ML20196A076

Exam Rept 50-254/OL-87-02 on 871207-11.Exam Results:All Six Senior Reactor Operator & Seven Reactor Operator Candidates Passed

ML20196A076
Person / Time
Site:	Quad Cities
Issue date:	01/25/1988
From:	Burdick T, Dave Hills, Mcghee J, Nejfelt G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20196A074	List: ML20196A070 ML20196A076
References
50-254-OL-87-02, 50-254-OL-87-2, NUDOCS 8802040246
Download: ML20196A076 (86)

Text

{{#Wiki_filter:/ U.S. NUCLEAR REGULATORY COMMISSION REGION III Report-No. 50-254/0L-87-02 Docket Nos. 50-254; 50-265 Licenses No. DPR-29; OPR-30 Licensee: Comr nwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Quad Cities Nuclear Power Station Examination Administered At: Quad Cities Nuclear Power Station Examination Conducted: December 7-11, 1987 Examiners: G.M. Nejfelt , Ah / Jf Datie / D.E. Hills [ //2f/88 / Date )f M d /[z3 7 J.M. McGhee 2% / Date Ma# / KY Approved By: T.M. Burdick, Chief Operator Licensing Section Date' Examination Summary Examination Administered on December 7-11, 1987 (Report No. 50-254/0L-87-02): Written examinations were administered to s.x (6) Senior Reactor Operator (SRO) candidates and seven (7) SR0 candidates were given oral examinations. Results: All candidates passed. $h D V

i DETAILS 1. Examiners . G.M. Nejfelt, Chief Examiner D.E. Hills J.M. McGhee 2. Exit Meeting At the conclusion of the site visit, the examiners met with facility representatives. The following personnel attended tnis exit meeting: Facility Representatives R.L. Bax, Station Manager R. Robey, Services Superintendent J. Neal, Training Supervisor N.P. Digrindakis, Regulator Assurance Group Leader C. Norton, Quality Assurance Engineer NRC Representatives G.M. Nejfelt, Operating Licensing Examiner A.D. Morrongiello, Resident Inspector The following items were discussed during the exit meeting-a. No generic training weaknesses or strengths were observed during the operating examinations. (This comment was further substantiated upon review of examination results in NRC Regional Offices.) b. Security and radiological accesses for examiners to the plant did not result in any undue delays. c. Status of the suspension of NRC Requalification Examinations was discussed. d. Active versus inactive license status in accordance with 10 CFR 55 as it applies to a Senior Reactor Operator Limited to Fuel Handling License was discussed. 3. Examination Review Responses to licensee's comments, and other changes made to the December 7, 1987 examination are provided respectively in Attachment 1 and Attachment 2. Discrepancies identified during the oral portion of the examinations between training lesson plans and plant procedures are provided in Attachment 3.

ATTACHMENT 1 RESPONSE TO QUAD CITIES NUCLEAR POWER STATION COMMENTS CONCERNING QUESTIONS AND ANSWERS OF THE NRC ADMINISTERED SENIOR REACTOR OPERATOR LICENSE EXAMINATION OF DECEMBER 7, 1987. 5.07 Facility Comment: The required answer does not include the pellet cracking and swelling that are the bases for LHGR [ Linear Heat Generation Rate] limits. This would would be an appropriate response to the question and should also be accepted for full credit. Reference - HTFF Chapter 9, Page 45, Paragraph 1. - HTFF Chapter 9, Page 22, Paragraph 1. NRC Resolution: Comment is accepted, as an alternate answer for the changes in pellet geometry. The answer key point is revised to read: "a. Fuel pellets have a tendency to increase in density [0.5]. b. The change in density causes the pellet geometry to: decrease in the pellet length and a decrease in the pellet diameter [0.75] OR crack [0.37] and swell [0.38]." 5.09.6 Facility Comment: Answer "b" only discusses axial flux shaping. Another acceptable answer should be "Radial flux shaping" or "flux shaping" alone which accounts for both axial and radial shaping. Reference - Reactor Theory lesson plan Page 25. NRC Resolution: Comment is partially accepted. The reference used does not substantiate that the gadolina rods are used for radial flux shaping. Furthermore, the reference stated that the "... deep rods locations set the desired radial power shape...." 2

However, since "flux shaping" infers both radial and axial directions, partial credit will be given for "flux shaping." The answer key' point value is revised to read: " b. Facilitate axial [0.25] flux shape or power shape control [0.25] (limits flux peaking problems and simultaneously simplifies control rod patterns)." General Comment Concerning Section 6 Facility Comment: The use of general operating procedures and abnormal operating procedures for this section of the exam was felt to be an unusual practice. It required the examinee to memorize facts in these procedures when this information would be readily available during plant operation. This line of questioning also made the questions more integrated plant response questions instead of ones that dealt with the design, control or instrumentation of a plant system. NRC Resolution: None of the facility comments pertaining to Section 6 questions substantiated that candidates were required to memorize any procedure. The references made in Section 6 questions to procedures were provided to aid candidates to associate questions concerning design intent, construction, operation, and interrelationships with normal nuclear power plant operation and reactor safety. Reference - NUREG 1021, ES-402.A.2, Revision 4. NOTE: The average grade for Section 6 was approximately 86.7%. 6.01.a Facility Comment: The required answer to this question could be considered incorrect. By adhering to the referenced procedure, the correct answer would be true but in reality an additional trip of the RCIC [ Reactor Core Isolation Cooling] turbine is still active. This trip is the "local manual" trip. If this trip was considered by the examinee, the correct response would be false. Either answer should be acceptable. 3

Reference - RCIC Pages 13, 16. r Reference - Procedure Change Request to add this trip to the stated procedure. NRC Resolution: Question 6.01, Part a, is deleted. The question total point value is reduced from 1.50 points to 1.00 point. 6.02.a Facility Comment: This question should be deleted because it is misleading and confusing. The question infers that the fluid is flow of the shutdown cooling flow path when it really is referring to a small flow path to an auxiliary heat exchanger on the pump oil cooler. The question infers that increased RHR [ Residual Heat Removal] service water is required as pressure is reduced in the shutdown cooling mode of RHR. In fact, RHR service water is always on during shutdown cooling and there is always flow to this heat exchanger. This flow can never be increased since it is always valved in. It is impossible to answer the question as stated. NRC Resolution: Comment is not accepted. This question did not infer that the fluid flow is in the shutdown cooling flow path. Also, the "additional" cooling by RHR service water was the consequence of following the procedure for SHUTDOWN COOLING START-UP AND OPERATION, QOP 1000-5, Section F.2, Revision 13. This question came directly from Quad Cities Lesson Plan, LIC-1000, RHR, Revision 2, page 8. 6.03.a Facility Comment: Answer "a" should not require "mode switch in refuel" for full credit. This is not specified in Tech Specs [ Technical Specifications]. Reference - Tech Spec Page 3.10/4.10-2. NRC Resolution: Comment is accepted, because it is consistent with the exact wording used in Technical Specification (TS) 3.10.A.1.a. The answer key point value for Question 6.03, Part a, is reassigned as: i 4

"With any control rod out [0.17] and fuel on any refueling hoist [0.17] and refueling platform near or over the vessel [0.16]." NOTES: (1). TS 3.10. A for both Unit 1 and Unit 2 requires that "The reactor mode switch shall be locked in the Refuel position during core alterations, and the refueling interlocks listed below [e.g., Refueling Platform Hoist Upward Travel Blocks] shall be operable...." (2). QFP 100-1, MASTER REFUELING PROCEDURE, Section E.1.b(3), Revision 13, Page 4, specifically states that the mode switch is in "Refuel" for the Refueling Platform Hoist Upward Travel Blocks. 6.04.a Facility Comment: Answer should allow for similar wording responses such as "oscillations" or "instabilities." NRC Resolution: Comment is accepted. Also, other synonyms will be given full credit. Part "a" of the answer key is revised to read: "a. Vibration or Oscillations or Instabilities [0.50]." 6.06 Facility Comment: The question is confusing in that it asks for a relation between Unit 2 being at power and the electrical lineup of a Unit 1 switchgear. Each is independent of each other. If Unit 2 is at power Unit One may or may not be, and it is Unit One's condition that determines the loading of transformer T-12. With Unit One at power T-12 carries buses 12 and 13. With Unit One shutdown, T-12 carries buses 11, 12, 13, and 14. NRC Resolution: Comment is accepted. Because the question did not state, l if Unit I was or was not at power, the answer key is i revised to read: i "Any two of the following buses: 11, 12, 13, and/or 14. [0.50 point for esch bus]." l 5

Reference - QOP 6100-5, REMOVING RESERVE AUXILIARY TRANSFORMER 12(22) FROM SERVICE WITH UNIT 1(2) SHUTDOWN, Section C.3, Revision 3. 6.08 Facility Comment: Answer "a" is incorrect. The correct answer is HPCI [High Pressure Coolant Injection] WILL AUTO INJECT. There is no HPCI trip on low vacuum. The adverse affect would be gland steam and valve leak-off steam would cause the room to become airborne. Another adverse affect would be the room temperature rising to the isolation / trip setpoint. Either of these effects should 'ae acceptable for full credit. Reference - HPCI page 13. Reference - HPCI page 31/32. Answer "b" is correct, but for the wrong reason. The lack of high pressure oil will prevent the stop and control valves from opening. If the turbine could start, which it cannot, the omergency oil pump would provide adequate lubrication. Reference - HPCI Page 8. Reference - HPCI Page 9. Reference - HPCI Pages 4 and 5, Section d and e. Answer "c" - Another adverse affect that should be accepted for full credit would be reduced system flow to the reactor since a portion of the flow is diverted to the torus. Answer "d" is incorrect. The correct answer is HPCI WILL NOT INJECT. The motor Gear Unit (MGU) will hold the turbine to 2000 RPM by running and staying on the Low Speed Stoo (LSS). Insufficient discharge head will prevent iiijection to the reactor. Reference - HPCI Page 12. 6

NRC Resolution: All comments are accepted. The answer key is revised to read: "a. (1). WILL AUTO INJECT. (2). Gland seal condenser will be unable to maintain a vacuum (because non-condensable gases would not be removed to maintain -10 inches of water). b. (1). WILL NOT AUTO INJECT. (2). The lack of high pressure oil will prevent the stop and control valves from opening, c. (1). WILL NOT AUTO INJECT. (2). It would be possible to drain the CCST into the torus OR It could be possible to reduce system flow to the

reactor, d.

(1). WILL NOT AUTO INJECT. (2). The desired system flow would be unable to be achieved (to accommodate varying reactor pressures. At operating pressure, the HPCI discharge head would be insufficient to inject, because the motor gear unit (MGU) would hold the turbine speed to 2,000 RPM by running and staying at the low speed stop (LSS)). [0.50 point for each item]. (Correct alternate answers will be accepted)." 6.09 Facility Comment: The question implies a required action to be performed and misleads the examinee to produce actions for the question when by the referenced procedure NO ACTIONS ARE REQUIRED. This question should be deleted. Reference - 00A 8650-1. NRC Resolution: Comment is not accepted. The question asked for the "effect(s)" and not for any action to be performed. 7

6.11.a Facility Coment: Answer "a" is incorrect. The correct answer is TRUE. The ACAD [ Atmospheric Containment Atmosphere Dilution] System is placed into operation manually when predetermined plant conditions exist. It does not start automatically. Reference - QOP C500-1. NRC Resolution: Comment is accepted. The question did not specifically refer to the ACAD Containment Atmosphere Monitoring (CAM) Subsystem that would be automatically initiated upon a Core Spray (CS) initiation signal, as stated in Q0P 2400-1, Section F.2.a, Revision 7. The answer key is revised to read: "a. True" 6.13 Facility Comment: Answer "a" infers that the APRM [ Average Power Range Monitor] 15% scram is not valid when the mode switch is in "Shutdown." A better answer would be ".. 15% when not in the RUN mode." Answer "a" and "b" weight the response "high flux" heavily. Since APRMs are flux detectors, this can be assumed and should not be required in the answer for full credit. I NRC Resolution: Comments are accepted. Parts a and b for Question 6.13 is revised to read: "a. APRM (fixed high flux) less than equal to 15% rated neutron flux [0.25] in REFUEL Mode or STARTUP HOT STANDBY Mode or 60 when not in RUN Mode. [0.25].' b. APRM (variable high flux) less than equal to '0.58 W + 62' (FRP/MFLPD) [0.25] in RUN Mode [0.25] (maximum set point of 120% for core flow of greater than equal to 98E+6 lbm/hr)." NOTE: The inference that the APRM 15% scram is not valid in the SHUTDOWN position of the mode selector switch is based on the exact wording used in Q0P 700-4, Section l E.2.a Revision 5, which reads: 8

4 APRM high flux 15% of rated neutron flux when in REFUEL or STARTUP HOT STANDBY Mode. (TS)." 6.14.a Facility Coment: Answer."a" is incorrect. The correct answer is OPEN. The system lesson plan is incorrect in stating the valve is normally shut. The procedure for normal Core Spray Standby Operation has this valve open. Reference - Q0P 1400-1, Page 2. NRC Resolution: Comment is accepted. Part "a" of Question 6.14 is deleted, because of the conflict in position of the core spray minimum bypass flow valve (M0-1402-38A/B) between the System Lesson Plan, CORE SPRAY SYSTEM, LIC-1400, Revision 1, and procedure QOP 1400-1, Revision 4. The total point value for Question 6.14 is reduced from 1.50 points to 1.00 point. 6.15 l Facility Comment: In answer "b", the time delay shoeld not be required for full credit since it is not considered a part of the setpoint. At Quad Cities Station, the setpoint is considered simply 300% steam flow. Reference - Tech Specs Page 3.2/4.2-8. NRC Resolution: Comment is accepted. However, to be consistent with coment provided, Q0P 1300-2, Section E.1, Revision 6, needs to be revised. The answer key "b" is revised; and the question point values are redistributed to read: "a. RCICturbinearea[0.15]hightemperature[0.15]; and 200 +/- 5 degrees F [0.20]. b. RCIC Steam Line high flow [0.30]; and 300% of rated steam flow [0.20] (with a turbine delay of 3 seconds). c. Reactor vessel low pressure [0.30]; and 50 +/- 2 psig[0.20]." l 9 L

4 - 6'.16 Facility Comment: The fact that the opposite gas treatment train is started requires the use of a cross connect line. This could be assumed and should not be required for full credit. P NRC Resolution: Comment is accepted. The answer is revised to read: "Start the opposite train and draw air through the affected train [0.75] from the turbine building [0.50] (via the train cross connect)." 6.17 Facility Comment: At Quad Cities Station, the ECCS [ Emergency Core Cooling System] fill system is also referred to as the "Jockey fill" or "keep fill" or "Maintenance fill" system. Any of these answers should also be considered carrect. NRC Resolution: Comment is accepted. The answer key is revised to read: "... the ECCS Fill System (other acceptable names are: Jockey Fill, Keep Fill, or Maintenance Fill System)." 7.01 Facility Comment: This question should be deleted for the following reasons: a. The stated panel and alarm are physically located in the HRSS building. i b. A Radiation Protection Technician (RCT) would respond to this alarm, not an

operator, c.

Operators do not have access to this building since it is locked at all times. NRC Resolution: Comment is accepted. The Question point value of 1.50 points was deleted. L I i 10

1, 7.03 Facility Comment: This question is oath confusing and misleading because of the introductory statement describing a lighting strike. It is not clear if an actual toxic gas condition exists. Based on these considerations, any three immediate operator actions listed in the referenced procedure should be acceptable for full credit. Additionally, since step 6 of the referenced procedure, which is where the list answer originates, directs the operator to follow Q0A-010-5 (Control Room Inaccessible). Any three immediate operator actions from this procedure [Q0A 010-5] should be considered a correct response for full credit. Reference - QOA 5750-13. Reference - QOA 010-5. NRC Resolution: Comment is partially accepted. The question clearly sought the actions to be taken, "... if occupation of the control room is no longer possible." Only those actions of Q0A 010-5 that are specifically performed in the control room prior to its evacuation are added to the answer key. Question 7.03 Answer Key is revised to read: Remove breathing air mask. Isolate air line manifold supply valve. Don an air pack. Evacuate control room (CR) to shutdown /cooldown the unit. Announce on the public address system that the CR is being evacuated. Manually scram the reactor, if possible. Leave Feedwater System in automatic on the low flow bypass valve, if possible. Notify the Chicago load Dispatcher, if possible. [Any 3 of 8 required with each worth 0.50 point]." 7.05 Facility Comment: Answer "a" is correct, but other similar intent responses should be accepted. 11 i

Answer "b-2" is correct but other similar intent wording, such as "adequate steam cooling" or "adequate core cooling" 'should be acceptable. NRC Resolution: Comments are accepted. Similar wording is acceptable. No change to answer key is warranted. 7.07 Facility Comment: Another procedure could be used for the condition stated in the question. Any immediate actions required in "Reactivity Addition" procedure under the loss of feedwater heaters should be added to the list of acceptable responses. Reference - Q0A 400-1. NRC Resolution: Comment is not accepted. The Question specially requested "... five (5) Immediate Operator Actions using Q0A 3500-1, LOSS OF FEEDWATER HEATERS." 7.08 Facility Comment: This question asks for an answer for which there is no procedure or guideline and should be deleted from the exam. The question misleads the examinee to define an operable accumulator. Tech Specs, which is referenced in the question, states that if certain actions are taken, the accumulator need not be considered inoperable. This is very different than operable. Reference - QOP 300-10. NRC Resolution: Comment is not accepted. The answer key is taken directly from QOP 300-10, CRD SYSTEM ACCUMULATOR GAS DISCHARGING, Section E.2, Revision 4; and is based upon required Technical Specifications knowledge. 7.09 Facility Comment: The question implies that a reactor trip is required for varying conductivities in the stator cooling system. The answer key values of time are correct for the generator trip but not a reactor trip. It must be noted that the referenced procedure, Q0A 5300-1, refers to a unit trip. In this context the unit is the main generator and not the reactor. 12

s, NRC Resolution: Comment is accepted. Full credit will be give if reference is either made to a unit or to a turbine trip with the appropriate time limitations. 7.10 Facility Comment: A description of the Iodine Spiking Phenomenon or stating that iodine will increase should be acceptable for full credit. NRC Resolution: Comment is accepted. Also, other similar wording would be acceptable. No change to answer key is warranted. 7.11 Facility Comment: Answer "a" is incorrect. The correct answer is MORE THAN. Unit 1 MAPLHGR would change to 70% of its original value while Unit 2 will change 84%. Answer "c" is incorrect. Regarding Rod Block Monitor (RBM) rod blocks, U-1 will be LESS THAN U-2.as stated in the answer. The question simply asks for "rod blocks" which could also mean APRM rod blocks. U-1 APRM rod blocks WILL BE THE SAME as U-2 APRM rod blocks. Both the SAME or LESS THAN responses should receive full credit. Reference - Q0A 202-4, Pages 1, 2, and 3. NRC Resolution: The comment first part is accepted. The answer key is revised to read: "a. MORE THAN. (Unit 1 factor is 0.70; and Unit 2 factor is 0.84)." The comment second part is accepted, because it was not specified in the Question that only the APRM rod block set points were desired. The answer key is revised to read: "c. SAME AS or LESS THAN. (Unit ; and Unit 2 APRM set points are reduced by 3.5%; and Unit 1 RBM rod block set points are reduced by 3.5%, while the Unit 2 RBM rod block set points are reduced by 4.0%)." 7.12 Facility Comment: This question asks why condenser level is limited BELOW 35% level and references an operating procedure. The reference procedurt. infers but never states structural damage will occur at or above 35% as the answer key 13

s, states. Either the fact that circ [ circulating water] pumps are running or structural damage may occur should be acceptable.for full credit. Reference - QOP 201-1, Page 3. NRC Resolution: Comment is accepted. The answer key is revised to read: "Structural damage may occur to the condenser (if level is exceeded and additional structural support is not installed) OR circulation water pumps are running. [1.00]" NOTES: (1). The Caution Statement of QOP 201-2, Section F.2.a, Revision 4, is quoted as: "Do not exceed 35% on the wide range monitor while circulating water pumps are running. Structural damage may occur to the condenser if this level is exceeded and additional structural support is not installed." (2). It is unclear in the caution statement provided in NOTE (1) above, if the circulation pumps are needed-to be running to cause structural damage above a main condenser level of 35%. Because of this ambiguity, 'i credit is' allowed for the alternate answer provided. 7.13 Facility Comment: The answer key is wrong in saying drive water does not cool.... Drive water DOES supply cooling header. WRC Resolution: Comment is accepted. The answer key is revised to read: "Electrical disarm is preferred because drive water cools [0.5] and it minimizes crud accumulation in the drive [0.5]." 7.15 Facility Comment: Answer "b" should allow for alternate, similar wording I responses such as fouling or plugging. NRC Resolution: Comment is accepted. Similar wording for response is acceptable. The answer key is revised to read: "b. biofouling (other possible answers are ' fouling' and ' plugging')." 14

s, 8.13 Facility Comment: In addition to the actions specified in the answer key, other similar actions are specified in QAP 300-27. These SCRE [ Shift Control Room Engineer) actions should also be acceptable for credit. Reference - QAP 300-27, Operating Department Procedure Revision Training. NRC Resolution: Comment is accepted. Although the question specifically reference QAP 1100-5, TEMPORARY PROCEDURE AND TEMPORARY CHANGES TO PERMANENT PROCEDURES, it is not expected that a candidate memorizes a procedure. Therefore, the question modification is limited to those additional actions that would be taken by a SCRE involving the Operation Department. The answer key is revised to read: The SCRE will consider initiating training of shift personnel. The SCRE will ensure that the Shift Engineer receives an authorized copy of the temporary procedure. If training is determined to be necessary, the SCRE I will attach to a copy of the temporary procedure the appropriate list of names of personnel needing training. If training was necessary, the SCRE will ensure that the proper training is completed within one (1) week. If training was done, the SCRE will file list of names of personnel receiving training." NOTE: Neither QAP 1100-5, Revision 17, nor QAP 300-27, Revision 1, references each other, i although each procedure have separate administrative requirements for temporary procedures (e.g., QAP 300-27 requires the use of form QAP 300-T20; and QAP 1100-5 allows retention of a terminated temporary procedure, if the temporary procedure is stamped, "TERMINATED," i while QAP 300-27 does not). 8.15 Facility Comment: This question should be deleted since it does not apply to operations at Quad Cities Station. It is a valid question for Maintenance or Contractor personnel. Fire watches applicable are generally the ones specified in Tech Specs. i 15

4 ' a-NRC Resolution: Comment is.not accepted. The licensee's knowledge of conducting normal business using the facility procedure, particularly, in the area of fire protection is expected. 8.17 Facility Comment: This question should be deleted. The question strongly implies that something must be checked prior to rod maintenance. At Quad Cities Station, and as stated in the reference procedures, shutdown margin [SDM] is verified simply by checking with a qualified Nuclear Engineer. The question leads the examinees to put down incorrect responses when something "physical" is asked for. NRC Resolution: Comment is not accepted. A means to physically verify the SDM is provided in Unit 2 TS BASIS 3.3.A.1, Amendment No. 21; and it is correctly stated in the answer key.

Secondly, the Question did not state that the SOM must be performed by procedure QOP 300-14, but rather how can the SDM be physically verified before using QOP 300-14.

8.22 Facility Comment: At Quad Cities Station, Gene Schabilion is the Station + Industrial Hygiene Advisor. His name vice his title should be acceptable for full credit. It is also noted in the reference procedure that anyone, not only the SCRE, should contact the Hygienist if there is a question of safety. Regarding this concept, another appropriate response to the question may be "contact the man in charge of the work to get his men out of the space." NRC Resolution: First part of comment, concerniag the use of Station Industrial Hygiene Advisor's actually name, is acceptable i for full credit. However, the second part of comment, concerning contacting "the man in charge of the work," is not acceptable, because the question specifically required the candidate to provide who the SCRE would contact to obtain a "definitive" answer for a worker health and safety concern. The question answer key is revised to read: "Station Industrial Hygiene Advisor or the actual name of the Station Industrial Hygiene Advisor provided by the facility. [0.50]" I 16 t -o ~ ,m ._m,._,, ..r ,m_

J 9 ATTACHMENT 2 4 EXPANSION OR CLARIFICATION OF QUAD CITIES NRC SENIOR REACTOR OPERATOR LICENSE EXAMINATION OF DECEMBER 7, 1987. Question No. Answer Key Modification 5.02 Point values were redistributed. Answer key was revised to read: "a. LHGR fuel pellet expansion [0.50]; and 1% plastic strain on cladding. [0.50] b. APLHGR decay heat and stored heat following LOCA [0.50]; and clad temperature of 2200 degrees F. [0.50] c. CPR loss of nucleate boiling (around cladding) [0,50]; and boiling transition. [0.50]" 6.09 Point values were redistributed; and an alternate answer t for full credit was added. The answer key was revised to read: "Loss of high speed protective relaying or direct transfer trip capability for incoming power lines (0403 and 0404), (The Unit 2 generator trip scheme upon loss of these lines is necessary, because the Iowa-Illinois System cannot handie the output from both units). OR Loss to transmit / operate in Economic Generation Control (EGC). [1.00]" 4 J k j 17

l i

1. e ATTACHMENT 3 TRAINING DEPARTMENT MATERIAL DISCREPANCIES NOTED OURING THE ADMINISTRATION OF QUAD CITIES SR0 ORAL OPERATOR LICENSING EXAMINATIONS ON DECEMBER 8, 49, and 10, 1987 1.

FIRE PROTECTION SYSTEM, LIC-4100, Revision 8: No plant procedures was located that electrically disconnected the diesel-driven fire pump discharge valve as stated in the lesson plan. Also, no reference was made in the lesson plan of the administrative centrols that are used to prevent the inadvertent closure of this valve (e.g., the removal of the control handles in the control room; and the valve was chained and locked with a break away lock). 2. SERVICE WATER SYSTEM, LIC-3900, Revision 1; and CIRCULATION WATER SYSTEM, LIC-4400 Revision 2: The lesson plans stated that hypochlorite could be injected into the circulating water system either via a batch method or service water system. SERVICE WATER SYSTEM, QOP 3900-1, Revision 3, does to provide means for sodium hypochlorite injection as indicated in LIC-3900. Also, CIRCULATING WATER SYSTEM, QOP 44-2, Revision 7, Section F.1.h and F.2.c, require the operation of the circulating water hypochlorite system. However, 00P 4500-0, Revision 5, has deleted all operational hypochlorite procedures. No reference to the Chemistry Department procedures is stated in the QOPs. 3. STANDBY LIQUID CONTROL SYSTEM (SBLC), LIC-1100, Revision 1: Interlock associate with both SBLC pumps running has been removed. 4. "Site Specific Training Procedure," Revision 4, Page 6, stated that if a card reader red light occurs, the person should immediately contact security; and "Quad Cities Nuclear Power Station Training Department Booklet," 1985 Revision, Page 3, stated that the person should wait five (5) minutes before contacting security. 5. SERVICE WATER, LIC 3900, Revision 1, Page 12: Lesson Plan stated that the low fire protection pressure alarm is 65 psig. The actual alarm set point is 68 psig. 18

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U. S. HUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION 'a FACILITY: gyeQ_gIIIgg______________ REACTOR TYPE: 38B-953__________________ QL h p [iu. d V.v'M. A-DATE ADMINSTERED: gZfigf92_________________ A 5 w A 4,., 4 4 , o s <. /,. s on, 4.otr, 7.o.'9,,< l.ie.4 ). EXAMINER: M E g E E L I;. _9 3_ _ _ _ _ _ _ _ _ _ _ _ _ _ CANDIDATE IBSIBUGII985_ID_Ge8DIDeIEi Uso separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers sill be picked up six (6) hours after tho excmination starts. % OF CATEGORY % OF CANDIDATE'S CATEGORY __YeLUE_,,1gI66, ___gGQRE___ _26 lye __ ______________G61EggBI_____________ ) 6.ib _2D159._ Add ly ___________ ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS,AND THERMODYNAMICS -Mrity _ifzt97___________ ________ 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION .2.$. 5 0 Sk b b _-iHrrtO2 _tfzf 9 % _ _ _ _ _ _ _ _ _ _ _ ________ 7. PROCEDURES - NORMAL, ABNORMAL, d EMERGENCY AND RADIOLOGICAL CONTROL 24.7.5, _3912D__ _44r193.___________ ________ 8. ADMINISTRATIVE PROCEDURES, v CONDITIONS, AND LIMITATIONS gc g, z _44tr2 5-Totals Final Grade All work done on this examination is aiy own. I have neither given nor received aid. Candidate's Signature MISTER CODY

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

10. Skip at least three lines between each answer.

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

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

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

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

15. Partial credit may be given.

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

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

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completin3 the examination.

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

s

18. Whan you co:plote your excaination, you shall:

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

11__IBE981.9E_NUGLE88_E9BEB_E668I_QEgB611gHg Posa 4 EbWIgS egg _IugggggIdedIgS t QUESTION 5.01 (1.00) SELECT the one correct statement that describes the condition known as ' Condensate Depression!' a. Can lead to condensate pump cavitation, if condensate depression is too great. b. Decreases as hotwell level rises. c. Reduces thermal cycle efficiency. d. Increases as condensate temperature increases. QUESTIO!! 5.02 (3.00) STATE the 'Cause of Failurei' AND the ' Limiting Condition' for each of the following core thermal limits; a. LHGR b. APLHGR c. CPR QUESTION 5.03 (1.00) SELECT the one correct answer. For a reactor that is just critical, a given reactivity addition will; a. cause a shorter period at BOL than at EOL. b. cause a shorter period at EOL than at BOL. c. cause a shorter period that is the same throughout core life. d. have no effect on reactor period because the reactor is critical. (xxxxx CATEGORY 5 CONTINUED ON NEXT PAGE xxxxx) k_

5___IBEQBY_9E_HUGL5eB_E9BEB_EbeNI_9EEBeIIQN1 Posa 5 - ELVIgS egg _IUgBugg18edICS t QUESTION 5.04 (1.00) SELECT the one correct answer. As a subcritical reactor nears criticality, the length of time to reach equilibrium count rate after an insertion of equal positive reactivityt a. IS THE SAME as the length of time required to reach equilibrium count rate after an equal insertion of nosative reactivity. b. INCREASES, primarily because of the increased population of delayed neutrons present in the core with no increase in prompt neutrons. c. DECREASES, because the source neutrons are becomins less important in relation to the total neutron population. d. INCREASES, because of a larger number of neutron life cycles required to reach equilibrium. QUESTION 5.05 (1.00) ANSWER each of the fo110 win 3 items either TRUE or FALSE. The percenta3e of power from decay heat from reactors that have respectively operated continuously at 100% power for 30 and 365 days. is gg-EEEEf'T:f.LLY THE S AME af ter a scram for thet ,qy__ a. First hour b. First week i I (xxxxx CATEGORY 5 CONTINUED ON NEXT PAGE xxxxx)

51. 1BEQBl_QE_dWGLE68_EQUEB_EL6HI_QEEB6IIQUI F*S3 6

ELWIQfteNQ.IBEB5QQldedIGE QUESTION 5.06 (2 00) SELECT the one correct choice in the parentheses for each of the following items! a. The delayed neutron fraction, beta bar (INCREASES, DECREASES, or REMAINS CONSTANT) over core life, because... b. the percentage of reactor power from... (1). U-235 (INCREASES, DECREASES, or REMAINS CONSTANT) (2). U-238 (INCREASES, DECREASES, or REMAINS CONSTANT) (3). Pu-239 (INCREASES, DECREASES, or REMAINS CONSTANT) DUESTION 5.07 (1.25) DESCRIBE how fuel pellets deform under operating conditiuns. INCLUDE the change (s) that occur in the pellet density and geometry. QUESTION 5.08 (1.50) If a multiple feedwater heater or stri.19 loss occurs with the unit at 75% power, EXPLAIN what happens to reactor power. (INCLUDE the reactivity coefficient (s) involvedi and EXPLAIN to the point where reactor power etabili::es f or full credit). ( Ma arrA A

• A ).

e QUESTION 5.09 (1.00) LIST two (2) reasons for the use of gadol,..a rods in the core fuel bundle. 1 (xxxxx CATEGORY 5 CONTINUED ON NEXT PAGE xxxxx)

E1__IBEQBY_QE_HUGLE68 EQWEB_EkeHI_QEEBoIIQB1 Paso 7 EkWIQfteHQ_INEBBQQIdeBIGH QUESTION 5.10 (2.00) A reactor startup is planned approximately 12 hours after a scram from a two month 100% power run. EXPLAIN the difference between the expected and the previous rod reactivity worths for each of the followingt ' r. ). center control rods; (b). peripheral control rods. QUESTION 5.11 (1.00) DESCRIBE two (2) removal mechanisms of Xe-135 from the reactor core. QUESTION 5.12 (1.00) SELECT the one following statement that correctly completes the statement Departure from nucleate boiling is the point where... a. the void fraction equals one. b. the heat transfer mechanism changes from nucleate boiling to single phase, c. radiative heat transfer becomes insignificant. d. the heat transfer rate sustainable with nucleate boiling reaches its maximum. QUESTION 5.13 (1.75) DESCRIBE (i.e., significant or insignificant, increase or decrease, large or small, as appropriate) and EXPLAIN the effects of withdrawing a ' deep control rod' (Notch 00-18) in terms of a. change in core power. (0.75) b. void effect (negative reactivity). (0.50) c. axial power shape. (0.50) (muxxx CATEGORY 5 CONTINUED ON NEXT PAGE usurm)

Ez__IBEQBY QE_HUGLE68 EQWEB_EL6HI_QEEBBIIQH1 Paso 8 EtWIQEteHQ.IBEBdQQ1HeBIGE QUESTION 5.14 (1.00) EXPLAIN why the steady state MCPR value is increased for core flow less than rated core flow. QUESTION 5.15 (2.00) Core loadins requires a shutdown marsin (SDM) at least R + 0 25% delta K in the most reactive condition during the operating cycle. DEFINE the term 'R' in this SDM. QUESTION 5.16 (1.50) STATE the damase that would be caused to an induction motor (i.e., RHRS service water pump) by repeated starts and/or Joss, and EXPLAIN why repeated starts would cause this damage. QUESTION 5 17 (1.00) During a reactor startup, the first reactivity addition caused count rate to increase from 20 cps to 40 cps. The second reactivity addition caused count rate to increase from 40 cps to 80 cps. SELECT the correct following statement. a. The first reactivity addition was larger. b. The second reactivity addition was larger. c. The first and second reactivity additions were equal. d. There is not enough data given to determine relationship of reactivity values. QUESTION 5.18 (1 50) a. EXPLAIN the difference between driven flow and driving flow within the reactor vessel. (1.00 point) b. STATE which one of these flows provides the greater contribution to the total core flow. (0.50 point) (xxxxu END OF CATEGORY 5 xxxxx)

6 __ELONI.SYSIEdH_QESISN1_G9dIB961_eUQ_XUSIBydguleIIgg Page 9 1 /. N QUESTION 6.01 -44, M t g ANSWER each of the following items either TRUE or FALSE concerning 00A 1300-7, RCIC LOCAL MANUAL OPERATION: --e: The : e c h e n i c e l - = c r g e e d t r i p-4540a_cp O of the t r4p--throttle I y valve i s the-oMMP-s Qna-1--act-ive-t-or-l ocal-aanua l-o p e r a t i on. J ,b. When the local-remote selection switch for the RCIC Turbine 'T Steam Supply Isolation Valve, MD-1301-16, is placed in the LOCAL position, all position indication in the control room for that valve is lost. L ,c. A local self-powered tachometer for Unit 1 RCIC turbine was Y installed for fire protection considerations. QUESTION 6.02 (1.50) STATE why each of the following conditions would be imposed during shutdown cooling operations: a. During the normal shutdown cooling mode of operation, additional cooling by the RHR service water is required as reactor coolant pressure decreases. b. RHR inlet temperature to its heat exchanger is used to determine reactor coolant temperature. c. While usin3 shutdown cooling, the MOVs to the suppression chamber (MO-1001-34 A/B and MO-10001-36 A/B) are not open. QUESTION 6.03 (1.50) LIST three (3) sets of conditions that would cause ' Refueling Platform Hoist Upward Travel Blocks.' l GUESTION 6.04 (1 00) FILL in each of the following blanks with the correct one word answer. The purpose for placin3 a second main feedwater regulator into service when usins 00P 600-3, during reactor power operation, is to reduce ________________ at critical power limits. The critical power levels seem to be unpredictable but tend to occur above ________ % power. (xxxxx CATEGORY 6 CONTINUED ON NEXT PAGE xxxxx)

6t__ELeHI_f1SIENS_QESIGHt_GQUISQL1_eHQ_INSIBWHEHI6IIQB Pcso 10 QUESTION 6.05 (1.50) EXPLAIN the potential consequence (s) of losing the Reactor Building Exhaust Fans. (INCLUDE equipment automatic trip set point (s) as applicable for full credit.) QUESTION 6.06 (1.00) LIST the two (2) buses that are fed by Transformer 412, when Unit 2 is at power. (Stated in Procedure 00A 6100-1 for loss of transformer during power operation.) QUESTION 6.07 (0.75) With a station blackout, STATE the three (3) expected automatic Group Isolations of 00A 6100-4, STATION BLACKOUT. QUESTION 6.08 (4.00) STATE, for each of the High Pressure Coolant Injection (HPCI) System component failures listed below, whether the HPCI System 'IS' or 'IS NOT' still capable of automatic injection. If it 'IS NOT' capable of automatic injection, EXPLAIN why. If it 'IS' capable of automatic injection, then DESCRIBE any adverse effect(s)/ consequence (s) of automatic injection with this failure. CONSIDER each component failure as a separate case. op ed.- Assume that no Oper:ticiIaction occurs, the component fails at the time of + the automatic initiation signal, and reactor power is 100%. a. The gland seal exhauster fails to operate. (1.00) b. The turbine auxiliary lube oil pump fails to operate. (1.00) c. The alternate minimum flow valve (2301-14) (e.g., valve 2301-3 is inoperable and left opened) fails to close, when system conditions require it to be close. (1.00) d. The HPCI pump discharge flow element output signal to the HPCI flow controller is failed at its maximum output. (1.00) (xxxxx CATEGORY 6 CONTINUED ON NEXT PAGE xxxxx)

62__E,L8HI_HISIEdf_QESIGHt_G9dIBQLt_eUQ_INSIBWdEHIeIIQU Paso 11 / QUESTION 6 07 (1 00) STATE the effect(s) that losing the microwave radio system would have upon routine Unit 2 operations with Unit 1 on line. QUESTION 6.10 (2.50) ANSWER each of the followins questions either TRUE or FALSE concerning the Rod Worth Minimizer (RWM) rod blockst a. After transferrins from the A to B computer or back, the RWM is automatically initialized. b. Whenever reactor power is beloQ the low power set point, only INSERT rod blocks are active. c. The RWM low power set point requires both rated steam flow and rated feedwater flow to be below 20% of their values. d. If the RWM fails or is powered down with the mode switch in NORMAL, rod blocks will be applied only for reactor power levels less than 30%. o. Any rod inserted one or more notches beyond its insert limit will cause an insert block to be issued for all rods without exception. QUESTION 6.11 (2.00) ANSWER each of the followins questions either 1 RUE or FALSE concerning the Atmospheric Containment Atmosphere Dilution (ACAD)/ Containment Atmosphere Monitorins (CAM) System: a. The ACAD cannot be automatically initiated. b. The Shift Engineer must receive authorization to place the ACAD/ CAM mode switches (Panels 901-55/902-55 and 901-56/902-56) in OFF during a post-LOCA situation. c. If CAMS are turned completely off (i.e., the heater boxes are allowed to cool), it will require 15 minutes to 1 hour to warm the unit up before it will be operable. d. The hydrogen and oxygen monitor indications are not valid beyond their alarm points. (xxxxx CATEGORY 6 CONTINUED ON NEXT PAGE xxxxx) i

62__ELeHL EISIEBS_QESIGHt_GQUIBQLt_eNQ_INflBWdEHIBIIQB pog] 12 QUESTION 6.12 (1.00) STATE why the physical location of the drywell radiation monitors result in the need to apply a correction factor to the readings obtained on the monitor to convert the readings to actual dose rate. QUESTION 6.13 (2.10) LIST the four (4) APRM reactor scrams) and INCLUDE ti.e set points / conditions for each APRM reactor scram. /44) QUESTION 6.14 -4+r'Kr77 ANSWER each of the followins questions concerning the Core Spray (CS) System either TRUE or FALSE: T h e - n i n i m um b yp ess-f-lew v.1vv gig-38 n/B) in ivetr-loop-is-g 2. i 7 noese-1-ly-cren dvrina utendby opmtTener2Use-ttier1r-11s rio Tore-spra y-f+ ewe A.-bT) The inboard injection valve (MO-25 A/B) is interlocked with the core spray testable check valve to prevent cycling the testable check valve when inboard injection valve is open. y, -c'. Upon an automatic initiation of core spray, the CS systems logic will only inject CS flow into the recirevlation loop that appears to have a break. QUESTION 6.15 (1.50) STATE the three (3) Reactor Corr. Isolation Cooling (RCIC) System automatic isolations (Group 5); and INCLUDE the set points. QUESTION 6.16 (1.25) If radioactive materials have accumulated on the Standby Gas Treatment System (SBGTS) Filters durins operation, radioactive decay will cause internal heating of the filters. If heating is sufficient to require coolins, DESCRIBE the filter cooling flow path that can be used in accordance with 00P 1600-1, DRYWELL PRESSURE RELIEF THROUGH SBGTS. (***** CATEGORY 6 CONTINUED ON NEXT PAGE xxxxx)

t h _ _ Eke WI _lIIIE Bl_QE SIGH t _G Q HIBQL 1_6H Q _INSIBW HE HIGIIQ H Paso 13 QUESTION 6.17 (0.50) STATE the auxiliary system that prevents water nammers from occuring in the Core Spray (CS) System. 7 L i k P (xxxxx END OF CATEGORY 6 xxxxx)

Zz__EBQGEQUBES_:_H9Bdekt_eBNQBdeb1_EMEBGENGY Peso 14

• eUQ BeQIQLQGIGek_G9BIBQL 4

40COTION 7.01 '1.50) }p -GT ATE thr a s -(0)-Ieeediete Opei ster Act un. Twi "HVAC EXHAUST-FTL-TER-~p --TEMER AT U R E 9IC P ' :lere =ies 00A '01-0: uP99 LSP-ANNUNCIATOR _RROCEDURES f GUESTION 7.02 (1 50) With the reactor critical, a control rod position indication does not chan3e from Position 16 when a control rod withdraw signal is applied. STATE three Immediate Operator Actions required by 00A 300-2, INABILITY TO DRIVE A CONTROL ROD: CONTROL ROD STUCK. QUESTION 7.03 (1.50) On July 29, 1987, a lightning strike on the 345 KV line caused a power fluctuation that resulted in a toxic gas analyzer system isolation of the Control room. Other than a manual reactor scram (and its corresponding immediate operator actions), LIST three (3) Immediate Operator Actions required by 00A 5750-13, T0XIC AIR OR SMOKE IN THE CONTROL ROOM, if occupation of the control room is no longer possible. (1.5 points) GUESTION 7.04 (3.00) a. QGA 500-7, LEVEL / POWER CONTROL, describes the method of lowering Reactor Pressure Vessel (RPV) water level to reduce the heat generation rate. EXPLAIN how lowering RPV water level assists in reducins the heat generation rate. b. In order to lower RPV water level, QGA 500-7 prescribes terminatin3 and prev'snting all injection into the RPV except from the boron injection system or the control rod drive system. EXPLAIN why injection is still allowed from these two sources. c. OGA 500-7 further prescribes that RPV water level be lowered until any one of three conditions is met. One of these conditions is that RPV water level drops to -143 inches. EXPLAIN the significance of this -143 RPV inches water level. (xxxxx CATEGORY 7 CONTINUED ON NEXT PAGE xxxxx)

Zi__EEQGEQQBEE_:_HQBdokt_6ENQBdekt_EdEBGENGY Pass 15 ' BNQ_BeQIQLQGIGeL_GQNIBQL QUESTION 7.05 (3 00) D. QGA 500-2, EMERGENCY REACTOR PRESSURE VESSEL (RPV) DEPRESSURIZATION, requires verification that the suppression pool level is above 5.0 feet prior to opening all the Automatic Depressurization System (ADS) valves. EXPLAIN why this limit on suppression pool level is imposed for Emergency RPV Depressurination using the ADS valves. (1.00 point) b. QGA 500-2 further prescribes that if fewer than 3 ADS valves are open and RpV pressure is at least 50 psis above suppression chamber pressure then rapidly depressurize the RPV using one or more of several systems (e.3., main turbine bypass valves, main steam line drains, HPCI turbine, RCIC turbine, RPV head vent, steam Jet air ejectors, RWCU). (1). EXPLAIN why RPV pressia; e is required to be at least 50 psi 3 above suppression chamber pressure prior to performing this step. (INCLUDE the significance of this 50 psig value). (1.00 point) (2). EXPLAIN why three (3) ADS values are the minimum number required for Emergency Depressuri:ation. (1.00 point) QUESTION 7.06 (1 50) The unit is operatin3 at 100% power, when a complete loss of essential cervices occurs. LIST five (5) control room indications, which would be disabled due to the loss of essential service power. QUESTION 7.07 (2.50) While the unit is operating at 75% power in EGC, an 'A' feedwater heater high level occurs. STATE five (5) Immediate Operator Actions using 00A 3500-1, LOSS OF FEEDWATER HEATERS. (xxxxx CATEGORY 7 CONTINUED ON NEXT PAGE xxxxx)

Z1__EBQGEQQBEH_:_NQBdekt_eEHQBdeki_EdEBGENGY Pc33 16 ' eBQ_BeQIQLQQIGek_GQHIBQL QUESTION 7.08 (1.00) STATE the two (2) conditions required before an inoperable Control Rod Drive (CRD) Accumulatot-is reclassified as operable in accordance with 00P 300-10e CRD SYSTEM ACCUMULATOR CAS DISCHARGING, and Technical i Specifications. QUESTION 7.0? (1.50) Using the Immediate Operator Actions for LOSS OF STATOR COOLING, 00A 5300-1, STATE the maximum time that the unit can remain critieb? for each of the following stator cooling water conductivity valuest a. 0.2 unho/cm b. 2.0 umho/cm c. 20.0 umho/cm OUESTION 7.10 (1.00) EXPLAIN why an Off-Gas System chimney monitor alarm may be likely to occur following a rapid power reduction. QUESTION 7 11 (1.00) In single loop operatione SELECT for each parameter listed below, if the Unit i value is changed (MORE THAN, SAME AS, or LESS THAN) the Unit 2 change in valvet a. maximum average planar linear heat generation rate (MAPLHGR) limit multiplication correction factor. b. minimum critical power ratio (MCPR) safety limit. c. Rod Block Set Points. (xxxxx CATEGORY 7 CONTINUED ON NEXT PAGE xxxxx)

Zi__EBQGEQUBgS_:_NQBdekt_eBHQBdekt_EdEBGENG1 Pasa 17 eHQ B8QIQLQGIGeb_GQUIBQL QUESTION 7 12 (1.00) STATE why the main condenser level is limited below 35% level when implementing 00P 201-1, DRAINING THE REACTOR VESSEL AND RECIRCULATION LOOPS. QUESTION 7.13 (1.00) If a control rod is required to be taken out of service, EXPLAIN why it is preferable to electrically disarm the drive in accordance with 00P 300-7, CRD SYSTEM, DRIVE DISARMAMENT, rather than valvins out the drive in cecordance with 00P 300-8, CRD SYSTEM, HYDRAULIC CONTROL MODULE ISOLATION. QUESTION 7.14 (1.50) STATE the three (3) restrictions imposed by Technical Specifications and 00P 1100-1, STANDBY OPERATION OF STANDBY LIQUID CONTROL SYSTEM (SLCS), which allow the SLCS to be inoperable with fuel in the reactor vessel. QUESTION 7.15 (1.50) FILL in each of the followins blanks with a single word answer concerning 00P 1000-5, SHUTDOWN COOLING STARTUP AND OPERATION! o. If both recirculation pumps are off, temperature stratification may occur due to lack of upward core flow. This may result in reactor b. In the event of inadequate heat transfer across the RHR heat exchanger or inadequate RHR service water flow, consideration should be given to ___________________ of the heat exchanger as the possible cause. c. The differential temperature between the reactor vessel flange and l i is to be maintained less than 140 degrees F. i (*x**x CATEGORY 7 CONTINUED ON NEXT PAGE *****)

Z1__EBQGEQWBEE_ _HQBdekt_eEHQBdekt_EMEBGENG1 Paso 18

• 6t0_BeQIQLQGIGek_GQUIBQL QUESTION 7.16 (2.00) i Reactor Pressure Vessel (RPV) water level cannot be determined.

The RPV is therefore ficoded in accordance with QGA 500-6, REACTOR PRESSURE VESSEL FLOODING. Injection into the RPV is controlled in accordance with the procedure to maintain at least three Automatic Depressurization System (ADS) valves open and RPV pressure at least 77 psis above suppression chamber pressure, but as low as practical. Forty minutes later with five ADS valves open (reactor pressure has remained above suppression chamber pressure for this entire time) RPV water level instrumentation is availablet temperature near the RPV cold water level instrument les vertical runs is below 212 degrees F1 and suppression chamber pressure is below 55 psis. Under these conditions, OGA 500-6 then prescribes that all injection into the RPV be terminated and RPV water level be reduced. QGA 500-6 also prescribes a maximum coneuncovery time limit after y-commencing termination of injection into the RPV after which flooding is to be resumed, if RPV water level indication is not restored. EXPLAIN why QGA 500-6 requires this RPV a. water level reduction. (1 0 point) b. flooding to be resumed, if water level indication is not restored within the Maximum Core Uncovery Time Limit. (1.0 point) (xxxxx END OF CATEGORY 7 xxxxx)

? 02__6DMINISIBeIIVE_EBQGEQWBEft_GQHQIIIQHEt Paga 19 ' eHQ_LIBIIeIIQHS QUESTION 8.01 (1.00) SELECT the one correct answer. If an entry condition for an Emergency Operating Procedure (OGA) occurs, for a QGA procedure that has been completed, then the completed OGA procedure! a. is immediately performed again. b. is perfomed again, after completing the OGAs that have been started. c. is not required to be performed again. d. can be performed again, but it is entirely at the discretion of the Shift Engineer. QUESTION 8.02 (1.00) SELECT the one correct answer. QAP 500-9, PREVENTATIVE MAINTENANCE, requires the Operations Department tot a. lubricate motors and equipment which have a circulating oil system or a reservoir. b. lubricate motors and equipment without a circulating oil system or a reservoir. c. Ivbricate all motors and equipuent. d. lubricate neither motors nor equipment. QUESTION 8.03 (1.00) Technical Specifications (TSs) require the reactor to be shutdown, if it is determined that a jet pump is inoperable. STATE two (2) reasons, which are taken into consideration by the design base accident (DBA) for loss of coolant accident (LOCA), for this requirement. (xxxxx CATEGORY 8 CONTINUED ON NEXT PAGE xxxxx)

Bi _eQUIBIIIBeIIVE_ESQGEQWSEft GQHQIIIQUEt Pasa 20 ' BUQ_LIMIIeIIQUE QUESTION 8.04 (1 00) A spurious unplanned control room ventilation system isolation requires! (SELECT the one correct answer from the following.) a. A one (1) hour telephone notification to the NRC Operations Center. b. A four (4) hour telephone notification to the NRC Operations Center. c. No NRC telephone notification. d. Only a telephone call to the NRC Resident Inspector. QUESTION 8.05 (1.50) STATE the Technical Specification Basis for requiring a Condenser Low Vacuum Scram (1 00)I and how this scram can be bypassed. (0.50) GUESTION 8.06 (1.00) FILL in each blank with the correct value. Unit i Technical Specification Basis states that a leak as small as _______ spa is possible to be detected by the Main Steam Line Tunnel High Temperature Alarm. The alarm cet point for this h3sh temperature alarm is _______ degrees F. QUESTICN 8.07 (1.50) INDICATE whether each of the following statement concerning Unit 2 secondary containment is either TRUE or FALSE. a. Each train of the Standby Gas Treatment (SBGT) System is required to have the capability to maintain at least a 1/2 inch of water vacuum within the secondary containment. b. The SDGT charcoal filter should be tested, if it was exposed to paint fumes. c. An efficiency of 94.9% is adequate for the SBGT filter to retain particulates that may be released to the reactor building followins an accident. (***** CATEGORY 8 CONTINUED ON NEXT PAGE manum)

Bi__eQMINISIBoIIYE_ESQGEQWBESt_GQNQIIIQHft Pcg3 21 et!Q_LI5IIBIIQNE QUESTION 8.08 (1.00) STATE the primary disadvantage, as provided in the Technical Specification Basis, of lowering the reactor vessel low water level scram set point. QUESTION 8.09 (1.00) Other than personnel safety considerationse STATE the Shift Engineer's principal purpose for reviewing an area, in whiche radiography is to be performed. QUESTION 8.10 (1.50) In accordance with the Generating Station Emergency Plan (GSEP): LIST three (3) conditions that would prevent the evacuation of nonessential personnel, after assembly / accounting of personnel within the Protected Area has been completed. OUESTION 8.11 (1.00) i STATE two (2) conditions required by DAP 300-2, CONDUCT OF SHIFT OPERATIONS, to use the PULL-TO-LOCK switch position for testing. QUESTION 8.12 (1 00) SELECT the correct answer. An orderly unit shutdown will be initiated immediately with reduction of coolant temperature to less than 212 degrees Fe as rapidly as other plant constraints permit, when Chemistry issues an ACTION LEVELt a.

One, b.

Two. c. Three. d. Four. (xxxxx CATEGORY 8 CONTINUED ON NEXT PAGE xxxxx)

i H2__e9dIMISIBoIIYE_EBQGEQWBEft_GQUQIIIQMS1 Paso 22 ' GHQ LIMIIBIIQNH QUESTION 8.13 (1.00) If a temporary procedure review by the SCRE involvet the Operation Department (i.e., operation of a RHR pump), STATE two (2) SCRE actions that are required to be performed in addition to the review, in accordance with QAP 1100-5, TEMPORARY PROCEDURES AND TEMPORARY CHANGES TO PERMANENT PROCEDURES. QUESTION 8.14 (2.00) ANSWER each of the following questions either TRUE or FALSE concerning DAP 1120-6, ENTERING A LOCKED HIGH RADIATION AREA WITHOUT A TIMEKEEPER: a. Entry into a high radiation area is absolutely prohibited without the use of a safety man in lieu of a timekeeper. b. Transfer of the 'R-key' between individuals is only routinely allowed between security guards. c. The safety man is required to immediately notify the control room, when an individual enters and leaves a high radiation area. d. An individual will only be allowed one 'R-key' at a given time. OUESTION 8 15 (0.50) FILL in the blank with the correct value. QAP 1170-14, FIRE WATCH RESPONSIBILITIES, states that persons performing fire watch duties for other than cutting and welding jobs shall make a round of the assigned area at least once every ____________ unless otherwise defined in Technical Specifications. QUESTION 8.16 (1.00) STATE the two (2) restrictions imposed upon the Shift Engineer during absences from the control room / Shift Engineer's Office by QAP 300-1, OPERATIONS DEPARTMENT ORGANIZATION. (xxxxx CATEGORY 8 CONTINUED ON NEXT PAGE xxxxx) l

Bt._hDUINISIB6IIVE_EBQGEQWBEft_GQHQIIIQUEt Pasa 23 680.L15I101198E QUESTION 8 17 (1.25) EXPLAIN how an adequate shutdown margin-(SDM) can be physically verified before performing maintenance on a control rod drive using 00P 300-14, CONTROL ROD OR CRD MAINTENANCE. QUESTION 8.18 (1.50) EXPLAIN the Technical Specification Basis for requiring the Rod Worth Minimi:er (RWM) to be operable for less than 20% power. QUESTION 8.19 (1.00) SELECT the one correct answer. When performing DAP 300, EQUIPMENT OUT-OF-SERVICE, the individual items should be normally taken out in the following specific order a. electrical feed, main isolation points, centrol switch. b. main isolation points, control switch, electrical feed. c. control switch, electrical feed, main isolation points. d. main isolation points, electrical feed, control switch. QUESTION 8.20 (1.00) FILL in each blank with the correct value or one word answer. GAP 300-19, REVIEW OF ACTIVE OUT-OF-SERVICES, requires: ' Monthly, at least Ca.] percent of those out of services older than Eb.] days and not in a high radiation area shall be physically reviewed.' (xxxxx CATEGORY 8 CONTINUED ON NEXT PAGE xxxxx)

92._6DdINISIBeIIVE_EBQGEQWBEft_GUNQIIIQHft Pago 24 eNQ_LIMIIeIIQHE QUESTION 8 21 (1.50) LIST by title, the position that would assume each of the following on-site fire protection position title, in accordance with QAP 1170-17, FIRE PROTECTION PROGRAM: a. Fire Commissioner. b. Fire Chief. c. Assistant Fire Chief. QUESTION 8.22 (0.50) DAP 1150-6, ACCESS TO CONFINED SPACES, defines what constitutes a confined opace and the requirements of working in such an area. If the SCRE has any concern, which may affect worker health and safety, STATE by title, the person that the SCRE would contact to obtain a definitive answer to his concern. I i i l t (xxxxx END OF CATECORY 8 mamma) (mmmmxxxxxx END OF EXAMINATION xxxxxxxxxx)

52 _IHEQBI_QE_dWGLE68 EQWEB_ELedI_QEEBeII9dt Pa33 25 ELWIQEteHQ IBESdQQIdedIGE ANSWER. 5.01 (1.00) c. [1.00 point] REFERENCE HTFF Text, Chp. 7, Heat Transfer, Rev. 1, ps. 7-45. 293007K109 ..(KA's) ANSWER 5.02 (3.00) 5' fuel pellet expansion to.503; and 1%-t0.103 plastic strain O. LHGR 9--C^.3^2 on cladding E4.10 3. [c 9.-] b MO v b. APLHGR - decay heat M and stored heat following LOCA [Gre51-) and clad temperature 4^.4^3 of 2200 degrees F [0.fb]. b ) 33 andboilinstransition[0.503.j[aroundcladdinsto.ne}1 c. CPR loss of nucleate boiling '0.40 REFERENCE HTFF Text, Chp 9, BWR THERMAL LIMITS, Rev. 1, Fig. 9-5, pg. 9-15. Quad Cities, N-NOLR-FA848 SRO REQUAL, Question No. 5.05. 293009K112 293009K111 293009K108 293009K107 ..(KA's) ANSWER 5.03 (1.00) b. 01.00 point] REFERENCE GE Student Text, LIC-THEO, REACTOR THEORY, Rev. 2, Figure 46 Quad Cities, N-NOLR-FA84) SRO REQUAL, Question No. 5.11. 292008K108 ..(KA's) ANSWER 5.04 (1 00) i d. C1.00 point] t (xxxxx CATEGORY 5 CONTINUED ON NEXT PAGE xxxxx)

51,_IHEQBl_QE_dWGLEeB_EQWEB_EL6HI_QEEB6IIQN1 Paso 26 ELVIQSteNQ_IBshdQQ1Heb1GS l REFERENCE GE Student Text, LIC-THEO, REACTOR THEORY, Rev. 2, Figure 46. Quad Cities, N-NOLR-SRO-D-85) SRO REQUAL, Quest. No. 5.03. 292000K105 ..(KA's) ANSWER 5.05 (1.00) a. True b. False CO.50 point for each) REFERENCE Reactor Theory, LIC-THEO, REACTOR THEORY, Rev. 2, Figure 7 at top of pa38' 292000K130 ..(KA's) q ANSWER 5.06 (2.00) l a. Decreases b. (1). Decreases (2). Remains Conttant (3). Increases CO.50 point each] f REFERENCE Reactor Theory, Lic-Theo, Rev. 2, pg. 13 and Figure 29 292003K103 ..(KA's) ANSWER 5 07 (1.25) 4.,, J, g, ; +y pd,] %.l~?.u,y Fuel pellets have a tendency to increase in density 00 53. .Thit PAU5e5 E-T pd L e,17 a -( 56.J [ 0 if f 331n the CO.253 apd a decrepse E ^.f 5 decrease E&r253rin the pellet length pellet diameter [0,45) I o( c d.73 REFERENCE HTFF Text, Chp. 9. BWR THERMAL LIMITS, p g'. 9-41!ri l-71,'I"4I,'"' 293009K131 ..(KA's) (xxxxx CATEGORY 5 CONTINUED ON NEXT PAGE xxxxx)

li__IMEQBl_QE.HUGLEeB_EQWEB EkeHI_QEEBeIIQN1 Paso 27 ' EkUIQS eHQ_ISE0dQQldedIGH t ANSWER 5.08 (1 50) i Reactor power increases CO.503, due to the reduction in feedwater temperature CO.303. Positive reactivity is inserted by the moderator temperature coefficient CO.303. Natural feedback to limit power increase is provided by the void coefficient CO.203 and the fuel temperature coefficient (doppler) CO.203. REFERENCE 00A 3500-1, LOSS OF FEE 0 WATER HEATERS, Rev. 4, pg. 2. Quad Cities Lesson Plan, LIC-THEO, REACTOR THEORY, Rev. 2, pas. 15-18. 259001K312 ..(KA's) ANSWER 5.09 (1.00) a. Allow more fuel to be loaded (without increasing the number of control rods) CO.503. Ic,1O bue flig c A b b. Facilitate axial' power shape control'(limits flux peakins problems j and simultaneously simplifies control rod patterns). -{0.501]s REFERENCE t Quad Cities Lesson Plan, LIC-THEO, REACTOR THEORY, Rev. 2, ps. 25. 292007K101 ..(KA's) ANSWER 5.10 (2.00) a. The center control rods will be worth less CO.503 because the xenon concentration will be hishest in regions of the core where neutron flux was highest during the previous operational phase CO.503. i b. The peripheral control rods will be worth more CO.503 because the thersial flux will be pushed to the core edse by the xenon building in the core center CO.503. REFERENCE GE Reactor Theory, LIC-THEO, Rev. 2' Ps. 24. 292006K108 292006K107 ..(KA's) (**xxx CATEGORY 5 CONTINUED ON NEXT PAGE muunn)

22__IMEQB1_QE_HWGLEeB_EQWEB_EL6HI_QEEBoIIQNi page 28 'ELVIQfteHQ IBEBdQQXHedIGS ANSWER 5.11 (1.00) o. Burnout (Xe-135 absorption of a thermal neutron to become Xe-136 with a small thermal neutron cross section). [0.503 l b. Decay (Xe-135 half-life to Cs-135 is 9 2 hours). CO.503 REFERENCE GE Reactor Theory, LIC-THEO, Rev. 2, pg. 23. 292006K104 ..(KA's) l ANSWER 5.12 (1.00) d. C1 00 point] REFERENCE HTFF Text, Chp. 8, BWR THERMAL HYDRAULICS, Rev. l' p3 8-12. 293008K108 ..(KA's) ANSWER 5.13 (1 75) c. Core power is significantly CO.25] increased CO.253, because of its large rod worth CO.253. b. Void effect is saia11 C0.253, because the increase voids affect only a saia11 length of fuel CO.253. c. Only a small effect in axial power shape C0.253 because most of the bundle is controlled CO.253. i REFERENCE GE Reactor Theory, LIC-THEO, Rev. 2, pg. 21. 292005K112 ..(KA's) (4xxxx CATEGORY 5 CONTINUED ON NEXT PAGE xxxxx)

52,.IHEQBY_QE_HVGLE68.EQUEB_EL6HI_QEEBeIIQUt Pas] 29 ELVIQlteND_INEB5QQldeBIGH ANSWER 5 14 (1.00) This ensures that the MCPR will be maintained greater than that required (Unit 1 TS 1.1.A) to.503 even in the event that the motor senerator set speed controller causes the scoop tube positioner for the fluid coupler to cove to the maximum speed position CO.503. (Alternate word is acceptable for full credit). REFERENCE Unit i TS BASIS 3.5.K, Amendment No. 66, pg. 3.5/4.5-22. 293009K123 ..(KA's) ~ ANSWER 5.15 (2.00) The value of R is the difference CO.503 between the esiculated core reactivities CO.503 at the beginning of the operating cycle [0.503 and any time later in the cycle to.303 where it would be greater than at the beSinning CO.203. REFERENCE Unit 2 TS BASIS 3.3.A.1, Amendment No. 2, ps. 3.3/4.3-7 292002K110 ..(KA's) ANSWER 5.16 (1 50) c. Life of the winding insulation would be (steatly) reduced. [0.503 b. The heat produced CO.503 by each acceleration or Jos is much more than that produced (and dissipated) by the motor under full load [0.503. REFERENCE 00P 1000-4, RHRS SERVICE WATER SYSTEM STARTUP AND OPERATION, Section F.5.b, Rev. 9, pg. 2. 291005K106 ..(KA's) J ANSWER 5.17 (1.00) a. [1.00 point 3 (m**x* CATEGORY 5 CONTINUED ON NEXT PAGE

• • • • • )

Dia_IBEQBl_QE.UUGLE68.EQWEB_EL6HI_QEEB6IIQW1 Paso 30 ELUIQEteHQ_INEBdQQ1865 IGE l REFERENCE r Quad Cities Lesson Plane'LIC-THEO, REACTOR THEORY, Rev. 2, pgs. 9 & 11. 292008K103 ..(KA's) ANSWER 5.18 (1 50) [ c. Drivin3 flow iS Provided to the jet pumps from the recirculation pumps CO.503, while driven flow comes from the vessel downconer t region (e.s., dryer and separator drains plus feed flow). C0 503 b. Driven flow. CO.503 REFERENCE Quad Cities Lesson Plan, RECIRCULATION: LIC-0202-1, Rev. le pas. RECIR-2 & RECIR-3. i 290002K102 293006K102 ..(KA's) f i i + i (zuman END OF CATECORY 5 muaxx) i I

61u _BL6 HI_SISIE N f _Q E SI9 Bi _GQ UIBQ L t _e H Q. INQIBU8f,BI6IIQ H Paga 31 frv ANSWER 6 01 4+r5et -e- ' r v : + y-0.-bry True. b.-e.p True. CO.50 point each3 REFERENCE 00A 1300-7, RCIC LOCAL MAit04L OPERATION. Rev. 53 pg. 3 PRID, Diagram of ffC2C Pipin3+ h-SO, Rev. AS 217000K406 ..(MA's) ANSWER 6 02 (1 50) because, the linv could flash to stest (n temperature of a. 281 degrees F could be approached, which it the saturation temperature for 50 psis), CO.503 b. to obtain temp 9rature t eadins with ro reactor reeleen3ation pump operating

• C0.503 to prevent draining water from reentor vesss1, f.b. 503 c.

REFERENCE 00P 1000-5, SHUTQ9WN COOLING STARTUP AND OPERATION, Rev. 13, pgs. 1 and <?. Quad Cities Lennon Plan, L3t-1000, RHR, Rev.2, pg. 8. IE Rpt No. 50-244/87019 (DRP), pg, 7. 205000K102 20500CK101 205D00K114 205000K115 ..(KA's) ANSWER 4 03 (.3.50) C.* ] I pM ed e svHrh -ittr-r efve l-44,4 CG E i t h a n y c o n t r o l r o d o u t C+rty ] and fuel a. on any refueling hoist C6i44) and refueling platform near or over the vessel Corit h c- 0 cav b. Hoist overload. C0.503 c. High position limitations. CO.503 (us*** CATEGORY 6 CON;INUED ON NEXT PAGE xxxxx)

62a_EkeHI EIIIEBE_QESIGHt_GQHIBQLt_6HQ_INSIBWBENIeIIQB Paso 32 REFERENCE OFP 100-1, MASTER REFUELING PROCEDURE: Section E.1.b(3), Rev. 13, pg. 4. 234000K402 ..(KA's) ANSWER 6 04 (1.00) g ilcd,- s n L Nb g 4 6' g c. Vibrations to.503 b. 40 +/- 5%. [0.503 REFERENCE GOP 600-3, PLACING THE SECOND MAIN FEEDWATER REGULATOR IN SERVICE, Section Ae Rev. Se pg. 1 259001K307 ..(KA's) ANSWER 6.05 (1.50) Loss of these fans siay result in a positive pressure inside the reactor building 00 503. Excessive building pressure would eventually cause one (of the six) reactor building blow off panels (refuel floor level) to be released to.503. The reactor building supply fans E0.253 automatically trip at a building pressure of + 1.0 +/- 0.2 inches 00.253. REFERENCE 00A 5750-5, LOSS OF REACTOR BUILDING EXHAUST FAUS: Sect. Ee Rev. 7, pg. 2 288000K305 ..(KA's) i ANSWER 6.06 (1 00) 8,,$ g.[r' %.%,d~ps.,. if, i ?,13,7 L La g, po ,, s u wi, ni+rs].r.c 13-ms3 p ,1 REFERENCE 00A 6100-1, Loss of Transformer 12(22) During Power Operation, Rev. 2, Section Be pg. 1. 262001K103 ..(KA's) i I (us*** CATEGORY 6 CONTINUED ON NEXT PAGE assus)

fu,.Pj ANI_gISI[df_QESIGHt_QQNIBQ(1.66Q INSIBQUEMI61108 Paso 33 ANSWER 6.07 (0 75) c. Group I b. Group II c. Gro,up III CO.25 point for each item] REFERENCE 00A 6100-4, STATION BLACKOUT, Rev. 2, Section B.6' PS. 1. 223002K601 ..(KA's) ANSWER 6.08 (4 00) o. (1). WILL M hJUTO INJECT. (2). Gland seal reondensor will be unable to maintain a vaevum (because non-condensable gases would not be removed to maintain -10 inche, of water). WILL NOT AUTO INJECT. / g./u.41 e dj.gmew a[ c.a 6*t'O' M A4 n,_,d J vu ym n/,. b. (1). zt (2). Unsbie i.w -est epte: IvbMet i r.,n i egiftTmnt--(M1TET 17artu arui_.1/a t r:e d pmt i:n ba4<,* -2,00 0 r pe).y W,cu c. (1)."AUTr. INJECT. (2). It would be possible to drain the CCST into the torus,. ( 1 ). <' AUT O.IN JECT. En s,wlJ $ t<-W 6 6 L ~'*t h w UM '- % ~ LJAL"c / d. ,q -.). / g (to (2). The desired system flow would be unabis to be achieved 2,4+ d,. g w < A t. b n/% eactor pr essures1pb, rh accomodate varying s.w M /< ~ wyfu. t'/LT de u.lu. y 6 Ti< [0.50 p oint for each it'em3 (Correct alternate answers will be accepted). .w @ yet MJ ( &t ) MM /vM N 6O Vc MV /h1 5 Lw ;,9 3f (u $ }), REFERENCC pawt j Quad Cities Lesson Plan, LIC-2300-1, HPCI SYSTEM, Rev. O, pgs. HPCI-9, HPCI-12, HPCI-13, HPCI-17, and HPCI-31. Ruad Cities SRO Requal Exam, Duestion 6.09, date unknown. 206000A214 206000K417 206000K413 206000K401 ..(KA's) l (unt** CATEGORY 6 CONTINUED ON NEXT PAGE unmar)

412_EtoBI_SIBIEdH_QESIGU1_GQNIBQL1_6bQ_INSISQbEUI61190 Pagn_34 ANSWER 6.09 (1.00) d a Losp,of high speed protective relayins 40.1^:. 4-d.' rect transfer trip CO.4t9 capability for incoming power lines (0403 and 0404). [0.20] (The Unit 2 Senerator trip scheme upon loss of these lines is necessary, because the Iowa-Illinois System cannot handle the output from both units). Ogg 5 " b)" 7 6-6 3 (-. b/<0 REFERENCE 00A 8650-1, LOSS OF POWER TO MICROWAVE RADIO BUILDING, Section E.1,- Rev. 1, pg. 2 262001K404 ..(KA's) ANSWER 6.10 (2.50) s. False (operator needs to press SYSTEM INITIALIZE button). b. False (INSERT and WITHDRAWAL rod blocks are active). c. False (either steam flow or feedwater flow). d. False (at any power). e. False (except for rods withdrawn errors or rods in the current sequence step). [0.50 pt for each item] REFERENCE 00P 207-1, NEW ROD WORTH MINIMIZER OPERATION, Section Er Rev. 3, pas. 1-2 201006K402 201006K401 201006K409 ..(KA's) i ANSWER 6.11 (2.00) C-9 u ii i,i o i,i o n s i g n a 11p 7 eda t. a. Fsler 'eute etert ;F e ri b. False (Shift En3 neer can authorize this) 1 c. False (2-6 hours) d. True l l l l (xxxxx CATEGORY 6 CONTINUED ON NEXT PAGE xxxxx) l

6___P(8HI_@ISIEdg_QEf1GNt_GQUIBQLt_6HQ_IN@lBybEBI$11gd Pega 35-REFERENCE 00P 2400-1, ACAD/ CAM SYSTEM, Sections E and F.2.ar Rev. 7, Pss 2-3 223001K404 ..(KA's) ANSWER 6.12 (1.00) Drywell radiation monitors are not physically inside the drywell CO.753; cnd are located inside sleeves OR shielded by the material around the detector [0.253. REFERENCE 00P 2400-1, ACAD/ CAM SYSTEM, Section E.3, Rev. 7' P3 2. 272000K119 ..(KA's) ANSWER 6.13 (2.10) APRM(fixed {highflux)E4,Ot]hlessthanequal to 15% rated neutron a. flux E+cFP]rin REFUEL 6r STARTUP HOT STANDBY Mode E0.10' Oc "w4d"

c. h 7.7 a, fus o m.'

CotsJ T (variableihighflux) Mode E4vst301ess than equal to 'O.58 W + 62' b. APRM (FRP/MFLPD) C 263rin Run [Gv++3b(maximum set point of 120% for thanequal[ciI to 98E+6 lba/hr) core flow o greater eA c. APRM INOPERABLE CO.30] due to: (1). Less than 50% of assigned LPRM's in OPERATE. [0.103 (2). APRM module unplussed. CO.103 (3). APRM mode switch not in OPERATE. CO.103 d. APRM downscale LO.30] with an associated IRM Hi Hi or INOP [0.103 in Run Mode CO.103. REFERENCE 00P 700-4, APRM SYSTEM OPERATION, Section E.2, Rev. 5, pg. 2. 215005K402 ..(KA's) l l /, N ANSWER 6.14 (be50) nurmally u l v o d - v e-14eh-p c:lae. (T;.i> l 4. e d). -b, t-True. l l

6. se. V False.

(Both CS pumps will inject into both loops). [0*.50 point for each] 1 (xxxxx CATEGORY 6 CONTINUED ON NEXT PAGE xxxxx)

\\ 6_._BL88I_f!EIEdg_QESIGHt_QQ8IBQLt_68Q IUSIBQbEUIGIIQN Paso 36 REFERENCE 00A 1400-1, CS SYSTEM AUTOMATIC INITIATION, Sec. B.1, Rev. 8, pg. 1. Quad Cities' Lesson Plan, CS SYSTEMr LIC-1400, Rev.1, pgs. CS-5 and CS-6. Quad Cities SRO Requal Exam, Question No. 6.08.de Licensee's ref. pg. 1951G. 209001K408 209001K407 209001K405 ..(KA's) ANSWER 6.15 (1.50) a. RCIC turbine area CO.153 high temperature [0.153 200 +/- 5 degrees F CO.203. b. RCIC Steam Line high flow [0.30] / flow [0.jp'7withaturbinedelay-CO.103'of 300%ofrated)steamsecond,CO.1^g_ 3 ~Z-c. Reactor vessel low pressure [0.303 50 +/- 2 psis CO.103 REFERENCE 00P 1300-2, RCIC System Manual Startup, Section E.1, Rev. 6, pg. 1 259002K116 217000K107 ..(KA's) i ANSWER 6.16 (1 25) t Start the opposite train and dra air through the affected t ain CO.753 from the turbine building Cerf5} via the train cross connect .)' 00 REFERENCE 00P 1600-1, DRYWELL PRESSURE RELIEF THROUGH SBGTS, Sec. D.2, Rev. 5, pg. 1. 261000K402 261000G001 ..(KA's) ANSWER 6.17 (0.50) i t the ECCS Fill System. CO.503 l (fr+:0, cr w k J 4 Mm o (M *- 0cc W( . h d, c-t. M% k.a., wt REFERENCE 5 d S'* * ). l l Lesson Plan No. LIC-1400, CS SYSTEM, Sec. B.13.ar Rev. 1, pg. CS-8. 209001K402 ..(KA's) (xxxxx END OF CATEGORY 6 x*xxx) l l

23. _BRQQEQQB[g_- _NQBd6(t_6@NQBd6(t_Ed[BGENCY Pcss 37 8bE_B6EI9b99196b_99dIB9b t

AN ER 7.01 (1.50) \\ \\ u off filter ex ust f ns 1 and 2. N Tur bypass hav fan. \\ is a/[ fire in HVAC charcoal bed by '\\Detered i r ins i #s of e'cessive heat. If here s)titlic a tion of a f i r e, notify Shift Engineer. / /'R C o n t 'a t!J' O h pervisor. C 3 of 5 r equ/ // / '0 50iist'i%y' N' + at ts ea ,/ N REFERENCE y', sy h 00A 701-B Revision 1, Item B-5, .2 294001K 6 /. ( K A ' s ) ANSWER 7.02 (1.50) Attempt to operate the drive in both positions (to determine the exact position). Verify normal drive water flow fluctuation. Increase drive water pressure and attempt to move the rod. If control rod does not mover consult TS (TS 3.3.A.2.a and TS 4.3.A.2). l [3 of 4 required at 0.50 pts each] REFERENCE l 00A 300-2, Inability to Drive A Control Rod Control Rod Stuck, Rev. 4 201001G014 ..(KA's) l (***** CATEGORY 7 CONTINUED ON NEXT PAGE

• • • • • )

i ,-w w. -m -g y

Z.t.,_P8QQgQQBEji_ _HQBHekt_8@HQBde(1_gbgBQgNQX Paga 38 GHQ_BeQI9699IG66_G9 BIB 9L S #'" 4,,,,,,, c.., h g A d 4u? g- / u c. - ins,u,j k Tu w w r u d 't 'l (' g;, * . ANSWER 7.03 (1.50) - t u @M hA, *.4<f I p/ 4 ? Remove breathing air mask. e [u s s,30. Isolate air line manifold supply valve. Don an air pack. Evacuate CR to shutdown /cooldown the unit. [3 of 4 required with each worth 0.50 point each] REFERENCE 00A 5750-13, T0XIC AIR OR SMOKE IN THE CONTROL ROOM, Rev. 5, pgs. 1-2 IE Rpt No. 50-254/87019 (DRP) dtd 10-15-87, pg. 10 LER 87014, Rev. 0 294001K113 294001K111 ..(KA's) Qy 0/D - (, ?L W W M h) 4/'TH WE Cuk. Gem /4cca$)idLC~, / 4' ANSWER 7.04 (3.00) o. As RPV water level is lowered, the driving head for natural circulation is decreased [0.5]. The resultant reduction in core flow causes an increase in void fraction to add negative reactivity to the core [0.53. b. To continue attempts to achieve reactor shutdown [1.0]. c. Flow stagnation water level; OR lowest water level in the downcomer region, which can support natural circulation flow through the steam seperators with no control rod insertion from a 100% power control rod pattern and no boron injectioni OR top of the active fuel [1.03. (Any of these answers is acceptable for full credit). REFERENCE GGA 500-7, LEVEL / POWER CONTROL, Rev. 1, pg.3. Emergency Operating Procedures (GGAs) Lesson Plan, pg. 125. GE Emergency Operating Procedure Fundamentals, pg. C7-2. 295037K303 295037K209 295037K102 293008K134 293008K121 ..(KA's) 1 l (***** CATEGORY 7 CONTINUED ON NEXT PAGE xxxxx)

s Z1__PBQQEQQBEH_:_HQBd8(t_6@NQBd86t_EMEBGEHQY Pass 39 ' 689_B89I0699198L_G981896 ANSWER 7.05 (3.00) a. to ensure that steam will not be discharged directly into the air space of the suppression chamber. [1.00] b. (1). At least 50 psis is needed to keep the relief valves open. (Emergency depressurization can be considered cos-plete below this value). [1.003 (2). This is the minimum number required to attain the depressurization rate needed to maintain peak cladding temperature less than 1500 degrees F. [1 00] REFERENCE OGA 500-2, EMERGENCY REACTOR PRESSURE VESSEL (RPV) DEPRESSURIZATION, Rev. 1, pg. 3. GE Emergency Operating Procedure Fundamentals, pg. C2-1. Emergency Operatins Procedures (OGAs) Lesson Plan, ps. 97. 218000G007 295030K301 295030K208 295025A204 218000K302 ..(KA's) ANSWER 7.06 (1.50) HPCI flow controller (2340-1) Off sas panel (901-54 (902-54)) process radiation monitor panel (901-10 (902-10)) RPIS, rod select, RWM feedwater level control system process computer control room panels 90X-3, 5, 6, and 7 process radiation recorder (panel 912-4) PCI relay panel (901-17 (902-17)) SRM, IRM, APRM recorders RCIC flow controller and testable check valve YARWAY narrow ranse level instrumentation main steam relief and safety valve acoustic position monitors (Alternate correct answers will be acceptable). EAny 5 worth 0.30 point each] REFERENCE 00A 6800-3, 120/240 VAC ESSENTIAL SERVICE BUS FAILURE, Rev. 8, pgs. 3&4. Guad Cities SRO Rep 1 Exam, Question No. 7.01.b, Ref. No. N-NOLR-SRO-C-85. I 262002K305 262002K303 262002K302 262002K301 ..(KA's) i i I l (xxxxx CATEGORY 7 CONTINUED ON NEXT PAGE xxxxx) [-

21__PBQQE0gSEg_ _NgSd6Lt_6@HQ8d6Lt_gdgBGENG! Pass 40 l GUQ_B60IQLQGIGeb_GQUIBQL I i ANSWER 7.07 (2.50) Reduce loads as necessary. Trip EGC and return to MANUAL flow control. Reduce recirculation flow at least 20% speed. Place RWM mode switch in the BYPASS position. (00P 207-2 is not required to be completed.) Insert control rods startins at the present location in sequence and work backwards. Any rods inserted should be continuously inserted all the way to position 00. Check flow control line (FCL) and continue control rod insertion until the reactor is under the 100% FCL. Monitor reactor power and water level. Verify 'A' heater string isolates and bypass opens. If reactor power is low enough to permit operation in two heater strings (Note: it will be) prevent heat bypass opening by putting bypass valve control switch to PULL-TO-STOP. As soon as 'A' heater level is reduced, return switch to normal. Notify Shift Engineer if switch position is off normal. [5 of 10 required at 0.50 pt each3 REFERENCE GOA 3500-1, LOSS OF FEEDWATER HEATERS, Rev. 4, pg. 2 Feedwater Heater LIC-3200-2, Rev. 1, pg. 24 P&ID M-61, Diagram of Extraction Steam Pipins, Rev. H 259001G014 ..(KA's) ANSWER 7.08 (1.00) l a. Control rod with an inoperable accumulator is inserted ' full in.' (0.5) l - b. Its directional control valves are electrically disarmed. (0.5) l l l l l (xxxxx CATEGORY 7 CONTINUED ON NEXT PAGE xxxxx)

5 Z1._EBQGEQUBEE_:_HQBdebt_eBNQBdekt_EbEBGE8G1 Pogs 41 8ND_BeDIQLQ91Geb_GQHIBQL i REFERENCE 00P 300-10, CRD SYSTEM ACCUMULATOR GAS DISCHARGING, Section E.2, Rev. 4, PS. 1 Technical Specification 3.3.D 201001G001 ..(KA's) ANSWER 7.09 (1.50) c. 60 +/- 6 minutes b. 3 +/- 0.5 minutes c. immediately TRIP unit to.5 pts each3 REFERENCE 00A 5300-1, LOSS OF STATOR COOLING, Section C, Revision 4, pg. 1 245000K605 245000K303 ..(KA's) ANSWER 7.10 (1.00) The release rate of radioactive iodine increases due to the iodine spiking phenomenon. REFERENCE 00A 5400-1, Off-Gas Explosion - Recombiner and Filters Bypassed, Section Er Rev. 6, pg. 3 271000K102 ..(KA's) ANSWER 7.11 (1.00) twx6 c. p -bEs9-T H AN. (Unit i factor is 0.70; and Unit 2 factor is 0.84). b. MORE THAN. (Unit 1 change is 0.03 compared to 0.01 for Unit 2). c SAME AS01 (Unit 1 and Unit 2 set points all are reduced by 3.5%). L CD Tn*N REFERENCE Unit i TS License Condition, Item K, Am. 73 (6/30/81), pg. 6. l Unit 2 TS 3.6.H.3., Amendment No. 95, pg. 3.6/4.6-5a. i 202001G001 ..(KA's) l l t { (xxxxx CATEGORY 7 CONTINUED ON NEXT PAGE xxxxx)

Zi,_EBQGEQW8EH_:_NQBdekt_eQUQBdebt_EMESQENG1 Pass 42 edQ_B601960GIGeL_GQHIBQL ANSWER 7.12 (1.00) Structural damage may occur to the condenser (if level is exceeded and additional structural support is not installed). -Fi. v ) DC - ff M REFERENCE 00P 201-1, Draining The Reactor Vessel and Recirculation Loops, Section F.2.a, Rev. 4, p s. 4-p 3 245000G001 ..(KA's) ANSWER 7.13 (1.00) b Electrical disarm is preferred because drive water does pdT' cool E0.53 and it minimizes crud accumulation in the drive E0.53. REFERENCE 00P 300-7, CRD System, Drive Disarmament, Rev. 1 00P 300-8, CRD System, Hydraulic Control Module Isolation, Rev. 7 Unit 2 TS Basis 3.3.A.2, Amendment No. 21, pg. 3.3/4.3-7 201003G001 201003G006 ..(KA's) ANSWER 7.14 (1.50) a. Reactor is in Cold Shutdown Condition. b. All control rods are fully inserted. c. Core loading is limited (to that which can be made suberitical in the most reactive condition durins the operating cycle with the strongest operable control rod in its full out position and all other operable rods fully inserted). (Alternate wording is acceptable). CO.50 pt each] REFERENCE 00P 1100-1, Standby Operation of SLCS, Section E.1, Rev. 6, ps. 1 Units 1 and 2 TS 3.4.A 211000G005 211000G001 ..(KA's) (xxxxx CATEGORY 7 CONTINUED ON NEXT PAGE xxxxx) t i

ZA__PE9GEQUBES_ _HQ8d6(t_6@HQ8d6(t_EMEBGENG1 Paga 43 ~ 6NQ_869I9699IGek_G98I896 ANSWER 7.15 (1.50) c. re-pressurization " ge '} b. uling (CWA ft M N *NN * +f' 9 (0.5 pts each) . REFERENCE 00P 1000-5, Shutdown Cooling Startup and Operation, Sections D.6, D.8, and E.2, Rev. 13, pg. 2-3 205000K114 205000K115 205000K101 ..(KA's) ANSWER 7.16 (2.00) o. RPV water level must be reduced to verify proper level instrument response. C1.03 b, To ensure adequate core cooling. [1.03 (Correct definitions of Maximum Core Uncovery Time Limit will also be given full credit). REFERENCE OGA 500-6, REACTOR PRESSURE VESSEL FLOODING, pg. 15. GE Emergency Operating Procedure Fundamentals, pg. C6-6. Emergency Operating Procedure (GGAs) Lesson Plan, pg. 119. 295031K201 295031K101 295024K305 216000K501 216000K324 ..(KA's) i l l l (xx*mE END OF CATEGORY 7 xxxxx) i 1

Br._eQUINISIBoIIME_PBQQEQQBE@t_QQHQIIIQNSI Pcgo 44 880_LIMIIGIIQUE ANSWER 8.01 (1.00) a. E1.003 REFERENCE OGA-00, OGA MANUAL PREFACE, Rev. 3, pas. 1-3 295031K305 295026G005 295026A202 ..(KA's) ANSWER 8.02 (1.00) a. E1.003 REFERENCE QAP 500-9, PREVENTATIVE MAINTENANCE, Sec. C.4.at Rev. 2, pg. 2. 294001K117 294001K106 ..(KA's) ANSWER 8.03 (1.00) the blowdown area would increase. [0.503 eliminate the capability of reflooding the core. 00.503 REFERENCE Unit 1 TS BASIS 3.6.G, no Amendment No. listed, pg. 3.6/4.6-23. Unit 2 TS BASIS 3.6.G, Amendment No. 95, pg. 3.6/4.6-13. Quad Cities SRO Rep 1 Exam, Question 8.10.a, date unknown. 202001G006 ..(MA's) i ANSWER 8.04 (1.00) b. E1.00] REFERENCE IE Rpt No. 50-254/87019 (DRP) dtd 10-15-87 for closing violation 254/87008-01, pg. 3 10 CFR 50.72 290003G003 ..(KA's) (xxxxx CATEGORY 8 CONTINUED ON NEXT PAGE xxxxx)

Bi__&QdINISIB6IIYE_PBQQEQUBES _Q98QIII9N@t Pass 45 1 BNQ_kIdII6II9BS ANSWER 8.05 (1.50) Acts as a backup to the main stop valve closure scram E0.50] such that the pressure and neutron flux transient is less severe to.503. When not in the 'RUN' mode. [0.503 REFERENCE Quad Cities Lesson Plan, REACTOR PROTECTION SYSTEM, LIC-0500-1, Rev. 1, pg. 30. Unit 2 TS BASIS, Amendment No. 86, pg. 3.1/4.1-3. Quad Cities, SRO SRO Requal Exam, N-NOLR-SRO-B-85, Question No. 8.05, Items a & c. 212000G006 212000K412 212000K111 ..(KA's) ANSWER 8.06 (1.00) 7.5 +/- 2.5 spm (0.503 200 +/- 10 degrees F CO.503 REFERENCE Unit i TS BASIS, no Amendment No. listed, pg. 3.2/4.2-8. 239001K114 ..(KA's) ANSWER 8.07 (1 50) o. False (1/4 inch) b. True c. False (99% efficiency) [0.50 point each] REFERENCE Unit 2 TS BASIS 4.7.C, Amendment No. 34, pg. 3.7/4.7-17. 290001K104 290001G006 ..(KA's) ANSWER 8.08 (1.00) Lowering the reactor vessel low water level scram would increase the capability requirement of each of the ECCS components. C1.003 (xxxxx CATEGORY 8 CONTINUED ON NEXT PAGE xxxxx)

8 a___eQb1HISIB8IIME_P8QCEQQBE@i_GQH01I19851 Pog2 46 689_LIMIIeIIQHS REFERENCE Unit 1 TS BASIS, no Amendment No. listed, pg. 1.1/2 1-14. 259002G006 ..(KA's) ANSWER 8.09 (1.00) to anticipate actuation of any Engineered Safety Feature. [1.003 REFERENCE QAP 900-5, IN-PLANT RADIOGRAPHY--REQUIRED NOTIFICATIONS AND ACTIONS, Rev. 2, Section C.1.S. 50-265 LER 86018, Revi o 294001K103 ..(KA's) ANSWER 8.10 (1.50) Severe weather conditions threaten safe transport. A significant radiological hazard would be encountered. There is a security threat occurring which would have an adverse impact on the personnel while leaving the site. A condition similar to these in magnitude which, in the opinion of the Station Director, CCC Director, or Manager of Emergency Operations, would adversely affect the site personnel. [0.50 point each for any 3 items] REFERENCE GSEP, Section 6.4.3.1, Rev. 6, pg. 6-35 294001A116 ..(KA's) (xxxxx CATEGORY 8 CONTINUED ON NEXT PAGE xxxxx)

TEST CROSS REFERENCE Psso 1 9WESII98 _MeLWE BEEEBENCE_

• 5.01 1.00 ZZZ0000001 5 02 3.00 2Z20000002 5.03 1 00 ZZZ0000003 5.04 1.00 22Z0000004 5.05 1.00 ZZZ0000005 5.06 2.00 ZZZ0000006 5.07 1.25 ZZZ0000007 5.08 1.50 ZZZ0000008 5.09 1.00 ZZZ0000009 5.10 2.00 ZZZ0000010 5.11 1.00 ZZZ0000011 5.12 1.00 ZZZ0000012 5.13 1 75 ZZZ0000013 5 14 1.00 ZZZ0000014 5 15 2.00 ZZZ0000015 5.16 1.50 2ZZ0000016 5.17 1.00 ZZZ0000017 5.18 1.50 ZZZ0000018 25.50 6.01 1.50 Z270000019 6 02 1.50 22Z0000020 6.03 1.50 ZZZ0000021 6.04 1.00 ZZZ0000022 6.05 1.50 ZZZ0000023 6.06 1.00 ZZZ0000024 6.07 0.75 ZZZ0000025 6.08 4.00 ZZZ0000026 6.09 1.00 ZZZ0000027 6 10 2.50 ZZZ0000028 6.11 2.00 ZZZ0000029 6.12 1.00 ZZZ0000030 6.13 2.10 ZZZ0000031 6 14 1.50 ZZZ0000032 6.15 1.50 ZZZ0000033 6.16 1.25 ZZZ0000034 6.17 0.50 ZZZ0000035 26.10 7.01 1.50 Z2Z0000036 7.02 1.50 ZZZ0000037 7.03 1.50 Z220000038 7.04 3.00 ZZZ0000039 7.05 3.00 ZZZ0000040 7.06 1.50 ZZZ0000041 7 07 2.50 ZZZ0000042 7.08 1 00 ZZZ0000043 7.09 1.50 2ZZ0000044 7.10 1 00 ZZZ0000045 7 11 1.00 ZZZ0000046 7.12 1.00 ZZZ0000047 7.13 1.00 Z2Z0000048 7.14 1.50 2ZZ0000049

TEST CROSS REFERENCE Pass 2 DbESIIQH _YoLUE BEEEBEUGE_ 7.15 1.50 ZZZ0000050 7 16 2.00 ZZZ0000051 \\ i;;; 8 01 1.00 ZZZ0000052 8 02 1.00 ZZZ0000053 8.03 1.00 ZZZ0000054 8 04 1.00 ZZZ0000055 8.05 1.50 ZZZ0000056 8 06 1.00 ZZZ0000057 8.07 1.50 ZZZ0000058 8.08 1.00 22Z0000059 8.09 1.00 2ZZ0000060 8 10 1.50 ZZZ0000061 8.11 1.00 ZZZ0000062 8.12 1.00 22Z0000063 8.13 1.00 ZZZ0000064 8.14 2.00 22Z0000065 8.15 0.50 ZZZ0000066 8 16 1.00 ZZZ0000067 8.17 1.25 ZZZ0000068 8.18 1.50 2ZZ0000069 8.19 1.00 ZZZ0000070 8.20 1 00 ZZZ0000071 8.21 1.50 ZZZ0000072 8 22 0.50 ZZZ0000073 24.75 g 102.3 l l l l l

TEST CROSS REFERENCE Peso 1 9yESIIgg _V8Lyg BEEg8ENQg_ 5.01 1.00 ZZZ0000001 5 02 3.00 ZZZ0000002 5.03 1.00 ZZZ0000003 5.04 1 00 ZZZ0000004 5.05 1.00 ZZZ0000005 5.06 2.00 ZZZ0000006 5.07 1.25 ZZZ0000007 5.08 1.50 ZZZ0000008 5.09 1.00 ZZZ0000009 5 10 2.00 ZZZ0000010 5.11 1 00 ZZZ0000011 5.12 1.00 ZZZ0000012 5.13 1.75 ZZZ0000013 5 14 1 00 2Z20000014 5.15 2.00 ZZZ0000015 5.16 1.50 2ZZ0000016 5.17 1 00 ZZZ0000017 5.18 1.50 ZZ20000018 25 50 6.01 1.50 22Z0000019 6 02 1.50 ZZZ0000020 6.03 1.50 ZZZ0000021 6.04 1.00 ZZZ0000022 6.05 1.50 ZZZ0000023 6.06 1.00 ZZZ0000024 6.07 0 75 ZZZ0000025 6.08 4.00 2220000026 6.09 1.00 ZZZ0000027 6.10 2.50 ZZZ0000028 6.11 2.00 ZZZ0000029 6.12 1.00 ZZZ0000030 6.13 2.10 ZZZ0000031 6 14 1.50 2220000032 6.15 1.50 ZZZ0000033 6.16 1.25 ZZZ0000034 6.17 0.50 Z2Z0000035 26.10 7.01 1.50 ZZZ0000036 7.02 1.50 ZZZ0000037 7.03 1.50 ZZZ0000038 7.04 3.00 ZZZ0000039 7 05 3 00 2220000040 7.06 1.50 22Z0000041 7 07 2.50 22Z0000042 7.08 1 00 ZZZ0000043 l 7 09 1.50 ZZZ0000044 7.10 1.00 ZZZ0000045 7 11 1.00 ZZZ0000046 7.12 1.00 ZZZ0000047 7 13 1.00 ZZZ0000048 7.14 1.50 ZZZ0000049

TEST CROSS REFERENCE Pc32 2 99ESIIQB _VebuE BEEEBENGE_ ^ 7.15 1.50 ZZZ0000050 7 16 2.00 ZZZ0000051 26.00 8.01 1.00 ZZZ0000052 8.02 1.00 ZZZ0000053 8.03 1.00 ZZZ0000054 8.04 1.00 ZZZ0000055 8.05 1.50 ZZZ0000056 8.06 1.00~ ZZZ0000057 8.07 1.50 ZZZ0000058 8.08 1.00 ZZZ0000059 8.09 1.00 ZZZ0000060 8.10 1.50 ZZZ0000061 8.11 1.00 ZZZ0000062 8.12 1.00 ZZZ0000063 8.13 1.00 ZZZ0000064 8.14 2 00 ZZZ0000065 8.15 0.50 ZZZ0000066 8.16 1.00 22Z0000067 8.17 1.25 ZZZ0000068 8.18 1.50 ZZZ0000069 8.19 1.00 ZZZ0000070 8.20 1.00 ZZZ0000071 8.21 1 50 ZZZ0000072 8.22 0.50 22Z0000073 24.75 102.3

S___6DMINISIBoIIMg_P89QEQQ8E@i_GQNQIIIQMSI . Pass 47

• BHQ_LIdIIBIIQMS ANSWER 8.11 (1.00)

It is impractical to modify the equipment or procedure to allow testing in a normal alignment. The test is per a regular procedure. An operator is available to return the switch immediately when the test is completed or if interrupted. CO.50 point each for any 2 items] REFERENCE DAP 300-2, CONDUCT OF SHIFT OPERATIONS, Sec. C.8.b(3), Rev. 19, pg. 5. 294001K106 ..(KA's) ANSWER 8.12 (1.00) c. C1.00 point] fREFERENCE DAP 300-22, WATER CHEMISTRY CONTROL, Sec. C, Rev. 4. 294001A114 294001A116 ..(KA's) ANSWER 8.13 (1.00) Tla SDCE ^will consider initiating training of shift personnel. [0.50] 'Tta SVEE w L( ^ ensure the Shift Engineer receives an authorized copy of the temporary procedure. CO.50] EFE ENC gg.g g., f g/g# M/gg;>weg [bCchd IM//5d 1100-5, TEMPORARY PROCEDURES AND TEMPORARY CHANGES TO PERMANENT PROCEDURES, Sec. C.6, Rev. 17, pg. 2. 294001K106 ..(KA's) i [ w v.w. a c{ h b k r w ) 4: il v -f&g [(se' ev gf fd:2)s 7 a 1 X

• 3 ; z i m Wk m j*" v

% 5LA't~ "~' Y '. M M W A ta f*ytn ad 2 w iew()LL tu (')is .. _T %,.m wew rh De cuyGM u (xxxxx CATEGORY B CONTINUED ON NEXT PAGE xxxxx) 4 $ ' l M*'4" f w if yg 1 __u... 4 *,+4wk/LW l**

B_._eQblHISIBoIIVE_E8QGEQWBES _GQ891119831 Pogo 48 t 6HQ_LIMIIGIIQHE ANSWER 8.14 (2.00) a. False. b. False. c. False. d. True. CO.50 point each3 REFERENCE GAP 1120-6, ENTERING A LOCKED HIGH RADIATION AREA WITHOUT A TIMEKEEPER, Sec. C, Rev. 9, P3s. 2 & 3. 94001K103 ..(KA's) ANSWER 8.15 (0.50) 20 (or less) minutes. CO.503 I I REFERENCE QAP 1170-14, FIRE WATCH RESPONSIBILITIES, Sec. C.4, Rev. 1, Ps. 1. 294001K116 ..(KA's) i ANSWER 8.16 (1.00) a. be within 10 minutes of the control room. CO.503 b. be able to be reached immediately. CO.503 REFERENCE GAP 300-1, OPERATIONS DEPARTMENT ORGANIZATION, Sec. C.3.br Rev. 15, pg. 2. 294001A103 ..(KA's) ANSWER 8.17 (1.25) This margin is demonstrated by full withdrawal of the strongest rod [0.503 and partial withdrawal of an adjacent rod CO.503 to exceed a calculated margin (R + 0.25% delta K) CO.253. l i I l (xxxxx CATEGORY 8 CONTINUED ON NEXT PAGE xxxxx) l l l 1

EA__AQUIBISIBATIVE_P8QgEQUBES, CONDITIQBS1 Pcg3 49 889_LIMIIBII9NS REFERENCE 00P 300-14, CONTROL ROD OR CRD MAINTENANCE, Sections C.6 & F.1, Rev. 7. Unit 2 TS BASIS, 3.3.A.1, Amendment No. 21, pg. 3 3/4.3-7. 201001G006 ..(KA's) ANSWER 8.18 (1.50) To assure that the maximum in sequence individual control rod or control rod segments which are withdrawn CO.503 could not be worth enough to cause the rod drop accident design limit (280 cal /sm) to be exceeded [0.503, if the rods were to drop out of the core in a manner defined for the rod drop accident CO.503. Alternate wording is acceptable. REFERENCE Unit i TS BASIS 3.3.B.3, pg. 3.3/4.3-11, No Amendment No. listed. 215004G006 ..(KA's) ANSWER 8.19 (1.00) e. [1.003 REFERENCE DAP 300-14, EQUIPMENT CUT-OF-SERVICE, Sec. C.13, Rev. 14, pg. 3. 294001K102 294000K101 ..(KA's) ANSWER 8 20 (1.00) e. 30 +/- 5 % b. 30 +/- 5 days to.50 point for each item] REFERENCE QAP 300-19, REVIEW OF ACTIVE OUT-OF-SERVICES, Sec. C.2, Rev. 7, pg. 1. 294001K102 ..(KA's) (xxx** CATEGORY 8 CONTINUED ON NEXT PAGE xxxxx) i

a___eQUINIEIBoIIYg_EBgCggyBgst_GQNQIIIQBQ1 Peso 50 889_b15I10I1983 ANSWER 8.21 (1.50) a. Station Manager b. Shift Foreman. c. Radwaste Foreman. [0.50 point each3 REFERENCE QAP 1180-17, FIRE PROTECTION PROGRAM, Sections C.b(1), C.b(5), & C.b(6), Rev. 1r pgs. 2 & 4. 294001K116 ..(KA's) ANSWER 8.22 (0.50) Station Industrial,Hy iene Advisor,. [0.50] '[ pt % cAtwY 2%% f(M [fEli*" ibm {W REFERENCE p ( Wa - ~ QAP 1150-6, ACCESS TO CD FINED SPACES, Sec. C.2.a, Rev. 4 pg. 1. l 294001K114 ..(KA's) r l l (xxxxx END OF CATEGORY 8 maxxx) l (xxxxxxxxxx END OF EXAMINATION xxxxxxxxxx)

i Pcoo 1 of 5 Dele _SUEEI EFEBCIQB_IUEQBY_EQBduLOS: t 5UR(t) p. p e /T P=P 10 O I I th SUR = 26.06/v P = ---------10 3.12 x 10 fissions /sec 7I -(B L ~+~ ~~ th p th 2 2 y 1 + y 1 + (B L th K~ I -(B L ) P =e f A = ----- j K K AP = In bbOfb-- p,,-CN3CI,4j]/lI, initial ~ eff C (1-Peff!) =C (1-Keff2) g T = -------- 1 2 1* 1 C_flesl__ y. __ ,n 1-Cinitial 1 of 1 op OL 2 + 6L 2 th 2 (--f ---+----B e = T f at p at at at f~ ~~ K =E P pP f f) P =P g4 4 g 3 O Oeff P 1 1 i 1

Pc W 2 of 5 DOIe_geggy IUEBdQDYued1CS_0ND_ELVID_DEC8001CS_EQBuuLOS: 0 = 4 oh 2 w LaT Q = ----------------------- 1 In R /R In R /R 2 3 3 2 ,0=UA (AT ) - + -------- + -------- K K K 2 3 .Q =

m. c (oT) 4 p

b = cc &AR

n. _Le_:_0 0

_ewt n. -_Le___h_ewt _) ttel__ (h Q (h -hg ) ideal in g actual 1 1 22 y p W T T supplied 1 2 A = pAv pAv = p2"2 2 V g 3 1 3 & = KA 4 LP p 5 = KA di = KA ST [5T = KA op [ 3 x nc Q . GI_1101_ _eI_lew11 e._1!!b___ 67m 9 AT (in) 8.8x10 1n (--------) AT (out) Gr kAoT Q = ----- T -T = --- c1 ps u ox total ,Q = gg--- gg-- gy a b n ___ + ___ + + K K K a b n

Pcoo 3 of 3 Dele _syggy GEUIBIEUG96_EUdE_ LOWS .1. A_1 I I (N ) H (NI) P N I N (N H (N2) P 2 2 2 2 2 60D19110S_eND_CSEd1SI6Y_EQBdWL95: R/hr = 6CE/d I IO' 1 1 22 = 1 ill" C=CO* G = DLlyttgn_Batt I = 0 Volume 10 t O, A = AN A=A CONVEBS10SS: 62.4 lbm/ft Density of water (20 C) 62.4 lbm/ft 1 gr/cm = = 1 gal = 8.345 lbm 1 ft = 7.48 gal Avogadro's Number 6.023 x 10 = 1 gal = 3.78 liters Heat of Vapor (H O) = 970 Btu /lbm 2 1 lbm = 454 grams Heat of Fusion (ICE) = 144 Btu /lbm -24 e = 2.72 1 AMU = 1.66 x 10 n = 3.14159 Mass of Neutron = 1.008665 AMU 1 KW = 738 ft-1bf/sec Mass of Proton = 1.007277 AMU 1 KW = 3413 Btu /hr Mass of Electron = 0.000549 AMU l 1 Mc = 550 ft-lbf/sec One atmosphere = 14.7 psia = 29.92 in. Hg i H: =.746 KW 'F = 9/5 'C + 32 l 1 HP = 2545 Btu /hr

• C = 5/9 ('F - 32) 1 Btu = 778 ft-lbf

'R= 'F + 460 -6 1 MEV = 1.54 x 10 Btu 'K = 'C + 273 h = t.13 x 10' M-sec s 10 1 W= 3.12 x 10 fissions /sec 32.2 lbm-ft/lbf-sec c = 931 MEV/ AMU g = 0 2.54 cm C=3x 10 m/sec 1 inch = -8 e = 0.1714 x 10 Btu /hr ft R 1

Pcgo 4 of 5 DOIG_SWEEI e'VE B e QE _IB E 8 d e L _C QU DUC I1V II L IE L datettal K Cork O.025 Fiber Insulating Board 0.028 Maple or Oak Wood 0.096 Building Brick O.4 Window Gl ass O.45 Concrete 0.79 1% Carbon Steel 25.00 1% Chrome Steel 35.00 Aluminum 118.00 Copper 223.00 Silver 235.00 Water (20 psia, 200 degrees F) 0.392 Steam (1000 psi a, 550 degrees F) 0.046 Uranium Dioxide 1.15 Helium 0.133 Zircaloy 10.0 01SCELLONEQUS_INEQBdellON: 2 E = mc 2 KE = 1/2 mv PE = mgh V =V + at 4 O Geometric Object Area Volume Triangle A= 1/2 bh ///////////////// 2 Square A=S ///////////////// Rectangle A=Lx W ///////////////// Circle A= nr# ///////////////// Rec t angul ar Solid A = 2 (LxW + LxH + WxH) V=Lx Wx H 2 + 2(nrz) V = nr h Right' Circular Cylinder A= (2 nrz)h Sphere A= 4 nr V = 4/3 (nr2) 2 0 Cube ///////////////////////////// V=5 l

Pc00 5 of 5 e DGIG SeggI D15CELLONE0VS_1NEDBd8Il0N_1cootlawedi 10 CFR 20 Appendix B Table ! Table II Gamma Energy Col I Col II Col I Col II MEV per Air Water Air Water Material Half-Life Di si nt eg r ati on uc/mi uc/mi uc/ml u c / r.1 -6 -0 4x10 Ar-41 1.84 h 1.3 Sub 2x10 ~# ~# ~0 ~3 Co-60 5.27 y 2.5 S 3x10 1x10 1x10 5x10 -D ~IO ~# 1-131 8.04 d 0.36 S 9x10~ 6x10 1x10 3x10 ~D ~# l3x10 Kr-85 10.72 y 0.04 Sub 1x10 Ni-65 2.52 h 0.59 5 9x10 4x10 3x10 l'x10 " ~# ~3 ~0 ~ ~A" -6 Pu-239 2.41x10 y 0.008 S 2x10 1x10 " x10 5x10 -12 ~ ~Al ~# S 1x10~ 1x10'O 3x10 3x10 Sr-90 29 y Xe-135 9.09 h 0.25 Sub 4x10 [ut 10 ~6 ~# Any single radionuclide with T > 2 hr -10 -6 which does not decay by alpha br 3x10 9x10 ?.x!O 3x10 ~ ~ cpontaneous fission Neutron Energy (MEV) Neutrons per cm Average t'ux to deliver equi val ent to 1 rem 100 mrem in 40 hours .x.__._ thermal 970x10 670 6 0.02 400x10 280 (neutrans) 6 0.5 43x10 30 10 24x10 37 c,2 6 ,,c Linear Absorption Coef ficients p (cm-1) }, Energy (MEV) Water Concrete Iron Lead I O.5 0.090 0.21 0.63 1.7 1.0 0.067 0.15 0.44 0.77 g 1.5 0.057 0.13 0.40 0.57 ; 2.0 0.048 0.11 0.33 0.51 2.5 0.042 0.097 0.31 0.49

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