ML20236H784
| ML20236H784 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 07/17/1987 |
| From: | Elin J, Johnston G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20236H764 | List: |
| References | |
| 50-312-OL-87-02, 50-312-OL-87-2, NUDOCS 8708050334 | |
| Download: ML20236H784 (92) | |
Text
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I Report No.
50-312/0L-87-02 4
Docket No.
50-312 J
l Licensee:
Sacramento Municipal Utility District P. O. Box 15830 Sacramento, California 95813 i
Facility Name:
Rancho Seco Nuclar Generating Station I
I Examination Conducted:
May 6 8,
ul 7, 1987 Examiner:
du
/ /.c_;>
/[
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G fo ston/OperatorLicensing
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/ Uat'e Signed Approved By:
O
/7 M
/J. T). 'Elin, Chief, Operations
/
jfate' Signed Section I
Sunnary:
The results of the requalification examinations of 5 R0's and 9 SR0's were that two SR0's failed. One SRG failed the operating examination and one SR0 l
failed a portion of the writter examination. All of the R0's passed and 7 of j
the SRO's passed all portions of the examinations.
The evaluation of the i
facility requalification program is satisfactory. This evaluation is based on a pass rate of 85.7% overall exceeding greater than 80% as required in NUREG-1021, ES-601.
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1.
Persons Examined Five licensed Reactor Operators and nine licensed Senior Reactor Operators were examined.
2.
Persons Contacted Sacramento Municipal Utility District:
- P. Turner, Training Manager
- M. Harrell, Training Dept.
- B. Crowley, Plant Manager
- T. Hunter, Operations Training Supervisor
- B. Kemper, Operations Manager
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- S. Redecker, Ass. Operations Manager l
- P. Schwartz, Instructor
- Licensing Representative NRC:
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- G. Johnston, Chief Examiner NRC-RV l
- B. Gore, PNL i
- W. Appley, PNL
- J. Huenefeld, PNL 3.
Program Evaluation Examiners Standard ES-601 defines the criteria for evaluating the regulification training pmgram for licensed operators at power reactor facilities. The requirement for a Satisfactory evaluation is more than 80 percent of the examinees must pass all portions of the examination. This includes each section of the written examination, the written examination overall, and the operating examination. Of the 14 persons examined at Rancho Seco on May 6 - 7, 1987 and July 7, 1987, there were two failures.
This represents a pass rate of 85.7%. The requalification program at Rancho Seco is therefore evaluated as Satisfactory on this basis.
4.
Examination Results The results of the examination bear careful attention by the facility training staff. Section 7 of the SR0 written examination reveals a weakness for the Senior Operators in the area of auxiliary systems procedures. The two areas of most concern are in the Fire Protection Carbon Dioxide systems and in Heating Ventilation and Cooling systems (HVAC). Since the examination for this area is brief, the facility should bear in mind that other auxiliary systems procedure knowledge may be affected.
No significant generic weaknesses were identified during the operating examinations.
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5.
Exit Meeting The chief examiner met with facility personnel on May 7,1987 and July 7, 1987 to discuss tho' results of the examination process. to those dates.
The facility personnel were instructed as to the requirements for submittal of comments on the written examinations, l
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Resolution of Facility Comments
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l The.following are resolutions of coments by the ' Ranch Seco training staff of l
the written examinations given July 7.-1987, and forwarded by letter from G.
Carl Andognini dated July 13, 1987.
Reactor Operator Examination:
QUESTION 1.02:
Resolution: Deleted. From a conversation held with facility personnel over the phone on' July. 9,1987 the examiner reviewed the question and determined that the 4 possible responses had two answers that were I
correct and did not provide sufficient distractors for the question, j
QUESTION 1.06:
I Resolution: Deleted. No formula provided to calculate results.
l QUESTION 1.14:
Resolution: Will add to key.
QUESTION 1.18:
Resolution:
This question'was elicited from reference material provided by the facility, no change to key, i
QUESTION 2.01:
Resolution: ~ Will change key.
. QUESTION 2.06:
Resolution: The examiner will change key to accept supply breaker from those respective busses. The examiner notes that he instructed the i
participants to do so during the conduct of the examination, j
QUESTION 2.09:
Resolution: Will delete part 3 in key.
QUESTION 2.12:
Resolution: The examiner will-accept a reasonable flow path. But cautions that the key will not be changed.
QUESTION _3.01:
Resolution: Will add the suggested changes.to the key.
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QUESTION 3.04:
Resolution: Agreed, will change key.
QUESTION 3.06:
Resolution: Agreed, will change key, and portion points for any'2.-
QUESTION 3.07:
Resolution: Deleted. Modifications to facility made question not applicable..
QUESTION 3.08:
o Resolution:
Deleted. Modifications to facility made question not applicable.
QUESTION 3.13:
Resolution: Agreed, will change key.
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QUESTION 4.01':
Resolution: The examiner disagrees, and notes that 10 CFR 55 requires question of all candidates in this area.
QUESTION 4.07:
Resolution: The examiner disagrees, and points out that all licensed.
operators are held responsible to know the requirements for operability in the Technical Specifications.
QUESTION 4.08:
Resolution: The examiner disagrees and will not change the key. The comment is conclusionary.
QUESTION 4.09:
Resolution: The examiner quotes the Examiners Standard ES-202. The l
standard states in part that "The candidate'is not expected to have normal procedures committed to memory but should.be able to explain reasons, cautions, and limitations of normal. operating procedures."
QUESTION 4.13:
Resolution: The examiner does not expect word for word recitation of key.
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Senior Reactor Operator Examination:
QUESTION 5.03:
Resolution: Agreed, will change key.
QUESTION 5.05:
Resolution:
No reference material was provided, the examiner cannot determine if the comment is viable. No change to key.
QUESTION 5.08:
Resolution: Agreed, will change key.
QUESTION 5.09:
Resolution: The examiner disagrees with the comment, no change will be made to key. The comment is conclusionary as to the candidates' responses.
QUESTION 5.13:
Resolution: The examiner will accept for part b 4 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or the I
square root of the power change in percent. For part c the examiner will accept 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or 40 to 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />.
l QUESTION 6.01:
Resolution: The question is clear and the material may have been presented in 1980 but is still current.
QUESTION 6.05:
Resolution:
The question asked for methods, which is true.
However the key factor is by which source, and the DHR path is not required for the answer.
QUESTION 6.06:
Resolution:
Same as 2.01.
4 QUESTION 6.08:
Resolution:
Same as 3.01.
QUESTION 6.09:
Resolution:
The examiner will accept no effect for parts a and c and will delete part b.
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t QUESTION 7.01:
. Resolution:
The exaniner will change the key to allow any 3 of the 5 for 0.5 points each.
QUESTION 7.02:
Resolution: Deleted. At request of reviewers, and after review by examiner. Examiner determined questior. tas invalid by. not specifying adequately which of two reviews applies'in this case.; Grading would have been impossible.
QUESTION 7.06:
Resolution:
The action is cited-in.the procedure as an immediate action.
The examirer will change the keg by putting "to 18,000 amps" in parentheses, t
QUESTION 7.08:
Resolution: See coment 4.09.
l QUESTION 7.09:
Resolution:
See comment 4.09.
QUESTION 7.11:
Resolution: See comment 4.09.
QUESTION 8.02:
Resolution: Deleted. Question was found to be inapplicable in context.
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Only cna of the three answers is in.the Bases.
QUESTION 8.05:
Resolution: The question asks for the method in the bases.
QUESTION 8.06:
Resolution: Deleted. Procedure has been replaced.
QUESTION 8.09:
Resolution: The examiner feels that the individuals should have been able to supply the answers despite the wording of the question.
Change made during examination:
QUESTION 8.07:
This question was deleted because of inadvertent inclusion of answer key in examinations.
1 RANCHO SECO REQUALIFICACfION EXAMINATION REVIEW COMMENTS j
Section ~
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1.06 Requires memorization of a formula not given on the formula sheet (Pv = PV/n) 1.14-Answers not on key.
Expect a.-
Curve A b.
Curve C 1.18 At Rancho Seco there is no apparent power meter and nega VA's are not addressed in normal operation.
Section 2 2.01a & b The "j" inverter no longer exists.
Answer should state the "j" bus versus "j"' inverter.
2.06 Answer:
Operators are not required to memorize breaker numbers, therefore, acceptable answer should be S1, S2, ICS breaker on C bus and ICS breaker on J bus.
2.09 Answer #3:
DHR cooler and NSCW cooler are.not considered part of the HPI system, therefore, answer is invalid for question asked.
Question is misleading since there are only two (2) cooling functions.
2.12 Answer:
CP-101 is not a procedure required to be memorized by the Operator, therefore, any reasonable flow path should be acceptable.
Section 3 3.01 Answer:
a.
ULD runs back to 75% at 25*/ min, not 50*/ min b.
The multiplier used by ICS would allow "A"
flow to be 2.4 (2.44) times "B"
- flow, c.
Correct answer is about 20*/ min 3.04 Wording of the question is such that the first part of the answer is not asked for.
Full credit should be J
given for, "They will trip if closed when the pump starts."
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4 3.06 Add to answer #3 greater than 1* neutron error.
3.07 Invalid question for the modifications mede to the Feedwater in response to a Loss of ICS.
Main Feedwater Pumps trip now.
3.08 Invalid question becasue of the modifications made to TBV control circuits.
l 3.13 Acceptable answer would also be:
To take manual / hand control of the AFW pumps and valves on the controllers.
Section 4 4.01 Not RO's responsibility as per Emergency Plan.
E-Plan specifically states the Emergency Coordinator will class';y all events and this responsibility cannot be delegated.
4.07 This is not a Control Operator's responsibility.
This responsibility is the shift Supervisor's.
Questions should be deleted.
4.08 This is the Shift Supervisor (SRO's) responsibility.
Not required RO knowledge.
Question should be deleted.
4.09 Operators are taught to review the A-Procedures, limits and cautions prior to the Operation of a system or component.
They are not required to memorize these.
We feel the question is beyond the scope of manual operations, therefore, the question should be deleted.
4.13 AP.305 is not a required procedure to be memorized.
Answers may not be word specific as stated in the key.
Section 5 5.03 Answer "e":
The high pressure turbine exhaust contains approximately 15 - 17% moisture, therefore, we feel answers 3 of 4 should be acceptable.
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-5.05 Question does not reference specific procedure referenced in the answer.. Choice "a and b"'should.
also be acceptable.
Question does not state initial condition nor reference to a procedure.
For steady state natural circulation,; decreasing.0TSG pressure decreases'Tc and Th as a-constant core delta T is maintained.
5.08 Answer should be "b."
The burnout at 24' ramp will i
be greater, therefore the dip-for 2* will be larger than at 0.5% ramp.
Answer reference shows Xe peak' from various power conditions.
Nothing references the effect of ramp rate on the Xenon dip.
5.09 Requires the Operator to memorize the formula for prompt drop.
Because_a formula is given-in the answer-
"b" the individual may assume the formula is incorrect.
q He is asked to determine if formula given is correct.
5.13b Answer stated is correct for normal power maneuvers, however, the Operators have also been taught that the time to peak for large instantaneous power' changes, as shown on the figure, is approximately equal to the square root of the power change, therefore, 6-10 hours should also be accepted.
5.13c Correct answer is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, approximately 20-25. hours to reach the equilibrium values and'another 45-50 hours (5 half-lives) to Xenon free.
Section 6 6.01 The question isn't clear and there could be more than one answer.
This material has not been covered in training since 1980.
Should accept the answer if reasonable.
6.05 Answer reflects one (1) method (via DHR pump) with two separate sources.
6.06 Same comment as 2.01.
6.08 Same comment as 3.01.
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6.09 Directions given by the examiner during the exam were to assume the RTD failed open which is a high temperature.
The answer is written for a shorted RTD.
Answer "a" should be no n
effect.
Answer "b" should be deleted because of a new ICS modification.
Part "c" should be no effect.
Section 7~
l 7.01 Question and answer references AP.500,-however, Operators are only responsible for the E-Plan i
Implementing Procedure (AP.528) which only states
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three recommendations:
(1)
Shelter, (2) Evacuation, s
(3) Relocation.
7.02 The Operator isn't responsible to recall from memory these factors.
This kind of information is available and can be looked up if necessary.
Our training has centered around when an RWP's required.
Question should be deleted.
7.06 This requires memorizing a step in the normal operating procedures (A-series).
This is not a limit or a caution.
Question should be deleted or accept a general answer such as, " Reduce main generator loads."
7.08 See comment 4.09.
7.09 See comment 4.09.
i 7.11 See as comment 4.09.
Section 8 8.02 Reference 3.1.3.1 does not apply, should be 3.13.
The question is misleading because T.S.
3.6.2 states only one (1) condition, that is Refueling Shutdown, the answer key uses a combination of j
3 T.S.'s to get the answer listed.
To get the answer requested they should have asked for the i
definitions of refueling shutdown.
i 8.05 The bases states this is one method, however, there may be other acceptable methods, (1)
Radioactivity, (2) RCS Inventory.
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8.06 AP.3 has been deleted.
Question should be deleted.
8.09 Rancho Seco 7.8 bases states,'" Calculations show the above 525 F the positive moderator coefficient is acceptable."
Parts 2 & 3 should be deleted.
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U.S. NUCLEAR stEGULATORY COMMISSION SENIOR REACTOR OPERATOR REQUALIFICATION EXAMINATION Facility:
Rancho Seco Reactor Type:
Babcock & Wilcox Date Administered:
June 30, 1987 Examiner:
Cary W.,Johnston Candidate:
Gmds ka K o Lt INSTRUCTIONS TO CANDIDATE p
Read the attached instruction page carefully. This examination replaces the current cycle facility administered requalification examination. Retraining requirements for failure of this examination are the same as for failure of a requalification examination prepared and administered by your training staff.
Points for each question are indicated in parentheses after the question. The
. passing grade requires at least 70% in each category and a final grade of at least 80%.
Examination papers will be picked up four (4) hours after the examination starts.
% of Category
% of Candidate's Category Value Total Score Value Category 15.0 25.0 5.
Theory of Nuclear Power Plant Operation, Fluids, and Thermodynamics 15.0 25.0 6.
Plant Sy' stems Design, Control and Instrumentation 1
15.0 25.0 7.
Procedures - Normal, Abnormal, Emergency, and Radiological Control 15.0 25.0 8.
Administrative Procedures, Conditions, and Limitations 60.0 TOTALS Final Grade All work done on this examination is my own, I have neither given nor received aid.
Candidate's Signature a
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS Puring the administration of this' examination the following rules apply:
4 1.
Cheating on the. examination means an automatic denial of your applicatich and could result in more severe penalties...
2.
Restroom trips are to be limited and only one candidate at a time may.
leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
3.
Use black ink or dark pencil only to facilitate legible reproductions.
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4.
Print your name in the blank provided on the cover sheet of the examination.
5.
Fill in the date on the cover sheet of the examination (if necessary).
6.
Use only the paper provided for answers.
7.
Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
8.
. Consecutively number each answer sheet, write "End of Category
- as appropriate, start each categorg on a new page, write'only one sTde of the paper, and write "Last Page on the last answer sheet.
9.
Number each answer as to category and number, for examp1e, 1.4, 6.3.
- 10. Skip at least three lines between each answer.
i 11.
Separate answer sheets fron down on your desk or table. pad and place finished answer sheets face
- 12. Use abbreviations only if they are comonly 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 00 HOT LEAVE ANY ANSWER ~ BLANK..
15.
If parts of the examination are not clear us 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 assittance in completing the examination.
been completed.
This aust be done after the examination has Examiner Standards
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- 18. When you complete your examination, you shall:
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Asser.ble your examination as follows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are a part of the answer.
b.
Turn'in your copy of the examination and all pages used to answer
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the examination questions.
Turn in all scrap paper and the balance of the paper that you did c.
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 progr,ess, your license may be denied or revoked.
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Examiner Standards
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REQUIREMENTS FOR ADMINISTRATIDH OF WRITTEN EXAMINATIONS 1.
A cingle room shall be provided for completing the written examina-'
tion. The location of this room and supporting restroom facilities shall be such as to prevent contact with all other facility and/or contractor personnel during the duration of the written examination.
If necessary, the facility should make arrangements for the use of a suitable room at a local school, notel, or other building..Ob-taining this room.is the responsibility of the licensee.
2.
Miriimus spacing is required to ensure examination integrity as determined by the chief examiner. Minimum spacing should be one candidate per table, with a 3-ft space between tables.: No wall charts, models, and/or other training materials shall be present in the examination room.
3.
Suitable arrangements shall be made by the facility if the candi-dates are to have lunch, coffee, or other refreshments. These arrangements shall comply with Item 1 above. These arrangements shall be reviewed by the examiner and/or proctor.
4.
The facility staff shall be provided a copy of the written examination and answer key after the last* candidate has completed and handed in his written examination. The facility steff shall then have five working days to provide formal written comments with supporting documentation on the examination and answer key to the chief examiner or to the regional office section chief.
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5.
The Ifcensee 'shall provide pads of 8-2/2 by 'll in. lined paper in unopened packages for each candidate's use in ce=pleting the exam-ination. The examiner shall distribute these pads to the candidates.
All reference material needed to complete the examination shall be furnished by the examiner. Candidates can bring pens calculators, or slide rules into the examination room, pencils,
, and no other i
equipment or reference material shall be allowed.
6.
Only black ink or dark pencils should be used for writing answers to questions.
4 Examiner Standards
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EOUATION SHEET b
N.
ml = m2 = Constant
+
Z - aN m = pAv Tov P
3.10 X 101o V = Av P - Po10(SUR t) 0 = v(ap) + AY2 +g 28c 8c
,P - P eIDN}
o 0 = v(ap) + ap2 + glaz) + ht 1
Keff -
2gc Sc Keff 0 = v(ap) + ap2 + Efaz) + hL + hp c
Ec Keff -1
- ~
Keff Re. 09D L* + ie rf-v8c p_
T l'+ AT ht, f L 72 I*ff - "
D 2gc T-Ip hLkt $2 SUR E
28C T
hl=ks $2 n*
Ms*
2c 8
ICRR -
p = m (ah) = m (ou + v(ap)) : mu (ap)
E" p, ideal = bv(ap)
CR g,,
3 Cao BHP = Wp, real = 5vfop) 7
"~
1 - Keff "P
n
_g CR (1 - Keff ) - CR (1 - Keff )
3 3
2 2
EHP P = B@ - p i
KE - 1/2 m32
- 2g J at. " fop) (1,.,j)
'P]
- p l
e ne 1
N a V (Flow) q
{
N2 a AP (Head)
N3 l
a BHP (Power) i
)
hSAT - vPSAT i
1 hT>hSAT CONSTANTS & CONVERSIONS i
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NPSHA = h (Suction)-h 7
SAT A"
2 1 watt - 3.1 X 1020 fissions /second NPSHA - vP'- + "2 -hSAT zge 1 Curie - 3.7 X 1010 disintegrations per second 1 amu - 931 Mov NPSHA - vP1+h-ht -hSAT Ec g - 32 ft/ sect hgt,- hpy + hpg E - 32 ft-lbm/sec -lbf 2
c ft lbf J - 778 hp<hEl, BTU NPSHA < NP3HR
- C - (*F-32) 5/9 TDH - r.0; (Peold - Phot)
- R
- F 4 460 Ec
- K
'C + 273 z'n a AT /2
/3 aQ c
- 1.0 BTU /lbm *F @ STP p
i P
11:0 - 62.4 lbm/f t 8 1 gm/cm 3 O STP
. I - I c"# - I,10'I*'/ M )
a f
Id -Id g
2 2
.Idj-Idj 1
3 n
R/hr 0,
(meters) 2 R/hr - 6 CE/d2 (feet) 4 1
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i Section 5 Theory of Nuclear Power Plant Operation, Fluids And Thermodynamics QUESTION 5.01 MULTIPLE CHOICE Which of the following is a consequence of continued Reactor Coolant Pump operation following the situation where the pressurizer empties during a LOCA7 (0.5) a.
RCP's can continue to run despite voiding.
b.
Core uncovery may occur if RCPs are lost.
c.
No significant RCS voiding will occur.
d.
RCP's will trip on overcurrent.
- ANSWER b.
(0.5)
- REFERENCE 1.
Rancho Seco:
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MULTIPLE CHDICE q
For the same reactivity insertion at End-of-Cycle (EOC) the reactor responds more rapidly than at Beginning-of-Cylce (BOC).
i The reason is:
(0,5) a.
The resultant Moderator Temperature Coefficient increase over core life.
b.
The resultant Fuel Temperature Coefficient increase over core life.
c.
The delayed neutron fraction increased over the core life.
d.
The delayed neutron fraction decreased over the core life.
j
- ANSWER d.
(0.5)
- REFERENCE 1.
Rancho Seco:
Reactor Theory Manual, 9-6a 17.5.
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C QUESTION 5.03 MATCHING For the f ollowing systems, using the numerical descriptors, WHAT are the appropriate thermodynamic conditions?
(2.0)
(More than one condition may apply to each system.)
a.
1.
Subcooled
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Saturated water j
b.
Main Steam System I
3.
Saturated vapor l
4.
Saturated low j
c.
Low Pressure Turbine inlet I
quality vapor I
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Superheated d.
Main Condenser Hotwell l
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High Pressure Turbine exhaust i I
f.
Pressurizer (0.33 each) i
- ANSWER a.
1.
(0.33) b.
5.
(0.33) c.
5.
(0.33) d.
1.
(0.33) e.
3.
(0.33) f.
2.
and 3.
(0.33)
- REFERENCE 1.
Rancho Seco: Heat Transfer and Fluid Flow i
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QUESTION 5.04
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MULTIPLE CHOICE Gamma compensation isn't required in the power range for three f
reasons. Which of the statements below is one of those reasons?
l (0.5)
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a.
The gamma flux does not react with the baron coating inside the ion chambers.
b.
Fission gamma flux contributes approximately 10% of thermal power.
c.
Power range instruments are calibrated to a heat balance.
)
d.
Fission product decay gammas cause decay heat which can be approximately 5-7 % of thermal power.
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- ANSWER c.
(0.5)
- REFERENCE l
1.
Basic Ractor Theory, Intro to Nuclear Engineering, Lamarsh, p.
345.
2.
Rancho Seco: Reactor Theory Manual, Figure 4-7.
QUESTION 5.05 MULTIPLE CHOICE Which of the following is an indicator that shows RCS to OTSG heat transfer is established?
(0.5) j i
a.
Lower OTSG pressure corresponding to a decrease in T b.
Maximum expected RCS delta T of 30 F to 40 F.
c.
Incore temperatures within 10 degress F of T d.
T appr ximately equal to OTSG T h
- ANSWER l
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(0.5)
- REFERENCE 1.
Rancho Seco: E.04-6, " Loss of Heat Transfer".
QUESTION 5.06 An Auxiliary Feedwater pump starts and is running at rated flow.
An operator stationed at the discharge valve for the pump begins to close the valve. HOW will each of the following parameters j
change as the valve begins to close (INCREASE, DECREASE, REMAIN l
THE SAME)?
a.
Discharge Pressure (0.5) 6.
Total Net Positive Suction Head (0.5) c.
Motor Amps (0.5)
- ANSWER i
a.
Increase b.
Increase c.
Decrease (0.5 each)
- REFERENCE 1.
Rancho Seco: Heat Transfer and Fluid Flow l
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OUESTION 5.07 MULTIPLE CHOICE How would each of the following parameters have to change to effect an increase in the Departure from Nucleate Boiling Ratio for the reactor (INCREASE, or DECREASE)?
a.
Reactor Power (0.25) b.
RCS pressure (0.25) c.
RCS coolant temperature (0.25) d.
RCS flow (0.25) j
- ANSWER a.
decrease b.
increase j
c.
decrease d.
increase (0.25 each)
- REFERENCE 1.
Rancho Seco: Heat Transfer and Fluid Flow QUESTION 5.08 i
t MUL1IPLE CHOICE When performing a reactor startup that commenced five hours after a trip from full power equilibrium conditions, a 2% per minute ramp was used.
(0.5)
A Xenon dip for a 0.5% per minute ramp vice a 2% per minute ramp would occur a.
sooner and be smaller.
b.
later and be smaller.
c.
sooner and be larger.
l d.
later and be larger.
j 1
- ANSWER (0.5) b.
Ih COWN
- REFERENCE j
1.
Rancho Seco: Reactor Theory Manual, 16.4-5, Figure 16-5.
j e
r l
]
QUESTION 5.09 s
MULTIPLE CHOICE A " Prompt Drop" in reactor power following an instantaneous insertion of 2% delta k/k is not exactly double the power' decrease caused by a 1% delta k/k because (select the most accurate)
(0.5)
I a.
The less delayed neutrons there are, the less effect on power an instantaneous change in reactivity will have.
b.
A prompt drop caused by 1% delta k/k would equal Ebeta/ beta + 1] while a prompt drop caused by 2% would equal Ebeta/ beta + 23.
c.
The beta term in the numerator of the equation to determine the prompt drop is not linear with the reactivity insertion.
d.
The prompt drop is not wholly dependent on the value of beta as it is related to the reactivity insertion.
- ANSWER b.
(0.5)
- REFERENCE 1.
Rancho Seco: Reactor Theory Manaual, RT-11.5..
QUESTION 5.10 WHAT type of chemical additive would control the following Reactor Coolant System conditions?
a.
pH (acid - base balance)
(0.5) 6.
Oxygen concentration at operating temperature.
(0.5) c.
Oxygen concentration during low temperature conditions.
(0.5)
- ANSWER a.
Lithium Hydroxide b.
Hydrogen c.
Hydrazine (0.5 each)
- REFERENCE 1.
Rancho Seco: STM 5 i
b
f I
i 1
l c
OUESTION 5.11 j
MULTIPLE CHOICE Main Steam line pressure is 965 psig. Which of the following represents the enthalpy of the Steam assuming it is saturated?
(0.5) a.
1191.8 Btu /1bmass q
b.
1194.7 Btu /lb l
mass q
c.
1193.6 Btu /lbmass d.
1192.9 Btu /lb mass 1
f
- ANSWER l
c.
(0.5)
- REFERENCE 1.
Steam Tables i
j
._-------_-_____--_a
e QUESTIOt4 5.12 MULTIPLE CHOICE a.
Which the following regarding the Main Generator is correct?
(0.5) 1.
As Reactive Power is increased True Power remains the same.
2.
As Apparent Power is increased True Power decreases.
3.
As the phase angle increases the Reactive Power decreases.
4.
As the load on the generator increases the power factor becomes less lagging.
b.
Tccording to Ohm's Law the Apparent Power is equal to which of the following?
(0.5) 1.
VA = E x I
( 0 = Phase angle) 2.
VA = E x I x Cos 0 1
3.
VA = EWatts + VARs]
l 4.
VA = E x Ix PF x Cos O
- ANSWER a.
1.
(0.5) b.
1.
(0.5)
- REFERENCE 1.
Rancho Seco: STM 40 1
j o
e i
1 i
OUESTION 5.13 j
Refer to Figure 5.13 a chart of ~ Reactor power and Xenon concentration.
-a..
What is the approximate time from point A to point B7
( 0. 5 ).
b.
What is the approximate time from point C to point D7 (0.5) c.
What is the approximate time from' point E to point F7 (0.5)
- ANSWER a.
40-60 hours o/,
b.
-iiHfr-h our s 4'M 7 b WS #
/
c, 40-60 hours o tr 7 2. WW j
- REFERENCE 1.
Rancho Seco Reactor Theory GUESTION 5.14 MULTIPLE CHOICE The main steam line break accident forms the basis for the shutdown margin requirement at end-of-life (EOL) conditions because:
(0.5) a.
Beta-effective is at its maximum value.
b.
Baron concentration is at its maximu,n value.
c.
Control rod insertion limits are most restrictive.
d.
MTC is at its most negative value.
j
- ANSWER d.
(0.5) l
- REFERENCE B&W177 EQB 1
l l
r
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i s
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OUESTION 5.15 MULTIPLE CHOICE Which one of the following is the primary source of Hydrogen in the event of an accident that severely damges the reactor core?
j (0.5)
I a.
Zirc-water reaction.
b.
Safety injection tanks.
!j c.
Radic;ytic decomposition of water.
d.
100% failed fuel.
l
- ANSWER j
j a.
I
- REFERENCE l
1.
Rancho Seco: FSAR l
1 l
l i
1 I
1 l
I 1
L_______---_____-_-_____-____-__-____---_--_--
m.
i QUESTION 5.16 MULTIPLE CHOICE-A general rule is of ten stated' " doubling the count rate halves the margin to-criticality".
This is mathematically otated by the
- equation:
CR1/CR2'= (1-Keff2)/(1-Keff1).
Which.one of the following statements-is: CORRECT concerning the above. statement and equation?
' (0. 5 ) -
a.
Both Keff1 and Keff2 have to boiless'than 1.0.
b.
Equal. changes in Keff result in equal changes in subtritical multiplication level.
c.
The equation only-approximates the instantaneous change in count rate;.once-the equilibrium value is reached, the count rate will be higher.
f d.
A second doubling of the count rate will result in.the reactor becoming critical or supercritical.
I
\\
- ANSWER W
l (a)
(0.5) 1
- REFERENCE l
1.
Rancho Seco: Reactor Theory maunal.
i l
f 4
l t-__-----___---_-.____---.--_--__----_____-___---------__-
- 7..
QUESTION 5.17 1
MULTIPLE CHOICE Which one of the following statements is CORRECT concerning the paralleling of electrical systems?
(0.5) a.
Although it is desirable to have speed and phase position matched, it is m'.ch more important to have voltages matched.
b.
If voltages are not matched at the time the synchronizing f
switch is closed, there will be VAR flow from the lower voltage source to the highe. one.
c.
If the incoming machine is at synchronous speed but out of i
phase with the running bus when the breaker is closed, heavy currents will flow to either accelerate or retard the
, incoming machine.
d.
If the incoming machine is in phase but slightly faster than synchronou:s speed when paralleled, the system will tend to speed up the system to synchronous speed.
- ANSWER c.
(0.5)
- REFERENCE 1.
Rancho Seco: STM 40 Generator Theory 1
)
1
\\
s QUESTION 5.18 If the moderator temperature increases, how will the resulting change in each of the effects below affect reactivity (negative, positive, or no change)?
Assume middle of life, medium power.
(1.0) a.
Density.
b.
Rod Worth.
c.
Voids.
d.
Mass Flow Rate.
- ANSWER a.
negative (density decreases).
b.
negative (worth increases).
c.
negative (voiding increases).
d.
negative OR no effect (mass flow decreases).
(4 answers @ 0.25 ea.)
- REFERENCE 1.
Rancho Seco: Reactor Theory Manual.
End of Section 5 l
Go on to Section 6
- +++++++++++s.++++***,+++++++sss,++,,,
i 9
l l
1 l
r I
I Section 6
)
Plant System Design, Control and Instrumentation QUESTION 6.01 Figure 6.01 shows the response of RCS Pressure (Curve 1) and Pressurizer level (Curve 2) to a trip of one RCP at power.
a.
WHY does Curve 1 (RCS Pressure) peak before Curve 2 (Pressuri:er Level) does?
(0.5) 1 I
b.
WHY does Curve 1 (RCS Pressure) drop before Curve 2 (Pressurizer Level) does?
(0.5)
- ANSWER a.
Pressurizer pressure transient stopped by spray at (2205 psig).
(0.5) 6.
Spray continues to reduce pressure until the PZR spray valve c1cses at (2155 psig).
(0,5)
- REFERENCE 1
1.
B&W Operational Transi ent lecture notes, R.
Winks, June 1980.
QUESTION 6.02 You have just declared one train of HPI inoperable. What are four (4) of the five support systems which would have to be verified to be availiable f or the other train to be considered operable?
(2.0)
- ANSWER 1.
Vital electrical distribution.
2.
Nuclear Service Raw Water.
3.
Nuclear Service Cooling Water.
4.
Safety Features Actuation System.
5.
BWST Any four (4) (0.5) each.
- REFERENCE 1.
Rancho Seco: STM 27, p.
9C.
1 1
1 RAi4CHO SEC0 QUESTIO!1 6.01 May 5, 1987 es I
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l 1
QUESTION 6.03 WHAT are six (6) of the nine conditions that would place the Integratec Control System in " Track"?
(1.5)
- ANSWER i
1.
Rx to Fw crosslimit.
2.
Fw to Rx crosslimit.
3.
Both FW demand stations in manual.
4.
Diamond rod control in manual.
5.
Rx Bailey in manual.
6.
Rx trip.
7.
OCB's open.
8.
S/G-Rx station in manual.
9.
Turbine not in ICS auto.
(any 6 @ O.25 each)
- REFERE JCE 1.
Rancho Seco: STM 32 OUESTION 6.04 Subcooled margin has been lost and the Reactor Coolant Pumps must be tripped. However, you note that high pressure oil is not availiable for the "C"
pump.
Why must the "C" pump be tripped first, with the other three pumps still running?
(1.0)
- ANSWER To minimme the coast down time. (The other pumps will provide a backpressure on the pump, allowing it to coast down faster.)
(1.0)
- REFERENCE I
j Rancho Seco:
C.8, p.
1.
i i
a l
l l
QUESTION 6.05 While refueling is in progress, with the fuel transfer tubes open, the level of the spent fuel pool is found to be decreasing.
Reactor Building sump level is increasing at the same time.
What are the two (2) methods that can add significant amounts of water to maintain or slow the decrease of the Spent Fuel Pool level?
(1.0)
- ANSWER 1.
From the BWST (via DHR pump).
(0.5) 2.
From the RB sump (via DHR pump).
(0.5)
- REFERENCE 1.
Rancho Seco: C.38 and STM 10, p.
11.
QUESTION e 06 The "D" inverter is inadvertently tripped, thus adversely affecting NNI-X power.
a.
What happens to the 115 VAC power when the trip of the "D" inverter occurs?
(0.5) b.
Why is the +/- 24 VDC power not affected by this trip? (0.5)
- ANSWER bu6 a.
The 115 VAC power transfers by an ABT to the "J"
ir/crtcr (non-vital bus S1J), if it is availiable.
(0.5) b.
As long as "J"
inverter is availiable an auctioneering circuit selects the highest availiable voltage supply. (0.5)
- REFERENCE 1.
Rancho Seco: STM 33, Rev.
1.,
p.
3.
l
d o
QUESTION 6.07 The OTSG Operating Range level is measured with differential pressure transmitters. Before the signal is used or displayed, it is processed by a temperature compensating circuit.
WHY is this temperature compensation required?
(1.0)
- ANSWER
]
The temperature of the differential pressure reference and variable legs must be considered because a change in temperature will result in a change in density and introduce an error in the measured differential pressure. (Density Compensation)
(1.0)
]
I
< REFERENCE i
1.
Rancho Seco: STM 14 OUESTION 6.08 Rancho Seco is operating at 90% of full power with the ICS in full automatic. Reactor Coolant pump."D" trips. NO operator actions are taken.
a.
What happens to Unit Load Lomand (ULD)?
(0.33) b.
What will the ratio of feedwater be to each OTSG7
.(0.33) c.
At what rate will the Control Rods reduce reactor power as they drive in?
(0.33) d.
If " Reactor to Feedwater" crosslimits come in 10 seconds ofter the pump trip, what will happen to the mode of runback?
(0.5) e.
What two (2) factors cause the Tave initially to rise following the pump trip? (Tave returns to setpoint after the transient settles out.)
(0.5).
sie'( { oeCe(* f
- ANSWER 2)
',,2,f:l.
a.
ULD' runs back to 75% power at 64% per minutp.
(0,33) b.
A loop getc 2/3 and B loop gr*"
' O. rWf 8'o,#c 2 *No la (0.33) c.
About 2 "' p ~ mi.~te. / $ /-o 2-5#/o g<f *8 (0.33) d.
The system goes to TRACK and follows the rate determined by rod incertion.
(0.5) e.
Reduced RCS flow and mismatch of feed / steam flow versus power. reduction by the rods.
('s. 5 ).
- REFERENCE 1.
BL.W Notes on Operational Tr ansi ent s,
R.
Winks, 1980.-
1
\\
QUESTION 6.09 Feedwater Temperature is used in the Feedwater Demand Calculator and the BTU limits sections of the ICS. Consider the following questions if a Feedwater RTD failed while the plant is operating l
at 100% of full power.
j a.
WHAT effect would the failure of the RTD have on the BTU limits?
(0,5) 6.
WHAT effect would the failure of the RTD have on the Feedwater Demand Calculator?
(U.3) c.
WHAT condition would cause a Reactor Trip from this failure?
(0.5)
- ANSWER a.
Feedwater would be chut c#E to the affected ida.
(0.5) b.
The Feedwater. Demand Calculator would reduce Feedwater
- demand, c.
Plant will trip on High Pressure in the RCS.
(O.
)
'b
- REFERENCE Tf b
% /*
1.
Rancho Seco: STM 32.
QUESTION 6.10 l
l
\\
l The Power Range nuclear instrumentation has two amplifiers in the l
circuitry. The summing amplifier provides the Power Range i
indication in the control room and an input to Reactor l
Protection. The other amplifier is set to a difference mode.
WHAT function does the difference amplifier provide?
(1.0)
- ANSWER The difference amplifier generates the flux imbalance signal.
(1.0)
- REFERENCE 1
1.
Rancho Seco: STM 34, pp. 34b-64 and 34b-65.
l
i QUESTION 6.11 What is the neutron sensitive material used in the Source Range detectors?
(0.5)
- ANSWER Boron Trifluoride (BF3) gas.
(0.5)
- REFERENCE 1.
Rancho Seco: STM 34, p.
OUESTION 6.12 During load sequencing following a SFAS actuation AFW Pump P-318 starts with Block 3 equipment.
What is the time delay for AFW Pump P-318 to start following a SFAS actuation?
(0.5)
- ANSWER 30 seconds (Block 3 for Train B loads is 25 seconds.)
(0,5)
- REFERENCE 1.
Ranch Seco:
SMUD TDI Lesson Plan 1/5/97 OUESTION 6.13 What are the EFIC initiation or control actions for the following
{
setpoints at OTSG pressures?
l a.
600 psig (0.33) 6.
725 psig (0,33) c.
100 psi differential (0.33)
- ANSWER a.
Low Steam Generator Pressure.
(0.33) b.
Shutdown Bypass Permissive.
(0.33) c.
FOGG/ Vector Delta Pressure (0.33)
- REFERENCE 1.
Ranche Seco:
EFIC Lesson Plan 11/23/86 End of Section 6 Go on to Section 7
- +++++++++++++++++++++++++*******************************
1 l
Section 7 Procedures - Normal, Abnormal, Emergency, and Radiological Control OUESTION 7.01 According to AP-500 " Emergency Plan" the District Emergency Orgaini:atier, is resposible for recommending to the counties what protective actions should be taken to minimize of f site radiation exposure. What are four (4) of the five methods described in the
{
Emergency ~ Plan?
-( e. v r
- ANSWER h CcMWC*
{
h 1.
Rel ocat i on.
c
- 2. " Ingestion Pathway Interdiction.
I 3.
Sheltering.
4.
Decontamination.
5.
Evacuation.
(anyjy at 0.5 each)
- REFERENCE 1.
Rancho Seco:
Emergency Plan, AP-500, Section 6, p.
9.
h eof QUESTION 7.02
%f>*; C I Et *
$t)sch e kcs AP.305-4 " Radiation Work Permits - RWP's" requires that the Shift Supervisor, or Senior Control Room Operator, reviews for operational conditions, and approves all RWP's.
According to AP.305-4, WHAT three factors should the REVIEW include?
(1.5)
- ANSWER 1.
Tagging requirements.
(0.5) 2.
System alignments and operational requirements.
(0.5) 3.
Limitations imposed by the T.
S.
(0.5)
)
- REFERENCE 1.
Rancho Seco: AP.305-4-5, "Radi ati on Work Permi ts - RWP 's. "
r QUESTION 7.03 Following an earthquake nearby to Rancho Seco that results in a reactor trip, HOW would you, as Shift Supervisor, determine which Emergency Action Level (EAL) classification, in accordance with AP.523 " Earthquake", was appropriate for the event?
(1.0)
- ANSWER The classification of the event would be based on the maximum acceleration recorded on the seismic indicating panel in the control room.
(1.0)
+ REFERENCE 1.
Rancho Seco:
AP.523 " Earthquake" p.
3.
QUESTION 7.04 According to E.02 " Vital System Status Verification; Guideline No. 2:
a.
HOW would the operator verify, using SPDS, that inadequate primary to secondary heat transfer is occuring?
(1.0) b.
If both displays of SPDS are not availiable, HOW would the operator determine if there is INADEQUATE primary to secondary heat transfer?
(1.0)
- ANSWER a.
RCS temperatue is increasing, not stable inside the Post Trip Window.
(0.5)
Tc and OTSG Tsat are not coupled.
(0.5) b.
RCS is not stable and temperature increasing.
(0.5) and T and OTSG T are not coupled (from other indication.)
(0.5)
- REFERENCE l
1.
Rancho Seco:
E.02-9.
i i
)
i 1
OUESTION 7.05
)
i E.06 " Steam Generator Tube Rupture" states that the determination of whether to use the normal SGTR or emergency SGTR.cooldown rate is the responsibility of the Shift Supervisor. According to E.06:
a.
WHAT criteria chould be used by the Shift Supervisor in determining which cooldown rate to use?
(1.0) 6.
When must the Emergency Cooldown rate be terminated?
(0.5) c.
What is the maximum Emergency Cooldown rate that can be rallowed per E.027 (0.5)
- ANSWER a.
SGTR leak rate is greater than capacity of ONE normal makeup pump, OR the condenser is not availiable.
(1.0) 6.
500 F
(0.5) c.
240 F/ hour.
(0.5)
- REFERENCE 1.
Rancho Seco: E.02-13.
QUESTION 7.06 Procedure A.55 "22 kV Electrical System" requires WHAT immediate action shoo'.d be taken on a complete loss of all inophase buss duct cooling?
(1.0)
- ANSWER Reduce the main generator load to 18,000 amps.
(1.0) 1
- REFERENCE i
1.
Rancho Seco: A.55-3.
3 i
. ii..
1 l
I QUESTION 7.07
)
WHY does the Plant Operations Manual A.74 " Control Rod Drive System" caution the operators to NEVER attempt to withdraw a
" Stuck" CRA J7 Jeg speed?
(1.0)
- ANSWER The motor torque availiable is sufficient to destroy the CRA.
(1.0)
- REFERENCE 1.
Rancho Seco:
A.74-3.
QUESTION 7.08 l
According to A.14 " Heating, Ventilating, and Air Conditioning System":
a.
The Reactor Building Pressure Equalizing System may only be 5
used when below WHAT reactor power?
(0.5)
}
b.
Other than equalizing pressure between the Reactor Bulding and the atmosphere, WHAT three (3) conditions or requirements must be met to allow the system to be uLed?
(1.5)
- ANSWER a.
2.5 % power.
(0.5) b.
1.
Prior to RB entry.
(0,5) 2.
Prior to RB purge.
(0.5) 3.
A valid RB Purge permit.
(0.5) l I
- REFERENCE I
1.
Rancho Seco:
A.14-4.
l I
4 i
4 1
CUESTIta 7.09 A plant Auxiliary Operator reports that one of the Diesel Generators' lube oil supply is very low. The Plant Operations Manual A.31 " Diesel Generator System" states that tne Shift s
Supervisor's permission is required to authorize the use of the J
emergency lube oil supply.
l WHERE is that emergency supply of lube oil stored?
(0.5)
- ANSWER The West side of A warehouse.
(0,5)
- REFERENCE I
1.
Rancho Seco:
A.31-21.
QUESTION 7.10 A fire is observed in the Turbine / Generator ZONE 50, but the CO, system has not actuated automatically as required. The indicating light associated with the manual-electric pushbutton station is out.
HOW would you initiate the CO, system in Turbine /0enerator ZONE 50?
(1.0)
~
- ANSWER For manual discharge the glass for the manual actuator for both the Master va!ve and the Pilot Valve for ZONE 50 must be broken and the manual actuators used to discharge the CO, into ZONE 50.
~
(1.0)
- REFERENCE l
1.
Rancho Seco:
A.35-4.
ll l
l 1
{
d l
OUESTION 7.11 j
During refueling a fuel assembly with a pronounced bow is experiencing excessive insertion difficulties.
How can the "Upender" be used to correct this bowing condition?
l (1.0)
I l
- ANSWER The fuel assembly can be placed in the upender with the bow in the vertical plane of the upender and cycled several times between the horizontal and vertical.
(1.0) i
- REFERENCE 1.
Rancho Seco: Refueling Manual, B.8-118.
End of Section 7 Go on to Section 8
- * * * * * * * * * * * * + + + + + + + + + + + + +.n * + + + + + + s s s + + + + +.+ + s s s s s s s s s s,+ +,,4,,,.7, w l
l l
I l
l l
1 0
e.
I Section 8 Administrative Procedures, 1
Conditions, and Limitations I
I I
l QUESTION 8.01 l
l Technical Specification 3.2.2 specifies when the Low Temperature
[
Overpressure Protection System (LTOP) must be in operation. The system must be operable when the RCS temperature is below 350 degrees F and the RCS is not open to the atmosphere.
a.
WHY is Pressurizer level is limited to less than 220 inches when the Reactor Coolant System pressure is above 100 psig?
(0.5)
I b.
Why is the Makeup Tank level restricted to less than 86 inches when LTOP is required?
(0.5)
- ANSWER a.
This provides sufficient bubble space to retard pressure increases.
(0.5) b.
This limits the mass availiable from the MUT for injection into the RCS.
(0.5) l l
- REFERENCE 1.
Rancho Seco:
T.
S.
3.2.2.
QUESTION S.02 hp e
afe t#4 45M Cef Under WHAT two (2) conditions do Rancho Seco's Technical
)
Specifications require the Reactor Dulding Purge Exhaust Filter j
i l
System to be operable when the RCS is open to the atmosphere and fuel is in the core?
(1,0)
- ANSWER If either:
1.
The RCS is subcritical by less than 1 % delta k/k; (0.5) 2.
or RCS temperature at the DHR pump suction exceeds 140 degrees.
(0.5) l
- REFERENCE 1.
Rancho Seco:
T.
S.
1.2.6, 3.6.2, 3.1.3.1.
. c.
QUESTION 8.03 During full power operation, maintenance requests that Nuclear Service Cooling Water pump P-482A be tagged out for maintenance on the shaft seals. According to your Technical Specifications:
a.
WHAT must be done before this pump is placed out of service?
(1.0) b.
What condition must the reactor be in if the out of service pump has not restored to operability in 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />?
(0.5)
- ANSWER j
i a.
Pump P-482B must be tested to assure operability.
(1.0) b.
Hot Shutdown.
(0.5)
- REFERENCE 1.
Rancho Seco:
Technical Specifications 3.3.1, 3.3.2, and 3.3.3.
QUESTION 8.04 TRUE OR FALSE During refueling two (2) irradiated fuel assemblies may be handled simultaneously within the fuel transfer canal as long as one is being handled by the auxiliary bridge crane and a minimum of 10 feet separation is maintained between the assemblies. (0.5)
- ANSWER d
FALSE (0.5)
- REFERENCE 1
1.
Rancho Seco: Technical Specification 3.8.
i
1 QUESTION 8.05 During your shift the Reactor Building drain accumulation tank has been dumped several times.
WHAT method is specified to you in the Rancho Seco Technical Specification Bases for determining if this is due to Reactor Coolant System leakage?
(1.0)
- ANSWER Sample the tank and analyze for beric acid and radioactivity.
(i.0)
- REFERENCE 1.
Rancho Seco: Technical Specifications 3.1.6.
QUESTION 8.06 hv cs O PQ voc CC #C /
O According to AP.3 " Work Requests":
WHAT must be done to change a work request?
(0.5) a.
6.
WHAT must be done to void a work request?
(0.5)
- ANSWER a.
Entries should be printed legibly (using a black ball-point pen.) Changes shall be crossed out with a single line, initialed, and dated.
(0.5) 6.
Write " VOID" with a brief explanation in the work performed section, sign and date it, attach deficiency tag, (and place in pickup basket.)
(0.5)
- REFERENCE i
1.
Rancho Seco: AP.,, Section 3.10.
i 4
. i..
f UM g f {(#cL QUESTION 8.07 gg4 Regarding Administrative Procedure AP.3 " Work Request":
a.
WHAT is meant by a " STAMPED" work request as referred to in Administrative Procedure AP 37 (0.5) b.
WHO must review a " STAMPED" work request?
(0.5)
)
- REFERENCE a.
Work requests that involve a T.
S.
related item are stamped with the " Shift Management Log Entry" stamp.
(0.5) b.
The Shift Supervisor and Assistant Shift Supervisor.
(0.5)
- REFERENCE 1.
Rancho Seco: AP.3, Section 5.2.
QUESTION 8.08 As defined in AP.4B "Saf e Test Authorization Procedure":
a.
WHAT is meant by the term " Dual Verification"?
(0.5) b.
WHAT is meant by the term " Independent Performance"?
(0.5)
- ANSWER a.
When two authorized personnel independently perform the
]
desired lineup following one of the three proscribed methods.
(0.5) b.
This means that each person shall actually perform one of the three methods and should not be in the area of the component when the other individual is present to perform his portion of the dual verification.
(0.5)
- REFERENCE 1.
Rancho Seco AP.4B, Section 3.1.9.
QUESTION 8.09 Technical Specification 3.1.3 requires that the reactor not be made critical if the Reactor Coolant Syr, tem temperature is less than 525 F.
WHAT are the three (3) baces for this requirement?
)
(1.5)
- ANSWER 1.
Ensures moderator temperature coefficient is within its analyzed temperature range.
(0.5) 2.
Ensure consistency with FSAR analyses.
(0.5) 1 3.
The reactor vessel is above its minimum DTT +10 F.
(0.5) l
- REFERENCE 1.
Rancho Seco:
T.
S.
3.1.3.
QUESTION 8.10 Regarding Technical Specification 6.2 " Facility Staff":
a.
HOW many hours may an individual work in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period?
(0.5) 6.
HOW many hours may an individual work over a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period?
(0.5) c.
HOW many hours may an individual work over a 7 day period?
(0.5)
- ANSWER a.
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> b.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> c.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (0.5 each)
- REFERENCE 1.
Rancho Seco:
T.
S.
6.2.
.1
.. s o QUESTION 8.11 During plant cooldown, while personnel are entering the Reactor Building, a latching malfunction occurs that results in both doors of the personnel hatch being open for about one minute.
Personnel on the scene are able to relatch and secure the two doors. They then inform you as the Shift Supervisor.
WHAT actions must you take per the Emergency Plan?
(1.0) i
- ANSWER You must classify the event and make the required notifications, including PA address and siren.
(1.0)
- REFERENCE j
1.
Rancho Seco: Operations Special Order #87-12.
2.
Rancho Seco: AP.501, Attach.
7.2, Table 5.
QUESTION 8.12 According to Operations Special Order #87-9, WHAT determines the minimum number of instruments that are required to be operable for placing a system in service?
(1.0)
- ANSWER The number on the applicable Procedure / Valve Lineup.
(1.0)
- REFERENCE 1.
Rancho Seco: Operr.tions Special Order #87-9.
i s
i
-_.__.__..________.________J
e 4
QUESTION 8.13 The Emergency Coordinator has many duties and responsibilities, I
some of which may NOT be delegated.
WHAT are four (4) of the responsibilities that the Emergency Coordinator may NOT delecate?
(2.0)
- ANSWER 1.
Decision to notify offsite emergency management agencies.
2.
Making' protective action recommendations as necessary to offsite emergency management.
3.
Classi'fication of emergency events.
4.
Determining the necessity for assembly and/or evacuation of onsite personnel.
5.
Authorization for emergency workers to exceed the Rancho Seco Administrative Exposure Limits.
6.
Approving public information releases to be issued from the site.
(any 4 at 0.5 each)
- REFERENCE 1.
Rancho Seco: AP.501, Section 4.4.
End of Section 8 End of Examination
- m ***** m m m m
- m *** m ** m m ** m m. m **
I
~ Ml g
U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR REQUALIFICATION EXAMINATION Fac111ty:
Rancho Seco Reactor Type:
Babcock & Wilcox Date Administered:
June 30, 1987 1
Examiner:
Gary W. Johnston Candidate:
(A me(ln o 6v O
/
)
INSTRUCTIONS TO CANDIDATE
/
Read the attached instruction page carefully. This examination replaces the current cycle facility administered requalification examination. Retraining i
requirements for failure of this examination are the same as for failure of a requalification examination prepared and administered by your training staff.
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 30%. Examination papers will be picked up four (4) hours after the examination starts.
% of Category
% of Candidate's Category Value Total Score 5
Value Category 15.0 25.0 1.
Principles of Nuclear Power Plant Operation, Thermodyna'mics, Heat Transfer and Fluid Flow 15.0 25.0 2.
Plant Design Including Safety and Emergency Systems 15.0 25.0 3.
Instruments and Controls 15.0 25.0 4.
Procedures - Normal, Abnormal, Ymergency, and Radiological Control 60.0 TOTALS Final Grade All work done on this examination is my own, I have neither given nor received aid.
\\
\\
Candidate's Signature 9
9 L
1 x:'
NRC RULES AND CUIDELINES FOR LICENSE EXAMINATIONS Ouring the administration of this' examination the following rules apply:
l 2.
Cheating on the examination means an automatic denial of your application' and could result in more severe penalties.
2.
Restroom trips are to be liaf ted and only one candidata 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 p,nly to facilitate legible reproductions.
4.
Print your name in the blank provided on the cover sheet of the examination.
i 5.
Fill in the date on the cover sheet of the examination (if necessary).
j 5.
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 categor{ on the Icst answer sheet.on a new page, write' on e
the paper, and write "Last Page 9.
Number each answer as to category a'nd number, for example,1.4, 6.3.
- 10. Skip at least three Ifnes between each answer.
- 11. Separate antwar sheets fron pad and 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.
j
- 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,ANSWERAi.LPARTSOFTHEQUESTION 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 assittance in completing the examination. This must be done after the examination has i
been completed.
~
i Examiner Standards j
- s a
- 18. nfhen you complete your examination, you shall:-
a.
Assemble your examination as follows:
(1) Exam questions on tep.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are a part of the answer.
6.
Turn'in your copy of the examir;ation 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 progr,ess, your Ifeense any be denied or revokad.
Examiner Standards
l
~
REQUIREMENTS FOR ADMINISTRATE [0N OF WRITTEN EXAMINATIONS 1.
A single room shall be provided for completing the written examina-tion. The location of this room and supporting restroom facilities shall be such as to prevent contact with all other facility and/or contractor personnel during the duration of the written examination.
If necessary, the facility should make arrangements for the use of a suitable room at a local school, notel, or other building. 0b-taining this room }s the responsibility of the licensee.
2.
Miriisua spacing is required to ensure examination integrity as detemined by the chief examiner. Minimum spacing should be one candidate per table, with a 3-ft space betwen tables. No wall charts, models, and/or other training materials shall be present in the examination room.
3.
Sultable arrangements shall be made by the facility if the candi-dates are to have lunch, coffee, or other refreshments. These j
arrangements shall comply with Item 1 abm. These arrangements shall be reviewed by the examiner andhr proctor.
4.
The facility staff shall be provided a copy of the written examination and answer key after the last candidate has completed and handed in 1
his written examination. The facility staff shall then have five working
]
days to provide formal written comments with supporting documentation on the examination and answer key to the chief examiner or to the regional office section chief.
5.
The licensee 'shall provide pads of 8-2/2 by 'll in. lined paper in enopened packages for each candidate's use in completing the exas-ination. The examiner shall distribute these pads to the candidates.
All reference material needed to complete the examination shall be furnished by the examiner. Candidates can bring pens, calculators, or slide rules into the examination room, pencils.
and no other equipment or reference material shall be allowed.
5.
Only black ink er dark penctis should be used for writing answers to questions.
Examiner Standards
i
'm' i
EOUATION SHEET N
5 = 5 = Constant N
k6 1
2 AW I - aN m=DAv P = 3.1 X 102o
= A7 P - P 10(SUR t) 0 = v(AP) + 672 g(32g 28c '
&c
'y p,,(t/T) i O = v (oP) + Ay2 +. r,fa z ) + ht j
1 Sc Sc Keff 1
p i
Keff - 1 L.
O = v(AP) + 6;2 + L(az,l'+ ht + hp f
E
'28c Sc Keff -1
- ~
Keff p,, pyD 1*, 5eff 1 + IT ht. f L v1
,, 7 ff -,
D 2ge I
htkt v2 f
suR 25 T
+
ht. ks I2
~
t o
2gC CR Wp = m (oh) = m (ou + v(6P)) : mv (6P) o CR 2 "WP, ideal = $v(oP)
CRs CR, BHP =h,real=mv(aP) p 1
M-U 1 - Keff p
p, pgp n
CR (1 - Keff ) - CR (1 - Keff )
3 g
2 2
nm = BHP y
FE -
EHP KE - 1/2 mv,2. g 2 4 = BHP - M P
4 At="O (1--1) cpJ n
i p
N a 9 (Flow)
N2 a AP (Head)-
N3 a BHP (Power) hSAT - vPSAT a
hT>hSAT CONSTANTS & CONVERSIONS NPSHA - h (Suetion)-h3AT A
~
7 "2
1 vate - 3.1 x 1010 fissicas/second
'i NPSHA - vP2'+ hSAT
.2ge 1 Curie - 3.7 X 1010 disintegrations per second NPSHA - vP1 + D -hg.hSAT Be g - 32 ft/ secs g,- 32 ft-lbm/sec2-lbf ft - lbf J - 778 hp<hEL BTU
- F - (9/5*C) + 32 l
NPSHA < NPSHR
- C - (*F-32) 5/9 TDH gat (# cold - # hot)
- R
- F + 460 l
Ec
- K
'C + 273-E o AT /2 a4/3
- 1.0 BTU /lbm *F @ STP cp t
- ,0 - 62.4 lbm/fts _ i g,je,3 H
g 3TP.-
I - Ice"* - I,10'I*/ M )
I d: -Id g
na
.Idj-I,dj
.3 R/hr O'
CE (meters) 3 R/hr - 6 CE/d2 (g,,g) an
b 4
Section 1 Principles of Nuclear Power Plant Operation, Thermodynamics, Heat Transfer and Fluid Flow QUESTION 1.01 MULTIPLE CHOICE The reactor coolant system is at 2050 psig during a plant heatup.
Using the attached Steam Tables:
a.
What would the temperature be in the tailpipe of the pressurizer power operated relief valve if the valve inadvertently lifted (rel i ef tank backpressure is 5 psig)?
(0.5) i 1.
212 F
2.
227 F
3.
200 F
4.
252 F
l b.
What is the enthalpy of the steam in the pressurizer?
(0.5) 1.
1135.6 Btu /lbmass 2.
1138.3 Btu /lbmass 3.
1133.2 Btu /lbmass 4..
1130.5 Btu /lb mass
- ANSWER a.
2.
(0.5) 6.
3.
(0.5)
- REFERENCE g
i i
1.
Rancho Seco: Steam Tables b
]
l 0
l
QUESTION 1.02 h
(
b MULTIPLE CHOICE OW@
O The " Prompt Drop" in reactor power following an instantaneous insertion of 2% delte. k/k is NOT exactly dcuble the power decrease caused by a 1% delta k/k because: (select the most accu: ate)
(1.0) a.
The less delayed neutrens there are, the less effect on power an instantaneous change in reactivity will have.
W b.
A prompt drop caused by 1% delta k/k would equal l
Ebeta/ beta + 1] while a prompt drop caused by 2% would equal Ebeta/ beta + 23.
j i
c.
The beta term in the numerator of the equation to j
determine the prompt drop is not linear with the reactivity insertion.
d.
The prompt drop is not wholly dependent on the value of beta as it is related to the reactivity insertion.
j
- ANSWER b.
(1.0)
- REFCRENCE 1.
Rancho Secot Reactor Theory Mahaual, RT-11.5.
QUESTION 1.03 MULTIPLE CHOICE Which one (1) of the following is NOT one of the four contributors or factors that establish equlibrium Xenon?
(0.5) a.
Burnout cf Iodine b.
Decay of Xenon c.
Decay of. Iodine d.
Direct production of Xenon from fission
- ANSWER a.
(0.5)
- REFEAENCE 1.
Rancho Seco: Reactor Theory Manual, 16-1.
1 I
f e
a I
l QUESTION 1.04 1
I MULTIPLE CHOICE j
Which statement best decribes how the three heat transfer regions in the OTSG change as power INCREASES?
(0.5) 1 1
NUCLEAT BOILING I FILM BOILING
! SUPERHEAT
_g___________________g__________________
a.
remains constant I increases i decreases i
I b.
increases I decreases I reamins constant i
I l
c.
decreases I remains constant 1 increases I
I I
{
d.
increases I remains constant I decreases
- AWSV~R l
d.
(0.5)
- REFERENCE 1.
Rancho Seco: B&W OTSG General Theory Hendout, STM 2-41, figure 14.
QUESTION 1.05 1
1 TRUE or FALSE I
After a reactor shutdown, decay heat rate and count rate will exactly track down (percent to percent) with each other.
(0.5)
- ANSWER False - (Decay heat will decrease at a slower rate due to fission oroducts--reason not required for full credit.)
(0.5)
- REFERENCE l
1.
Rancho Seco: Reactor Theory Manual l
l 1
I
I
')
C
/
IM
/
QUESTIUN 1.06
}
cffs/u Wuks k cokdk MULTIPLE CHOICE bo 9 //v d:laficn~
The initial Waste Gas Decay Tank pressure is 10 psig with 2%-
oxygen. The oxygen concentration is reduced from 2% to 1% without venting, by adding nitrogen. What is the new-tank pressure? (1.0)
.a.
15 psig b.
20 psig c.
30 psig d.
35 psig l
- ANSWER d.
(1.0)
- REFERENCE 1.
Rancho Seco: A.23-4, Heat Transfer Manual, p.
25.
QUESTION 1.07 Figure 1.07 decribes two curves associated with detector position effects on 1/M plots.
1.
Which curve (a. or b.) represents the case where the detector is furthest away from the source?
(0.5) 2.
Which curve (a. or b.) would be the most conservative for use in an approach to criticality prediction?
(0.5)
- ANSWER 1.
b.
(0.5) 2.
b.
(0.5)
- REFERENCE 1.
Rancho Seco: Reactor Theory Manual, pp. RT-8.11, 8-13 and 8-14.
RdhCHOSECO QUESTf0N 1.07-May 5,1987-c
. -i (a.)
1.0 '
~
0.8 1/M 0:4 0.2 0.0 0
2 4
6 3
10 Fuel Assemblies Loaded (b.)
1.0 <
0.8
{
~
0.6 1
1/M 0.4 O.2 i
0.0 0
2 4
6 8
10 l
fuel Assemblies Loaded 4
1
4 g
QUESTION 1.08 The reactor is operating at 30% of full power when onu Reactor Coolant Pump trips, no reactor trip occurs and turbine load is not changed. Will the fc'. lowing parameters, INCREASE, DECREASE,
.or REMAIN THE SAME7 (2.0) a.
Once Through Steam Generator Pressure.
b.
Core delta T (core outlet to core inlet).
c.
Reactor Vessel differential Pressure (delta P).
d.
Flow in the non-affected Reactor Coolant Loop.
- ANSWER a.
REAMAINS THE SAME (0.5) b.
INCREASE (0.5) c.
DECREASE (0,5) d.
INCREASE (0.5)
- REFERENCE 1.
Rancho Seco STM 40 2.
Rancho Seco Heat Transfer and Fluid Flow Manual QUESTION 1.09
^
TRUE OR FALSE Assume the RCS is heated up at a constant rate (degree F/hr) from 300 to 500 F.
Answer the following TRUE or FALSE:
As the temperature gets higher, it will'take a greater letdown rate to maintain a constant Pressurizer level.
(0.5)
- ANSWER True (0.5)
- REFERENCE 1.
Rancho Seco: Basic Thermo Theory, Heat Transfer Manual, p.
46.
2.
Steam Tables.
u QUESTION 1.10 MULTIPLE CHOICE Which of the f ollowing is the primary reason / purpose f or using soluble baron to control excess reactivity of the reactor?
(0.5)-
a.
It does not affect flux shape.
f b.
It does not affect! rod worth, c.
It is cheaper than adding more rods.
d.
It decreases reactor fuel load requirements.
- ANSWER a.
(0.5)
- REFERENCE 1.
Rancho Seco: Reactor Theory Manual, RT-12.4.
QUESTION 1.11 MULTIPLE CHOICE Which of the f ollowing radioactive isotopes, if found in the reactor coolant, would NOT indicate a leak through the fuel-cladding?
(0.5) a.
Iodine 131 b.
Xenon 133 I
c.
Cobalt 60 d.
Kryps.n 85
- ANSWER c.
(0.5)
- REFERENCE 1.
Rancho Seco: Reactor Theory Manual, Figure 4-10.
i R
l ll
l QUESTION 1.12 MUTIPLE CHOICE RCS boration may reduce power without rod motion. Which of the following statements best describes the consequences of this method of power reduction?
(1.0) a.
Imbalance becomes less negative and power range NI calibration becomes less conservative.
I b.
Imbalance becomes more negative and power range NI calibration becomes less conservative.
c.
Imbalance becomes less negative and power range NI calibration becomes more conservative.
d.
Imbalance becomes more negative and power range NI calibration cecomes more conservative.
j i
- ANSWER c.
(Warmer water in downcomer and core bottom; less power differential along core axis; more neutron leakage makes NI's read high---reason not required.)
(1.0)
- REFERENCE 1.
Rancho Seco: Reactor Theory Manual, RT-6.4.
1 A
v.
QUESTION 1.13 An ECP (Estimated Critical Position) is calculated for a startup 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after a shutdown from 100% steady state power,. WILL the Actual Critical Position be GREATER THAN,.LESS THAN, or.THE SAME i
AS the ECP for the following conditions?
(2.0) a.
The Turbine Bypass Valves control Main Steam Pressure 35' psig higher than normal.
b.
The OTSG 1evels are increased by 5% one minute before the calculated ECP'is to be reached, c.
Condenser vacuum is reduced by 3 inches Hg due to a small air leak.
d.
The reactor starup is delayed f or 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> f or e maintenance repair to the turbine.
- ANSWER a.
greater than (0.5) b.
less than (0.5) c.
sa.me as (0.5) d.
greater than (0.5)
- REFERENCE 1.
Rancho Seco: Reactor Theory Manual, RT-12.2,3,4 also RT-16.4,5.
l
.-_-_______.-__2
L QUESTION 1.14 i
Figure 1.14 shows a system characteristic curves and a pump curve for a typical Auxiliary Feedwater pump.
a.
Which system characteristic curve represents the condition where the discharge valve for the pump is throttled partis 11y closed?
(0.5) b.
Which system characteristic curve represents the condition where the Atmospheric Dump valve f or the OTSG opens reducing pressure by 50% of normal (P )?
(0.5) 1
- ANSWER l
a.
cA (0.5) 6.
C-(0.5) i
- REFERENCE 1.
Rancho Seco Heat Transfer Fluid Flow Manual QUESTION 1.15 MULTIPLE CHOICE Which of the following statements regarding the.moder,ator characteristics of light water reactors is NOT TRUE7 (0.5) a.
An overmoderated reactor experiences an insertion of positive reactivity when the moderator heats up.
b.
An undermoderated reactor experiences an insertion'of I
negative reactivity when the moderator heats up.
c.
The addition of boron to the moderator will tend to make the reactor more undermoderated.
d.
The addition of boron to the moderator will tend to make the reactor more overmoderated.
- ANSWER c.
(0.5) j
- REFEFENCE 1.
Rancho Seco: Reactor Theory Manual i
J
neun /./f' d
Pressure S/0 f
A PORV 2 T
E
- r....... /
\\
A P lielgM !. }'-
@p g,,
- '
- I '
ng Aunusery Fee 6 Pumo
- = AP P40e +
NeaN 0, s' ina l Oper akn Cuck
/
/
@/@
Pn,,
i
/
//
/
l / ',-/., -
Pump' Operating p,
j '/
Curve
)
j
//'
%g P Voluma Flow Rate (Y) e
QUESTION 1.16 MULTIPLE CHDICE (Select the'best' answer.)
WHICH one of the collowing is a correct description of reactor-behavior versus reactivity?
(0.5) a.
A positive'startup rate ensures that the reactor is subcritical.
b.
A sustained positive startup rate without~ rod motion ensure the reactor is critical.
c.
When suberitical, equilibrium power level is independent of reactivity.
d.
When subcritical, startttp rate is independent of reactivity.
- ANSWER i
b.
(0.5)
- REFERENCE 1.
Rancho Seco Reactor Theory Manual 9
E QUESTION 1.17
- l MULTIPLE CHOICE In a ' critical reactor below the Point Of. Adding Heat -(POAH) an equal magnitude of reactivity, one positive, the other negative, does NOT produce the same magnitude of startup rate.
This is because:
(SELECT one)
(0.5) 1 a.
The source strength is more significant during a power j
decrease than a power increase.
]
b.
Fuel elements can heatup faster than they can'cooldown due to Newton's law of cooling.
1
]
c.
A. stable-power decrease always occurs at -1/3 decade per minute, regardless of the amount of negative reactivity inserted.
d.
The average neutron generation time. is changed depending upon whether power is increasing or decreasing.
> ANSWER j
d.
(0.5)
~
- REFERENCE 1
1.
Rancho Seco Reactor Theory Manual j
j i
l j
r 0
)
I QUESTION 1.18 i
MULTIPLE CHOICE Which of the following acronyms represents the appropriate notation for the APPARENT POWER output of the Main Generator 7 (0.5) a.
Mega Watts b.
Mega VARs c.
Mega VAs d.
Mega AVAs
- ANSWER c.
(0.5)
- REFERENCE 1.
Rancho Seco: STM 40, Generator Theory, p.
End of Section i Go on to Section 2
+
I l
l Section 2
]
Plant Design Including Safety and Emergency systems QUESTION 2.01 The "D" inverter is inadvertently tripped, thus adversely affecting NNI-X power.
a.
What happens to the 115 VAC power normally supplied by the "D"
inverter when the trip of the "D"
inverter occurs?
(1.0) j b.
Why is the +/- 24 VDC power not affected by this trip? (1.0)
- ANSWER I
a.
The 115 VAC power transfers by an ABT to the "J"
inverter (non-vital bus S1J), if it is availiable.
(1.0) b.
As long as "J"
inverter is availiable an auctioneering circuit selects the highest availiable voltage supply. (1.0)
- REFERENCE 1.
Rancho Seco: STM 33, Rev.
1.,
p.
3.
QUESTION 2.02 The "in-service" purification demineralized is normally allowed to saturate with lithium. WHY is the " spare" purification demineralized is not normally saturated with lithium?
(1.0)
- ANSWER j
This is to provide a means for lithium removal during operation (since lithium can be produced by activation of baron in a neutron flux.)
(1.0)
- REFERENCE 1.
Rancho Seco: STM 5, p.
5-167.
i QUESTION 2.03 One or more of Control Rod Drive Mechanism thermal barrier ball check valves stick shut during a reactor trip.
WHAT is.the resultant effect on the Control Rod upon a reactor' trip?
(1.0)
- ANSWER The rod drop time will be significantly lengthened (sl owed). (1. 0)
- REFERENCE 1.
Rancho Seco: STM 37, pp. 37a-4,5.
QUESTION 2.04 i
Which of the following 4160 VAC Train A vital pumps are powered l
from the 4160 VAC Bus 4A27 (0,5)
{
a.
HPI Pump P-23BA l
i b.
AFW Pump P-319 l
c.
DHS Pump P-261A d.
NSRW Pump P-472A
~
- ANSWER b.
(0.5)
- REFERENCE l
1.
Rancho Seco:
SMUD TDI lesson plan 1/5/87 I
l 1
i i
i I
QUESTION 2.05 l
Regarding the Control Rod Drive (CRD) breakers:
a.
What two trip devices are used to trip the CRD breakers?
(0.5)
I b.
What four configurations of CRD breakers (i. e. what various sets of breakers), are required as a minimum to trip the reactor?
(2;O)
- ANSWER i
m.
Shunt trip and undervoltage trip devices.
(0.5) b.
1.
A+B (2.0) 2.
A+D+F 3.
B+C+E 4.
C+D+E+F i
- REFERENCE i
1.
Rancho Seco: OD 24, C 0115.
QUESTION 2.06 If Integrated Control System power is lost WHAT four (4) breakers should be checked for determination of-the cause of the power I
losss?
(1.0)
- ANSWER S1, S2, C07 and JO4.
(1.0)
- REFERENCE 1.
Rancho Seco:
STM 32, p.
13.
2.
Rancho Seco:
STM 43, p.
102.
QUESTION 2.07 q
What purpose does the adjustable orifice plate in the OTSG serve (this'not the aspirating steam port)?
(0.5)
- ANSWER The orifice plate retards oscillations in the downcomer water i
level.
- REFERENCE 1.
Rancho'Seco: STM 14 Main Steam QUESTION 2.08 While running with the turbine driver, the dual driven Auxiliary Feedwater pump P-318 trips on overspeed.
a.
Why can the pump be operated with the motor driver if.the overspeed mechanism is not reset?
(0.5) b.
How is the overspeed mechanism reset locally?
(1.0)
- ANSWER a.
The overspeed mechanism does not affect the turbine drive.
(0.5) b.
The valve mechanism is driven down to engage geared limit switch and the latch and pawl mechar,i sm i s re-engaged.
(1.0)
- REFERENCE 1.
Rancho Seco:
STM 29
QUESTION 2.09 What are the three (3) cooling functions provided by the Nuclear i
Raw Water System for the High Pressure Injection (HPI) system?
jab
- ANSWER 1.
Cool the HPI pump lube oil coolers.
(0.33) 2.
Cool the emergency pump room air coolers.
(0.33) 3.
Cool the HPI flow via the DHR cooler and the NSCW coolers when piggy-Lack operat:,or is required.
- REFERENCE M$ l2 d dO C9 W)b SA[# !(0.33 Mo.3 defcWcs cod d
3, 1.
Rancho Seco:
STM 27, p.
95.
QUESTION 2.10 MULTIPLE CHOICE Which of the following is correct concerning the Reactor Building Spray System?
(0.5) a.
The spray additive tank must have an aquescus solution of 44% NaOH in the tank.
b.
The spray additive tank must have a minimum level of 68 inches.
c.
The level in the spray additive tank must not exceed 78 inches.
d.
The spray additive tank must have at least 32% NaOH in aqueous solution.
- ANSWER d.
(0.5) j
- REFERENCE 1.
Rancho Seco: STM 28-10, 11.
1 1
)
QUESTION 2.11 The Control Room and Techn'ical Support Center (TSC) have Essential Ventilation systems. The systems have.two distinct initiation modes; radiation / temperature and toxic gas.
WHAT'is the difference'in system operation between these two modes?
(1.0)
- ANSWER Radiation / temperature : draws in outside air.
(0.5)
Toxic. gas runs in recirculation.
(0. 5 ) '
- REFERENCE 1.
Rancho Seco Requalification-Exam Bank QUESTION 2.12 After a large Loss of Coolant Accident, during long term cooling, it is neccessary to establish flow through the reactor vessel to prevent boron precipitation.
Starting with the Reactor Building sump WHAT is'the preferred flow path to the core?
(1.5)
~
- ANSWER l
LPI - HPI - Spray Valve - PZR - HL - Core - (Cold Leg break)
(0.25 each)
- REFERENCE 1.
Rancho Seco: CP-101, Section 10.
End of Section 2 Go on to Section 3 l
o i
Section 3 Instruments and Controls QUESTION 3.01 Rancho Seco is operating at 90% of full power with the ICS in full automatic. Reactor Coolant pump "D".
NO operator actions are taken.
l a.
What happens to Unit Load Demand (ULD)?
(0.5) b.
What will the ratio of feedwater be to each OTSG7 (0.5) c.
At what rate will the Control Rods reduce reactor power as they drive in?
(0.5) d.
If " Reactor to Feedwater" crosslimits cone in 10 seconds after the pump trip, what will happen to the mode of runback?
(0.5) e.
What two (2) factors cause the Tave initially to rise following the pump trip? (Tave returns to setpoint after the transient settles out.)
(0.5)
( W ' a# " k / < ;
- ANSWER or 25 D
[
F a.
ULD runs back to 75% power at.50% per. minute. 2 ' *, /
(0.5) i b.
A loop gett ~2/3-and B loop est. 1/3.
v'a d ibe (0.5)
I Jg }s 2.5 % pcv manu N c.
Wu t %*L n=e mi n ut e.
(0.5) d.
The system goes to TRACK and follows the rate determined by i
rod insertion.
(0.5) e.
Reduced RCS flow and mismatch of feed / steam flow (versus power reduction by the rods).
(0.5)
- REFERENCE 1.
B&W Notes on Operational Transients, R.
Winks, 1980.
n QUESTION 3.02 The Decay Heat Removal Pumps'are interlocked in their start circuitry-with the drop line valves. If one of the valves comes off its open seat the pumps will trip if running.
What condition must be satisfied in order to restart a pump after the. valve is returned to it's open seat?
(0.5)
- ANSWER Three minutes must pass to allow the Time Delay before Opening relay to time out.
(0. 5) -
- REFERENCE 1.
Rancho Seco: STM 27-77.
QUESTION 3.03 How does the interlock for power supplies to Makeup Pump P-236
)
operate to ensure that only one power supply can be aligned to i
the pump motor?
(0.5)
- ANSWER Two key switches with only one key. (The key must be in a switch, with the position selected CLOSE-PERMISSIVE, to close a breaker.
When the key is in the OPEN position the breaker is opened, thus i
only one breaker can be aligned at a time.)
(0.5) 1
- REFERENCE 1
1.
Rancho Seco STM 5,
- MUP, p.
70.
QUESTION 3.04 How are the Emergency Pressurizer Heater breakers affected by Reactor Building Spray pump operation?
(1.0)
- ANSWER They cannot be closed if either pump is started and they will trip if closed when the pump starts.
(1.0)
- REFERENCE 1.
Rancho Secos Ch 3, p.
51.
j i
1 i
QUESTION 3.05 Regarding the High Pressure Injection system l
a.
Where is the isolation switch for HPI "A"
injection valve
{
SFV-23811 located?
(0.5) b.
What ef f ect does this switch have on the valve when it is placed in the " ISOLATE" position?
(0.5)
- ANSWER a.
It is in the West vital battery charger / inverter room. (0.5) b.
It isolates all controls and indiations from the control room, and allows valve operation locally (from panel H2SD).
(0.5)
- REFERENCE j
1.
Rancho Seco OD 24 C 0103, pp. 5 and 6.
QUESTION 3.06 WHAT are the two causes that will light-the " Auto Inhibit" lamp on the Diamond rod control' panel?
(1.0)
- ANSWER 1.
Safety group not at the out limit.
' O. 9) 2.
Auto permit signal not present from ICS.
to g() 2 C,[erac4)5
.3.
GronTt'v7bavt 1"/o r e<d vo A evro C
- REFERENCE 1.
Rancho Seco:
STM 37 QUESTION 3.07 h
/
f#
hetheresponseof ICS power.is lost. What will the Main
{
Feedwater System after power is restored to.the ICS without tripping the Main Feedwater Pumps?
(1.0)
- ANSWER MFP speed demand will go to 100% before dropping to 0% in about one minute, startup valve demand will go to full open, and MFW valve demand will go to (25%) open.
(1.0)
- REFERENCE 1.
Rancho Seco:
OD 24, C 0706, p.
9.
_____a
l i
i l
( /o89ed I
bdb noco c/ase c>n & fee o(
QUESTION 3.08 If
.rC S P'ou)# -
ICS power is lost, the Autoclose/ Disable switch f or the Turbine Bypass valves are used to control RCS temperature. HOW is the 4
Autoclose/ Disable switch used to to cycle the valves?
(1.0)
- ANSWEit The Autoclose/ Disable switch is used to cycle the valves. Val ves close in either Normal or Close position, and stroke to 50% open in Autoclose Disable.
(1.0)
- REFERENCE 1.
Rancho Seco:
OD 24, C 0701.
QUESTION 3.09 The Carbon Dioxide fire suppression system utilizes two sensors for initiation signals. What are those two types of sensors?
(1.0)
- ANSWER 1.
Ionization detectors.
(0,5) 2.
Infra-red flame detectors (f or D/Gs).
(0.5)
- REFERENCE 1.
Rancho Seco:
STM 24-79.
i QUESTION 3.10 l
l What three (3) places provide an indication of the output of the j
intore thermocouple?
(1.5)
- ANSWER i
1.
(16 Class I are inputed to the) SPDS.
(0.5 each) 2.
(All on) IDADS.
f 3.
(All non-Class I on) the Bailey.
- REFERENCE 1.
Rancho Seco: STM 38 f
)
{
i I
t i
e.
QUESTION 3.11 On Figure 3.11 MARK with letters the appropriate indication or setpoint for the followings (1.0) a.
Critical data power level.
b.
Source range auto-turn off.
c.
Maximum Source Range level that may be reached without Intermediate Range response during a startup.
d.
Minimum Intermediate Range level that may be reached without Source Range response during a shutdown.
- ANSWER 4
Key on Figure 3.11
- REFERENCE 1.
Rancho Seco:
STM 34
)
QUESTION 3.12 i
Given the following detector failures WHAT would an operator see happen to the indication fpr that channel?
(1.5)
A short circuit occurs in the leads to a Hot Le'g RTD.
a.
b.
An open circuit occurs in the leads from an Incore thermocouple.
c.
A leak occurs in the diaphragm of a Pressurizer level detector.
- ANSWER a.
The indication would f ail to the lowest indication on the scale.
(0.5) b.
The indication would f ail to the lowest indication on the scale.
(0.5) c.
The indication would f ail to the highest level (100%).
(0. 5 ).
- REFERENCE 1.
Rancho Seco: STM's 33, and 3, and Exam Question Bank.
103 1080 I
i 10*
- 125 108 te 100 g
10'S 10' ~
n.
~
=
10 EE'
?
g 30'8
.m 107 1
J i
8 10 7 g
t: - ~
,10' c
A 3
10 s d10 6
ono e
Q O
--105 2::
10-s 4
g 10 2
10-80
~~
103 8
"o Q
- 10' 10'"
102 e
3 5
10 l
10 8
=
wg-- 108 I
B a
5 10 10 1 o
_1 10 2
- - 0.1 e
.=
y
=
T
.a E.
8 5N
.U $
Ux c=
me mM o
C.
i 1
i 10*
- n go o I
i i
10
125 10*
Le 100 m
10-5 8
10 C
10 k
?
5 10 5 2
107
- 'x 1
g e,
et:
10'T I
> 10s a
U e
4 l10
c2-5 6
gi: 10 3
b
[10
c
-- 10' 2 104 g
g d
y y10 '
z
- 10' g
~ 103 8
"o
~~
1 0'82 102 m
8 E-- 10 10 g=
[-- 108 3
a c
10 3 j-0 1
10-2
- - 0.1 m
g 2
i I
K e8$
!E I
3 I
EE S m=
o
- ~
i Fisuus.
3.//
s.-
o QUESTION 3.13-
' You have initiated Auxiliary Feedwater manually'from 6.he'EFIC panel.-
How do you establish MANUAL control of each train of AFW7 (1.0)
- ANSWER i
(Manual initiation does not put AFW into manual operation'on EFIC.) The operator must press the RESET button.to establish manual control of AFW.
(1.0)
- REFERENCE l
1.
Rancho Seco EFIC Lesson Plan 11/23/86 QUESTION 3.14 What are the EFIC initiation or control actions associated with the following setpoints provided from the OTSG Low Range Level j
instrumentation?
l a.
13.5 inches (0.25) b.
27.5 inches (0.25)
- ANSWER a.
Low Level initiation.
(0.25) b.
AFW Low Level control.
(0.25)
]
- REFERENCE 1.
Rancho Seco:
EFIC Lesson Plan 11/23/86 l
1 i
l End of Section 3 i
Go on to Section 4 l
1 I
l l
1 r
Section 4 Procedures - Noram1, Abnormal, Emergency, and Radiological Control QUESTION 4.01 MATCH the Emergency Action Level (EAL) with the appropriate numerical descriptor (number).
(2.0) a.
Unusual Event b.
Alert c.
Site Area Emergency d.
General Emergency 1.
Responses required include precautionary actions within the five-mile Public Protection Area.
i 2.
Involves.no release of radiation or radioactive materials to j
the enviornment that exceeds federal limits.
t 3.
Releases of radioactive material are not expected to exceed the EPA PAG exposure levels except near the site boundary.
4.
Offsite notification is needed to ensure that key emergency personnel are activated and that additional staff is placed on standby.
- ANSWER a.
2 (0.5 points each)
I b.
4 c.
3 d.
1 l
- REFERENCE 1.
Rancho Seco: Plant Operations Manual, AP-500, Section 3, pp.
2 and 3.
1
.____________-_-_-___m
a....
o l
QUESTION 4.02 WHY does AP.305-10 " Initial Reactor Building Entry Guidelines" require that Operations run Emergency Cooling Units A-500A and B as soon as it is known that a Reactor Building entry will be made?
(1.0)
- ANSWER.
To reduce iodine concentration.
(1.0)
- REFERENCE 1.
Rancho Seco: Plant Operations Manual, AP.305-10.
QUESTION 4.03 Step 1.0 of E.02 " Vital System Status Verification" requires the operator to verify reactor power is decreasing. If actions to trip the rods are not successful, boration via two preferred methods are prescribed.
l What are those two preferred methods of emergency boration? (1.0) 1
- ANSWER Method in Start Boric Acid pumps and pump to Makeup tank.
Maximize makeup / letdown flow to flash tank.,
(0.5)
Method 2: Start HPI pump lined up to BWST.,
(0.5)
- REFERENCE 1.
Rancho Seco: E.02-3 QUESTION 4.04 Guideline No. 2 " Inadequate Primary to Secondary Heat Transfer" describes preferred and alternate methods to verify inadequate heat transfer between the primary and the secondary.
What is the alternate method of verifying inadequate primary to secondary heat transfer?
(1.0)
(1.0)
- REFERENCE 1.
Rancho Seco: E.02, Guideline No.
2.
l l
I l
a
.. 4.- j QUESTION 4.05 Rule No. 4 "OTSG Level Setpoints" specifies OTSG 1evels appropriate for various conditions that may exist when Emergency Procedures are in effect.
What are the level-setpoints for the following conditions?
(2.0) l a.
Main Feedwater Low Level Limit i
b.
AFW Control (no RCP's running) l 1
d.
Loss of Sub-Cooling Margin
- ANSWER a.
24 inches Startup Range (0.5 for each) b.
27.5 inches EFIC Low Range c.
317 inches EFIC Hi Range d.
381 inches EFIC Hi Range
- REFERENCE l
1.
Rancho Seco Rule No. 4 QUESTION 4.06 How is the Generator Hydrogen System filled f rom initial i
conditions (air atmosphere) to 95% hydrogen purity while avoiding flammable mixtures?
(1.0)
- ANSWER The air is purged with carbon dioxide then the carbon dioxide is purged with hydrogen to the 95% concentration.
(1.0)
- REFERENCE 1.
Rancho Seco: Plant Operations Manual, A.42-2 to A.42-4.
)
I 1
1 i
. 3 QUESTION 4.07 You have just returned to work after a long vacation. During the review of the Control Operators log you determine that the f ollowing shif tly surveillance were perf ormed. The following is a schedule of when the surveillance was done over the last three surveillancess June 29 - 0900 hrs June 29 - 2400 hrs June 30 - 2400 hrs a.
When is the next surveillance due to be performed AT THE LATEST 7 (0.5) s b.
Which surveillance was missed if any?
(0.5)
- ANSWER a.
3.25 x 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> = 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> for the last three.
(0.5)
June 29 - 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br />
+ 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br />, or June 30 - 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> + 15 Therefore 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on July 1.
(0.5) b.
A surveillance should have been performed before 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on June 30.
(1.0)
- REFERENCE 1.
Rancho Seco: Technical Specifications definitions 1.9, 1.9.1.
QUESTION 4.08 Administrative Procedure AP.2.02 provides f or making temporary changes to operating procedures. What three (3) requirements must be met before a temporary change may be made to an operating procedure?
(1.0)
- ANSWER 1.
The intent of the procedure cannot be changed.
(0.33) 2.
Change can initiated only by SS, and ASS or responsible Plant Engineer. (ASS can sign for SS with concurrence.)
l (0.33) 3.
Must be forwared for review and approval within 7 days.
(0.33)
- REFERENCE 1.
Rancho Seco: AP.2.02
QUESTION 4.09 Regarding A.9 " Control Rod Drive Cooling Water System":
WHAT is the maximum time allowed before a reactor trip is required on a loss of CRDM stator cooling water?
(1.0)
- ANSWER 4 minutes (1.0)
- REFERENCE 1.
Rancho Seco:
Plant Operations Manual A.9-2.
QUESRTION 4.10 l
Procedure A.31 " Diesel Generators" cautions that the Diesel Generator never be paralleled to the system with the normal-droop l
l switch in normal. WHY7 (1.0)
)
- ANSWER The DG will attempt to pick up all of the load it sees.
(1.0)
- REFERENCE 1.
Rancho Seco:
A.31-9.
QUESTION 4.11 During the performance of a valve lineup on the Auxiliary Gas System, procedure A.34 " Auxiliary Gas System", requires that the closed valves be checked first. WHY7 (0.5)
- ANSWER To prevent an inadvertent release of gas.
(0.5)
- REFERENCE 1.
Rancho Seco:
Plant Operations Manual, A.34.
l
l 1
QUESTION 4.12 During refueling of the reactor, a single fuel assembly is inserted, the source range count rate goes from 4 to 25 counts per second.. What two (2) IMMEDIATE actions should be taken? (1.0)
- ANSWER 1..
Cease-fuel movement (0.5) 2.
Notify the responsible senior licensed operator. (0.5)
\\
- REFERENCE
.1
'1.
Rancho Seco Refueling Manual, B.8-6.
QUESTION 4.13 What three (3) requirements must be met, according to procedure i
AP.305 " Article 3 ' Control of External Exposure *", when an entry must be made into a Secured High Radiation Area?
(1.5) l
- ANSWER 1.
A specific RWP. (0.5)
I 2.
Accompanied by Radiation Protection personnel. (0.5)
)
3.
Continuous dose rate instrumentation. (0.5) 1
- REFERENCE 1.
Rancho Seco Radiation Control Manual, AP.305-5.
End of Section 4 End of Examination
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