ML20195J246
| ML20195J246 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/15/1988 |
| From: | Burdick T, Mark King, Picker B, Reidinger T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20195J195 | List: |
| References | |
| 50-346-OL-88-01, 50-346-OL-88-1, NUDOCS 8806290087 | |
| Download: ML20195J246 (117) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-346/0L-88-01 Docket No. 50-346 License No. NPF-3 Licensee: Toledo Edison Company 300 Madison Avenue Toledo, OH 43652 Facility Name: Davis Besse Examination Administered At: Davis Besse Examination Conducted: May 17, 1988 o k S . b u e d t.r l l w $ n Examiners: T. D. Reidinger 6 68 Date (W<ht fn B. Picker (o 8 8 Date g
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- 6-l5-66 Date ctd . bwdttbd et Approved By: Thomas M. Burdick, Chief 6-15-88 Operator Licensing Section 2 Date Examination Summary Examination administered on week of 16 May 1988 (Report No 50-346/0L-88-011 to ten senior reactor operators and one reactor opreator candidate.
Results: Nine senior reactor operators and one reactor operator candidates passed the examination.
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8806290087 880620 PDR ADOCK 05000346 DCD
REPORT DETAILS
- 1. Examiners
'T. D. Reidinger, NRC, Chief Examiner M.-King, EGG B. Picker, EGG
- 2. Exit ~ Meeting On May 20, 1988, the Chief Examiner met with members of the plant staff to discL.,s generic findings made during the course of the examinations.
The following personnel attended the exit meeting.
C. Blay, Nuclear Licensing J. C. Sturdavant, Nuclear Licensing P. Byron, NRC, SRI T. Reidinger, NRC, RIII A. Stallard, Nuclear Training (0perations) -
J. Syrowski, Nuclear Training R. Flood, Assistant Plant Manager, Operations R. Simpkins, Operations Training Sumary of NRC comments the chief examiner presented the following facility strengths: (1) the candidates were technically strong in the application of emergency and abnormal procedures, (2) the candidates exhibited good conceptual understanding of radiation protection, accident analysis and the facility emergency plan.
A programatic genaric weakness of the facility was observed to be a general failure of the plant personnel to follow HP 1601.03.11 Radiation Work Permits. This procedure requires each worker using an RWP upon exiting from the RCA to read the Self-Reading Dosimeter (SRD) and each person using the RWP system shall track his/her exposure.
It was observed that the vast majority of people exiting the RCA after the last portal radiation monitor were depositing the SRD into the appropriate box but not reading the SRD prior to depositing it into the box. The utility is currently revising the requirements to emphasize to all personnel exiting the RCA that they shall read the SRD. All personnel will be issued a pocket card specifying the requirements to read the SRD.
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The chief examiner made the observation that there were no procedures for directly dealing with instrument failures relating to the Integrated Control System.
The NRC recognizes that the facility has implemented long term corrective action in this regard.
- 3. Examination Review A copy of the examination and ai.swer key was given to the facility personnel for review at the conclusion of the written examination.
Facility personnel mailed their comments to the Chief Examiner after their review. Their comments and resolution of the comments are Attachment 1 to this report.
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_- ATTACHMENT 1 -
f NRC COMMENT RESOLUTION e
, 4 DAVIS-BESSE SRO EXAMINATION !
MAY 17, 1988 Question No. 5.02 -
Facility Comment: Answer given in Part b should be False. Explanation
. is contained in attached reference.
NRC Resolution: Agree with comment. .
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Answer key was modified prior to examinaticn, but review copy was not modified. -
i Question No. 5.07 Facility Comment: Part b asks to explain differences, the answer key-only gives two responses. The assigned point values indicate only two responses required. Recommend giving full credit if these two responses are among the three ~
provided on candidate exams.
NRC Resolution: Agree with comment.
Answer will be graded as indicated on the key with the two major points needed for full credit.
i Question No. 5.12 Facility Comment: Answer a is not completely accurate. Heat transfer coefficient units are BTU /hr-ft2-degrees F. The pool boiling curve is a plot of heat flux vs. differential 1
temperature. Heat flux units are BTU /hr-f t2, Heat
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transfer coefficient would be the highest where the slope of the heat flux is the steepest (in'the positive directio0 This occurs in the Nucleate Boiling region.
RecommenC accepting for full credit for Part a, additional
! response cf Nucleate Boiling region.
Answer b while Nucleate Boiling heat transfer does l~ occur at various core locations during normal full power operation, the "bulk" (as stated in the question)
RCS fluid condition is subcooled. Recommend accepting additional responses of s bcooled Nucleate Boiling or forced convection for full credit.
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l' NRC ResolutiAn: Part_a: Partially agree with coment.
Answer key is modified to accept "Nucleate
- Boiling region" as the correct answer.
Part b: . Partially agree with coment. -
Answer key is modified to accept "Forced Convection region" as the correct answer.
The answer was changed because the reference provided by the facility's comments is more accura _te or disagrees'with the reference T >
material provided for use by the examiner in developing the written examination. The referenced Examination Bank question should be corrected or destroyed.
Question No. 5.13 Facility Comment: On Part b,' recommend accepting responso for full credit explanations that describe changes in prompt neutron population. Davis-Besse does not normally refer to ,
the rho dot term in describing changes in SUR.
Reference provided will describe the Davis-Besse approach.
NRC Resolution: Agree with comment.
Answer key is modified to accept additional answer after rho dot in the answer "or prompt neutron population instantaneous changes."
Question No. 5.14 Facility Coment: Reference provided lists additional method of preventing water hammer. Reccmend accepting additional responses provided in reference for full credit.
l Partially agree with comment.
l NRC Resolution:
Answer key is modified to accept "6 starting and l stopping pumps." The other answers are already l
contained in the present answer, l
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Question No. 5.16 Facility Comment: Another method could be used tu do this calculation.
Equation sheet gives Q = mcp (Tout-Tin). If c6ndidates assumes Cp f 1.3 BTV/lbm-degrees F then:
Q m = ------------
Cp (Th-Tc) 2700 MW (3.41 x 10E6 BTV/hr/MW) m = ---------------------------------
1.3 BTV/lbm-degrees F (606 degrees F-554 degrees F) 9.207 x 10E0 BTV/hr m = ----------------------------------------
1.3 BTV/lbm - degrees F (52 degrees F) 9.207 x 10E9 BTV/hr m = ---------------------
67.6 BTU /lbm m = 1.362 x 10E8 lbm/hr = 136.2 MPPH Using Cp = 1.0 BTV/lbm degrees F m = 1.771 x 10E8 lbm/hr = 177.1 MPPH Recommend giving credit for calculation in this manner.
NRC Resolution: Agree with comment.
Answer key modified to accept either approach to the problem, i
l The answer was changed because the reference provided i
by the facility's comments expands and/or clarifies the reference material provided to the examiner for use in l developing the examination.
i Question No. 6.06 Facility Comments: Part a: The question elicits four specific responses.
l The candidates may assume supply breakers opening I (receiving a prevent close) is one response l instead of two (as identified to satisfy the question). Recommend accepting for full credit any ccmbination of correct responses.
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1 Part b: The question is worded in such a way that the candidates may respond to why the EDG is required to be shutdown using the Emergency Stop Push-button.
Recommend accepting for full credit a response similar to: Emergency Stop Push-button must be used since the normal Stop Push-Button will not lock out the EDG.
NRC Resolution: Part a: Agree with comment.
Answer key will be graded as requested, but any additional incorrect material will cause loss of credit.
Part b: Agree with comment.
Answer key will be changed to accept the utility's suggestion as an alternate correct answer for full credit.
QuestionNo.6.09 Facility Comment: Any time that the HPI pumps are operating while taking a suction from the emergency sump, they must be in the piggy back mode of operation. Recommend adding similar statement to Part 2 of the answer key.
NRC Resolution: Agree with coment.
No change to the answer key because Item 2 of answer key identifies the situation referred to in the facility comment.
Question No. 6.12 Facility Comment: Recommend the following two additional responses to this question be considered for full credit:
Administratively both HPI pump breakers are racked out.
Thermal expansion flowpath between DH11 and DH12.
Recommend not requiring setpoints for full credit since the numbers vary depending on the location and sensing device used.
Recommend adding to Ans'..:rs No. 1 and No. 2 "or will close" at specified setpoint.
Recommend accepting, in lieu of Response No. 3, "The Pressurizer Heater /DH11 and DH12 interlock.
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. NRC Resolution: Agree with comment. ,
Answer key is modified to add-the following: "5. !
' Administrative 1y both HPI pump breakers are racked out;
- 6. Thermal expansion flow path between 011 and 12;" for Items 1, 2, and 3 the reference to "301 psig" is changed to "setpoint"; also in Item 3, add "0R Pzr heater /D11 and 12 interlock and in Items.1 and 2 add "or will Close 8t" ,
after<"than."
Question No. 6.13 Facility Comments: The Diesel Fire Pump automatically starts VIA a weekly timer which simulates a low pressure condition. Recommand-accepting weekly timer as _a correct answer. !
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NRC Resolution: Agree with comment.
. Answer key is modified to accept an additional answer "3. Weekly timer."
Question No. 7.04 Facility Comment: Reconmend accepting an additional parameter for 0.5 pts of annunciator alarm, "RC PRZR PLF VLV OPEN."
Reactor coolant pressurizer relief valve open annunciator ,
receives its input from 0.25 gpm flow indication. ;
NRC Resolution: Disagree with comment. ,
The answer was not changed because the reference provided a
s by the facility is an alarm and not a parameter as asked
- in the question.
Question No. 7.07 ,
Facility Comment: Answer No. I would be satisfied within the context of the question (prior to exceeding 1.25 rem). Recommend accepting for full. credit an alternate response that
- conveys obtaining Management of Health Physics approval prior to exceeding administrative limits, t
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.NRC Resolution: Disagree with comment.
Further investigation of question has concluded that the answer key should indicate the following for answers:
- 1. Whole body dos'e shall not exceed 3 rem /qtr.
- 2. Dose calculation on NRC Form 4 complete.
- 3. 5(N-18) rule not exceeded.
Question No. 7.09-Facility Comment: An asymmetric rod @ 5% deviation (seven inches) will result in an asymmetric alarm on the Rod Position Indication Panel.
An asymmetric fa' ult @ 6.5% (seven inches) may alsc' produce the "CRD LC0" annunciator (Control Rod Drive Limiting Condition for Operation). Recommend accepting for. full credit additional response of CRD LC0 Annunciator and asymmetric alarm lamp on Rod Position Indication Panel.
NRC Resolution: Agree with comment.
1 Answer key is modified to accept "3. CRD LC0 annunciator 4
[0.5] @ 5% or 6.5% deviation. [0.5]; 4. Asymmetric rod light on rod indication panel [0.5] @ 5% deviation [0.5]." .
Quest, ion No. 7.12 Facility Comment: Although the question states "Do not list detail sub-steps," recommend accepting detail sub-steps ,
t as correct responses if they satisfy the intent of the major actions.
NRC Resolution: Partially agree with comment.
l Answer key will accept detailed sub-steps if every
, sub-step listed in the EP is provided for those major steps which are detailed. f Question No. 7.13 Facility Comment: A condition to indicate a leaking PORV is Quench Tank Pressure. Recommend accepting "Quench Tank Pressure" as an additional response for full credit.
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NRC Resolution: Agree with comment. I Answer key is modified to accept "add Item 4. I breakdown to [0 @ 5.0 each].
The answer was changed because the reference provided by the facility's comments expands and/or clarifies the reference material provided to the examiner for use in developing the examination.
Question No. 7.14 Facility Comment: Part 2 Item a states "If core cooling is not being provided by MU/HPI cooling." Additional information is provided in termination criteria that states "at least one SG is available as a heat sink." Recommend accepting for full credit in Part 2.a, "at least one SG is available as a heat sink."
NRC Resolution: Partially agree with comment.
Answer key is modified to accept "at least one SG available as a heat sink" as alternate to Part 2.a.
Question No. 7.15 Facility Comment: Uncovering the core implies that core damage will occur. Recommend deleting the point value assigned to prevent core damage and reassigning this 0.5 pts, to remainder of answer.
NRC Resolution: Agree with comment.
Answer key is modified to accept facility comment points redistributed to 0.75 on the other two parts.
Question No. 7.17 Facility Comment: Preventing inadvertent breaker closure will prevent l
overloading the No. 1 EDG with No. 1 and No. 2 site components. Recommend accepting for full credit "Prevent overloading the Emergency Diesel Generator."
NRC Resolution: Agree with comment.
1 1 The answer key is modified to accept "To prevent
! overloading No. 1 EDG" for full credit as an alternate l answer.
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Question No. 8.05 Facility Comment: Item d, recovery from a reactor trip. There are two different ways this item could be viewed.
- 1. Recovery from a reactor trip could be viewed as taking the reactor critical; therefore, prior notification required (per your key) or;
- 2. Recovery from a reactor trip could be viewed as entering the Trip Recover Procedure PP1102.03.
This procedure is entered from EF1202.01 the trip Procedure Step 4.15.11. A reactor trip requires an immediate notification.
Recommend accepting for full credit for Item d either prior or immediate.
NRC Resolution: Disagree with comment.
No change to the answer because the question referenced the Administrative Procedurt DB-0P-00002 and not those indicated in the comments.
Question No. 8.06 Facility Comment: Item b lists the DBTS (Davis-Besse Tagging Supervisor) as the individual who determines whether or not a system is critical. This procedure also states in the definition Section 4.1, that the DBTS shall be the on-duty Shift Supervisor. Recommend accepting for full credit as an alternate response Shift Supervisor.
NRC Resolution: Agree with comment.
Answer key is modified to accept "Shift Supervisor or DBTS or Shift Supervisor Designee."
Question No. 8.11 Facility Comment: Answer No. 5 lists two separate logs: Locked Valve Log and Capped Valve Log. Recommend splitting these into two separate responses and allowing 0.25 points per response, NRC Resolution: Agree with comment.
Answer modified to spiit Item 5 into two parts and redistribute valve to 0.25 for each of six responses.
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Question No. 8.14 Facility Comment: Section 6, administrative section of Technical Specifications has additional action for a Technical Specification violation. Recomend accepting additional responses that deal with administrative requirements for full credit.
NRC Resolution: Disagree with comment.
The question was designed to elicit a response containing imediate corrective actions as opposed to long term reporting requirements.
No credit will be taken off for additional information to deal with the Safety Limit Violation.
Answer key remains the same.
Question No. 8.16 Facility Comment: Based on the following reasons, this question should be deleted or alternate responses be accepted for full credit based on )rrect table identification. Some of this information tas corrected during the exam for individuals that a>Ked for clarification, however, a general announcement was not made to all candidates.
Attachment (Table 4-1) to the examination was from the '
Emergency Pian, not the Implementing Procedure EP 1500, which is used to classify events.
Davis-Besse used two separate makeup pumps and two separate HPI pumps. The candidate may assume the leak to be within the capacity of one makeup pump, therefore, not recognizing d potential loss of the fission product barrier.
NRC Resolution: Agree with coment.
Question deleted from exam.
MODIFICATIONS MADE TO ANSWER KEY DURING GRADING BY THE EXAMINER:
Question No. 6.07 Answer key modified to accept as different conditions correct RCP combinations where the power operating point of the plant is changed.
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- U. S. NUCLEAR REGULATORY COMMISSION SENIOR R4 ACTOR OPERATOR LICENSE EXAMINATION STA6 I'#6 FACILITY: DAVIS-BESSE Sfe/1TM6 RE/.CTOR TYPE: PWR-B&W177 _,
oL p 3r cA pro 47E jgp DATE ADMINSTERED: 88/05/17 g a r ~17 M S EXAMINER: E19KER..B.
CANDIDATE JfTI"l% MOV JESTRUCTIONS TO CANDIDATE:
Use separate paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 7'% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 24.50 24.35 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS,AND THERMODYNAMICS 25.40 25.25 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION 25.50 25.35 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 25.20 25.05 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 100.6 % Totals Final Grade All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS 4
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During the administration of this examination, the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating. ,
- 3. Use black ink or dark pencil 2Dlz to facilitate legible reproductions.
- 4. Print your name in the blank provided on the cover sheet of the examination.
- 5. Fill in the time you START and STOP on the cover sheet of the examination.
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of each page of the exam.
- 8. The exam has one question per page. Write the answer beneath the question (start just below ***** CATEGORY . . . ) . Write only an nam side of the exam and any extra answer sheets.
- 9. Number each answer continued on additional paper as to category and number, for example, 1.4, 6.3.
- 10. Attach continued answers to back of question to which it applies.
- 11. Place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility .
literature.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of thaa gKaminar only.
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- 17. You cuct cign the ototcaant on tho covar choct that indientcs that tha w2rk ic ycur own end ycu hcyo not recoived or bsen given cscictanca in co:pleting tha extmin tion. This cuat bo dons efter tha cxtminction
, has been completed.
- 18. When you complete your examination, you shall:
- a. Assemble your examination as follows:
(1) Exam questions with answers on top.
(2) Exam aids - figures, tables, etc. ,
(3) Scratch paper used during the examination.
- b. Turn in your copy of the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions,
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
- 5. ' THEORY OF NUCLEAR _ POWER PLANT OPERATION. Paga 2 FLUIDS.AND THERMODYNAMICS QUESTION 5.01 (1.00)
Which ONE of the following would NOT be an acceptable means for elimination of a void that has formed in an idle loop.during a single loop natural circulation cooldown?
- a. Venting through the hot leg vents
- b. Bumping an RCP
- c. Establishing full HPI flow until the void collapses
- d. Allowing the void to condense through ambient heat losses I
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
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QUESTION 5.02 (1.00)
TRUE or FALSE
- a. Doppler coefficient becomes more negative frca 0-100% power due to the increased overlapping of resonance peaks at higher fuel temperatures.
- b. Doppler coefficient becomes less negative over core life due to the buildup of Pu240 and fission products with large resonances in the epithermal range.
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
QUESTION 5.03 (1.00)
During a reactor startup, power is being raised above the point of adding heat (POAH). Which one of the following statements is CORRECT?
(Assume a linear reactor power increase to about 34 power).
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- a. Since header pressure is RSE psik, Tave will not rise above the corresponding saturation temperature of 532 degF..
- b. Since the OTSGs are low level limited and header pressure is being maintained at &&4 psi tend to follow Th.1U* g, Tave will rise and the steam temperature wil:
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- c. With the header pressure being maintained atT364 psi (g, the OTSGs wil; remain at saturated conditions and no superheat will be added.
- d. Since the OTSGs are low level limited, the steam is superheated at zero power conditions and superheat rises proportionally with power.
a
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QUESTION 5.04 (1.00)
The reactor is suberitical by 2.5 % delta K/K. The count rate is 115 cys. After a positive reactivity insertion, the count rate increases to 345 cys. How much reactivity was added to the core?
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1 QUESTION 5.05 (2.00)
Will the Departure from Nuclear Boiling ratio INCREASE, DECREASE, or REMAIN THE SAME if the following plant parameters INCREASE during power operation? Consider each parameter independently,
- a. Reactor Coolant System (RCS) Pressure
- b. RCS Temperature
- c. RCS Flow
- d. Reactor Power
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
QUESTION 5.06 (1.00)
Following a reactor trip from two weeks 100 percent power operation, i Xenon concentration will peak in approximately how many hours? ;
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QUESTION 5.07 (3.00) 6 A+
The reactor is critical at 10 E-4A POWER when an atmospheric dump fails open. (Isolasion valve is open.) (Continue explanation until stable conditions are reached.)
- a. EXPLAIN what heppens to reactor power and Tave.
ASSUME the reactor is undermoderated, at BOL, no reactor trip occurs and N0 operator actions. ( 2.00)
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- b. Assume the same transient occurs at,EOL. EXPLAIN 9HRiiE-differences in the power /Tave response between EOL and BOL. (I.co) i
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QUESTION 5.08 (1.50)
Why does Moderator Temperature COEFFICIENT (MTC) generally become more negative as temperature increases with a con'atant boron concentration?
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QUESTION 5.09 (1.50)
Explain why and in what direction the boron coefficient changes ;
when the concentration is increased 500 ppm.
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QUESTION 5.10 (1.50)
What TWO temperature instrument responses best indicate the presence of natural circulation if OTSG pressure is lowered 100( ysis. Answer should include instrument and direction of change. M
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QUESTION 5.11 (1,00) i Explain the affect on shutdown margin as a plant heat up from cold shutdown condition to normal operating temperature / pressure (without any change in rod position or boron concentration) is conducted.
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QUESTION 5.12 (1.00)
Answer the following concerning the Pool Boiling Curve.
- a. Where on the Pool Boiling Curve is the heat transfer coefficient the greatest?
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- b. During normal operation of the RCS, where on the curve (what region) does the RCS hulk fluid condition fall?
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QUESTION 5.13 (2.00)
A reactor at BOC is critical at 10E(-9) amps and rods are withdrawn at 30 inches per minute for 5 seconds. Assume a Start-up Rate is calculated immediately AFTER rod motion stops:
- a. WHY would the SUR change if the initial conditions were at EOC?
No calculations are necessary. .
- b. WHY would the SUR change if it were calculated just BEFORE rod motion stopped? No calculations are necessary.
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QUESTION 5.14 (2.00)
List FOUR ways that the operator can minimize the likelihood of causing waterhammer.
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QUESTION 5.15 (1.50)
How is Xenon-135 produced and removed in the core? Give decay times. (1.5) i
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QUESTION 5.16 (1.50)
Given the following data:
core output 2700 MW Th 606 deg. F Tc 554 deg. F Tave 580 deg. F -
superheat 35 deg. F OTSG Header pressure 900#
Temperature of the feedwater 480 deg. F OTSG Levels 88%
CALCULATE the primary coolant flow.
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QUESTION 5.17 (1.00)
The following questions concern Centrifugal Pump Characteristics.
Consider each question separately. .
- a. Select the correct phrase from the list.
When a second centrifugal pump is started in series with a running centrifugal pump (same size pump) ... . (0.5)
- 1. discharge head is reduced by a factor of 2.
- 2. available flow (runout) is increased by a factor of 2.
- 3. shutoff head is increased by a factor of 2.
- 4. first pump current reduced by the square root of 2.
- b. What happens to pump head (INCREASE, DECREASE, or REMAI!I THE SAME) if pump speed la doubled? State the magnitude of the change, if any.Q (0.5)
(***** END OF CATEGORY 5 *****)
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- 6. PLANT SYSTEt!S DESIGN. CONTROL. AND INSTRUMENTATION Paga 19 E QUESTION 6.01 (1.00) 1 Match the following SFRCS equipment to their power supply.
- a. SGLIC 2 a. D1? .
- b. D1N
- b. SGLIC 3 c. Y2
- d. D2N
- c. SFRCS Channel 1 e. Yi
- f. YAU
- d. SFRCS Channel 4 g. YBU
- h. D2P l
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QUESTION 8.02 (1.00)
Which one of the following statements concerning the Control Rod Drive Position Indication System is CORRECT?
- a. When actuated, the out-limit switch for all groups will generate an out-inhibit condition on the Diamond Panel.
- b. The 100 percent switch is located 1.5 inches above the out-limit switch.
- c. The zero (0) percent switch is 1ccated 1.5 inches above the in-limit switch.
- d. The first rod in any group to reach the 100 percent switch will stop further travel of all rods in that group.
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
QUESTION 6.03 (1.50)
With the unit operating at 100% power with all control systems in automatic, a turbine bypass valve fails full open. Indicate how the following parameters will change (INCREASE, DECREASE, REMAIN THE SAME) relative to their initial values when plant conditions stabiline.
ASSUME NO REACTOR TRIP. NO EXPLANATION REQUIRED.
- a. Tavg I b. MWE
- c. Reactor Power
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
-o - -
'l s QUESTION 6.04 (2.50) f Match each of the following' inputs to its possible functions or controls (One answer each)
Inputs Functions / Controls
- a. T-hot (narrow) 1. Core flood interlocks
- b. T-cold (wide) 2. PZR Htr control
- c. RC pressure (wide) 3. RCP interlock
- d. RC pressure (narrow) 4. Provides the ICS the signal to adjust total and loop
- 5. Adjust MFP speed to maintain constant d/p across feedwate control valves
- 6. ICS BTU limit l
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QUESTION 6.05 (2.40)
List the six changes made to the Reactor Protection System (either ;
automatically, manually, or administratively) as'a result of placing the '
shutdown bypass key switch in bypass position. SETPOINTS ARE NOT REQUIRED.
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QUESTION 6.06 (3.00)
- a. List the FOUR sequential actions initiated by a "Bus Lockout" on the C1 essential bus? (2.0)
- b. Explain why a C1 bus lockout requires the EDG to be shutdown
' using the Emergency Stop Push-button. (1.0) ,
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QUESTION 6.07 (2.00) l List FOUR conditions which will cause a runback of the Unit Load Demand Subsystem.
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,. . .. . ..+.. . . . . . . . . . - . . ... . - .-
f QUESTION 6.08 (1.50)
Excluding SFRCS, LIST THREE inputs to ARTS and from where the signal is being sensed.
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QUESTION 6.09 (1.00)
List TWO reasons for the "piggyback" mode of operation of the HPI system.
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QUESTION 6.10 (2.00) l 1
List FOUR conditions required to activate the Rapid Feedwater l i
Reduction circuit.
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~~,--w e- v +---,-,--,e_,,,.,,, . _ , , _ _ _ _ . , _ , _ _
. ~ . . =--.. -
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QUESTION 6.11 (1.50)
What THREE conditions are required to allow the Tave calibrating integral to operate in the tie back mode?
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QUESTION 6.12 (2.00)
What are FOUR methods of overpressure protection for the DHR suction piping from RCS hotleg 2-2.
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, ,~,,,.-.,._,n ,,,., _ _ , _ ,., n.. ,_ ,.a.,,,,,n , , _ , _ _ --_,,nn,..,,..,,,,..-,,n.- - -, , , - - -- ------ - --
QUESTION 6.13 (1.00)
List TWO automatic starts of the Diess. Driven Fire Pump, except for low header pressure.
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- s. _ . . .. . - . . . _ _ . _ . . . . . . - - _ ..
i QUESTION 6 .1. 4 (1.00)
Briefly describe the flow path of gases from the Containment to the installed Hydrogen Recombiners back to the Containment. Identify all major components and interconnecting systems. (Valves not required.)
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QUESTION 6.15 (1.00)
DESCRIBE what will cause the Auto / Manual Transfer Switch to automaticall:7 transfer to a loop Tave from the Unit Tave position during normal power operation.
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QUESTION 6.16 (1.00)
How can it be determined locally if the Auxiliary Feedwater Pump Turbine trip / thro.ttle valvc connecting rod has been properly reset when resetting the Overspeed Trip Mechanism?
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(***** END OF CATEGORY 6 *****)
{
- 7. PROCEDURES - NORMAL. APNORMAL. EMER9ENCY Pago 35 AND RADIOLOGICAL CONTROL QUESTION 7.01 (1.00)
Which one of the following should be done, if during a plant cooldown, the RCS pressure is above the limit for the existing RCS temperature.
- a. Lower pressure, hold temperature constant.
- b. Raise temperature and lower pressure,
- c. Soak for one hour before changing temperature or pressure.
- d. Raise temperature, hold pressure constant.
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QUESTION 7.02 (1.00)
Which one of the following describes the response of the plant to failure of NNIY AC power according to AB 1203.41 "Loss of NNI Power"?
Assume the plant was stable at 80% power prior to the loss.
- a. Remain stable at 80% pwr because of selected instruments redundancy.
- b. Go on high level limits on OTSG's,
- c. Runback to 60% power due to failed FW valve DP indication.
- d. Reactor trip occurs from midscale failure of OTSG pressure.
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l QUESTION 7.03 (2.00)
According to D-B Control Room Evacuation, AB 1203.12, WHAT actions should the Assistant Shift Supervisor perform prior to evacuation (excluding keys) and WHERE should he go after evacuation.
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QUESTION 7.04 (1.50)
According to AB 1203.19, "Pressurizer System Abnormal Operation", list THREE parameters derived from the Acoustic Monitors for indication of PORV status.
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QUESTION 7.05 (1.50)
- a. LIST the TWO entry conditions per the Emergency Procedure EP 1202.01 other than RPS, SFAS, SFRCS. Trip, or SG Tube Rupture.
(D0 NOT use examples) (1.0)
- b. What is.the exception to the SFAS Trip requiring entry into this procedure? (0.5) 9 i
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l QUESTION 7.06 (1.50)
List the THREE radiological alert levels, as stated in HP 1601, used to assure that Davis-Besse personnel do not exceed the operating guidelines for occupationa". whole body exposure without proper approval.
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QUESTION 7.07 (2.00)
What THREE conditions / prerequisites must be met, according to 10 CFR 20, before permitting an individual to exceed the 1.25 rem per quarter whole bocy limit?
(
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QUESTION 7.08 (1.50)
Under what THREE conditions must RC personnel "STOP WORK" under RWPs when termination of the RWP is not necessary?
(DO NOT use examples)
(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
._ . ~.
F QUESTION 7.09 (2.00)
Provide TWO deviation alarms and setpoints which would be received as a group of rods is moved with one rod stuck according to AP1203.23 "CRD Malfunction."
(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
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QUESTION 7.10 (2.00)
Describe the TWO methods used in EP1202.01 "RPS, SFAS, SPRCS Trip or SG Tube Rupture" to provide boron to the RCS if all rods (except APSR's) cannot be verified on the bottom.
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QUESTION 7.11 (1.00)
What actions are required if component cooling water to all RCP's is permanently lost while operating at power?
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QUESTION 7.12 (1.50) ,
What MAJOR actions must be implemented by the operator per EP1202.01 should the control rods fail to deenergize in response to the RPS trip and manual trip. (Do not list Detail sub-steps.)
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QUESTION 7.13 (1.50)
What are Three conditions in the quench tank which will alert the operator of a leaking PORV or Code Safety, per AB1203.19, Pressurizer System Failure?
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QUESTION 7.14 (2.00)
P According to Emergency Procedure EP 1202.01 RPS, SFAS, SFRCS Trip, or SG Tube Rupture, Specific Rule 2, list the TWO conditions where it is permissible to terminate HPI flow after an HPI initiation.
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( QUESTION 7.15 (1.50) i EP.1202.G1, LACK OF ADEQUATE SUBCOOLING MARGIN has you secure RCP'S within two minutes of loss of subcooling margin. What are the BASES for that action, include the bases for the two minutes?
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.m o.._._ . - m . _ . - . . . . _ _ _ _ _ . . . _ _ . _ . . . .
m QUESTION 7.16 (1.00)
According to a caution statement in AP 1203.23 "CRD Malfunctions" why is a stuck or suspected stuck rod not moved in jog speed?
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t QUESTION 7.17 (1.00)
During "Recovery of #2 side essential buses with DG1", in procedure 1203.28, WHY are the close control power fuses pulled for DG2 output, HPI pump 2, DH pump 2 and other equipment?
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(***** END OF CATEGORY 7 *****)
8 .- ADMINISTRATIVE PROCEDURES. CONDITIONS. Pcas 52 AND LIMITATIONS QUESTION 8.01 (1.00)
Which one of the following is NOT approved as a breathing apparatus for use in enclosed spaces? .
- a. Self contained breathing device,
- b. Airlino respirator with auxiliary self contained air supply,
- c. Airline respirator with auxiliary air filtration device,
- d. Full face respirator with self contained air supply.
(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)
QUESTION 8.02 (1.00)
Which ons of the following is NOT required of the Shift Supervisor upon notification of a potential condition adverse to quality?
- a. Contact personnel for additional information on the Potential Condition Adverse to Quality. (PCAQ)
- b. Take necessary action to maintain the plant operating in its present manner.
- c. Initiate a PCAQ report if it has not been done.
- d. Assign an identifying number to the PCAQ report.
(***** CATEGOP.Y 8 CONTINUED ON NEXT PAGE *****)
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QUESTION 8.03 (1.00)
Assume full power operations and refer to the attached Tech Spec excerpts 3/4-8.1 to answer the following:
In the event Emergency Diesel Generator (EDG) 1 is taken out of service for scheduled preventive maintenance repair, which one of the following actions would be most correct in accordance with Tech Specs?
- a. Restore at least two diesel generators to operable status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from time of initial loss,
- b. Restore at least one of the inoperable sources to operable status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or be in at least Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- c. Demonstrate the operability of the remaining AC sources by performing SR 4.8.1.1.la within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
- d. Demonstrate the operability of two diesel generators by performing SR 4.8.1.1.2.94 after (EDG) is repaired after i day within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)
QUESTION 8.04 (1.00)
Which one of the following is required when reducing the boundaries of a clearance per AD 1803.00, Safety Tagging Procedure.
- a. Shop foreman completes the entire Change to Clearance form.
- b. The reduced area must verbally agreed to by all parties holding clearances.
- c. Tag removal is completed according to the procedure for temporary removal of tags.
- d. Completeness and accuracy is checked by the DBTS.
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QUESTION 8.05 (2.00)
For each condition below, indicate whether notification to the STA must be PRIOR to the evolution, IMMEDIATELY upon occurrence, for INFORMATIONAL purposes or NOT REQUIRED according to DB-OP-00002, "Operations Department Event / Incident Notifications and Actions."
- a. Failure of the Emergency Diesel to Pass Surveillance Test.
- b. Power change of 30 MWe/ minute,
- c. Loss of 1 RCP e 78% power.
- d. Recovery from a reactor trip.
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QUESTION 8.06 (1.00)
According to AD 1823.00; Jumper and Lifted Wire Control.
- a. Installation of a jumper on Critical systems / equipment requires independent verification by whom?
- b. Who determines whether a system is critical or not when a jumper is to be installed?
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QUESTION 8.07 (2.00)
According to AD 1839.00 Conduct of Operations, What are FOUR items the Shift Supervisor is task with during an emergency when procedures are inadequate for situation.
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QUESTION 8.08 (1.50)
- a. Under what TWO circumstances may the Shift Supervisor assume responsibility for authorizing tag removal on his cognizance, according to AD 1803.00, Safety Tagging Procedures? (1.0)
- b. What special restriction does taking the action described above place on the Shift Supervisor? -
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QUESTION 8.09 (2.00)
- a. What TWO electrical lockouts may the SS direct to be reset without obtaining concurrence from other plant staff personnel, according to AD 1839.00, Conduct of Operations?
- b. What FOUR items must be recorded in the Unit Los prior to resetting relay targets (flags).
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l QUESTION 8.10 (2.00) ,
What are the FOUR conditions when components / systems are required to be independently verified, according to AD 1839.00 "Conduct of Operations?"
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QUESTION 8.11 (1.50)
List all LOGS that the on-coming Shift Supervisor must review prior to assuming the shift according to AD 1839.05 Shift Turnover.
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QUESTION 8.12 (1.00)
FILL IN THE BLANK Tech. Spec. 4.0.2 States:
Each Surveillance Requirement shall be performed within the specified time interval with:
- s. A maximum allowable extension not to exceed of the surveillance interval, and
- b. A total maximum combined interval time for any 3 censecutive tests not to exceed times the specified surveillance interval.
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QUESTION 8.13 (1.00)
At what Emergency Classification Level is the On-site Emergency Organization required to be activated per the Emergency Plan?
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QUESTION 8.14 (1.00)
If a safety limit is violated, what action (s) must be taken per Technical Specifications if plant is in mode 57 (Include maximum time limit) 5 l
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' 4 QUESTION 8.15 (1.00)
Referring to Technical Specification 3.4.6.2 actions a & b attached, what is the basis for not allowing a time period to reduce the leakage through a pressure boundary?
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QUESTION 8.16 (2.00)
Using the following scenario and referring to Table 4-1 of the Davis-Besse Emergency Plan attached. Indicate the Emergency Action Level required and where in the table you found your answer.
W Reactor power was at 100% power all systems normal, except 11% makeup pump has been out of service for six hours and g2 Emergency Diesel was just placed out of service one hour ago due to failur of the starting air system. Another known plant maintenance item is a leaking containment penetration for 1B RCP. A reactor trip occurred on low pressure from a LOCA. High pressure injection system failed to actuate at its setpoint along with failure of the pump suctions to transfel' to the BWST. Both OTSG and remaining safety equipment are responding normally.
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QUESTION 8.17 (1.00)
Whom, by job titles and order of preference can assume the position of Emergency Director upon initial classification if the Shift Supervisor
=cannot assume the duties?
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QUESTION 8.18 (1.00)
According to AD 1844.11 Post Maintenance Testing Requirements, who by title is responsible for verifying all post maintenance testing has been performed and that the equipment, components, systems, or facility meets Technical Specification Operability requirements prior to returning them to service?
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I QUESTION 8.19 (1.20)
List, in order, the following actions required to isolate and remove a MFP Turbine from service as required by DB-OP-00016 "Removal and Restoration of Station Equipment."
- 1. Isolate the discharge line.
- 2. Isolate the suction line.
- 3. Vent and drain the pump.
- 4. Isolate the recirculation line.
- 5. Isolate the steam supply.
- 6. Isolate the auxiliary systems. [6 @ 0.2)
(***** END OF CATEGORY 8 *****)
(********** END OF EXAMINATION **********)
- \
5.. Pago 71 THEORY OF NUCLEAR POWER PLANT OPERATION.
FLUIDS.AND THERMODYNAMICS ANSWER 5.01 (1.00) e REFERENCE B&W Technical Document, Emergency Procedures Technical Bases, k/a (3.3/3.4) 193008K125 ..(KA's)
ANSWER 5.02 (1.00)
[0.5 each]
- a. False
- b. 4 ,ue.FIse REFERENCE D-B Lesson Plan, RTH-SRO-003.01 D-B Lesson Objective, RTH-SRO-003.01-02, 03 h/a (2.9/2.9) .
192004K107 ..(KA's)
ANSWER 5.03 (1.00) b REFERENCE D-B Training Information Manual, Vol. 3, ICS, pp 43-45 k/a (3.3/3.4) 192008K117 ..(KA's)
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
. ... . . . . . - - - . ~ . . . . - . - . . - - . . . .
5 .- THEORY OF NUCLEAR POWER PLANT OPERATION, Pago 72 FLUIDS.AND THERMODYNAMICS ANSWER 5.04 (1.00)
Keffi = 1/(SDM + 1)
Keffi = 1/(.025 + 1) .
Keffi = 1/1.025 = .9756 CR1/CR2 = (1-keff2)/(1-keff1) 115/345 = (1-keff2)/(1 9756)
.3333 = (1-keff2)/.0244
.3333 * .0244 = (1-keff2)
.00813 - 1 = -keff2
.99187 = keff2 React 1. = (keffi - 1)/keffi React 1. = (.9756 -1)/.9756 = .0250 React 2. = (keff2 -1)/keff2 React 2. = (.99187 - 1)/.99187 = .00819 React added = React 2. - React 1.
React added = .00819 - ( .0250)
React added = .01681 = 1.68% dk/k T.05 .,
REFERENCE D-B Lesson Plan, RTR-OLC-022 & 023 k/a (3.8/3.8) (2.4/2.5) (2.9/3.2) .
001010K508 192002K112 192008K104 ..(KA's)
ANSWER 5.05 (2.00)
[0.5 each]
- a. INCREASE
- b. DECREASE
- c. INCREASE
- d. DECREASE
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5e THEORY OF NUCLEAR POWER PLANT OPERATION.- Paga 73 FLUIDS.AND THERMODYNAMICS REFERENCE D-B Lesson Plan, HTT-SRO-008 k/a (3.4/3.6) 193008K105 ..(KA's)
ANSWER 5.06 (1.00) 8-10 REFERENCE D-B Lesson Plan, RTH-SRO-007 h/a (3.7/3.7) (3.5/3.7) (2.6/3.1) (3.4/3.4) 192006K107 015000K504 001010K526 015000A103 ..(KA's)
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- 5, THEORY OF NUCLEAR POWER PLANT OPERATION, Pega 74 FLUIDS.AND THERMODYNAMICS i
ANSWER 5.07 (3.00)
- a. [0.5 for each major point indicated below)
- 1. The excess steam flow causes Tave to decrease,and insert positive reactivity.
- 2. The positive reactivity increase causes power to rise.
- 3. The increase in power will cause fuel temperature to rise and will add negative reactivity via the doppler feedback.
- 4. The power rise will castinue until the neg react. from the doppler equals the pos react, from Tave decreasing.
(Answer addressing "power overshoot" from mod temp coef. is acceptable. in addition to doppler.)
- b. [0.5 for each major point below)
- 1. The rate at which power rises will be much higher.
OR The time to reach the POAH will be much shorter because the Beff is smaller and the rate at which reactivity is introduced is larger (more negative MTC).
- 2. Power will be the same but the temperature decrease will be less (more negative MTC) and still below no-load Tave.
(Answer addressing "power overshoot is more severe" is acceptable in addition to Beff and MTC.)
REFERENCE D-B Lesson Plan, RTH-SRO-012 D-B Lesson Objective, RTH-SRO-012.01-01 k/a (3.3/3.4) 192008K117 ..(KA's)
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION 1 Page 75 FLUIDS.AND THERMODYNAMICS i
ANSWER 5.08 (1.50)
-Water expands exponentially (or the water density change is non-linear) as temperature increasen (0.75). .
This increases the density change in the mod. per degree change and([therefore increases the reactivity inserted per degree change in moderatortemperature)(0.75).
(A~ drawing of specific volume vs temp. is acceptable for part a.)
REFERENCE D-B Lesson Plan, RTH-SRO-002.01 D-B Lesson Objective, RTH-SRO-002.01-03 h/a (2.9/3.1) 192004K103 ..(KA's)
ANSWER 5.09 (1.50)
Increasing the boron concentration 500 ppm will cause the coeff. to become LESS NEG or move in the POS. direction [0.75] because of the competition for neutrons in the core [0.75).
REFERENCE D-B Lesson Plan, RTH-SRO-006.01 D-B Lesson Objective, RTH-SRO-006.01-03 k/a (2.8/2.9) 192004K109 ..(KA's)
ANSWER 5.10 (1.50)
[0753
- 1. TcdecreasingEG-69hndcoupledwithTsatofOTSG)TC's) [0. 5 ?r
- 2. Incore TC's decreasing EOv69. (Th tracking incore
{0 75]
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION. Pcga 76 FLUIDS.AND THfRMODYNAMIGH l
REFERENCE 1
D-B Emergency Procedure, EP 1202.01, Section 5, p. 47 B&W Emergency Procedure Technical Bases Document. l l
- Cbeck at Facility for additional Heat Transfer references *** ;
)
k/a (4.2/4.2) 193008K122 ..(KA's)
ANSWER 5.11 (1.00)
Shutdown margin will increase from the affects of negative reactivity due to the temperature increase (tiTC).
REFERENCE D-B Lesson Plan, RTH-SRO-002.01 D-B Lesson Objective, RTH-SRO-002.01-03 k/a (3.8/3.9) 192002K114 ..(KA's)
ANSWER 5.12 (1.00) .
- a. oA+ nan-rturefromNucleateBoilingreytk
.) Luk (subwlad b.Jy"n1-steSciling-region) .
REFERENCE D-B Exam Bank, Section 05, question 16 D-B Lesson Plans, HTT-SRO-008 k/a (2.8/3.1) 193008K103 ..(KA's) l
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
l I
- g. ---- - _ _ _ _ _
5i THEORY OF NUCLEAR POWER PLANT OPERATION. Pogo 77 FLUIDS.AND THERMODYNAMICS ANSWER 5.13 (2.00)
- a. At EOC, beta effective is less (0.5) which gives a higher SUR . (0.5)
- b. Due to the rho dot f actor ce fxem,i ndmo Mh IMrssE s.(0,5) 3 the SUR would be higher (0.5)
REFERENCE D-B Lesson Plan, RTH-SRO-010.01 h/a (2.9/3.1) (2.9/3.4) (3.5/3.6) (3.2/3.3) 192003K106 015000A102 001000K547 001000K530 ..(KA's)
ANSWER 5.14 (2.00)
[ any 4 9 0.5 each]
- 1. Slow opening (closing) of valves between voided and full systems.
- 2. Proper venting of components prior to starting.
- 3. Ensuring adequate level in tanks of systems where these tanks provide a supply and /or surge function. ( #PSH prublems)
- 4. Proper use of steam traps and vents.
- 5. Following o rating procedures. (5/@ earmIe ((veu/h (de, G. NE3 &N S P O P W wibh d isc.ke y g. ye /ve e.lo sec/.
REFERENCE D-B Exam bank, Sect 05, question 37 D-B HTFF, Water Hammer Causes and Effects k/a (3.4/3.6) 193006K104 ..(KA's)
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
.' 5, THEORY OF NUCLEAR POWER PLANT OPERATION, Pago 78 FLUIDS.AND THERMODYNAMICS ANSWER 5.15 (1.50) production: Some from direct fission [0.25]
From decay of fission products:
(Te-135) --> (I-135) with 2 min half lif5. [not required)
(I-135) --> (Xe-135)[0.25) with 6.6h half life [0.25).
Removal: Burnout [0.25]
(Xe-135) --> (Cs-135)[0.25) with 9.2h half life [0.25).
REFERENCE D-B Lesson Plan, RTH-SRO-007 k/a (2.7/2.8) (2.8/2.8) 192006K104 192006K103 ..(KA's)
ANSWER 5.16 (1.50)
Qpri
- 1. Mpri = --------- (0.75 for equation)
(hh - hc) 2700 MW (3.41 btu /w)
Mpri = -------------------- (0.5 for correct "h" determination) 622.8 - 552.3 btu /lbm .
9207 E6 btu Mpri = -------------------- (0.25 for calculation) 70.5 btu /lbm Mpri = 130.6 E6 lbm/hr + 10E6 CR Se ca/Oc$m. on r)e d g (1.5)
REFERENCE D-B Lesson Plan, HTR-OLC-023 k/a (3.1/3.4) 193007K108 ..(KA's)
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
ofkj{tesl Cele.Jdn'm &#ad Ar '
.' s.t c.
Anathsr method c:uld be used to do this calculation. Equ3ticn thSot giv s Q = tcp (Tout-Tin). If candidate assumes Cp = 1.3 RTU/lba_*F then:
0 i . _________
Cp(Th_Tc) 2700 MV 3.41 x 10 6 s - _________(____________ BTU /hr/MV)
_________ j 1.3 BTU /lbe *F (606'F-554'F) 9.207 x 10 9BTU /hr
~
s . _____________________ -
1.3 BTU /lbe *F (52'F) 9.207 x 10 9BTU /hr s . ___________________
67.6 BTU /lba 0
& = 1.362 x 10 lba/hr = 136.2 MPPH Using Cp = 1.0 BTU /lba 'F
& - 1.771 x 100 lba/hr - 177.1 MppR I
l
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION.- Pago 79 FLUIDS.AND THERMODYNAMICS I
1 ANSWER 5.17 (1.00) 1 I
- a. 3 (0.5)
- b. Increases (0.25] by a factor of 4 [0.25).
REFERENCE D-B Lesson Plan, HTT-SRO-013, pgs. 6, 7, 13, Figure 13.15 HTR-ORC-021, pg. 6 h/a (2.4/2.5) 191004K114 004000K604 ..(KA's)
I i
i
! (***** END OF CATEGORY 5 *****)
- 6. PLhNT SYSTEMS DESIGN,_QONTROL. AND INSTRUMENTATION Paco 80 ANSWER 6.01 (1.00)
- a. SGLIC 2 = c
- b. SGLIC 3 = a ,
- c. SFRCS Channel 1 = e
- d. SFRCS Channel 4 = h REFERENCE D-B Lesson Plans, PWR-OLC-030 D-B Training Information Manual Volume 5, SFRCS k/a (3.2/3.3) 061000K201 ..(KA's)
ANSWER 6.02 (1.00) c.
REFERENCE D-B, Lesson Plans, PWR-OLC-036.02, pages 28 & 29 Objectives, PWR-OLC-036.01, WO4 .
k/a (3.5/3.8) 001000K401 ..(KA's)
ANSWER 6.03 (1.50)
[0.5 each)
- a. Decrease
- b. Decrease
- c. Increase
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
T-
- 6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Pcga 81 4
REFERENCE D-B Lesson Plans, ICS-OLC-004, pg. 12 k/a (3.6/3.9) (3.5/3.6) (3.1/3.6) 041020K507 041020K105 041020A202 ..(KA's),
ANSWER 8.04 (2.50)
[0.5 each]
- a. 6
- b. 3
- c. 1
- d. 2
- e. 5 REFERENCE D-B Lesson Plans, PWR-OLC-035.01, pg. 9, pg. 12 k/a (3.2/3.3) (3.1/3.1) (3.4/3.4) (2.5/2.6) 059000A107 016000K101 016000G007 016000G004 ..(KA's)
ANSWER 6.05 (2.40)
.[0.40 each] .
- 1. Bypass power / imbalance / flow trip
- 2. Bypass power / pumps trip
- 3. Bypass pressure / temperature trip
- 4. Bypass low / pressure trip
- 5. Adds shutdown bypass high RCS pressure trip
- 6. High flux setpoints reduced to 5% (Administrative)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
- 6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Paga 82 REFERENCE D-B Plant Procedure, PP 1102.10.9, step 5, 2, 14 D-B System Procedure, SP 1105.02.08, step 8.2, SP 1105.02.06, pg. 11 k/a (3.3/3.6) ,
012000K604 ..(KA's)
ANSWER 6.06 (3.00)
- a. [0.5 each]
- 1. Normally closed eupply breaker opens.
- 2. The EDG is prevented from tying to the bus.
- 3. The other TWO supply breakers get a "prevent close" signal.
(f
- 4. All load breakers trip. (Accept load stripping.)
- b. The EDG is started on loss of C1 but bus lockout prevents the output breaker from closing. The EDG is running without any CCW for cooling. (1.0) 02: Eme sthy fus4LHon ms & Ae xsed sia,ce ho xorma/ , f>p REPE5CEfuge-bn will nof slof die @G. C 1.0)
D-B, Lesson Plans, PWR-OLC-054.01, pages 8-9 Objectives, PWR-OLC-054.01, #04 k/a (2.5/2.7) (2.8/3.1) 062000K403 062000K402 ..(KA's) ,
t i
l I
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
1
- 6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Pega 83 l I
ANSWER 6.07 (2.00) !
[0.5 each]
- 1. Power greater than limit allowed for number of RCPs
- 2. Loss of Feed Pump (Assumes two pumps were operating) and power greater than one pump limit.
- 3. Low Deaerator Tank I evel and power greater than limit.
- 4. High MFP discharge pressure and power greater than limit.
- 5. Power greater than Max load limit.
REFERENCE D-B Training Information Manual, Vol. 3, ICS, pg. 24, Fig. 6-ULD k/a (3.3/3.6) (2.8/3.0) 045010K425 045000K412 ..(KA's)
ANSWER 6.08 (1.50)
[0.5 each]
- 1. Turbine trip signal -Emergency trip system oil pressure. (on the main stop valves less than 275 psig in the turbine EHC and reactor power >20%).
- 2. Main feedwater pump trip signal - control oil pressure (less than 75 psig on both pumps).
- 3. Out of core flux signal - from RPS.
REFERENCE D-B Lesson Plans, PWR-OLC-040 D-B System Procedure, SP 1105.21 D-B Training Information Manual Vol. 6, ARTS k/a (3.9/4.3) 012000K402 ..(KA's)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
.v -
6.. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Paga 84 AN WER 6.09 (1.00)
[0.5 each]
gt) 1. If additional coolant to the RCS is required at a pressure higher L than the HPI discharge pressure. .
{(f than the discharge pressure of the DH pumps such that HPI is required and the BWST is nearing its low level setpoint REFERENCE D-B, System Procedure, SP 1104.04.24, page 28.
k/a (3.9/4.2) 006000K406 ..(KA's)
ANSWER 6.10 (2.00)
- 1. At least one main feedwater pump turbine reset.
- 2. Circuit defeat switch on the ICS cabinet is activated.
- 3. Reactor Trip signal present.
Two
- 4. hil euzg main feedwater control valves in automatic. -
7too
- 5. SU Reg. Valves in automatic.
(4 @ 0.5 na.)
REFERENCE D-B Exam Bank, Sect. 06, Question #9 D-B System Procedure, SP 1105.04 PWR-023.03 pg. 21 k/a (2.8*/3.0*)
059000K418 ..(KA's)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
6 .- PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Pago 85 ANSWER 6.11 (1.50)
[0.5 each]
- 1. Reactor control station (Bailey) in manual.
- 2. No calibrating integral block in effect.
- 3. Diamond in manual.
REFERENCE D-B Exam Bank, Section 06, Question #18 D-B Training Information Manual, Vol 3, ICS, p. y/ 6 k/a (2.8/3.3) 001000K602 ..(KA's)
ANSWER 6.12 (2.00) b i
[0.5 each) \ or W'O & ,
A, 1. DH11 cannot ba open greater thsngN1 ir dPo#M-
- 2. DH12 cannoY h open greater than selMid s 3. Par heaters cannot be energized if DH11 or DH12 is oppn and RCS Pressure is greater than a p . OR %.Nade.r/OH ll aM /t ta/er/ock
,' mjdf ae YPT Pum rud<tdoh
- 6. ~%rtrol w'nogQow pN Otflla d 12.
REFERENCE D-B Exam Bank, Sect. 06, Question #23 k/a (3.2/3.5) 005000K407 ..(KA's)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
6 .- PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Pcgo 86 ANSWER 6.13 (1.00)
M
[2 R 0.5 each]
- 1. Loss of power to diesel fire pump controller.
- 2. Low level in FWST (3' 6").
Y) 3 % kl3 & er REFERENCE D-B Lesson Plans, PWR-OLC-003, p. 8 k/a (3.1/3.7) 086000K401 ..(KA's)
ANSWER 6.14 (1.00)
Gases from CTMT are supplied directly to the Hydrogen Recombiner via the Hydrogen Purge line. (0.5) The gases are returned to CTMT from the Hydrogen Recombiner through the 1-2 Hydrogen Dilution Blower discharge line. (0,5)
REFERENCE D-B Training Information Manual Vol. 7, Hydrogen Removal System, CTMT k/a (2.5/2.5) 028000K101 ..(KA's)
ANSWER 6.15 (1.00)
A RCS Flow error greater than 10% between loops will cause the auto transfer of Tave(to the loop with the highest flow)
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
1 6 .- PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Pago 87 i
~
1 REFERENCE D-B Lesson Plan, PWR-OLC-035 D-B Training Information Manual Vol. 5, NNI k/a (3.4/3.4) (2.8/2.9) 016000K403 016000K101 ..(KA's)
ANSWER 6.16 (1.00)
An indicator arrow verifies the correct reset position.
(A//ou ltalf-cred'ih if bh me roof' )$ nsh Ngkjen& byh obker prQe/h REFERENCE M4NN are inc/qb/, D-B Exam Bank, Sect. 06, Question #8 D-B System Procedure, SP1106.06 h/a (4.0/4.2) 061000K406 ..(KA's) (***** END OF CATEGORY 6 *****) [
7 .. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY Pe.cs 88 AND_ RADIOLOGICAL CONTROL ANSWER 7.01 (1.00) b REFERENCE D-B Plant Procedure, PP1102.10, page 3 D-B Exam Bank Section 7, Question 4 K/A (3.6/4.1) 002020G005 ..(KA's) ANSWER 7.02 (1.00) a EEFERENCE D-B Abnormal Procedure, AB1203.41, p. 1 K/A (2.4/2.5) (2.9/3.2) 016000A202 016000K201 ..(KA's) ANSWER 7.03 (2.00) [0.5 each)
- 1. Initiate Emergency procedures alarm.
- 2. Announce over Gaitronics the control room is being evacuated, Alert is declared. (All personnel proceed to their assigned assembly area.)
- 3. Remain in control room until operators leave.
- 4. Proceed to Auxiliary Shutdown Panel.
(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
7.. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY Pega 89 AND RADIOLOGICAL CONTROL REFERENCE D-B Abnormal Procedure, AB 1203.12, pg. 1, step 3.1 k/a (4.2/4.5) (4.1/4.5) 000068K312 000068K318 ..(KA's) ANSWER 7.04 (1.50)
- 1. Acoustic Monitors located on the FORV discharge pipe, and provide
\ the following information.
Flow (Range: 0.0-1.0) [0.5] {}
\
Position (%) (50% open corresponds to a 0.25 flow indication) [0.5) Open/ Closed ind. (Open W/ Flow >0.25) (Closed W/ Flow <0.25) [0.5] (1.5) REFERENCE D-B Abnormal Procedure, AB 1203.19 D-B Lesson Plan, GOP-OLC-001 ATT.19 h/a (3.9/4.1) , 000008A203 ..(KA's) . ANSWER 7.05 (1.50)
- a. 1. When directed by another procedure (0.5)
- 2. When in the judgment of the operator, plant conditions indicate this procedure should be implemented. (0.5)
- b. Level one on CTMT RAD (0,5)
(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
f 7 .* PROCEDURES - NORMAL. ABNORMAL. EMERGENCY Pago SO AND RADIOLOGICAL CONTROL REFERENCE D-B Emergency Procedure, EP 1202.01 k/a (4.1/4.3) . 000007G011 ..(KA's) ANSWER 7.06 (1.50) [0.5 each)
- 1. 900 mrem / quarter
- 2. 1800 mrem / quarter
- 3. 4000 mrem / year REFERENCE D-B External Exposure Administrative Guides and Limit HP1601.01.11/DB-HP-01201, p. 2 K/A (2.8/3.4) 194001K103 ..(KA's)
ANSWER 7.07 2.00) E, yr f't"N' -
\
N > s- . Ul* hf'h(se shall nob eMed riaav A c vvuy 0050 uvs5 aav b. eXCecu , .__ Q
& Pose cakakhn on
- 2. C::;1;ted;NRC form 4 v. I11;. comjo /e/e.
Q
- 3. 5(N-18) rule not exceeded. [0.66 ea.]
Q = g a V= W e ~ e! d h 3+ c.),z;,;, l ) k 4d* REFERENCE 10CFR20.102(b) K/A (2.8/3.4) 194001K103 ..(KA's) (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
l 7 .- PROCEDURES - NORMAL. ABNORMAL. EMERGENCY Paga 91 AND RADIOLOGICAL CONTROL ; l l ANSWER 7.08 (1.50) l [0.5 each] '
- 1. Worker violated RWP requirements. .
i
- 2. Violation of RC procedures.
- 3. Performance of work outside the scope of the RWP.
REFERENCE D-B Radiation Work Permits, HP1601.03.11/DB-HP.01901 p. 2 K/A (2.8/3.4) 194001K103 ..(KA's) ANSWER 7.09 (2.00) [An Two co- ledt anwers]
- 1. CRD symmetrifRod[0.5]@5% deviation (7 inches) [0.5].
M 2. Diamond Station "Asymmetric Fault" [0.5] @ 6.5% (9 inches) [0.5]. L 3, CRO LCO AHN . LOS] G v % jagfoy[pg}, REFERENCEh!,/fssyndfe roof / }{ orr yd j,,,f*c ;,,y (p.j5[,,g g gy , , D-B Abnormal Procedure, AB1203.23 p. 2 . K/A (3.4/3.9) 014000A204 ..(KA's) ANSWER 7.10 (2.00) [1.0 each] 8
- 1. Shift MU pump suction to KWST (by closing 3-way valve MU3971.)
- 2. Boric acid added to MU tank (per SP 1103.04).
l (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
I 7 .* PROCEDURES - NORMAL. ABNORMAL EMERGENCY Paga 92 AND RADIOLOGICAL CONTROL REFERENCE D-B Emergency Procedure, AB1202.01, p. 20 K/A (4.2/4.4)
~
000024K302 ..(KA's) ANSWER 7.11 (1.00) t
- 1. Trip Reactor (0.33]
- 2. Trip RCPs (0.33]
- 3. Carry-out actions of EP1202.01 [0.33]
REFERENCE D-B Abnormal Procedure AB1203.21, p. 10 K/A (3.4/3.5) 008000K301 ..(KA's) SWER 7.12 (1.50) . [0.5 each)
- 1. Maintain primary to secondary heat transfer balance.
\\
- 2. Attempt to manually deenergize CRDs.
L 3. Attempt to manually shutdown the reactor.
%: Dekiled sulstep euefW 4e Gil ec.digif eve 7 sab,),, (;,y Or f4e EP sf, yk; / [3 d d l/ d
~
REFERENCE D-B Emergency Procedures, EP1202.01 page 6 K/A (4.4/4.7) 000029K312 ..(KA's) (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
l
- 7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY Pego 93 l
^
AM RADIOLOGICAL CONTROL 1 l ANSWER 7.13 (1.50) 456.
- 1. ec k emperature(of150degreesF)andpump, start.
- 2. Quench tank high temperature alarm, (200 F) 4 alarm on.
- 3. High level alarm.
+. Q>MWk emun.
REFERENCE D-B Abnormal Procedure, AB1203.19 D-B Exam Bank Section 7 Question 97 K/A (3.4/3.6) 000008A220 ..(KA's) ANSWER 7.14 (2.00)
- 1. HPI may be stopped if the LPI system has been started and flow has been greater than or equal to 1000 gpm/
line for greater than or equal to 20 minutes. (1.0) [0.333 each] Ar' I M "' ' *'
)E 2. a. If core cooling is NOT being provided by MU/HPI cooling.. AND ,#g b. Adequate subcooling margin has been restored. AND Pressurizer level is greater than 100 de re-- and increasing.
(@' c. 8M (1.0) REFERENCE D-B Emergency Procedures, 1202.01, Specific Rule 2 D-B Exam Bank, Section 7, Question #8 K/A (4.1/4.6) 000009K324 ..(KA's) (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
- 7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY Page 94 AND RADIOLOGICAL CONTROL NSWER 7.15 (1.50) p To prevent core damage . TWO MINUTES IS TO prevent the RCS from reaching a significant void fraction [0.75) such that the core would be i uncovered if the RCPs were tripped at a later time [0J5]
REFERENCE D-B Lesson Plan, GOP-OLC-003 TECHNICAL BASES DOCUMENT pg IV.A-2 B&W Document No. 77-1149091-00 k/a (3.9/4.2) 000074K304 ..(KA's) ANSWER 7.16 (1.00) There is a possibility of overloading the CRD spider assembly. REFERENCE D-B Abnormal Procedure, AB1203.23, p. 3 K/A (3.5/4.2) . 001000A203 ..(KA's) ANSWER 7.17 (1.00) 5 reve,,[ 4 To prevent inadvertent closure of the breakers, o r o verlodo87 W1 GD6, (eilbergmver- acceflable hy $g ll c,g);(l,) REFERENCE D-B Abnormal Procedure, 1203.28, p. 8 K/A (3.6/3.9) 000057A220 ..(KA's) l (***** END OF CATEGORY 7 *****) l l 1
ADMINISTRATIVE PROCEDURES. CONDITIONS. Pego 95
') .-
AND LIMITATIONS ANSWER 8.01- (1.00) c REFERENCE D-B Industrial Safety Guidelines, ISG-8/0 page 1 K/A (3.3/3.8) (3.3/3.6) 194000K114 194001K113 ..(KA's) ANSWER 8.02 (1.00) b REFERENCE D-B Administrative Procedure AD 1807.00, Rev. 11. P. 5 D-B Lesson Objectives ADM-SRO-003.01-02 K/A (3.2/3.9) 001000G002 ..(KA's) ANSWER 8.03 (1.00) c REFERENCE , l D-B Technical Specifications 3/4.8.1, LER 87-007 l k/a (3.4/3.9) l 064000G011 ..(KA's) l l l l l
*****)
l l (***** CATEGORY 8 Cody!P"E9 ON NEXT PAGE i l l -- - - - . . - . _ . _ . . _ ~ ._ , .,_. _ _ __, ,, , . , _ _ _ _ __ ,_,_, __ . _
- 8. ADMINISTRATIVE PROCEDURES. CONDITIONS. Pzca 96 AND LIMITATIONS i
ANSWER 8.04 (1.00) d REFERENCE D-B Administrative Procedure. AD 1803.00; Rev. 16, P. 11 D-B Lesson Objectives ADM-SRO-005.02-05 K/A (3.7/4.1) 194001K102 ..(KA's) ANSWER 8.05 (2.00) [0.5 each]
- a. INFORMATIONAL
,qt b. PRIOR
.n-
@' ' c. IMMEDIATE
- d. PRIOR REFERENCE D-B Administrative Procedure, DB-OP-00002, P. 8 D-B Lesson Plans ADM-SRO-002.00, PP. 4-5 D-B. Lesson Objectives ADM-SRO-001.01-02 K/A (3.7/3.9) f 001000G001 ..(KA's) l ANSWER 8.06 (1.00) l
[0.5 each] l l Yp [ a. A qualified Journeyman or above.
^
t gN b b. The DETE (Opcis-2:s;; Taggius Suvu rion ) - ShO S W # OA N U vt $h/(f$u rv/Sor Mc5 #ee
**** CATEGORY 8 CONTINUED ON NEXT PAGE *****)
l l
8: ADMINISTRATIVE PROCEDURES. CONDITIONS. Pcco 97 AND LIMITATIONS REFER"NCE D-B Lesson Plans, ADM-SRO-OO6 B.1 D-B Administrativa Procedure, AD 1823.00.17 k/a (2.5/3.4) . 194001A110 ..(KA's) ANSWER 8.07 (2.00) [0.5 each]
- 1. Take such action as necessary to minimize personnel injury and damage to the plant.
- 2. Return the plant to a stable and safe condition.
- 3. Protect the health and safety of the general public and site personnel.
- 4. Document the steps taken and, if appropriate, incorporate the steps into a revision of the affected procedure.
REFERENCE D-B. Administrative Procedure, AD 1839.00, Rev. 17, p.21 D-B Lesson Objectives, ADM-SRO-001.01-11 K/A (4.3/4.3) - 000009G010 ..(KA's) ANSWER 8.08 (1.50)
- a. 1. The SS determines the requesting person is not on site and cannot be contacted off site [0.5].
- 2. When the requesting persons immediate supervisor cannot be contacted [0.5]. (1.0)
- b. The responsibility for notifying the requesting person cannot be delegated to anyone else. (0.5)
(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)
8 ADMINISTRATIVE PROCEDURES. CONDITIONS. Paga 98 AND LIMITATIONS REFERENCE D-B Administrative Procedure AD 1803.00, Rev. 16, P. 15 D-B Lesson Objectives ADM-SRO-005.02-06 K/A (3.7/4.1) . 194001K102 ..(KA's) ANSWER 8.09 (2.00)
- a. (0.5 each]
- 1. Main generator lockout due to a Rx/ Turbine trip.
- 2. Emergency DG lockout.
- b. [0.25 each)
- 1. Location / panel number
- 2. Relay P9-number
- 3. Relay type
- 4. Target type (from the relay name plate).
REFERENCE D-B Administrative Procedure, AD 1839.00, P. 27 D-B Lesson Objectives, ADM-SRO-001.01-07 . (3.6/3.7) K/A 194001K107 ..(KA's) (***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)
8 .- ADMINISTRATIVE PROCEDURES. CONDITIONS < Pcco 99 AND LIMITATIONS ANSWER 4.10 (2.00) [0.5 each)
- a. When alignment changes have been made in a Mode where the system is required.
- b. When alignments on safety related systems and individual components important to safety are made in preparation for entering a Mode where the system is required.
- c. Following a plant outage where maintenance was performed prior to entering a Mode where that system / component is required to be Operable.
- d. When delineated in administrative or operating procedures.
REFERENCE D-B Administrative Procedure, AD 1839.00, P. 23 of 31 D-B Lesson Objectives ADM-SRO-001.01-05 K/A (3.6/3.7) 194001K101 ..(KA's) ANSWER .11 (1.50) . o. y [0 each] 1 1. Unit Log gd 2. Tagging Log d 3. Jumper / Lifted Wire / Temporary Mechanical Modification Log (,0p 4. RO Los
- 5. LockedValveLoganpdCappedValveLog 4.
REFERENCE D-B Administrative Procedure 1839.05.05, P. 4 D-B Lesson Objectives ADM-SRO-004.01-02A K/A (3.7/3.8) 001000G001 ..(KA's) (***** CATEGORY 8 CONTINU,tD ON NEXT PAGE *****)
-_.n.-_.. . . . . _ _ _ . _ . _ . - . - . _ . - - . _ _ _
8 .' ADMINISTRATIVE PROCEDURES. CONDITIONS. P2ga100 AND LIMITATIONE ANSWER 8.12 (1.00)
- a. 25% or 1.25 times (0.5)
- b. 3.25 (0.5) -
REFERENCE D-B TECHNICAL SPECIFICATION 3/4.0.2 h/a (2.5/3.4) J 194001A103 ..(KA's) ANSWER 8.13 (1.00) Alert level (or higher) REFERENCE D-B Emergency Plan Sec 5.3.2
- k/a (2.5/3.4) l l 194001A116 ..(KA's) l .
I ANSWER 8.14 ,1. 00 'd.eh l g[/, Red R S pre ura wii its limit with'in 5 minutes nEYEMENUE l D-B Technical Specification, pg. 2-1 k/a (2.9/4.1) 012000G006 ..(KA's) l i (***** CATEGORY 8 CONTINUED ON NEXT . I
. . . _ 't_.. . . _ _ _ _ . _ _ _ . . _ . . . _ . _ _ _ _ i 8' ADMINISTRATIVE PROCEDURES. CONDITIONS. Paga101 AND LIMITATIONS ANSWER 8.15 (1.00) Any pressure boundary leakage indicates impending gross failure of the RCS pressure boundary. - REFERENCE D-B Technical Specifications 3.4.6.2 and basis. - D-B Lesson Plans PWR-OLC-034.02, p. 17 & 18. K/A (3.5/4.3) 000009K320 ..(KA's) ANSWER 8.16 (2.00) .g en ral
/
brgency J \ (1.0) s H{ age 3 I erd - L(ys_t.o d o:! 3 sion Product to arr er wwth-potential lo 3rd barrier. (1.0) f0 b, - QL
, / REFERENCE D-B Emergency Plan, Section 4, Table 4-1 D-B Lesson Objectives SRO-EPT-001.01-14 K/A (3.1/4.4) 194001A116 ..(KA's)
ANSWER 8.17 (1.00)
- 1. Assistant Shift Supervisor
- 2. Shift Technical Advisor
(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)
8/ ADMINISTRATIVE PROCEDURES. CONDITIONS. Peg 2102 AND LIMITATIONS REFERENCE D-B Emergency Plan, Sec. 3, Page 3-2 Rev. 11 D-B Lesson Objectives, SRO-DPT-001.01-13 K/A (3.1/4.4) . 104001A116 ..(KA's) ANSWER 8.18 (1.00) The Shift Supervisor REFERENCE D-B Exam Bank, Course OPS-OR4, Cat. 8, Quest. 7 D-B Lesson Objectives ADM-SRO-010-08 K/A (3.4/3.6) 004020G001 ..(KA's) ANSWER 8.19 (1.20)
- 1. Isolate the steam supply. (5)
- 2. Isolate the discharge line. (1) -
- 3. Isolate the recirculation line. (4)
- 4. Isolate the suction line. (2)
- 5. Isolate the auxiliary systems. (6)
- 6. Vent and drain the pump. (3) (6 @ 0.2 ea) l ,
REFERENCE l i D-B Administrative Procedures, DB-OP-00016, P. 4 No Lesson Plan available on this subject. K/A (3.7/4.1) 104001K102 ..(KA's) (***** END OF CATEGORY 8 *****) (********** END OF EXAMINATION **********) 1
u EQUATION SHEET Where mi w m2 (density)1(velocity)1(area)1 = (density)2(velocity)2(area)2 KE = mv 2 PE = mgh PEi +KEi +Pi Vi = PE +KE 2 +P 2 Y22 where V = specific "li volume P = Pressure Q = mcp (Tou t. Tin) Q = UA (Tay,-Tstm) Q = m(ht -h2 I P = Po10(SUR)(t) p . p ,t/T SUR = 26.06 T = (B-o)t I p del ta K = (K,f f-1) CR 1 (1-X,ffi) = CR 2 II"Keff2) CR = S/(1-Keff) H = (1-K,ffi) SOM = (1.K,ff) x 100% ll-h e,f f2 ) K eff decay constant = In (2) = 0.693 A1 = Age-! decay constant)x(t) t 1/2 t1/2 - Water Parameters Miscellaneous Conversions , 1 gallon = 8.345 lbs 1 Curie = 3.7 x 1010 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs
- I ft3 = 7.48 gallons I hp = 2.54 x 103 8tu/hr Density = 62.4 lbe/ft 3 1 MW = 3.41 x 106 Btu /hr Density = 1 gm/cm d 1 Stu = 778 f t-lbf Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 inen = 2.54 centimeters 1 Atm = 14.7 psia = 29.9 in Hg g = 32<.174 f t.lbm/lb f.sec 2 I
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