

K1.19 (3.6/3.7) K6.03 (1.9/2.0) ANSWER 6.05 (1.00) c. REFERENCE MNS OP-MC-SYS-SP-NI K/A 000-068-EK3.10 (3.9/4.2) ANSWER 6.06 (1.00) c. REFERENCE MNS OP_MC_SPS_SY_KC p. 11 K/A 008-000-K1.02 (3.3/3.4) ANSWER-6.07 (1.00) b. REFERENCE MNS OP-MC-SPS-SY-NC pg 29 K/A 012-000-K4.02 (3.9/4.3)

1 = 1 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 39 ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C -c Y~/~I ANSWER 6.08 (2.50) O. Any three required [1.53 1. Battery charger to inverters to bus. PREFERRED SUPPLY

2.. p ' t t e r, te irfeete- ' - b :. Y-H e d e M 5! r A61-SC A435*f 3.

600VAC to standby battery charger to inverters to bus. _ a loceo power to 60u/1zu xrormer to rc r. e y i n i, u r i u Jr. t-d; "oD ^ [0.4 ea. with 0.3 for proper PREFERRED supply] b. No E0.43 Only one channel of B/S will trip E0.63. E1.03 REFERENCE MNS PSM Vol 2 MC-SYS-EPG MC-SYS-EPL-1 K/A 062-000-K4.09 (2.4/2.9) ANSWER 6.09 (2.00) a. Nitrogen from the cold les accumulators E0.53

b. 320 des F E0.53 c.

Operator selection EO.53

d. Normal PZR PORV's v"C lb Y ' /' I' E0.53 REFERENCE MNS SD NC-1223.03 p 11 K/A-010-000-K4.03 (3.8/4.1)

ANSWER 6.10 (1.00) c. REFERENCE MNS MC-IC-ILE-5 Component pressure transmitters (2.4/2.5)

L. 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 40 ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 6.11 (1.00)

a. Pulser

[0.53 b. Power Mismatch circuit CO.53 REFERENCE MNS OP-MC-SPS-IC-IRE K/A 001-000-K4.03 (3<5/3.8) ANSWER 6.12 (2.00) 1. sammarscintillation,close s/s blowdown Heat exchs. inlet and demin outlet

2. beta, scintillation and GM, close WG 160 3.

beta, scintillation, close air intake C.2ea], 0.2 e s.], C.2 ea3 radiation,

detector, action REFERENCE MNS MC-IC-RM-2 K/A 073-000-K1.01 (3.6/3.9)

K4.01 (4.0/4.3) K6.01 (2.2/2.4) ANSWER 6.13 (1.50) a. false CO.53 ~ b. false E0.5] c. false to.5] REFERENCE MNS OP-MC-SPS-IC-IPE K/A 012-000-K4.06 (3.2/3.5) _m. _ _ _ _,-,

6. PLANT SYSTEMS DESIGNr. CONTROL, AND INSTRUMENTATION PAGE 41 ~ ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 6.1 (2.00) re y / Ye ve/V# / *S //"% 4

c. right e - si==-

lina o r o c s i i tm CO.253 left s'de - manual loader output E0.253 b. Auto - steam pressure is controlleo to maintain setpoint Set Pt - changes output to maintain set pt in auto Man - output controlled manually E0.25ea.3 c.(4) (0.75) REFERENCE MNS OP-SPS-IC-IDE K/A 041-020-K6.03 (2.7/2.9) A4/03 (2.4/2.5) 035-010-A4.01 (3.7/3.6) l ANSWER 6.15 (1.00) b. l REFERENCE HNS OP-MC-CTH-CP K/A 012-000-K5.01 (3.3/3.8) C.Sd% ANSWER 6.16 +1 -dH>+ A ' "" ^ el [

a. St signal

.5},qt b. 1. deluge a ve press re

2. sprinkle alarm check valves 3.

manual lation valves

4. fire d, ors open E0.25 ea.]

REFERENCE MNS MCSD 0133-03 pg 2 K/A 006-000-A1.05 (2.9/3.1) A4.02 (3.5/3.5)

f 6. PLANT SYSTEMS CONTROL, AND INSTRUMENTATION PAGE 42 __________________' DESIGN, ANSWERS -- MCGUIRE 182 -86/03/10-CASTO,C ANSWER 6.17 (1.50) a. 1. would not 2. would not 3. would 4, would not E0.25 ea.] b. auto - runback load 2 200%/ min man - runback governor valves e 200%/ min E0.53 REFERENCE MNS MC-IC-DEH-13 K/A 045-000-K4.12 (3.3/3.6) ANSWER 6.18 (1.00) 3 - { con 1 power, undervoltase, underfrequency} (( y./

4 REFERENCE MNS OP-M PS-CM-NCP K/A 003- 00-A4.06 (2.9/2.9)

ANSWER 6.19 (1.00) h/ g /ls f ,J'

s. 100% pump speed or safety breaker open E^.25 m

.] b. false E0.53 REFERENCE MNS MC-CMP-NCP-12 K/A 003-000-K4.03 (2.9/3.4) ANSWER 6.20 (.50) kirk-key int clock to al ernate source br aker from 1LXF REFERENCE /' [' MNS MC-IC-ILE-4 K/A PZR PCS K2.01 (3.0/3.4)

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 43 ~~~~ A5i5E55iEAC E5ATRUE~~~~~~~~~~~~~~~~~~~~~~~~ R ANSWERS -- MCGUIRE 182 -86/03/10-CASTO,C -ANSWER 7.01 (1.00) c. REFERENCE MNS-OP/1/A/6100/01 pp. 1-2 K/A 059-SWG-7 (3.0/3.4) ANSWER 7.02 (1.00) c. REFERENCE MNS OP/1/A/6200/09 enc 4.4 ps 1 K/A 006-000-K4.16 (2.6/3.0) ANSWER 7~.03 (1.00) d. REFERENCE MNS EP/2/A/5000/01, foldout page K/A 003-000-A2.02 (3.7/3.9) ANSWER 7.04 (1.00) c. REFERENCE MNS EP/2/A/5000/10 p. 2 K/A PWG 22 (4.3/4.3) ANSWER '7.05 (1.00) b. REFERENCE MNS EP/2/A/5000/10 p.2 K/A PNG-22 (4.3/4.3)

= o 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 44 ~~~~ 5656E66 65L C6 TR6L'~~~~~~~~~~~~~~~~~~~~~~~ ~ R ANSWERS -- MCGUIRE 182 -86/03/10-CASTO,C ANSWER 7.06 (1.00) c. REFERENCE MNS HP MANUAL p.2.1.-3 K/A PWG 15 (3.4/3.9) 1 ANSWER 7.07 (1.00) a. REFERENCE MNS HP MANUAL 2.5.5 KA/ PNG 15 (3.4/3.9) ANSWER 7.08 (1.00) d. REFERENCE MNS AP/1/A/5500/38, p.2. K/A 004-010-A2.07 (3.8/3.9) 3 ANSWER 7 09 (2.00) 1. Reactor coolant temperature and baron concentration are beins maintained at the hot shutdown, xenon free condition. ~

2. The reactor coolant has been borated to the cold shutdown concentration and the plant is beins cooled down.

fW Ylh b"' Yb YU S Wf [1.0 ea.3 REFERENCE HNS OP/0/A/6100/08, p. 28 K/A 004-010-A2.02 (3.8/3.9)

7. PROCEDURES - NORMAL, ADNORMAL, EMERGENCY AND PAGE 45 ~~~~ A5i6E55fEAE E5ATRUE~~~~~~~~~~~~~~~~~~~~~~~~ R ANSWERS.-- MCGUIRE 182 -86/03/10-CAST 0rC ANSWER 7.10 (1.00) Pressurizer level below 5% - SI Pressurizer pressure approaching 1945 psis - reactor trip REFERENCE MNS AP/1/A/5500/10 p. 8 K/A 013-000-A4.03 (4.5/4.7) ANSWER 7.11 (1.00) a. 3 -- 5 Eminutes] E0.53

b. TRUE E0.5]

REFERENCE MNS AP/1/A/5500/38 p. 4 K/A 000-024-EA2.06 (3.6/3.7) 000-024-EK3.02 (4.2/4.4) i ANSWER 7.12 (1.00) b. REFERENCE MNS AP/1/A/5500/12 p. 2 K/A 004-000-A2.07 (3.4/3.7) ANSWER 7.13 (1.00) d. REFERENCE MNS OP/1/A/6150/02A p. 3 K/A 003-000-A4.07 (2.6/2.6)

~ l 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 46 ~~~~ 5656LUUE6 L"66UTR6L R ANSWERS -- MCGUIRE 182 -86/03/10-CASTO,C ANSWER 7.14 (1.00) b. REFERENCE MNS OP/1/A/6250/01 p. 1 K/A 059-000-A4.11 (3.1/3.3) ANSWER 7.15 (1.00) d. REFERENCE MNS AP/1A/5500/14 K/A 000-005-SWG-11 (4.4/4.3) ANSWER 7.16 (1.00) Indicates a failure in the secondary pressure boundary,CO.51 S/G steam pressure der eerir;3 ir e 'mee W -1' .a. WG w, tkpr-e+sr>me d CO.25 ea.3 tt /. 4 REFERENCE Westinghouse Users Guide 6689B;1 p. 7 K/A 000-038-EA2.02 (4.5/4.8) ANSWER 7.17 (1.00) Open any pump breakers closed in on bus Turn on D/G synchroscope Manually close 1 ETA Emergency Breaker Load bus per enclosure (sequence) REFERENCE MNS AP/1/A/5500-07 p. 2 K/A 000-056-SWG-11 (4.5/4.6)

+ e 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 47 ~~~~~~~~~~~~~~~~~~~~~~~~ ~~~~ 5656E65565L"66 TR6L R ANSWERS -- MCGUIRE 1a2 -86/03/10-CAST 0rC ' ANSWER 7.18 (1.00) e d 'l ps) /m/ le d s'n e n w Low vacuum pre-trip alarm Main generator load decreasing Loss of condensate flow Exhaust hood high temperature alarm Loss of RC pumps / flow lkfM <A to 00.5 ea./33 p%e,LA Yt#f LT 4 REFERENCE MNS AP/1/A/5500/23 K/A 000-051-SWG-10 (3.6/3.9) ANSWER 7.19 (1.00) 3 minutes CO.53 to allow the hydraulic / nitrogen emergency blow cccumulator to recharge CO.53 REFERENCE MNS OP/1/A/6250/01 p. 2 K/A 059-000-A4.11 (3.1/3.3) ANSWER 7.20 (.50) Open the Reactor Trip Breakers REFERENCE MNS OP/1/A/6100/01 p. 13 K/A 014-000-SWG-11 (3.9/4.2) ANSWER 7.21 (1.00) Break vacuum CO.253 limit system flow Eto 1400 spm3 CO.253 to provide minimum NPSH CO.53 REFERENCE MNS OP/1/A/6250/02 .K/A 061-000-SWG-7 (3.6/4.1) c_

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 48 ~ ~~~~~~~~~~~~~~~~~~ ~~~~~ ~~~~ 5656L66565L 66UTR6L R ANSWERS -- MCGUIRE 1&2 -86/03/10-CAST 0rC ANSWER 7.22 (1.00) .B' REFERENCE .Westinshouse ERG guideline manual K/A PNG 22 (4.3/4.3) ANSWER 7.23 (1.00) Next step /substep left-hand column REFERENCE Westinghouse ERG manual-K/A PNG-22 (4.3/4.3) ANSWER 7.24 (1.00) c. REFERENCE MNS EP/1/A/5000/12.1 p. 2 K/A 000-074-EK3.11 (4.0/4.4) ANSWER 7.25 (2.00) Stop both DEH pumps Place turbine in manual and close GVs fast Locally trip turbine Close all S/G steam isolation valves W ? Trif ferrhekL Cs y. t. is REFf5ENCE 7 MNS EP/1/A/5000/11.1 p. 2 K/A 000-029-EA1 13 (4.1/3.9) , _ _w +. ..--,--mm

o 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 49 ~~~~ 56EUEU55EEE~EUUTRUE------------------------ R ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO.C ANSWER 7.26 (1.00) c REFERENCE VCS, E0P-12.0, p. 4 Westinghouse ERG manual K/A PWG-22 (4.3/4.3) ANSWER 7.27 (1.50)

a. NO b.

YES

c. YES REFERENCE MNS EP/1/A/5000/10 enc's K/A PWG-22/10 (4.3/4.3)/(4.1/4.5)

ANSWER 7.28 (1.00) Stop fuel movement and take corrective action REFERENCE MNS OP/0/A/6550/04 p. 5 K/A 034-000-A1.01 (2.4/3.2) SWG-7 (2.9/3.7) SWG-11 (2.0/4.1)

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 50 ANSWERS -- MCGUIRE 182 -86/03/10-CASTO,C ANSWER 8.01 (1.00) b. REFERENCE MNS T.S. Bases 3.4.3.4 K/A 045-050-SWG-4 (2.9/3.1) ANSWER 8.02 (1.00) c. REFERENCE MNS 3/4.7.10.1 T.S. K/A 086-000-SWG-36 (2.8/3.7) ANSWER 8.03 (1.00) c. REFERENCE MNS T.S. 3/4.3.3 K/A 073-000-SWG-5 (3.0/3.8) 8 (3.3/4.2) ANSWER 8.04 (1.00) b. REFERENCE MNS T.S. 4.0.2 K/A PNG-8 (3.5/4.5) ANSWER 8.05. (1.00) c. REFERENCE MNS OMP 1-2 p. 2 K/A PNG-21 (3.8/4.1) s -,c

s 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 51 ANSWERS -- MCGUIRE 182 -86/03/10-CAST 0rC ANSWER 8.06 (1.00) a. REFERENCE 'MNS OMP 1-5 P. 5 K/A PWG-7 (3.5/4.0) ANSWER 8.07 (1.00) c. REFERENCE MNS OMP 9-4 p. 3 K/A PWG-26 (3.3/3.6) A SWER 8.08 (1.00) g, tu Y o / Y' REFERENCE MNS Sta.'Dir. 3.8.1 K/A PWG-30 (3.5/4.5) ANSWER 8.09 (1.00) 4"'~* b. REFERENCE MNS Sta. Dir. 4.4.2.

p. 3 K/A PWG-7 (3.5/4.0)

ANSWER 8.10 (1.50)

1. control copy 2.

master copy

3. verified working copy E0.25 ea.]

4 REFERENCE MNS OMP 1-2 p. 3 K/A PWG-21 (3.8/4.1) 1 k

-3 o 8o ADMINISTRATIV

E. PROCEDURE

S, CONDITIONS, AND LIMITATIONS PAGE 52 ANSWERS -- MCGUIRE la2 -86/03/10-CASTO,C ANSWER 8.11 (1.00) A Supervisor that holds an SRO license must make the decision [0.53 The initials of the Supervisor documented.on the working copy beside the N/A. [0.53 REFERENCE HNS OMP 1-2 p. 7 K/A PNG-22 (4.3/4.3) ANSWER 8.12 (1.00) The individual must hold a current license on the applicable unit, [0.53 or has been qualified in accordance with the Non-NRC licensed personnel training pro 3 ram.[0.53 REFERENCE MNS 0MP 1-6 p. 4 K/A PWG 22 (4.3/4.3) ANSWER 8.13 (1.00) Both Tech Spec and Non-Tech Spec items are turned over to the next shift. [0.53 In addition, Tech Spec items the SS/US shall notify the Duty Engineer secg,fk}/4_ m i t-c o orc / w)-.A [0.53 REFERENCE /4/ pm / 2 I MNS OMP 2-1 p. 3 g,)L K/A PWG-1 (3.5.3.9) ANSWER 8.14 (1.00) Reviews the US Logbook for at least the last 7 days REFERENCE MNS OMP 2-2 Att. la p. 4 K/A 23 (2.8/3.5)

3 g e . x= 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 53 r.-------------------------------------------------- ANSWERS 1-- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 8.15 (2.00)

c. They are Hi-lited b.

1. initial the entry acknowledgins out of service equipment as inop.

2. evaluation of the entry for Tech Spec conditions.

3. discuss potential problems with Control Room SRO.

REFERENCE MNS OMP-2-5 p.p. 6,8 K/A PWG 23 (2.8/3.5) ANSWER 8.16 (.50) TRUE. REFERENC$ MNS-0MP 2-7 p. 4 K/A PWG 23 (2.8/3.5) ANSWER 8.17 (1.00) The' authority to notify and make protective action recommendations to offsite authorities. REFERENCE-HNS Sta. Dir.'3.0.2 p. 2 K/A PNG-36 (2.9/4.7) ANSWER 8.18 (.50) Trip the Reactor (s) REFERENCE MNS RP/0/A/5700/07 K/ A PWG-36( 2. 9/4. / ) -11 (4.3/4.4)

? l. l 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 54 ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 8.19 (1.00) 1. Water level of <= 92%

2. Two groups of pressurizer heaters each having a capacity of at least

-150KW. REFERENCE MNS T.S. 3/4.4.B 3/4.4-9 K/A 000-008-EPE-5 (3.0/4.0) 010-000-SWG-5 (2.9/4.1) ANSWER 8.20 (1.00) d. REFERENCE MNS T.S. 3.4.4.4 K/A 010-000-SWG-5 (2.9/4.1) ANSWER 8.21 (1.00) 30 REFERENCE MNS Sta. Dir. 3.8.1 p. 4 K/A PWG-36 (2.9/4.1) ANSWER 8.22 (1.50)

c. false b.

false c. true REFERENCE MNS H.P. Manual 2.1 p. 2/section 4.4/section 2.5.4.2 K/A PNG-16 (2.9/3.5)

1 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 55 ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C ANSWER 8.23 (1.00) b. -REFERENCE MNS T.S. def. K/A PWG 5 (2.9/3.9) ANSWER 8.24 (1.50). 1. yes

2. yes

3. no REFERENCE MNS OMP 2-4 p. 7 K/A PNG-3 (2.8/3.8)

ANSWER 8.25 (1.50)

1. Isolation valve open

2. Water filled accumulator [containing minmum of l1850 cu fu of) borated water having a concentration hf between 1900 and 2100 p of baron and

3. N2 accumulator pressurized [o between 1206 and 1264 psi REFERENCE MNS T.S. 3.5.1.2 K/A 006-SWG-5 (3.2/4.3)

ANSWER 8.26 (1.00) c. REFERENCE MNS T.S. 3.4.1.3 K/A 001-050-SWG-5 (2.9/4.3) t 1 1 I

8. ' ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 56 ANSWERS -- MCGUIRE 1&2 -86/03/10-CASTO,C \\ ANSWER 8.27 (1.00) d. REFERENCE MNS T.S. 3/4.2.5. K/A PWG-5 (2.9/3.9) ANSWER 8.28 (1.00) o.1-4 b. 10 REFERENCE MNS OMP 1-7 p. 4 K/A PNG 23 (2.8/3.5) 1 l A t - - - -.}}

ML20211B244

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E. PROCEDURE

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ML20211B244

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E. PROCEDURE

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