ML20214Q966
| ML20214Q966 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/30/1987 |
| From: | Elin J, Meadows T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20214Q942 | List: |
| References | |
| 50-361-OL-87-01, 50-361-OL-87-1, NUDOCS 8706050281 | |
| Download: ML20214Q966 (209) | |
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Enclosure (1)
U. S. NUCLEAR REGULATORY COMMISSION
- REGION Y 4 EXAMINATION REPORT Examination Report No.: 50-361/0L-87-01 Facility: San Onofre Nuclear Generating Station, Units 2 and 3 Docket No.: 50-361 and 50-362 Examinations administered at San Onofre Nuclear Generating Station, Units 2 and 3, San Clemente, California Chief Examiner: XW- s A "Y-~~-> v z '- 11 Thomas R. Meadows Date Signed Approved by:
- k John /0.Elin, Chief,OpergionsSection M' 3d N Date Signed Summary:
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Written examinations were administered to one R0 candidate and eleven SR0 candidates on March 31, 1987. The operating portion of the examination was waived for the R0 candidate. Operating examinations were administered to eleven SR0 candidates during the period of April 1-3, 1987. All candidates were found to meet the minimum requirements for licensing.
i 8706050201 870511 ~"
REPORT DETAILS
- 1. Examiners:
- Thomas R. Meadows, RV Joe Upton, PNL Leo Defferding, PNL
- Chief Examiner
- 2. Persons Attending the Exit Meeting:
T. Meadows, RV, Chief Examiner D. Mette, SCE, Supervisor of Operator Training M. Hyman, SCE, Unit 2/3 Training Administrator L. Simons, SCE, Unit 2/3 Training Administrator S. Freers, SCE, Training Analyst T. James, SCE, Simulator Administrator R. Maisel, SCE, Compliance K. de Lancey, SCE, Nuclear Af fairs and Emergency Planning C. Anderson, SCE, Station Emergency Preparedness R. Reed, SCE, Station Emergency Preparedness
- 3. Written Examination and Facility Review:
Written examinations were administered at the facility EOF on March 31, 1987 to one R0 candidate and eleven SR0 candidates. All of the candidates passed these examinations.
The chief examiner met with the facility training staff imediately following the examination to conduct the exam review. Facility generated comments were formalized, endorsed by the facility Vice President and Site Manager, and subsequently forwarded to Region V in accordance with NUREG-1021, ES-201, paragraph H. The NRC resolutions of these comments are attached for both the SRO and R0 examinations, respectively (Attachments 1 and 2).
- 4. Operating Examination:
Operating examinations were conducted during the period of April 1-3, 1987 for the eleven SR0 candidates. All of the candidates passed this portion of the examination. The operating examination portion was waived for the R0 candidate.
The plant specific simulator was found adequate to conduct comprehensive NRC examinations. No general training weaknesses were noted during the operating examinations. However, some operational concerns were identified by the NRC examination team during course of the operating examination.
These concerns were addressed by the Chief Examiner at the examination exit meeting with cognizant facility staff.
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- 5. Exit Meeting:
On April 3, 1987, the chief examiner met with the licensee representatives listed in paragraph 2. The satisfactory performance of the simulator was discussed.
The Chief Examiner expressed the following concerns:
(a) During the preparation of the written examination and the subsequent examination review, the facility references were found marginal for proper NRC written examination development. Many of the facility generated coments on. specific examination questions were based on technically inaccurate or inconsistent facility supplied reference material. Specific examples were identified to the facility training staff during the course of the examination review, and in the resolution of facility comments (Attachments 1 and 2).
(b) During the simulator portion of the examinations, the NRC examination team identified a problem that the operator candidates had in the use of the facility Emergency Plan Procedures. These procedures do not give adequate event analysis for loss of steam generator feedwater type events until the evolution degenerates to an ultimate loss of heat sink. Eventually, the CRS is directed to the Emergency Plan Procedures via the Emergency Operating Procedures.
(c) During the oral portion of the examination, the NRC examination team had difficulty in accessing controlled radiation areas. The examiners names were not on the general access REP despite assurances that all administrative preparations had been made. At the control point, an examiner noticed that some of the radiation areas survey maps were missing for the areas into which he wanted to take his candidate. Furthermore, the Chief Examiner got contaminated when he entered an area, under escort with his candidate, that was not identified as a contamination area (CCW heat exchanger and pump rooms).
ATTACHMENT 1 SONGS 2/3 FACILITY COMMENTS AND NRC RESOLUTIONS - MARCH 31, 1987 SR0 EXAM QUESTION 5.2(b)(c)
COMMENT:
The flux peak in the lower portion of the core is also a function of fuel depletion. The predominant fuel depletion occurs in the center of the core causing the power to shift to both top and bottom, although the depletion would be slightly more at the bottom of the core than the top, due to normal power distribution being maintained slightly below the centerline. Part b &
c of this question are not separable. The answers for parts b and c could be substituted for each other.
REQUESTED RESOLUTION:
Modify the answer key to accept fuel depletion and lower temperature /high density in the bottom of the core for full credit for-either part b or c.
NRC RESOLUTION: Comment not accepted.
The question breakdown was clear and comprehensive as a unit. This was clearly identified in the structure of the question. The answer key reflects the comprehensiveness of the questinn structure and is consistent with facility supplied references; however, the answer key was adjusted to further clarify the intent of the point assignments upon grading.
QUESTION 5.04b COMMENT:
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The name of the chemical lithium hydroxide is commonly referred to as
" lithium" by Operations and Chemistry Department personnel.
REQUESTED RESOLUTION:
Modify the answer key to accept either lithium or lithium hydroxide for full '
credit.
NRC RESOLUTION: Comment accepted.
No adjustment to the answer key is necessary. " Lithium" or any responsible fonnula for lithium-hydroxide would be accepted, since it is not the intent of the question to examine the candidate as a plant chemist. We are looking .
for operational knowledge. The answer key is consistent with facility l supplied references.
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ATTACHMENT 1 J
QUESTION 5.8c COMMENT:
Technical Specifications state the major reason for the DNB Safety limit is to protect the cladding. The 3 safety limits function in conjunction to prevent fission product release.
REQUESTED RESOLUTION:
Modify the answer key to accept " protect the cladding" for full credit.
NRC RESOLUTION: Comment not accepted.
The scope of the answer key clearly addresses the intent of this concern.
The wording of the key is consistent with facility supplied references.
QUESTION 5.12 COMMENT: I 1
(a). Using the Combustion Engineering Steam Table conversion factor for BTU /HR to KW results in a slightly lower calculated value(3405 MW).
(b) SONGS 2/3 are rated at 3410 MW thermal, rather than 3425 MW. Since 3425 MW exceeds the licensed power limit this may have caused undue confusion for some candidates.
REQUESTED RESOLUTION:
Modify the answer key to accept a reasonable numerical range. Allow 3410 MW j as an acceptable value for rated thermal power in the calculation of efficiency.
NRC RESOLUTION: Comment not accepted.
(a) The answer key cannot identify all reasonable ranges for a numeral response, such as required for functional or setpoint type responses.
This action must be performed by the grading examiner. Acceptable ranges depend on the Operational Orientation of the question. Any reasonable range of possible answers will be accepted by the grading examiner. Any awarding of points other than full credit must be l documented by the grading examiner, commensurate with NUREG-1021, '
Examiner Standards.
(b) The intended valve (3425 MWTH) to be used for 100% power was clearly identified by the question.
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ATTACHMENT 1 QUESTION 5.13 COMMENT:
Using the Mollier diagram will not yield first decimal place accuracy as in the answer key (306.5 F).
REQUESTED RESOLUTION:
Modify the answer key to accept a reasonable range of accuracy for full credit such as:
530-540 F for Part 1 300-320 F for Part 2 NRC RESOLUTION: Comment not accepted.
Same as Question 5.12(1) resolution.
QUESTION 6.1 COMMENT:
The answer key implies a written explanation is required to satisfactorily respond to the question.
REQUESTED RESOLUTION:
When grading the examination, accept an appropriate drawing of the logic ,
diagram for full credit, as an alternative answer, i NRC RESOLUTION: Comment not accepted.
Any reasonable logic diagram that conforms to the intent of the answer key would be accepted. Adjustment of the answer key is not necessary.
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f ATTACHMENT 1 QUESTION 6.2(a)(b)(c)
COMMENT:
(a) The answer key response is incomplete (b) Theanswerkeyresponseisunreasonablyrestr'ic$ive (c) The answer key response is unreasonal'!y restrictive REQUESTED RESOLUTION:
(a) Expand the answer key to include " preheating incoming colder RCS water".
(b) Accept a reasonable range of values such as:
Pressurizer level setpoint deviation 4% 1 .4%
i Pressurizer pressure 2200 psia i 1%
(c) Accept a reasonable range of value such as:
Pressurizer Heater Cutout 27% i 1%
NRC RESOLUTION: Comment not accepted.
Same as Question 5.12(1) resolution.
QUESTION 6.4 COMMENT:
The answer key response is incomplete.
REQUESTED RESOLUTION:
Modify the answer key to accept the following answers:
" Maintain subcooling" or prevent flashing to steam for full credit.
Exclude the location of flashing from the answer key.
NRC RESOLUTION: Comment not accepted.
Answer key is consistent with the facility suppled reference. Knowledge of the location of possible system damage is required.
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ATTACHMENT 1 i
QUESTION 6.5 COMMENT:
Reference SD-5023-360 also states " Rapid motion of the letdown throttle control valve can cause pressure transients which the letdown backpressure regulating valve controller may not be able to control." ,
REQUESTED RESOLUTION:
Modify the answer key to accept "provides improved backpressure control valve response" or linits pressure transients. Either answer should be acceptable for full credit.
NRC RESOLUTION: Comment not accepted.
Answer key is consistent with facility supplied references. The concern is clearly addressed by the answer key since a pressure transient is certainly the root cause for lifting the relief valve. Subsequently, partial credit would be awarded by the grading examiner. Adjustment of the answer key is not necessary.
QUESTION 6.6 r
COMMENT:
The answer key response is inappropriate. The reference describes " Preferred Manual Mode" as Master Controller in manual and all other stations in automatic.
There is no specific mode selector switch asscciated with the Feedwater Control
- System.
REQUESTED RESOLUTION:
l Modify the answer key to accept the above description of preferred manual as ;
an alternative answer. '
NRC RESOLUTION: Comment accepted. 1 The answer key was adjusted to clarify that an accurate description of this mode of operation would be acceptable.
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ATTACHMENT 1 QUESTION 6.9 COMMENT:
The RCS Pressure / Temperature figure supplied with the examination had the word "Heatup" removed. Candidates may have been confused by this since the figure could easily be interpreted as a composite heatup and cooldown curve. While SONGS Technical Specifications do not employ a composite heatup and cooldewn curve, this would not be an unreasonable assumption on the part of the candidates since the labeling of the figure was intentionally modified. The question has responses for both heatup and cooldown curves which would further convince the candidates that the examination figure was a composite diagram.
REQUESTED RESOLUTION:
Modify the answer key to give full credit for the below responses:
Part a (A) accept either 3 or 4 as the correct response.
Part a (B) accept either 5 or 1 as the correct response.
NRC RESOLUTION: Comment not accepted.
The question clearly identifies the requirements of the answer key. The heat up curves (when collectively considered as a group) can be easily identified by any operator candidate with adequate system and operational knowledge of the safety analysis.
QUESTION 6.10(a)(b)
COMMENT:
(a) Common terminology at SONGS to describe switch position associated with the Excore Nuclear Instrumentation is "any switch out of operate or -
off" will cause trouble light.
(b) The question requires memorization beyond that required of an operator.
An operator would be expected to analyze this situation with the appropriate reference material in hand, however, no reference material was provided.
REQUESTED RESOLUTION:
(a) Modify the answer key to accept "any switch out of operate or off."
(b) Delete the question from the exam and redistribute the points as it is beyond what operators are required to memorize.
NRC RESOLUTION: Comment not accepted.
(a) Intent of concern is already incorporated within the answer key for partial credit. The answer key is consistent with the facility supplied reference.
(b) The question is operationally oriented and is consistent with facility references.
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ATTACHMENT 1 QUESTION 6.11 i COMMENT:
! The range for CPC pressurizer pressure. auxiliary trip was modified between Cycle 2 and 3 from 1825 to 1860 PSIA. Also two additional CPC auxiliary trips 4 were added. The examination did not state whether the question was pertaining i to Cycle 2 or Cycle 3.
REQUESTED RESOLUTION:
Modify the answer key to accept 1860 and 1825 PSIA, and the additional auxiliary
- trips listed in the attached reference.
i j NRC RESOLUTION: Connent not accepted.
The question was structured such that the specific responses identified by the i answer key would be required. The answer key is consistent with the facility 1 supplied references. The requested changes would elevate the level of ,
! difficulty beyond the original ~ intent of the examination outline. ';
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QUESTION _6.14(b)
COMMENT:
j Candidates could interpret the question to require stating the name of the j system, or the specific components. The answer key only recognizes specific ;
components.
REQUESTED RESOLUTION:
l Modify the answer key to accept SDC/ECCS system or SDC/ECCS system pumps and j heat exchangers.
j NRC RESOLUTION: Comment not accepted.
The question is objective and the answer key is consistent with facility i supplied references. "SDC/ECCS" is certainly implied, and therefore,
{ adjusting the answer key is not necessary.
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ATTACHMENT 1 QUESTION 7.2(a)
COMMENT:
Procedure S023-VII-7.4 states that all areas exceeding .6 mrem /hr (average) will be within restricted areas in addition to .25 mrem /hr being within or
- posted as restricted areas.
I REQUESTED RESOLUTION:
Modify the answer key to accept .6 mr/hr for full credit.
i NRC RESOLUTION: Comment accepted.
The answer key was adjusted in light of information supplied by the facility.
QUESTION 7.4 COMMENT:
5023-13-2 " Shutdown From Outside the Control Room" is an Abnormal Operating Instruction (A01) and therefore consistent with SONGS policy has no immediate actions. The responses required by the answer key are subsequent
, actions.
It is SONGS philosophy that only irmediate actions (which are contained in Emergency Operating Instructions E0Is) require rote memorization.
REQUESTED RESOLUTION:
In-as-much as the question is beyond what SONGS requires operators to
, memorize modify the point distribution to allow full credit for 4 responses rather than six. Additionally, a response to " station an operator at the remote S/D panel" would be an acceptable answer.
NRC RESOLUTION: Comment not accepted.
Question is operationally oriented, especially for an SR0 candidate; however, Step 3.4.1 will be accepted as a possible response in light of ;
facility supplied information. The answer key was adjusted accordingly. '
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ATTACHMENT 1 QUESTION 7.5(c)
COMMENT:
The answer key should be expanded to allow additional acceptable answers.
REOUESTED RESOLUTION:
Modify the answer key to accept " siphon breaker" as an acceptable response for full credit.
NRC RESOLUTION: Comment accepted.
The answer was modified to accept, " siphon breaker on the return header from the cooling system", for full credit. The additional reference supplied by the facility was also included on the answer key.
1 QUESTION 7.10 COMMENT:
Indication in addition to those listed in the answer key are available to give symptoms of an RCP seal failure such as alarms (seal press) and PMS indications such as CB0 flow.
! REQUESTED RESOLUTION:
~l Hodify the answer key to accept additional control room indications other than just the four listed in the answer key such as "RCP seal press HI/LO" j alarm and PMS indication of excessive CB0 Flow / Temp. i NRC Resolution: Comment not accepted.
Question was sufficiently objective such that the four (4) control room indications required by the answer key would not be confused with associated i annunciator and computer generated alarm inputs. Since these associated l indicators are implied by the answer key, no adjustment of the key is '
necessary. Appropriate credit will be awarded by the examiner if it is clear that the candidate is addressing one of the indications required by the answer key.
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ATTACHMENT 1 1
QUESTION 7.13 COMMENT:
The answer key response is beyond what the question requires. The question asks for " Critical Indications" not the quantifying criteria to verify RCS inventory control.
REQUESTED RESOLUTION:
Modify the answer key to accept " Pressurizer Level" and "RCS Saturation Margin" for full credit, without requiring the range of indication necessary to verify RCS inventory control.
NRC RESOLUTION: Connent not accepted.
This was the intent of the answer key. The key is clear in its guidance.
QUESTION 8.4(a)(b)(c)
COMMENT:
(a) CDM is not a' term used in the Technical Specifications (T.S.). This may have confused the candidates. T.S. refer to "2 plant management staff" as a review of the TCN.
(b) Cognizant Functional Division Manager (CFDM) is not a term used in the Technical Specifications. This may have confused the candidates.
(c) This question has multiple correct answers depending on whether the procedure is or is not QA Affecting.
REQUESTED RESOLUTION:
(a)&(b) Request that these parts be graded according to the appropriate TechnicalSpecification(6.8.3) terminology.
(c) Delete this question and redistribute the points as it is an ambiguous question.
NRC RESOLUTION: Comment not accepted.
The question utilizes the facilities terminology commensurate with administrative reference 50123-VI-1.0.1. The intent of the question is to test the candidates knowledge of SONGS 2/3 administrative procedures as they address Technical Specification requirements for procedural changes.
Both the question and answer key are clear in this intent.
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ATTACHMENT 1 i
QUESTION 8.5 J COMMENT:
i l The answer key requires expansion to include 1) Radial Peaking Factors and j 2)Xenonredistributioneffects. The question is so general that the Technical j Cpecifications being referenced include not only the Transient Insertion 4 Limits but also the Short and Long Term Insertion Limits. <
1 l REQUESTED RESOLUTION:
I Modify the answer key to include Radial Peaking Factors and Xenon redistribution
- as acceptable answers.
t j NRC RESOLUTION: Comment accepted.
l Answer key adjusted to accept requested resolution in light of facility j supplied references, t I
a QUESTION 8.6 COMMENT:
5 j Somecandidatesmayhavelumpedsystemstogether(f.e.,HPSI,SDC, Containment Spray as ECCS.) At SONGS it is comon practice to refer to the
! HPSI, SDC and Containment Spray Systems as Emergency Core Cooling Systems.
- Some candidates may have combined systems under the combined nomenclature of ECCS, therefore some candidates may only have four responses.
i REQUESTED RESOLUTION:
i j ' Request that ECCS be graded as an equivalent answer to HPSI, SDC and CS.
Give full credit for compiling systems under a comon heading, e.g. ECCS, i PASS (includes sample supply and return).
t i NRC RESOLUTION: Comment not accepted.
Same as Question 7.3 Resolution.
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ATTACHMENT 1 1
I QUESTION 8.9 COMMENT:
At SONGS the SR0 Operations Supervisor is not a commonly used position title. The correct SR0 titles are Control Room Supervisors (CRS) or Shift Superintendent.
REQUESTED RESOLUTION:
Modify the answer key to accept " Control Room Supervisor" or " Shift Superintendent" for full credit, as both of these positions can be considered "SR0 Operations Supervisors".
NRC RESOLUTION: Comment accepted.
Answer key adjusted to accept " Shift Superintendent" only. " Common Usage" is not an acceptable reference. The answer key must be based on clear and accurate reference material.
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F ATTACHMENT 2 SONGS 2/3 FACILITY COMMENTS AND NRC RESOLUTIONS - MARCH 31, 1987 R0 FXAM QUESTION 1.01 COMMENT:
The question requires the direction not magnitude of the power consumption.
REQUESTED RESOLUTION:
Modify the answer key to accept power consumption decreases with no reference to magnitude as a full credit response.
NRC RESOLUTION: Comment not accepted.
The question is adequately stated. No misunderstanding of this question occurred during the course of the exam, subsequently, the answer key will stand as is.
QUESTION 1.04(a)
COMMENT:
The answer key requires accuracy to the second decimal place. This is beyond the number of significant figures in the question.
REQUESTED RESOLUTION:
Modify the answer key to accept a range of acceptable answers from 4.5-5.0 'F for full credit.
NRC RESOLUTION: Coment not accepted.
The answer key cannot identify all reasonable ranges for a numeral response, such as required for functional or setpoint type responses. This action must be performed by the grading examiner. Acceptable ranges depend on the operational orientation of the question. Any reasonable range of possible 3
answers will be accepted by the grading examiner. Any awarding of points other than full credit must be documented by the grading examiner, comensurate with NUREG-1021, Examiner Standards.
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ATTACHMENT 2 QUESTION 1.07(b)
COMMENT:
The question does not imply the number of responses necessary for full credit.
REQUESTED RESOLUTION:
1 Modify the answer key to accept lowest temperature or highest pressure.
Either response should be acceptable for full credi T NRC RESOLUTION: Connent not accepted. ,
The question is sufficiently objective, and the answer key is consistent with the facility supplied references. No additional references were provided. '
QUESTION 1.08(b)
_ COMMENT:
Fuel temperature is also affected by the increase in steam demand. It is considered as an effect in part "a", therefore reactivity effects due to changes in fuel temperature should be considered.
REQUESTED RESOLUTION: f Modify the answer key to incorporate FTC positive reactivity effects as part of the answer. ,
NRC RESOLUTION: Coment accepted.
Answer key adjusted to accept requested resolution. ;
QUESTION 1.11(d)
COMMENT:
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(a) Assuming that the CEA insertion is independent and hasn't affected RCS temperature, CEA position has a negligible effect on Power Defect (coefficient).
(b) Parts (A) (B) (C) of this question were used on the SR0 exam but part ;
(D) was not. It is not reasonable to hold an R0 candidate to a broader level of theoretical knowledge than an SRO candidate.
REQUESTED RESOLUTION (a) Delete question 1.11(d) of accept " remain the same" as a full credit response. If the question is deleted redistribute the points.
NRC RESOLUTION: Coment not accepted. I The question is sufficiently objective, and the answer key is consistent with the facility supplied references. No additional references were provided.
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ATTACHMENT 2 QUESTION 1.15(b)
COMMENT:
i The response "The Reactor will be critical" is acceptable per the answer key.
This should be worth full credit since the question only asks "What will i happen," which is a vague statement. The count rate will also increase and should be recognized for partial credit. The use of the thumbrule which states "When Keff is close to 1, the amount of reactivity added may be added directly to Keff." Therefore, no calculation of Keff is necessary, i
REQUESTED RESOLUTION:
When grading the examination accept "the reactor will be critical" as a ,
full credit answer, with no calculation required, and count rate will increase as a partial credit answer.
NRC RESOLUTION: Comment not accepted.
This was the intent of the answer key. The key is sufficiently clear in its j guidance.
QUESTION 1.16(b) 3 COMMENT:
The equation for apparent power is as follows:
s Apparent power = real power / power factor. If the candidate describes power factor as the difference between apparent and real power caused by
) reactive load, the formula would te sufficient.
A drawing of the " power triangle" is an acceptable response to demonstrate
)j candidate knowledge.
j REQUESTED RESOLUTION:
Hodify the answer key to accept the above equation as an alternative response for full credit or a drawing of the power triangle.
NRC RESOLUTION: Comment accepted.
The answer key says by " vector sum"; therefore, a drawing or description that inparts this knowledge is acceptable. An adjustment of the answer (ey is not necessary.
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ATTACHMENT 2 i
QUESTION 2.04(a)
COMMENT:
1 The RCS Pressure / Temperature figure supplied with the examination had the
! word "Heatup" removed. Candidates may have been confused by this since
- the figure could easily be interpreted as a composite heatup and cooldown
- curve. While SONGS Technical Specifications do not employ a composite
, heatup and cooldown curve, this would not be an unreasonable assumption on the part of the candidates since the labeling of the figure was intentionally modified. The question has responses for both heatup and cooldown curves j which would further convince the candidates that the examination figure was a composite diagram.
REQUESTED RESOLUTION:
Modify the answer key to give full credit for the below response:
Part a (A) accept either 3 or 4 as the nrrect response.
NRC RESOLUTION: Coment not accepted.
> The question clearly identifies the requirements of the answer key. The I heat up curves (when collectively considered as a group) can be easily identified by any operator candidate with adequate system and operational j knowledge of the safety analysis.
QUESTION 2.05(c) i COMMENT:
The question is a plant transient with no information provided to the candidate about the rate of decrease of Tave. A boration is a relatively
, slow reactivity addition event and therefore the S/G level control l system will maintain the S/G level at the constant programed value.
i REQUESTED RESOLUTION:
Modify the answer key to accept " remain the same" as a full credit response.
NRC RESOLUTION: Coment not accepted.
A boration event that results in a 10*F decrease in Tave is not a "relatively i slow" event. No facility references were provided to support this coment.
The answer key supports the scenario outlined in the question, and sub-sequently, will stand as is, i
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ATTACHMENT 2 I
l l QUESTION 2.07 l COMMENT:
The question requires the candidate to state from memory various types of
, inverter failures. This level of detail is beyond what operators are i required to memorize. l REQUESTED RESOLUTION:
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! Delete this question from the examination as it is beyond the level of I knowledge required for operator candidates and redistribute the points.
NRC RESOLUTION: Comment accepted.
{ The question is deleted from the exam.
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QUESTION 3.01(a) i
! COMMENT:
i j The answer key is correct, however, the question gives no indication to the candidate of the depth the answer key requires. The question could be answered simply by stating that the " Emergency Off" eliminates the" permissive so the valves go' closed and will not open under any conditions.
j REQUESTED RESOLUTION:
1 f j When grading the examination accept any answer that indicates that any ;
- open valves close and/or prevents any closed valves from opening.- No
credit should be deducted if the candidate does not state " fast close".
NRC RESOLUTION: Coment accepted.
The answer key is adjusted to accomodate this requested resolution.
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l QUESTION 3.03
, COMMENT: ;
.l The answer key is correct, however, at SONGS it is comon practice to refer to Power Operating Limits as POL.
REQUESTED RESOLUTIONS:
! Modify the answer key to accept DNB POL and Linear Heat Rate POL.
i NRC RESOLUTION: Comment accepted.
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ATTACHMENT 2
. QUESTION 3.04(c)
COMMENT:
The question asks for the purpose of Raw Linear Power. The answer key is correct, however the primary function for.the Raw Linear Power signal is as an input into CPC's, not for the 5% deviation alarm. The answer key should reflect that it is primarily used for DNBR and LPD calculations, not for the 5% deviation annunciator.
REQUESTED RESOLUTION:
Modify the answer key to reflect that the primary purpose of the Raw Linear Power input is for DNBR and LPD calculations.
NRC RESOLUTION: Comment accepted.
Based on additional references supplied by the facility, the answer key is adjusted to accommodate the requested resolution.
QUESTION 3.05 COMMENT:
The answer key is correct, however, some candidates may use a simple drawing of the reactor trip breaker arrangement as part of the response.
REQUESTED RESOLUTION:
Modify the answer key to accept an appropriate drawing of the reactor trip breaker arrangement.
NRC RESOLUTION: Comment not accepted.
Same as question 1.15(b) resolution.
QUESTION 3.06 COMMENT:
This question is beyond what an operator is required to memorize. The control room indication for the diesel Fuel Oil Storage Tanks is calibrated in percent. There is no indication of fuel tank level in the diesel building.
The indication is located in the fuel tank vault which is normally inaccessible.
The Technical Specifications Limiting Condition for Operation are stated in gallons. Stating fuel tank levels in feet and inches without the use of a strapping table is an inappropriate question.
REQUESTED RESOLUTION:
Delete the question ar.d redistribute the points. 1 NRC RESOLUTION: Comment accepted.
Question 3.06 is deleted from the exam. l 6
ATTACHMENT.2 l QUESTION 3.08(a)(b)
COMMENT:
(a) Comon terminology at SONGS to describe switch position associated with the Excore Nuclear Instrumentation is "any switch out of operate or-off" will cause trouble light.
(b) The question requires knowledge beyond that required of an operator.
An operator would be expected to analyze this situation given the appropriate reference material, however, no reference material was provided.
REQUESTED RESOLUTION: '
(a) Modify the answer key ,to accept "any switch out of operate or off."
(b) Delete the question from the exam and redistribute the points as it is beyond what operators are required to memorize..
- NRC RESOLUTION
- Comment not accepted.
Same as question 1.07(b) resolution.
QUESTION 3.09 COMMENT:
The range for the CPC, pressurizer pressure auxiliary trip was modified between Cycle 2 and 3 from 1825 to 1860 PSIA. Also, two additional CPC auxiliary trips were added. The examination did not state whether the question was pertaining to Cycle 2 or Cycle 3.
, REQUESTED RESOLUTION:
Modify the answer key to accept 1860 and 1825 PSIA, and the additional auxiliary trips listed in the attached reference.
NRC RESOLUTION: Comment not accepted.
The question was structured such that the specific responses identified by the answer key would be required. The answer key is consistent with facility supplied references. The requested changes would elevate the level of difficulty beyond the original intent of the examination outline.
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_. . . . . - - . . _ - _ - - 0
ATTACRMENT 2 QUESTION 3.13(c)
COMMENT:
The S/G high level trip is 90% Narrow range not wide range as stated in the answer key.
REQUESTED RESOLUTION:
Modify the answer key to correct the S/G high level trip to 90% Narrow Range.
i NRC RESOLUTION: Comment accepted.
The answer key is adjusted to accommodate the requested resolution, based on the information within supplied facility references.
QUESTION 4.02 COMMENT:
This question is based on a chart that is referenced in the Normal Operating Instruction that is not required to be memorized. Normal Operating Procedures by their very nature are extremely detailed and used under a methodical
~
controlled environment. It would be contrary to SONGS stated policy to require operators to operate from memory rather than in verbatim compliance '
with approved procedures. Allowance should be given for being in a reasonable range for this response.
REQUESTED RESOLUTION:
When grading the examination allow full credit for responses between 20-30%
per hour.
NRC RESOLUTION: Comment accepted.
Based on information within supplied facility references, the answer key is adjusted to accommodate the requested resolution.
8
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ATTACHMENT 2 o
QUESTION 4.07(a)
COMMENT:
The answer key should include conserving IE 125VDC battery power since this is what insures adequate 125VAC instrumentation power is available. The answer key response is more detailed than the question indicates.
RESOLUTION REQUESTED Modify the answer key to accept conserving IE 125VDC battery power for full credit. Delete from the answer key the section that refers to monitoring natural circulation if the blackout lasts more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
NRC RESOLUTION: Comment accepted.
Same as Question 4.02 resolution.
QUESTION 4.08 COMMENT:
The answer key response #3 should be corrected to reflect a SDM of less than 5.15% delta K/K. Answer #4 should be less than 3% delta K/K.
_ REQUESTED RESOLUTION:
Modify the answer key as stated above.
NRC RESOLUTION: Comment accepted.
Same as Question 4.02 resolution.
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c r
g ,f rd'A SY ANSWER KEY
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U.S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION Facility: SONGS 2/3 Reactor Type: PWR-CE Date Administered: MARCH 31, 1987 ,
Examiner: THOMAS R. MEADOWS, RV l Candidate: ;
INSTRUCTIONS 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 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.
1
% of Category .% of Candidate's Category
. Value Total Score Value Category 25 25 5. Theory of Nuclear Power Plant Operation, Fluids, and Thermo-dynamics .
25 25 6. Plant Systems Design i Control, and Instrumentation ,
25 25 7. Procedures - Normal, Abnormal Emergency and Radiological Control -
25 25 8. Administrative Pro-cedures Conditions, and Limitations 100 Totals All work done on this examination is my own, I have neither given nor received Candtdate's 51gnature.
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REQUIREMENTS FOR ADMINISTRATION 0F WRITTEN EXAMINATIONS .
- 1. A single room shall be provided for completing the written examina- -
tion. The location of this room and supporting restroca facilities I
shall be such as to prevent contact with all other facility and/or 1
.:. . 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, motel, or other building. 0b- '
l,,,;g , taining this room is the responsibility of the licensee. 1 2.
Miriinus spacing is required to ensure examination integrity as determined by the chief examiner. Minisua spacing should be one ;
candidate per table, with a 3-ft space between tables. No wall l i- charts, models, and/or other training materials shall be present in l the examination roca. '
i
- 3. Suitable arrangements shall be made by the facility if the candi- l 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 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 8-1/2 by 'll in. lined paper in __
t unopened packages for each candidate's use in completing the exas- l 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 r- -
calculators, or slide rules into the examination room,,and pencils, no other equipment or reference material shall be allowed.
- 6. Only black ink or dark pencils should be used for writing answers to questions. -
I e
Examiner Standards i
- s. .
4 ; .' NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this' examination the following rules apply:
e -
- 1. Cheating on the _ examination means an automatic denial of your application' and could result in more severe penalties. . . .
1 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.
I" 's ! * .
- 3. Use black ink or dark pencil only to facilitate legible reproductions.
s-
! h.ir. 4. Print your name in the blank provided on the cover sheet of the examination.
'g).-5 ,
p 5. Fill in the date on the cover sheet of the examination (if necessary). I f 5. Use only the paper provided for answers.
- E 7. Print your name in the upper right-hand corner of the first'page of each I
< 4 section of the answer sheet. 1
- 8. Consecutively number each answer sheet, write "End of Category " as .
appropriate, start each category on a new page, write only g ee side of the paper, and write "Last Page" on the last answer sheet. '
l S. Number each answer as to category and number, for example,1.4, 6.3. -
- 10. Skip at least three lines between each answer. .
, 11. Separate answer sheets from pad and place finished answer sheets face * '
- ;., down on your desk or table. ,
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- L 12. Use abbreviations only if they are comonly used in facility literature. -
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- ) 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. i l
- . . .)
- 14. Show all calculations, methods, or assumptions used to obtain an answer l to mathematical problems whether indicated in the question or not, l i
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- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS 0F THE QUESTION AND DO NOT LEAVE ANY ANSWER 8 LANK. ,
- 16. If parts of the examination are not clear as to intent, ask questions of
,' the examiner only.
! 17. You mest sign the statement on the cover sheet that indicates that the -
1 work is your own and you have not received or been given assiktance in J completing the examination. This aust be done after the examination has been. completed. -
i Examiner Standards ,
)
- 18. When you complete your examination, you shall: .,
- a. Assemble your examination as follows: .-
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(1) Exam questions on top. . j (2) Exam aids - figures, tables, etc. '
(3) Answer pages including figures which are a part of the answer.
- b. Turriin 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 1 [.@g. -l 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.
L t .
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.1 Examiner Standards .
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EQUATION SHEET f = ma y . s/t l
" - 88 2 Cycle efficiency._=: Net Work (out) s = y e + Isac ,
2 o Energy (in) l E = aC a = (vg - y )/t
~A*
KE = lsev y f=y o
+t .
A = AN A=Ae .o PE = agh a = 6/t A = In 2/tg = 0.693/tg W = v&P eq (eff) = (t,I)(t,)
AE = 931Am *
(c +g) 6=fnCAT p d*AAh I = I IX -
Q = UAAT h *Vl%(Teser -
UX I = I Pwr = Wg In I=I o
10"*
, p=p lo SUR(t)' TVL = 1.3/p P=P o et /T HVL = 0.693/p SUR = 26.06/T T = 1.44 DT SCR = S/(1 - K,gg)
SUR = 26 I CRx = S/(1 - Keffx)
T = (t*/o ) + [(6 'o)/A,ggo ] CRy (1 - Keff)g = CR 2 (l - Keff)2 T == 1*/ 6 - D M = 1/(1 - K,gg) = CR g/CR 0 T = (I - o)/ A,gg o M = (1 - K,gg)0/ (1 - K,gg)g o = (K,gg-1)/K,gg = AK,gg/Keff SDM = (1 - K,gg)/K,gg p= '
(1*/TK,'gg) + [E/(1 + A,ggT )] ,
1*.= 1 x 10" seconds P = E(V/(3 x 1010) -I A,gg = 0.1 seconds I = No Idlg=Id22 WATER PARAMETERS Id =Id2 g
I gal. = 8.345 lbm 2 R/hr = (0.5 CE)/d (meters)
I gal. = 3.78 liters R/hr = 6 CE/d (feet)
I ft3 = 7.48 gal. MISCELLANEOUS CONVERSIONS .
Density = 62.4 lbm/ft 3
~
10 1 Curie = 3.7 x 10 dps Density = 1 gm/cm I kg = 2.21 lba Heat of varorization = 970 Etu/lbm I hp = 2.54 x 10 3BTU /hr
, Heat of fusica = 144 Btu /lba 1 Hw = 3.41 x 10 Beu/hr 6
1 Atm = 14,7 psi = 29.9 in. Eg. 1 Bt.u = 778 ft-lbf 1 ft. H 30 = 0.4333 lbf/in 1 inch = 2.54 cm F = 9/5 C + 32 "C = 5/9 (*F - 32) "
r- .
7 SECTION 5 .
THERORY OF NUCLEAR PLANT OPERATION, FLUIDS AND THERMODYNAMICS
- QUESTION 5.1- (1.0)
As a subtritical reactor nears criticality, the length of time to reach equilibrium count rate after an insertion of given fixed ,
amount of positive reactivity...
(SELECT THE ONE CORRECT ANSWER)
(a) decreases primarily because of the increased population of delayed neutrons in the core.
~
(b) increases primarily because of the increased population of delayed neutrons in the core.
(c) increases because of a larger number of neutron lifa cycles required to reach equilibrium. '
(d) decreases because the source neutrons are becoming less important in relation to total neutron population.
- ANSWER 5.1 (1.0)
(c)
- REFERENCE SONGS 2/3 Reactor Theory, Nuclear Physics, and Core Operating Characteristics review text e
i b-1 i
- OUESTION 5.2 (3.0) s Concerning Axial Flux Distribution at 100% power, at end of life:
(a) Why does the axial flux distribution (the uoper homo shown in Figure 5.5.b) peak in the upper portion of the core 7 (1.0)
(b) Why does the axial flux distribution (the lower humo shown in Figure 5.5.b) peak in the lower portion of the core 7 (1.0)
(c) Why is the lower axial flux distribution hump shown in -
Figure 5.5.b slightly lower than the peak at BOL, 100% power as shown in Figure 5.4.b 7 (1.0)
- ANSWER 5.2 (3.0)
(a) At 100% power the axial flux distribution peaks in the upper portion of the core as a result of fuel depletion in the bottom (1.0).
O (b) The peak in the lower portion of the core in due to the higher moderator density ( 1. O) [e 4 to pye- rv /* e-t- er#2 4'reE" <* f
.rsosossecrr r e s'r sew norswsrm se nn r r.2.c I po e vest (c) The peak is located lower than itm was at bOL due to fuel e""" "" "
depletion .just below centerline (1.0).
- REFERENCE SONGS 2/3 Reactor Theory, Nuclear Physics, and Core Operating -
Characteristics review text l
l h "" l
. t 0% POWER 100% POWER 100% - -- - -- 1005 . - _
- 0 I
_c .l LUX PEAK g c FLUX YE Z
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U E - I PEAKS f
8
, d i e o AXIAL FLUX - AXIAL FLUX -*-
ini (b) e Typical axial thermal flux profile for EOL conditions.
. Figure 5.5 -
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1ess -- -- .
see5 . . _
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1 ^
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se o
! .c -
i cm I l *E W i I 505 - = PEAK E05 I
g PEAK 8
i j e 'e l AXIAL FLUX e AXIAL FLUX +
i M M,
- 4 a
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Typical antal thermal flus proffle for BOL conditions.
I Figure 5.4 '
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- QUESTION 5.3 (1.5 ) ,-
1 Commensurate with Technical Specifications (Bases B 3/4 5-2),and System Discription SD-SO23-740 (Containment Spray), there are two(2) basic reasons for adding NADH to Containment Spray:
What are the two(2) reasons for adding NADH to the Containment
- Spray upon initiation? (0.75 each )
1
- ANSWER 5.3 (1.5 ) ,
NADH minimizes the possibility of corrosion cracking of ESF and containment metal components following a LOCA (by maintaining a basic PH coolant inventory)(0.75), and assist in the removal of Iodine in the containment atmosphere.(0./6) 1 m
- REFERENCE i SD-5023-740, page 2 Technical Specifications b 3/4 S-2 1
o WS 1
f 4
5-3
- QUESTION ' .~
5.4 (1.0)
(a) What chemical is added to the RCS to control Oxygen concentration, via the CVCS system, while the plant is shutdown 7 (0.5)
(b) What chemical is added to the RCS for PH control, via the CVCS system 7 (0.5)
%AN3llCR "
5.4 (1.0)
(t) hydrazine (0.5)
(b) ' t thium Hydroxide (0.5)
- REFERENCE SD-5023-390 e
a wm 9
0
.,4 5-4
- QUESTION 5.5 (1.5) s (a) Which operating Emergency Diesel Generator system No. 1 output parameter ( VOLTAGE or VARS ) will change ,when the voltage regulator switch is taken to " raise" during the following conditions :
(1) DG system No. 1 is loaded, but NOT paralleled to to the grid system. (0.5)
(2) DG No. 1 is loaded and paralleled to the grid. (0.5)-
(b) Identify the acronym ( KVA, KW, or KVAR) that is commonly used for each of the following types of electrical power n ( O.5 pts., 0.25 each )
- (1) Apparent Power '
(2) Real Power
,
- ANSWER 5.5 (1.5)
(a) (1.0, 0.5 pts. cach)
(1) voltago (increase)
(2) VARS (increase or decroeue)
(b) (0.5 pts, 0.25 pts.each ) -- '
(1) KVA (2) KW
- *PEFERENCE 5D-5023-750 SD-SO23-10*J APPENDI X C paqo c-3 and Figuro C-5
,s 5-5
]
-r_ _ . - _ _ _ . _ . .
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- QUESTION 5.6 (1.0)
! Why does Baron Worth decrease with increasing coolant temperature ?
- ANSWER
, 5.6 (1.0)
Boron worth decreases with increasing moderator temperature because of the decrease in moderator density (displaces baron out' j of the core - at a given ppm there will be more pounds of boron j in the core when the system is cold than when hot).
- REFERENCE
! SONGS 2/3 Reactor Theory, Nuclear Physics, and Core Operating
~
l Characteristics review text l
1
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- QUESTION '
5.7 (1.5)
- During a plant startup, below the POAH, 0.05% reactivity is added to the core via baron dilution.
- i What is the resultant transient Start Up Rate 7
(
assumef=0.0072 K/K )
eff
- A .
- ANSWER 5.7 (1.5) .
i SUR = 26 (2eff4K/K) / ( kf- K/K)
= 26'( O.1 x 0.0005)/(0.0072-0.0005)
= .19 dpm '
i 1'I I *
- REFERENCE S0 tit 382/3 Reactor Theory, Nuclear Physics, and Core Operating l Characteristics review te>:t
)
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$ QUESTION ' ,
5.8 (2.0)
During an operational occurrence at power operation , assume that l
DNB would be reached when the local heat flux at a given fuel rod position reaches 30 Kw/ft:
(a) What would the value of DNBR be if the actual heat flux at that same fuel pin was five(5) kW/ft 7 (0.5)
(b) What is the DNBR reactor Saf ety Limit f or San Onof re-Unit 2 7, (0.5)
(c) What is the reason or basis f or the DNBR Saf ety limit ? (1.0)
- ANSWER '
5.G (2.0) l (a) (0.G, Word definition is not necessary )
1 DNBR = huat flux causing DNG at local fuel position / actual heat l flux at that local j po:ition DNBR= 00/5
=6 i
,b)
( The DNBR of the reacter core shall be maintained greater than or equal to 1.31. (0.5)
(c) To maintain the intoqrity of the fuel cladding (and prevent fission product releaso under all operational conditions).
(
.1.0) i
! 1 REFERENCE j SONGS HTFF Study Guide Nuclear Enorgy 'fraining, Plant Performance,NUS trainino Corporation.
Tor.hnical Spectficalione. 2.1.1.1 1
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- QUESTION ;
5.9 (1.0) , l l s l What is the reason for the 80 second period (-1/3 DPM), which lasts for approximately 15-20 minutes following a reactor trip 7
- ANSWER 5.9 (1.0)
)
The 80 sec. period is determined by the longest delayed neutron
, precursor half-life ( The longest delayed neutron precursor half life is 55.3 seconds, yielding a negative period of 80 seconds.)
i
- REFERENCE SONGS 2/3 Reactor Theory, Nuclear Physics, and Core Operating 1
Characteristics review text,
! G.P. Physics. Vol. II,
.( SD-SO23-470, Encore Nuclear Inutrumentation i
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q $ QUESTION ,
5.10 (1.0)
Why is a rupture of a Main Steam line at End of Life (EOL) a more limiting accident than at the Beginning of Life (BOL)*?
- ANSWER 5.10 (1.0)
- The Moderator Temperature Coefficient is less negative at BOL
- than at EOL . At EOL the sudden cooling of the reactor coolant .
upon a MSL rupture results in a larger addition of positivo reactivity (uncontrolled).
i
- REFERENCE -
- SONGS 2/3 Reactor Theory, Nuclear Physics, and Core Operating Characteristics review text,
_ G.P. Physica- Theory Text, NRC DEGRADED CORE PERSPECTIVES - CE CE-EPG's I
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- QUESTION 5.11 (1.0) ,-
r The Xenon peak that occurs after a reactor trip from 100% l I equilibrium Xenon condition is greatcr than the peak for a trip '
i from 50% power since:
(Complete the statement by selecting the ONLY correct response from the choices listed below)
(a) The fission yield for Xenon is higher at 100% power.
9 (b) There are more thermal neutrons in the core at 100% power.
(c) There is more Iodine in the core at the time of the trip f rom
, 100% power.
J (d) There are more delayed neutrons in the core at 100% power.
1
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- ANSWER 5.11 (1.0)
(c) i i tREFERENCES SONGG2/3 Reactor Theory. Nuclerie Physics, and Coro Operatinq Characteristics review ters t 0
+
4 d
0 s
b-11 ;
s SOUESTION 5.12 (3.0) .
The reactor in operating at 100% power (3425 MWth) as indicated on nuclear power instrumentation. The following data in recorded Feedwater Temperature 439 dog F Total Feedwater Flow 15,000,000 lbm/hr Feedwater Enthalpy (hf) 418 BTU /lbm Steam Pressure 992 psig Other System gains and lossen .
What is the the actual power output (in percent of rated power) of the primary system f or this operational situation 7 (Use the inf ormation provided in the attached steam tables, EHOW ALL WORK !)
$ ANSWER 5.12 (3.0)
O = rn del t a h (g) steam nnthalpy FW enthalpy enthalpy rico POWER (DTU/lbm) (DTU/lbm) (DTU/lbm) Hfo x Total --
- FW flow (DTU/hr) 1193 ( g ) 410 775 11.66 x ,
10^9 11.66x10^9 DTU/hr x iMw / 3.413n10^6 DTU/hr = 3415.5 Mw (o.M) 3415.5 Mw/3425 Mw = 99.'/ % (1.0) me=
- RCFEREN,CE Hoat Tronefor, T her rend yn nm t e n . and Fluid F1ow F*undamuntals-thinural Phycien 4
.S
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l $ QUESTION s 5.13 (1.5)
The plant is in hot standby with one of the steam, generators at 905 psig. Use the attached steam tables and/or mollier diagram to answer the f ollowing questions:
(1) What in the steam temperature in the steam generator?
(0.5)
(2) Assuming an atmospheric relief valve is opened, what -
will the steam discharge temperature be (assume the discharge steam pressure is atmospheric) 7 (1.0) 4 ANSWER 5.13 (1.5) '
(1) 534 degreen F (0.5)
(2) 306.5 degrens F (superheated, adiabatic proconu) (1.0) tREFERENCE Heat Trennfor. Thermodynamien, and Fluid Flow Fundamentals-General Phynics ene t
t 8
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$ QUESTION s 5.14 (1.0)
- Regarding the feedwater heaters
! If the level in a feedwater heater is allowed to increase above ,
, its normal operating level, Why will the temperature of the ,
feedwater exiting the heater decrease ? !
e
- ANSWER I 5.14 (1.0)
- The level increase expones less surface area availability betwoon the heater tubes and heating steam,
) ( less latent heat removed from the steams thereforo. less heat transfered to the feedwater), i resulting in a lower enit feedwator temperatura.
i
-l ,, 4 REFERENCE j Hoat Transfer, Thormodynamics. and Fluid Flow Fundamentats-j Guneral Physics i
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- sOUESTION ,.
{ 5.15 (2.5) i i A motor driven centrifugal pump is used in a closed cooling system. The pump has two speeds, 1200 RPM and 1900 RPM. l
)
(a) How does each of the following parameters vary (in both j
direction and magnitude) when the pump is switched from fast 3
to slow speed n (0.5 pts. mach) 4 j (1) Pump differential pressure 7 .
i j (2) Flow ?
i
)
(3) Power 7 1
(b) Why does the observed indicated pump motor Amps increase when
, , the ONLY change is that the temperature of the fluid being pumped decreases 7 (1.0) 4 ANSWER i 5.15 ( 2. 5.)
j (a) (1.5, 0.5 pts. cach) ' I i i j (1) (Differentist pretsuro is preportional to speed equored) j Pump differential proscuro will go down by a factor i of 0.44. ,
l l (2) (Flow is proportional to spoed)
! Flow will go down by a factor of 0.67.
j (3) (Power is proportional to nprod to the third power) --
l Power will go down by a factor of 0.3. f i
, (b) As tho temporaturo of the fluid being pumped decreason its ,
dunnity and vincoatty will incenoso. This will incenase .
l pumping power and thorofore motor Amps will incroaco. I 1
( mnro pump wor 0* morn pump powne= Amps increase ) i j (1.0) l:
- REFERENCE Heat Transfer. Thermodynamien, and Fluid Flow Fundamenteln-General Physics '
?
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j 5.16 (1.5)
- For each of the factors listed below, does the magnitude of the l
negative Power Coefficient increase or decrease, as the factor is changed in the direction described?
- a. Moderator temperature decreases (0.5) .
, b. Core age increases (0.5)
- c. Baron concentration increases (0.5) ,
l sANSWER l . 5.16 (1.5)
) a. docroono (0.5)
) b. incrosso (0.5)
- c. decrcAte (0.5)
- REFERENCE
- Robcter Theory. Nuclear Physics. And Coro Oper.iting ,
j Charactoriutics pailes 159 to 101. '
i
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- 1e sessesses***sses*********ssessssssses*****ss**sssssssssssssssssse END OF SECTION 5.0 --
?
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!1-16
SECTION 6.0 s Plant Systems Design, Control, and Instrumentation
- QUESTION i 6.1 (2.0)
Upon a Steam Generator Main Feedwater Pipe rupture and subsequent MSIS :
How does the EFAS system logic initiate Auxiliary Feedwater and l ensure that only the INTACT steam generator is fed 7 i .
- ANSWER 6.1 (2.0) l The EFAS system loqic measures the difference in prosaure j
betwoon the two S/G'*n . When the low level condition exits 1 and the delta-pressure between the S/G's setpoint is reached, the EFAS will start its associated Aux 1111ary Feed Pumps. The S/G with the highest preneure will
- he fed (overrides the MSIS , allowing Aux feed valvos feeding the intact S/G to opon). ,
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s 6-1
$ QUESTION s ' -
6.2 (2.5)
The backup heaters in the Pressurizer are normally turned on by either a low Pressurizer pressure signal or a Pressurizer high-level error signal.
(a) What is the reason for the Pressurizer high-level error signal energizing the backup heaters?
(1.0)
(b) What are the low PZR pressure and high PZR level error setpoints, that auto-energize the B/U heaters ?
(0.5 pts each) (1.0)
(c) What is the Low PZR level setpoint that deenergizes ALL the PZR heaters ? (0.5)
- ANSWER 6.2 (2.5)
. (a) This minimizes pressure transients from load increases causing pressuri=er insurgos. (1.0)
(b) Low PZR pressure - 2200 psia (decreasing) O).5)
High PZR level deviation from setpoint +4% (0.5)
(c) Low PZR level. 27% (decreasing) (0.5)
- REFERENCE SD-GO23-360 i
l l
6-2 j l
t
- QUESTION 6.3 (1.5) -
What are the three(3) diesel generator trips that remain functional after an emergency start (LOVS or SIAS) ?
(0.5 pts. each)
- ANSWER 6.3 (1.5)
- 1. Engine overspeed (0.5)
- 2. Low lube oil pressure (0.5)
- 3. Generator differential (0.5)
- REFERENCE 5D-5023-750 l o
- e t l
4 o
J 6
i i
6-5
- QUESTION ,, .
6.4 (1.0)
Regarding S023-3-2.1, CVCS Charging and Letdown precaution:
Why must letdown backpressure be maintained at or above 460 psig any time the temperature of the outlet letdown flow of the Regenerative Heat Exchanger exceeds 450 deg.F 7
- ANSWER 6.4 (1.0) ,
To prevent the letdown process flow from flashing to steam upstream of the Letdown HX.
- REFERENCE S023-3-2.1; SD-SO23-390 i
e I
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0 .
e 6
f 2
f' $
1 i
l 6-4 w -
- DUESTION ,,.
6.5 (1.0)
There is a lag unit between the Pressurizer Level Controller and the Letdown Throttle valve controller. This lag unit slows down the speed at which the Letdown Throttle valves stroke.
What would happen if the Letdown Throttle valves were allowed to open too rapidly?
- ANSWER 6.5 (1.0)
A rapid opening of the valves could cause the relief valve upstream of the backpressure regulating valve to lift. (1.0)
- REFERENCE SD-5023-360 page 66.
O e
+
6 e
N 6-5
$ QUESTION 6.6 (0.5) s -
The Feedwater Control System has three modes of manual operation.
What manual mode of operation allows bumpless and balanced transfers between manual and automatic? (0.5)
- ANSWER 6.6 (0.5)
Preferred Manual (0.5) (A sy rg enshrs?" g /~ yp s 'y ,,, ;,,,
tREFERENCE 9/ 0'FM A N 0" s 'r / ce t-rs ett, SD-SO23-250 page 55. f,,y , f ,.
n retw e ~ 7844 ten in es m as &
J sus A4L
- TH FA trs rlows
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6-6
- QUESTION -
6.7 (1.0)
A SIAS has just occured from a Steam Line Break in containment, with a concurrent loss of preferred power to the class 1E buses.
If an EFAS is present also, the Motor Driven Auxiliary Feedwater pumps will start 30 seconds later.
What is the reason for this time delay ? ,
- ANSWER 6.7 (1.0)
To prevent overloading the D/G's
~
- REFERENCE SD-SO23-780 pages 44 and 45.
SD-SO23-750 SD-SO23-120, page 116 O
e 9
e
.i 6-7
20UESTION . _ -
6.8 (2.0)
Regarding the Qualified Safety Parameter Display System:
What are the four (4) parameters monitored by the QSPDS?
(0.5 pts. each)
- ANSWER 6.8 (2.0) ,
- 1. (Maximum temperature) subcooled margin (0.5)
- 2. Reactor vessel level (0.5)
- 3. Representative Core Exit Thermocouple temperature (0.5)
- 4. Core exit subcooled margin (0.5)
~
- REFERENCE SD-SO23-820 page 56.
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{
l 6-8
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- QUESTION 6.9 (3.0)
Commensurate with Technical Specification LCO 3/4.4.8, PRESSURE / TEMPERATURE LIMITS, the RCS temperature.and pressure shall be limited in accordance with the limit lines shown on attached Figure 6.9.a for specific operating conditions:
(a) MATCH the LIMIT LINE (A-D) with its associated OPERATING CONDITION by selecting its specific operating' condition from the choices given below ( 1-6 ).
(2.0, 0.5 pts. each)
LINE Condition # OPERATING CONDITION (choices):
(A) # (1) Cooldown 30 deg/hr below 280 deg F (B) #_____ (2) Core Critical o (C) # (3) Lowest service temp (heat up)
(D) # (4) Lowest service temp (cooldown)
(5) Inservice Tests (6) Heatup 30 deg/hr below -
280 deg F (b) Why, as the reactor vessel ages, do these limits imposed __
from the cooldown limit curves become more restrictive than limits for heatup 7 (1.0)
- ANSWER 6.9 (3.0)
. (a) ( 2.0, 0.5 pts. each )
(A) #3 (C) #6 (B) #5 (D) #2 (b) The inner wall receives the higher neutron flux, which i'ncreases metal embrittlement as the core ages. (1.0) tREFEREUGE Technical Specification LCO 3/4.4.8, PRESSURE /TEt1PERATURE LIMITS 6-9
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.Figur . 6.9.a
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\, c.. .u'3\' -. RESSURE/ TEMPERATURE LIMI
/ MRf i 6 'N AMtextsi 140-
- /t,4-29
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ggA7ep Figure6.9.a-
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- sco/HR <25~.
INSERVICE TESTS
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0 TEMP . 202 F 3200 <-
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^ RESSURE/TEMFERATURE l. IMITA
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MKfi6'W AMEN:P.ENT UO
- 3/4 4-29
- QUESTION 6.10 (2.5)
Concerning EXCORE instrumentation Safety Channels A,B,C,and D:
(a) The TROUBLE BISTABLE for each Safety Channel is initiated by a Loss of Drawer Low Voltage. What other four(4) conditions will trip this TROUBLE BISTABLE? (2.0, 0.5 pts. each)
(b) Why may each drawer Trouble Light NOT come on upon an associated Loss of Drawer Low Voltage? (0.5)
- ANSWER 6.10 (2.5)
(a) (2.0, 0.5 pts. each)
(1) calibration switch out of OPERATE (2) trip test switch out of OFF (3) removal of any circuit card (will accept " pulled card / channel")
O (4) loss of detector HIGH voltage (b) (0.5)
The drawer trouble light may not come on upon a loss of drawer LOW voltage since drawer low voltage supplies power to the TROUBLE LIGHT.
- REFERENCE SD-SO23-470
. i 6-10
- QUESTION
! 6.11 (2.5) -
The particular combination of credible input parameters into the CPC's is known as the CPC " Operating Space". Any input that falls outside its associated specified range gives DNBR and Local Power Density channel trips. Two of these input parameters are:
> (1) No core protection calculator failure, and (2) Quality Margin < O .
What are the five(5) remaining credible input parameters that define the normal CPC operating space (specify the range for each" stated parameter) 7 (0.5 pts. each) -
- ANSWER 6.11 (2.5, 0.5 pts. each)
(a) 1925 psia < pressure < 2375 psia (b) 495 deg.F < Tc < 580 deg.F (c) >2 RCPs running (d) 1.29 < Radial Peaking Factor < 4.28 (e) .5< Axial Shape Index < +.5
- REFERENCE SD-SO23-710 Technical Specifications O
I e
. i 6-11
- QUESTION 6.12 (3.0)
Concerning the Low Steam Generator Flow Trip (S/G flow low):
(a) From what component failure and subsequent Safety Limit violation does the Low Reactor Coolant Flow trip protect the plant. (2.0)
(b) Where is this low flow condition sensed 7 (1.0) . ,
- ANSWER 6.12 (3.0) -
(a) A Reactor coolant pump (RCP) shaft shearing (1.0), causing a
~
low flow condition that could cause a DNBR or Local Power Density safety limit violation (1.0) (2.0)
- (b) delta P across primary side of either S/G
. (1.0) 1 O
- REFERENCE Technical Specifications SD-SO23-710 m
. I i
s f
6-12 . l
- QUESTION ._-
6.13 (1.0)
Concerning the SBCS " Quick Open" signal development upon a rated load rejection (45% power): ~
The output of the load change detector, for each valve group, goes to a " Track and Hold " circuit, prior to being passed on into the Quick Open Demand Programs. The purpose of this circuit is to add a slight time delay to the change circuitry.
What is the reason for this time delay 7
- ANSWER -
6.13 (1.0)
The track and hold citcuitry time delay prevents the SBCV's
, from cycling upon a load reject.
- REFERENCE SD-SO23-175 o
O s
. 4 6-13
l
- OUESTION '
6.14 (1.5)
Considering Spent Fuel Pool Cooling system operational design:
(a) (1.0)
During plant shutdown and refueling operations, the Spent Fuel Pool average temperature will not exceed 150 deg.F with both Spent Fuel Pool pumps and both Heat Exchangers in service, while the MAXIMUM design cara heat load is in the Spent Fuel Pool.
~
What is this MAXIMUM design core heat load, in terms of number of reactor core loads into the SPF 7 (b) (0.5) - -
i During plant shutdown and refueling operations, under MAXIMUM
~
design core heat 1 cad conditions, the Spent Fuel Pool average i temperature will not exceed 140 deg.F when using the BACKUP Cooling system.
What cooling systems' pump (s) and/or heat exchanger (s) constitute this Backup Cooling System 7
- ANSWER 6.14 (1.5)
(a) 3 2/3 cores (1.0)
( 2 2/3 core is in the SFP and then the full core is .
unloaded)
(b) (1) one LPSI pump (0.25)
(2) one Shutdown Cooling heat exchanger (0.25) ,,
- REFERENCE SD-SO23-430
- t******$t************* l END OF SECTION 6.0 I
. l l
1 6-14
SECTION 7.0 Procedures-Normal, Abnormal, Emergency . _ .
and Radiological Control
- QUESTION 7.1 (2.5)
Concerning Main Turbine startup Operations:
(a) Commensurate with the GEC Turbine Instruction Manual, Why must the critical speed bands be avoided upon turbine roll to rated speed 7 (1.0).
(b) At approximately what Reactor Power level is Main Turbine roll to the first hold point ( turbine -
status checkpoint ) commenced 7 (0.5)
(c) Why must the Control Valve Opening Limit (CVOL) be returned
, to 0% whenever there is a delay in rolling the turbine when the governor is armed 7 (1.0)
O
- ANSWER 7.1 (2.5)
(a) Prolonged operation in a critical speed band may cause Turbine /blading damage (vibration and/or overheating) (1.0) .
(b) any value between 7% and 15% acceptable (0.5)
(c) To prevent a possible uncontrolled Turbine Roll to rated ,.
speed (1800 rpm) (1.0)
- REFERENCE SO2-10-1; GEC Turbine Instruction Manual; SO23-10-9;SD-SO23-180 e
7-1 v
- QUESTICH 7.2 (3.0) ,
As detailed in S0123-VII-7.4, Posting and Access Control:
(a) What are the radiation levels that require posting a restricted area? (1.0)
(b) What are the radiation levels that require posting a Red Badge Zone Radiation area? (1.0)
(c) What are the radiation levels that require posting a Red Badge Zone High Radiation area? (1.0)
- ANSWER -
7.2 (3.0, 1.0 EACH)
(a) Radiation levels exceeding 0.25 Mrem /hr. [04 0 s *rdM AvveM (b) Radiation levels of 2.5 Mrem /hr or greater (c) Radiation levels of 100 Mrem /hr or greater
- REFERENCE SO123-VII-7.4, Posting and Access Control, pages 3-4 e
9 l
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I 7-2 l
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- QUESTION 7.3 (2.0)
S023-12-7, Loss of Forced Circulation, identifies four(4) conditions that should exist (and be verified) when Natural Circulation has been established in at least one loop upon a loss of forced circulation.
What are these four(4) conditions 7 .
(0.5 pts. each)
- ANSWER 7.3 (2.0, 0.5 pts. each )
(a) delta T less than 58 deg F (b) Tc and Th NOT rising (c) Reactor Vessel Level (plenum) GREATER THAN 82%
U k
(d) Operating loop Th and REP CET w/in 16 deg.F
- REFERENCE SO23-12-7 e -
9 0
l
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7-3
- QUESTION s u 7.4 (3.0)
Regarding SO23-13-2, Shutdown From Outside the Control Room, the operator is required to perform the certain functions prior to leaving the control room, such ass (1) manually tripping both the Reactor and Main Tu-bine (2) Notify plant personnel that Reactor has been tripped / control room being evacuated. '
(3) Obtain the plant control keys rg-p d'] y v '~
4 What are six (6) of the other ra.. svi ACTIONS, required by l SO23-13-2, assumming time is available to the operator?
(0.5 pts. each)
- ANSWER
. 7.4 (3.0)
(0.5 pts. each, any six-6 of the following)
(a) Ensure reactor trip breakers open/ reactor power decreasing (b) Ensure all CEA rod bottom lights illuminated .
(c) Ensure Turbine stop valves closed (d) Ensure Unit Aux's xfered to reserve Aux Transformers ,
(e) Ensure Unit output breakers open (f) Transfer D/G control to LOCAL (g) Start Turning Gear and Oil Lift Pumps (h) Select channel Y for PZR Pressure and Level control (i) Place PZR level control setpoint in LOCAL at 40%
- REFERENCE S023-13-2
% (7) G ci , pse-x sra r r s r s'o w e o sr rac~ g nages.,e y f,, e r .os,p
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7-4
_ __- . _ = _ . _ _
1 l
- QUESTION -
7.5 (3.0) s '
A precaution in SO23-3-2.11, Spent Fuel Pool Operations, states that at least 23 feet of water shall be maintained ov.er the top of irradiated fuel assemblies seated in the storage racks.
(a) What is the reason or bases for this? (1.0)
(b) Why must the Fuel Pool Purification pump discharge temperature be maintained below 140 deg.F during Spent Fuel Pool operations? (1.0)
(c) Considering SO23-3-2.11, Spent Fuel Pool Operations, What precaution is taken to ensure that the SFP is not drained below its minimum Tech. Spec level with the SPF Purification system in service 7 (1.0)
- ANSWER 7.5 (3.0)
(a) (1.0)
The restrictions on minimal water level ensure that suffigient I water depth is available to remove (99% of the assumed 10%) iodine gap activity released from the rupture of an irradiated tuel assembly. *
(b) (1.0)
To prevent damage to the resin bed fn the SFP ion . -
e>: changer (E-071) .
(c) (1.0) i The SPF Skimmers should be placed in service when the SPF Purification system is in service.
[Ae,rd , 3-spxcx 4xesxtA ow M ro x x sof ' 'L*" F M f## # ## ""# **
- REFERENCE ^ # # '' ' ' 0 ' f f"" !** C < ** 0 ' ! ] .
Technical Specification 3/4.9.11, B 3/4.9.11 S023-3-2.11 i S'O - T 9 2 3 */ J d , ' o l~
f7 /- '70
,N 7-S
f
- QUESTION 7.6 (1.0 ) , , ,
Commensurate with SO23-5-1.3, startup from cold shutdown, WHY should there be at least 30,000 gallons of capacity available in the Radwaste Primary Tanks, prior to plant startup from cold' shutdown ? -
- ANSWER 7.6 (1.0)
To recieve radwaste due to unit heatup.
- REFERENCE SO23-5-1.3 W
l l
1 4
. 1 l
7-b
- QUESTION 7.7 (1.5)
Commensurate with,SO23-3-2.19, Control Element Drive'Mhchanism Control System Operations For each operation listed, What is the manual mode of control normally used on the Control Element Drive System?
- a. Withdrawing Shutdown Group CEA's during a reactor startup. (0.5)
- b. Inserting Regulating Group CEA's durirq reactor ~
, shutdown. (0.5)
- c. Recovering a dropped CEA. (0.5) -
- ANSWER 7.7 (1.5)
~
- a. Manual Group (0.5)
- b. Manual Sequential (0.5)
- c. Manual Individual (0.5)
- $ REFERENCE SD-SO23-510 SO23-3-2.19
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- QUESTION ,
7.8 (2.5)
In MODE-4, a RCP or SDC pump shall be operating and a second RCS/ loop or SDC pump shall be operable.However,all RCP's and SDC pumps may be de-energized for up to one hour provided TWO(2) conditions are met commensurate with 5023-5-1.3, Plant S/U From Cold S/D to Hot Standby and Technical Specifications.
What are these two conditions? (1.25 pt. each)
- ANSWER 7.8 (2.5, 1.25 each) l (a) No operations are permitted that would cause dilution of the RCS baron concentration.
1
~
(b) The core outlet temperature is maintained at least 10 deg.F.
below saturation temperature.
i
- REFERENCE S023-5-1.3
- Technical Specifications i
e e
. 1 7-8
- QUESTION '
7.9 (1.0)
Concerning the operation of the Steam Bypass Control System, 5023-5-1.3.1 precautions:
Why is it recommended that manual permissive operation of the Steam Bypass Control System be minimized upon startup from Hot Standby to Minimum Load?
- ANSWER 7.9 (1.0)
To prevent opening of more than one SBCS valve from a singlo
- failure.
- REFERENCE S023-3-1.3.1
~
SD-SO23-175 1
Y
-1 1
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)
f N-7-4
- OUESTION 7.10 (2.0) t .
5023-13-6, Reactor Coolant Pump Seal Failure, identifies four(4) symptoms of RCP seal failure that are associated with indications available in the control room.
What are these four(4) symptoms?
(0.5 pts. each)
- ANSWER 7.10 (2.0, 0.5 each) .
(a) Individual seal cavity pressure (s) indicating above/below normal.
(b) Individual RCP controlled bleed off temperature above normal.
. (c) RCP bleed-off relief valve outlet temperature increasing.
(d) RCP controlled bleed off header pressure increasing.
- REFERENCE SO23-13-6 e
l l
l 4
7-10
$ QUESTION s 7.11 (1.0)
Upon increasing Main Turbine speed to 1800 RPM, SO2-10-1 (Turbine S/U), states that the Run-Up Terminal Speed Selector should be set at 1860 rpm 7 What is the reason for this 7
- ANSWER 7.11 (1.0) .
To ensure that the Narrow Range Governor takes control at approximately 1800 rpm. -
- REFERENCE S02-10-1 O
e
- ,N 7-11
- DUESTION 7.12 (1.5)
What are the six (6) factors identified by Technical Specifications that must be considered when calculating shutdown margin?
(assume Tave is greater than 200 degrees).
- ANSWER 7.12 ( O.25 each, 1.5 max.)
(a) Baron concentration.
(b) CEA position.
(c) RCS temperature
~
(d) Fuel burnup.
(e) Xe concentration.
(f) Sm concentration.
o
- REFERENCE San Onofre 2/3 : Safety Technical Specifications, pp.
3/4.1-1 to 3/4.1-2.
I e
S I
i S
I l
l l l
l 7-12
- OUESTION '
7.13 (1.0) -
Commensurate with Standard Post Trip Actions,SO23-12-1:
What Two(2) critical indicators are used to verify that RCS Inventory Control Criteria are satisfied?
(0.5 pts. each)
- ANSWER 7.13 (1.0)
(0.5 pt. each)
(1) PZRlevel(controlledbetween 10%and70%)
(2) RCS saturation margin (greater than 20 deg.F
- REFERENCE SO23-12-1 O
END OF SECTION 7.0 4
7-15
- ~
SECTION 8.0 -
Administrative Procedures, Conditions, and Limitations SOUESTION 8.1 (1.0)
Concerning Diesel Generator Operability, as detailed in Technical Specification 3.8.1.1 (st /n siA cit a rf is197)ef /, z,. y, y) l (a) What is the minimum required fuel volume (in gallons) for each D/G systems day tank 7 (0.5)
(b) What is the minimum required fuel volume (in gallons) f or -
each D/G systems fuel storage tank 7 (0.5) o
- ANSWER 8.1 (1.0, 0.5 pts, each)
(a) 325 gallons ( any matching level )
(b) 47,000 gallons ( any matching level )
t
Reference:
Technical Specification 3.8.1.1 l
i 1
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3-1 l
l
- QUESTION , "v3 8.2 (2.0, 0.4 pts. each) w,7g J- g What is the shif t crew composition f or Unit 33 in Mode 1, for the following positions, per Tech. Spec. Table 6.2.1 7 -
( 0.4 pts. each )
(a) SS (b) SRO (c) RO (d) AD (c) STA
- ANSWER 8.2 (2.0, 0.4 pts. each)
- a. 1
~
- b. I
- c. 2
- d. 2
- e. 1 tREFERENCE T.S. TABLE 6.2.1 d
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1
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8-2
y V i
- S
- QUESTION i B.3 (2.0)
,p The operability of the main steam isolation valves ensures that no more than one steam generator will blow down in the event of steam line rupture. Technical Specifications identifies two(2) reasons for this function: ,
What are the two(2) reasons identified'by Technical Specifications for limiting the blow down of one steam generator?
- ANSWER \ .
8.3 (2.0)
(a) Minihize the positive reactivity effects of the RCS cooldown associated with the blowdown. (1.0) 4 (b) Limit the pressure rise w/in the containment in the event that the rupture occurs inside the containment. (1.0)
- REFERENCE ~
Technical _ Specifications B 3/4 7-3 SD-SO23-160 o i s
9
- l 1
1 l
l s.
i i
8-3
i i
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l i
l B.4 (3.0) - ;
Specification 6.8.3, Temporary changes to procedures as de i met. may be made providedscribed by Technical One of these is that the intent of three(3) not altered. original criteria are the procedure is (a)
What is the minimum required Document Management (CDM) staff, manning of the Corporate responsible for TCN review?
(b) ,
(1.0) have to perform his finalHow long a does the Cognizant Fu Division Manager (CFDM) :
approval by the CDM 7 approval the TCN upon initial (c)
(1.0)
Commensurate with SO123-VI-1.0 1 .
for final approvalorganization has the last respons, Documents what and of a TCN. ibility (review /signiture) i
- ANSWER 8.4 (1.0)
( 3. 0, 1.0 pt. cach)
(a) 3 Two members of whom holds a SRO license en the unitthe unitone at least management of s (b) 14 days affected.
(c) Quality Assurance *
(OA) i
- REFERENCE Technical SO123-VI-1.O.1 Specifications 1
. I I
l e
8-4
]
- QUESTION .-
B.5 (1.0)
What~~are the two(2) reasons identified in Technical ~
Specifications, based on safety considerations, that CEA insertion limits are established 7 (0.5 each)
- ANSWER 8.5 (1.0, 0.5 pts. each) .
- a. To ensure adequate shutdown margin.
- b. To limit the reactivity worth of an ejected CEA.
AL.rd / m *Ff"
"*[ p.,,,*rsr% ss y is e Pts s' w& /s e t 'n f W' 7"'N l'"'f')
$ REFERENCE ^ "" "'"'E f Yrpow A$cirm i p rios
~
C*f'" " red!)
SONGS 2 Technical Specifications, p. B 3/4 1-5
(
e 0
,4 b ** J
- QUESTION B.6 (3.0)
Technical Specification 6.8.4 requires that a program'shall exist which will reduce leakage to a level as low as practical from those portions of systems lying OUTSIDE the containment that could contain highly radioactive fluids during a serious transient or accident.
What are the six (6) ' systems, designated by Technical .
Specification 6.8.4, that are included in this program?
(0.5 pts. each)
- ANSWER 8.6 (3.0, 0.5 pts. each)
(a) HPSI ( recirculation)
(b) Shutdown cooling system (c) reactor coolant sampling system (PA3 piping only)
(d) Containment Spray system (e) Rad. waste gas system (PAS return piping only)
(f) Li quid Rad. waste system (PAS return piping only) i
- REFERENCE Technical Specification 6.8.4 4
0-6
l l
\ l l
SQUESTION B.7 (3.0) ._-
Technical Specifications bases identifies three(3) basic reasons for the limits on RWST minimum volume and boron concentration?
l What are these three(3) reasons / bases for the limits c4 RWST minimum volume and baron concentration?
- ANSWER 8.7 (3.0)
(a) To ensure that sufficient water is available within the containment to permit recirculation cooling flow to the core in the event of a LOCA. (1.0)
(b) To ensure that the reactor will remain suberitical in the cold condition following mixing of the RWST and the RCS water -
. volumes following a LOCA(with all control rods inserted, except for the most reactive control assemb1). (1.5) 9*
(c) The limits on water volume and baron concentration also ensure that the solution recirculated within the containment after a LOCA has the proper (8.0 to 10.0/ basic PH at the end of the NADH injection periog). (0.5)
- REFERENCE Technical Specifications, B 3/4 5-2 through 5-3 ,
SD-SO23-740 O
t e
e e
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9 I O
'. o-7
- OUESTION ,
8.8 (3.0)
EPIP, SO23-VIII-1, Event Classification, gives the following guidance (EVENT CODES) for classification of " Technical Specification Related" UNUSUAL EVENTS:
(1) Inoperability of containment systems (2) Inoperability of required instrumentation (3) Any other required reactor shutdown or cooldown which warrents notification of local or state authorities.
What are four(4) of the other eight(8) event codes identified by EPIP, SO23-VIII-1, Event Classification for an Unusual Event?
- (0.75 pts each)
- ANSWER 8.8 (3.0, any four - 0.75 pts. each)
(1) Exceeding radiological liquid effluent concentration limits (2) Exceeding RCS leakage limits (3) Exceeding any Safety Limit (4) Exceeding RCS specific activity limits (5) Inoperability of AC power sources (6) Inoperability of emergency core cooling systems (7) Inoperability of safety related systems due to natural disasters (8) Inoperability of safety related systems due to manmade ,
disasters
- REFERENCE EPIP, SO23-VIII-i, Event Classification, page 5 e
a-a
. = . - .. _ _ - _
- QUESTION s -
8.9 (0.5)
As detailed in, SO23-O-17, Locking of safety related critical valves and breakers, Who has the authority to change the status of critical locked valves and breakers during normal shift operations (no emergencies) 7
- ANSWER 8.9 (0.5)
SRO Operations Supervisor ('fg e p r f ,. e 4 , L r f y g , p y-
- REFERENCE SO23-0-17 O
e e
9 e
i , 4 8-9
- OUESTION 8.10 (1.0)
Concerning Technical Specification 3/4.9.3, Refueling Operations:
The reactor must remain subcritical 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before the movement of irradiated fuel in the RPV can commence.
What is the reason for this time delay? (1.0)
- ANSWER 8.10 (1.0)
The minimum requirement (time) for reactor subtriticality prior to movement of irradiated fuel assemblies in the RPV ensures that suf ficient time has elapsed to allow the radioactive decay of short lived fission products.
- REFERENCE Technical Specification 3/4.9.3, B 3/4.9.3 0
e e
0 e
G-10
- QUESTION s -
8.11 (1.5)
Technical Specification 6.7, Safety Limit Violation, requires four(4) administrative actions in the event a safety limit is violated.
What are three(3) of the four(4) required actions ?
(0.5 pts. each)
- ANSWER 8.11 (1.5, any 3 of the following items, 0.5 pts. each)
(a) The NRC operations center notified by telephone ASAP and in all cases w/in one hour.
(b) A safety limit violation report shall be prepared (reviewed by OSRC).
]
(c) The safety limit violation report shall be submitted to the commission ( the Manager of Nuclear Operations and the NSG ,
w/in 14 days of the violation).
(d) (Critical) Operation of the Unit shall not be resumed until authorized by the Commission. .
- REFERENCE 1
9 4
I
.i 0-11
- QUESTION ,
8.12 (3.0)
Commensurate with SONGS (2) Technical Specifications, Primary Containment Integrity must be established in operational MODES 1,2,3,and 4. .
What plant conditions constitute CONTAINMENT INTEGRITY ?
.
- ANSWER 8.12 (3.0)
Containment Integrity shall exist when:
(a) All penetrations required to be closed during accident conditions are either:
(1) Capable of being closed by an operable containment automatic isolation valve system, or (0.5)
(2) Closed by manual valves, blind flanges, or deactivated automatic control valves secured in their closed po'sitions or as specified in the specifications. (0.5) l (b) All equipment hatches are closed and sealed. (0.5)
(c) Each air lock is operable (0.5)
(d) Containment leakage rated are w/in limits. (0.5) .
(e) The sealing mechanism associated with each penetration is operable. (0.5)
- REFERENCE Technical Specifications, 1-2 A
9 s
i 4
6-12
- QUESTION B.13 (1.0)
SO23-VIII-1, Recognition and Classification of Emergencies, identifies four(4) Emergency Action Levels (EAL's). Two(2) of these are Unusual Event and Alert. .
4 What are the other two(2) of these four(4) EAL's ,in order of increasing potential hazard to the general public ?
(0.5 pts f or the EAL's, 0.25 pts. each)
(0.5 pts. for the order of increasing hazard)
- ANSWER 8.13 (1.0) (0.5 pts for the EAL's, 0.25 pts. each)
(0.5 pts. for the order of increasing ha:ard) 1 (1) Site Area Emergency (2) General Emergency
- REFERENCE
, SO22-VIII-1 i
- t******t4$$*4***
END OF SECTION O.0 .
END OF EXAM 9
i e
I
,4 0-12
1 .
i e a _
A-12 !
Aretwo's A-P"vsiCAt recetmas Cf FtWOS ANO ftOw CCACitmhCS OF WAtytt tm .
~
Properties of Saturated Steam and Saturated Water
- N o Abolute Pressure Vacuurn Temper.
Inches Heat of 1,1>,'( Inches ature the Latent Heat Total Heat . Specific Volume sq, of Hg of Hg Liquid of of Steam Evaporation -y P'
o.. r. neo ns. neons.
o.08459 0.01 29.90 31.018 e.on . co.,..,,,lco.,,.,,,,,,
- 0.10 0.20 0.0003 1075.5
, 29.72 35.023 3.026 1075.5 0.016022 0.15 0.31 29.61 1073.8 1076.8 JJ02.4 0.20 45.453 13.498 0.016020 0.41 29.51 53.160 1067.9 1081.4 2945.5 0.15 21.217 1053.5 0.016020' 2004.7 0.51 29.41 59.323 1084.7 0.016025
, 0.30 0.61 27.382 1060,1 1526.3 29.31 64.484 32.541 1087.4 0.0160J2 0.35 0.71 29.21 1057.1 1089.7 1235.5 0.40 68.939 36.992 1054.6 0.016040 1039.7
. 0.81 29.11 72.869 1091.6 -
0.45 0.92 40.917 1052.4 0.016048 898.6 29.00 76.387 44.430 1093.3 0.016056 0.50 1.01 1050.5 1094.9 792.1 28.90 79.5 % 47.613 0.016063 708.8 0.60 1.22 28.70 1048.6 1096.3 OJO 85.218 53.245 1045.5 0.016071 641.5 1.43 28.49 90.09 1098.7 0.80 1.63 58.10 1042.7 0.016085 540.1 28.29 94.38 1100.8 0.016099 l 0.90 1.83 62.39 1040.3 4 %.94 28.09 98.24 66.24 1102.6 0.016112
%?
- 1.0 1038.1 1104.3 411.69 y;,.
- 1.1 2.04 27.88 101.74 69.73 10M.1 0.016124 368.43 V.
- "5 8.4 3.6 2.44 2.85 3.26 27.48 27.07 26.%
107.91 113.26 75.90 81.23 1032.6 1029.5 1105.8 1108.5
!!!0.7 0.016 t h 0.016158 333.60 ~
280.% - -
- lM* --
1.8 117.98 85.95 0.016178 243.02 3.H 26.26 122.22 1026.8 1112.7 0.0161 %
2.0 90.18 1024.3 1114.5 214.33 2 4.07 25.85 126.07 0.016213 2.2 4.44 94.03 1012.1 191.05 - -
25.44 119.61 1816.2 0.016130 2.4 4.89 97.57 1020.1 1117.6 173.76 25.03 --
' 2.6 8.29 24.63 132.88 135.93 100.84 1018.2 1119.0 0.016245 150.87 - =
2.8 103.88 0.016260 146.40 ~ ~
5.70 24.22 138.78 1016.4 1120.3 0.016274 3.0 106.73 1014.7 1121.5 135.80 6.11 23.81 141.47 0.016787 126.67
-~
3.5 7.13 22.79 109.42 1013.2 1111.6 =__
4.0 147.56 115.51 1009.6 0.016300 118.7J
~
8.14 21.78 152.% 1125.1 0.016331 4.5 9.16 20.76 120.92 1006.4 1127.3 102.74 -
5.0 157.82 0.016338 10.18 19.74 162.24 125.77 130.20 1003.5 1129.3 0.016384 90.64 83.03 5.5 11.10 1000.9 1131.1 18.72 1 %.19 0 016407 73.532 6.0 12.22 17.70 134.26 998.5 !!32.7 6.5 170.05 138.03 0.016430 67.249 "
13.23 16.69 173.56 9%.2 1834.2 0.016451 7.0 14.25 141.54 994.1 1135.6 61.984 7.5 15.67 176.84 144.83 0.016472 15.27 992.1 57.506 ;
8.0 14.65 179.93 147.93 990.2
!!36.9 0.016491 53.650 -
d 16.29 13.63 1138.2 0.016510 8.5 181.86 150.87 50.294 17.31 12.61 185.63 968.5 1139.3 0.016527 ,
9.0 18.32 11.60 153.65 986.8 1140.4 47.345 im 2 9.5 188.27 156.30 0.016545 44.733 -
19.34 10.58 190.80 985.1 1141.4 0.016561
'10.0 20.36 9.56 158.84 983.6 1142.4 42.402
- l 193.21 0.016577 .,
11.0 22.40 7.51 161.26 982.1 1143.3 0.016592 40.310 G -
12.0 197.75 165.81 38.420 -
24.43 5.49 979.3 1145.1 13.0 26.47 201.% 170.05 976.6 0.016621 J5.141 14.0 3.45 205.88 1146.7 0.016650 32.394 28.50 1.42 174.00 974.2 1148.2
- =
209.56 177.71 . 0.016676 30.057 -
971.9 1149.6 0.016702 28.043 _ u Pressure Temper.
Lbs. per 59 . In. Heat of Latent Heat Total Heat sture the of Specifle Volume --- * "
Absolute of Steam Gate Liquid Evaporation y bA P' P o,e,.
f he r li,o n.. n ns, Water 5 team \
14.696 0.0 n,o ns. co. ,,. ,,, m. co. ,.. - is.
g 4 15.0 211.00 180.17 1 0.3 213.03 970.3 1150.5 0.016719 26.799 16.0 1.3 181.21 969.7 t 216.32 184.51 1150.9 0.016726 26.290 17.0 2.3 %7.6 -
- 18.0 219.44 187.66 965.6 1152.1 0.016749 24.750 - d=
3.3 222.41 1153.2 0.016771 i 19.0 4.3 190.66 %J.7 23.385 l 125.24 193.52 1154.3 0.016793 22.168 _
10.0 5.J %l.8 1155.3 - d_
21.0 2U.% 196.17 %0.1 0.016814 23.074 -
6.3 230.57 il56.J 0.016834 22.0 7.3 198.90 958.4 20.087 233.07 201.44 1157.3 0.016854 19.190 g=
23.0 8.3 956.7 1858.1 24.0 235.49 203.88 0.016873 18.373 9.3 237.82 955.1 1159.0 1 206.24 0.016891 17.624 25.0 16.0 10.3 240.07 20s.51 953.6 952.1 1159.8 0.016909 _!6.9 M -
'm 11.3 241.25 1160.6 0.016927
'll 27.0 13.3
- 210.7 950.6 16.301 244.36 212.9 1161.4 0.016944 15.7138 i
l 28.0 13.3 949.2 1162.1 29.0 246.41 214.9 947.9 0.016 % I 15.1684 '" 11
'l 14.3 248.40 1162.8 0.016977 14.u07 30.0 217.0 946.5 31.0 15.3 16.3 250.J 4 252.22 218.9 220.8 945.2 1163.5 1864.1 0.016993 0.017009 14.1869 13.74M g 'h q 32.0 17.3 - 943.9 1164.8 33.0 254.05 222.7 0.017024 13.3280 18.3 941.7 1165.4 l 34 0 255.84 224.5 0.017029 !!.9276 941.5 19.3 257.58 226.3 940.3 11 % .0 0.017054 12.5700 E- %
' Abstracted from ASME Steam Tables (l%71. eth permmion of the pubhsher The American 11 %.6 0.017069 11.2234
-0 Society el Mechanical En8ineers 245 East 47th Street. New York. New Yorkfeena ,
10017. d e.
h aeeuese)
DN y
3--d l
~
. - - . ...,- . , , .,,w ,pe n p au M
4NE CRANE Antwoir A-rmsiCat Pforettits ce fivios ANo fLJW CHiBACTittsflCS C7 V4tvls. FamNis. AMO Piet A.13 km Properfi;s cf S:turnt:d St::m cnd 5:tur:t:d Wct:r--centinund Pressure Temper. Heat of Latent Heat Total Heat Specific Volume g Lbs. per Sq. In. sture the u
of bapontion of Steam p Absolute Gage I P' .P o.. Wa co.r.. ,ter St nio ris. neo ns. ,, i ..
. p.
siviis. co. t eam
. ,., i n.
35.0 20J 259.19 228.0 939.1 O 36.0 21.3 260.95 229.7 938.0 1867.1 0.017083 11.8959 M 37.0 38.0 22.3 23.3 262.58 264.17 231.4 233.0 936.9 935.8 1167.7 1168.2 1168.8 s 0.017097 0.017111 0.017124 11.5860 11.2923 11.0136 39.0 24.3 265.72 2J4.6 934.7 !!69.3 0.017138 10.7487
- 40.0 25J 267.25 236.1 933.6 1169.8 0.017151 10.4965 41.0 26.3 268.74 237.7 932.6 !!70.2 0.017164 10.2563 42.0 27.3 270.21 239.2 . 931.5 1170.7 0.017177 10.0272 43.0 28.3 271.65 240.6 930.5 1171.2 0.017189 9.8083 44.0 29.3 273.06 242.1 929.5 1171.6 0.017202 9.5991 45.0 30.3 274.44 243.5 i 928.6 !!72.0 0.017214 9.3988 46.0 31.3 275.80 244.9 927.6 1172.5 0.017226 9.2070 47.0 32.3 277.14 246.2 926.6 1172.9 0.017238 9.0231 l 45.0 33.3 278.45 247.6 925.7 8
~
1173.3 0.017250 8.8465 49.0 34.3 279.74 248.9 924.8 1173.7 0.017262 8.6770 I
8 J0.0 35.3 281.01 250.2 923.9 1874.1 0.017274 4.5140 51.0 36.3 282.27 251.5 923.0 1174.5 0.017285 8.3571
~.
- 52.0 37.3 283.50 252.8 922.1 1174.9 0.017296 8.2061
- ' 53.0 38.3 284.71 254.0 921.2 1175.2 0.017307 8.0606
[ *54.0 39.3 285.90 255.2 920.4 1175.6 0.017319 7.9203
-- - 55.0 40 3 187.08 256.4 919.5 !!75.9 0.017J 29 7.7650 56.0 41.3 288.24 257.6 918.7 M 57.0 58.0 42.3 43.3 289.38 290.50 258.8 259.9 917.8 917.0 1176.3
!!76.6
!!77.0 0.017340 0.017351 0.017362 7.6543 7.5280 7.4059 59.0 44.3 291.62 261.1 916.2 1177.3 0.017372 7.2879
~
60.0 45.3 292.71 262.1 915.4 1177.6 0.017383 7.1736 61.0 46.3 293.79 263.3 914.6 1177.9 0.017393 7.0630 62.0 47.3 294.86 264.4 913.8 1178.2 0.017403 6.9558 63.0 48.3 295.91 265.5 913.0 1178.6 0.017413 6.8519 2
64.0 49.3 296.95 266.6 912.3 1178.9 0.017423 6.75I1 65.0 50.3 297.98 267.6 914.5 1879.1 0.017433 6.65J3 0* 66.0 51.3 298.99 268.7 910.8 1179.4 0.017443 6.5584 I
67.0 52.3 299.99 269.7 910.0 !!79.7 0.017453 6.4662 68.0 53.3 300.99 270.7 909.3 1180.0 0.017463 6.3767 l 69.0 54.3 301.96 271.7 908.5 1180.3 0.017472 6.2896 p- 70.0 55.3 302.93 272.7 907.8 g
I D 71.0 72.0 56.3 57.3 303.89 304.83 273.7 274.7 907.1 906.4 1180.6 1880.8 1181.1 0.017482 0.017491 0.017501 6.2050 6.1226 6.0425 73.0 38.3 305.77 275.7 905.7 !!81.4 74.0 59.3 0.017510 5.9645 .
l 306.69 276.6 905.0 1181.6 0.017519 5.8885
.- 75.0 60J J07.64 277.6 904J l181.9 0.017529 5.8844
[. 76.0 61.3 308.51 278.5 903.6 1182.1 77.0 0.017538 5.7423 62.3 309.41 279.4 902.9 1181.4 0.017547 5.6720 g . 78.0 63.3 310.29 280.3 902.3 !!82.6 0.017556 79.0 5.6034
~
64.3 311.17 281.3 901.6 1182.8 0.017565 5.5364 80.0 65.3 312.04 282.1 900.9 1183.1
- 0.017573 5.4711 81.0 66.3 312.90 283.0 900.3 1183.3 0.017582 82.0 67.3 5.4074 313.75 283.9 899.6 1183.5 0.017591 5.3451 83.0 68.3 314.60 284.8 899.0 1183.8 0.017600
- 84.0 69.3 3.2843
- 315.43 285.7 898.3 1184.0 0.017608 5.2249 85.0 70.3 316.26 286.5 897.7 1184.2 sus * . 86.0 0.017637 5.1669 78.3 317.08 287.4 897.0 1184.4 0.017625 87.0 72.3 5.1101
."' 317.89 288.2 896.4 1184.6 0.017634 5.0546
- .,*. 88.0 73.3 318.69 289.0 895.8 1884.8 89.0 74.3 0.017642 5.0004
, 319.49 289.9 895.2 1185.0 0.017651 4.9473
- , 90.0 75 3 J 20.28 290.7 694.6 1885.3 91.0 76.3 0.0.7659 4.6953 321.06 291.5 893.9 1185.5 0.017667 4.8445
- 92.0 77.3 321.84 292.3 893.3 1185,7
- 93.0 78.3 0.017675 4.7947 8-m 322.61 293.1 892.7 1185.9 0.017684 4.7459
- = 94 0 79.3 323.37 193.9 892.1 1886 0 0.017692 4.6982 95.0 80.3 J 24.13 194.7 598.5 96.0 1886.2 0.017700 4.6514 M = ag 81.3 324.88 295.5 891.0 1186.4
- 97.0 82.3 325.63 0.017708
- 4.6055 l 296.3 890.4 l 186.6 98.0 83.3 316.36 197.0 0.017716 4.5606 I 889.8 1186.8 0.017724 4.5166 g %,9 99 0 84.3 327.10 297.8 889.2 1187.0 0.017732 4.4734 100.0 85.3 327.82 298.5 888.6 1857.2 0.087740 4.4340 101.0 86.3 328.54 199.3 .
- 888.1 1887.3 0.01775 4.J895 102.0 87.3 329.26 300.0 887.5 1887.5 0.01776 4.J 487 103.0 88.3 329.97 300.8 886.9
__ 104,0 1887.7 0.01776 4.J087 89 3 330.67 301.5 886.4 1887.9 0.01777 4.2695 105.0 90.3 J31.37 J02.2 685.8 1858.0 0.08778 4.2Jo9 106.0 91.3 332.06 303.0 885.2
~ 1888.2 0.01779 4.1931 107.0 92.3 332.75 303.7 884.7 0,o1779 108.0 1188.4 4.1560 1 93.3 333.44 304.4 884.1 1888.5
, __ 109 0 94.3 334.11 0.01780 4.1195 305.1 843.6 1888.7 0.01781 4 0837 1
--. .- A% - w dw -- _ _ _ _ =. 't-~ m re- m Ae. -.-.-.. N - % w . w +
1
1
- )
l A 14 APPENOG A-MSICM PsCPitfit$ U FLUCS AND FLOW CMACittilhC$ U VAlvgg, pMWC$. AND PtPt CRANE Properties of Saturated Steam and Saturated Water-continued 5::%g (
Pressure Temper- Heat of Latent Heat Total Heat Specific Volume - I
- Lbs, per Sq. In. sture the of of Steam Absolute Gage '8 Liquid Evaporation V <
P' P o.em r. seurib. seurrs. mio ns. co.$.Tli . c2,',P,7, , .
!!0.0 95.3 334.79 305.8 883.1 1I88.9 0.01782 111.0 %.3 335.46 306.5 882.5 4.0484 1 1189.0 0.01782 4.0138 112.0 97.3 336.12 307.2 882.0 1189.2 0.01783 3,9798 .
113.0 98.3 336.78 307.9 881.4 1189.3 0.01784 l 114.0 99.3 337.43 308.6 3.9464 880.9 1189.5 0.01785 3.9136 115.0 100.3 338.08 309.3 880.4 !!89.6 0.01785 116.0 101.3 338.73 309.9 3.8883 879.9 1189.8 0.01786 3.8495 117.0 102.3 339.37 310.6 879.3 1889.9 0.01787 3,8183 118.0 103.3 340.01 311.3 878.8 1190.1 0.01787 3,7875 119.0 *104.3 340.64 311.9 878.3 1190.2 0.01788 3.7573 120.0 105.3 341.27 J12.6 877.8 !!90.4 0.01789 121.0 106.3 341.89 313.2 3J275 l 877.3 1190.5 0.01790 3.6983 122.0 - 107.3 342.51 313.9 876.8 1190.7 0.01790 3.6695 123.0 108.3 343.13 314.5 876.3 1190.8 0.01791 3.6411 l 124.0 109.3 343.74 315.2 875.8 1190.9 0.01792 3.6132
. 125.0 110.3 344.35 315.8 875.3 1191.1 0.01792 3.5857 326.0 127.0 128.0 111.3 112.3 113.3 344.95 345.55 346.15 316.4 317.1 317.7 874.8 874.3 1191.2 1191.3 0.01793 0.01794 3.5586 3.5320 g ,
873.8 1191.5 0.01794 3.5057 129.0 114.3 346.74 318.3 873.3 1191.6 0.01795 3.4799 130.0 !!5.3 347.33 319.0 872.8 1191.7 0.01796 J.4544 131.0 116.3 347.92 319.6 872.3 1191.9 0.01797 3.4293 132.0 133.0 134.0 117.3 118.3 119.3 348.50 349.08 349.65 320.2 320.8 321.4 871.8 871.3 870.8 1192.0 1192.1 0.01797 0.01798 3.4046 3.3802 Q I?92.2 0.01799 3.3562 ,
135.0 120.3 350.23 322.0 870.4 !!92.4 0.01799 3.3325 i 136.0 121.3 350.79 322.6 869.9 1192.5 0.01800 3.3091 137.0 122.3 351.36 323.2 869.4 1192.6 0.01801 3.2861 138.0 139.0 123.3 124.3 351.92 352.48 323.8 324.4 868.9 868.5 1192.7 1192.8 0.01801 0.01802 3 2634 3.2411 N
140.0 125.3 353.04 315.0 868.0 1193.0 0.01803 J.2190 141.0 126.3 353.59 325.5 867.5 1193.1 0.01803 3.1972 142.0 127.3 354.14 326.1 867.1 1193.2 0.01804 3.1757 143.0 128.3 354.69 326.7 866.6 1193.3 0.01805 3.1546 144.0 129.3 355.23 327.3 866.2 1193.4 0.01805 3.1337 145.0 130.3 355.77 327.8 865.7 1193.5 0.01806 3.1130 146.0 131.3 147.0 148.0 132.3 133.3 356.31 356.84 357.38 328.4 329.0 329.5 865.2 864.8 864.3 1193.6 1193.8 0.01806 0.01807 3.0927 3.0726 Q 1193.9 0.01808 3.0528 149.0 150.0 134.3 135.3 357.91 358.43 330.1 330.6 863.9 863.4 1194.0 1194.1 0.01808 0.01509 3.0332 3.0139 g
152.0 137.3 359.48 331.8 862.5 1194.3 0.01810 2.9760 154.0 156.0 139.3 141.3 360.51 361.53 332.8 333.9 861.6 860.8 1194.5
!!94.7 0.01812 0.01813 2.9391 2.9031 Q
158.0 143.3 362.55 335.0 859.9 1194.9 0.01814 2.8679 160.0 145.3 363.55 336.1 859.0 !!95.1 0.01815 2.8336 162.0 147.3 364.54 337.1 858.2 1195.3 0.01817 2.8001 164.0 149.3 365.53 338.2 857.3 1895 5 0.01818 2.7674 166.0 168.0 151.3 153.3 366.50 367.47 339.2 340.2 856.5 855.6 1895 7 119;.8 0.01819 0.01820 2.7355 2.7043 O
170.0 155.3 368.42 341.2 854.8 1196.0 0.01821 2.6738 !
172.0 157.3 369.37 341.2 853.9 11 % .2 0.01823 2.6440 174.0 159.3 370.31 343.2 853.1 1896.4 0.01824 2.6149 176.0 161.3 371.24 344.2 852.3 1196.5 0.01825 2.5864 178.0 163.3 372.16 345.2 851.5 1196.7 0.01826 2.5385 7
180.0 165.3 37J.08 346.2 850.7 !!96.9 0.01827 2.5312 .
182.0 167.3 373.98 347.2 849.9 1197.0 0.01828 2.5045 184.0 169.3 374.88 l 348.1 849.I 1897.2 0.01830 2.4783 +
186.0 171.3 375.77 349.1 848.3 1197.3 0.01831 2.4527 188.0 190.0 173.3 175.3 376.65 377.53 350.0 J50.9 847.5 846.7 1197.5
!!97.6 0.01832 0.01833 2.4276 2.4030 gj 192.0 177.3 378.40 351.9 845.9 1197.8 0.01834 2.3790 I 194.0 196.0 198.0 179.3 181.3 379.26 380.12 352.8 353.7 845.1 844.4 1197.9 1198.1 0.01835 0.01836 2.3554 2.3321 Q* l l
183.3 380.96 354.6 843.6 1198.2 0.01838 2.3095 200.0 185.3 388.60 355.5 842.8 1898.3 0.01839 2.28728 205.0 {
190.3 383.88 357.7 840.9 1198.7 0.01841 2.23349 210.0 195.3 385.91 359.9 839.1 !!99.0 0.01844 2.18217 ,
215.0 200.3 387.91 362.1 837.2 1899.3 0.01847 2.13315 a 220.0 205.3 3 389.88 364.2 835.4 1199.6 0.01850 2.08629 225.0 210.3 J91.80 366.2 833.6 1899.9 0.01852 2.04:43 '
230.0 215.3 393.70 368.3 831.8 1200.1 0.C IB55 8.99846 -
235.0 220.3 395.56 370.3 830.1 1200.4 0.01857 1.95725 240.0 2 25.3 397.39 372.3 828.4 1200.6 0.01860 1.91769 l 245.0 [
230.3 399.19 374.2 826 6 1200.9 0.01863 1.87970 ' *l a ... .....:,
}
. 1
.... . . . ~ . .
ANE
~ CRANE g.= :q Amwoix A-tmsicAt nemnts or etusos Awoi ucs atow enactit or vuves, nmwos. s Ano mt
~'~~ A.L e -l Pressure Properties of Saturated Steam and Saturated Water-conclu Temper.
~ Lbs, per Sq. In. Heat of
- sture the Latent of Heat Total Heat Specific Volume Absolute Gage Liquid of Steam
,.
- 8 Evaporation y
_ , , P' P
~ o. . p.
neons. W 250.0 e,o ns. s ons.
255.0 235.3 400.97 376.1 co.r ater,o is.
e S,t,eam,,is.
825.0
- - 240.3 402.72 1201.1
"~ 260.0 245.3 378.0 823.3 0.01865 1.84317 265.0 404.44 379.9 1201.3 0.01868
~~~
250.3 406.13 821.6 1201.5 1.80802
=
270.0 255.3 381.7 820.0
- 0.01870 1.77418 407.80 1201.7
% 275.0 160.3 409.45 383.6 818.3 1201.9 0.01873 1.74157 280.0 385.4
- 0.01875 1.71013
- 265.3 411.07 816.7 1202.1 285,0 387.1 0.01878
=
$ 270.3 412.67 815.1 1202.3 1.67978 290.0 275.3 388.9 813.6 0.01880 1.65049
~~ 295.0 414.25 390.6 1202.4 0.01882
- 280.3 415.81 812.0 1202.6 1.62218 300.0 392.3 810.4 0.01885 5 E 320.0 285.3 305.3 417.35 394.0 808.9 1202.7 0.01887 1.59482 1.56835 340.0 413.31 400.5 1202.9 0.01889
- 325.3 42E.99 802.9 1203.4 1.54274
" 360.0 406.8 0.01899
~
- 5 380.0 345.3 365.3 434.41 412.8 797.0 791.3 1203.8 0.01908 1.44801 439.61 1204.1 2.36405 400.0 418.6 785.8 0.01917 1.28910
% - 420.0 385.3 444.60 424.2 1204.4 0.01925 1.22177
- 405.3 449.40 780.4 1204.6 440.0 425.3 429.6 775.1 0.01934 1.16095
{ 454.03 434.8 1204.7 460.0 445.3 770.0 0.01942 1.10573 480.0 458.50 439'8 1204.8 0.01950 465.3 462.82 765.0 1204.8 1.05535 500.0 444.7 760.0 0.01959 l 485.3 467.01 1204.8 0.01967 1.00921 M 1 520.0 540.0 560.0 505.3 525.3 471.07 475.01 449.5 454.2 458.7 755.1 750.4 1204.7 1204.5 0.01975 0.01982 0.96677 0.92 h l I 545.3 478.84 745.7 1204.4 0.89137
$80.0
- 565.3 463.I 741.0 0.01990 0.85771 482.57 467.5 1204.2 0.01998 600.0 585.3 736.5 1203.9 0.82637 620.0 486.20 471.7 0.02006 605.3 132.0 1203.7 0.79712 640.0 489.74 475.8 0.02013 625.3 493.19 727.5 1203.4 0.76975 660.0 645.3 479.9 723.1 0.02021 0.74408 680.0 4 %.57 483.9 1203.0 0.02028 665.3 499.86 718.8 1202.7 0.71995 700.0 487.8 714.5 0.02036 0.69724 685.3 503.08 1202.3 720.0 498.6 0.02043 0.67581 705.3 5 % .23 710.2 1208.8 740.0 725.3 495.4 706.0 0.02050 0.65536 760.0 509.32 499.1 1201.4 0.02058
,,,, 745.3 512.34 701.9 1200.9 0.63639 780'.0 765.3 502.7 697.7 0.02065 0.61821 515.30 506.3 1200.4 0.02072
@ 800.0 820.0 840.0 785.3 805.3 825.3 518.21 521.06 509.8 513.3 693.6 689.6 685.5 II99.9 1199.4 0.020$0 0.020$7 0.60097 0.58437 523.86 1198.8 0.565 %
D _
860.0 880.0 900.0 845.3 865.3 526.60 529.30 516.7 520.1 523.4 681.5 677.6 673.6 1198.2 1197.7 0.02094 0.02101 0.02109 0.55408 0.53988 885.3 531.95 1197.0 0.52631 920.0 905.3 526.7 0.02116 0.51333 534.56 669.7 1196.4 940.0 925.3 530.0 665.8 0.02123 960.0 537.13 533.2 1195.7 0.50091 945.3 539.65 661.9 0.02130 0.48901 980.0 536.3 1195.1 0.02137
% 5.3 542.14 658.0 1194.4 0.47759 1000.0 539.5 654.2 0.02145 985.3 544.58 1893.7 0.46662 1050.0 1035.3 542.6 0.01152 0.45609 550.53 650.4 1892.9 1100.0 1085.3 550.1 640.9 0.02 59 1150.0 556.28 557.5 1891.0 0.44596 1135.3 631.5 0.02177 0.42224
_ 1200.0 1185.3 561.82 564.8 622.2 1189.1 0.02195 567.19 571.9 1187.0 0.40058 1250.0 1235.3 613.0 0.02214 0.38073 572.38 1184.8 1300.0 1285.3 578.8 603,8 0.02232 0.36245 1350.0 577.41 585.6 1182.6 0.02250 1335.3 582.32 594.6 1180.2 0.J4 556 1400.0 1385.3 592.1 585.6 0.02269
. 587.07 0.32991 1450.0 598.8 1177.8 0.02288 1435.3 567.5 591.70 605.3 1175.3 0.31536 ,-
Q 1500.0 1600.0 1700.0 1485.J 1585.3 1685.3 696.20 604.87 611.7 624.2 567.6 558.4 540.3 1172.9 1870.1 0.02307 0.02327 0.02346 0.30178 0.28909 613.13 0.27719 D _ 1900 0 1800.0 2000.0 1785.3 1885.3 621.02 628.56 636.5 648.5 660.4 522.2 503.8 1864.5 1158.6 1152.3 0.02387 0.02428 0.25545 0.23607
- 1985.3 485.2 1145.6 0.02472 0.21861 Il00.0 635.80 672.1 0.02517
% f 2200.0 2045.3 642.76 683.8 466.2 446.7 1138.3 0.01565
' 0.20278 2185.3 649.45 1830.5 0.15536
- 2300 0 695.5 g g _ 2400e 2285.J 2385.3 655.89 707.2 426.7 406.0 1122.2 0.02615 0.02669 0.17508 2500.0 662.11 719.0 1113.2 0.16212 2485.3 384.8 0.02727 0.15833 2600.0 668.11 731.7 1103.7
- P" - - 1585.3 366.6 0 02790 0.14076 673.91 M 1700.0 1800 0 2645.3 679.53 744.5 757.3 337.6 1093.3 1082.0 0.02859 0.02938 0.13ubs 2785.3 684.% 312.3 0.12810 1900.0 ' 2885.3 770.7 285.1 1069.7 0.03019 690.22 785.1 1055.8 0.11194 3000.0 2945.3 254.7 0.03134 0.10305 3100.0 695.33 801.8 1039.8 0.03262 3085.3 700.28 218.4 0 09420 D _ 3208.2 3200.0 3185.3 3191 5 705.08 705.47 814.0 875.5 906 0 169.3 56.1 00 1020.3 993.3 931.6 0.03428 0.03641 0.04472 0.05500 0.07451 906.0 0.05663 005078 R:::a 0.05078 ML _ . _ . - - ^
A.16 LPPtNDnt A- PMYSIC*.t PROPftfff5 f f PLUlI$ AND PLOW CM'RACittl171C3 (, VItVtl. PlfilNC5. AND CRANE(1Pt N
Pr:p:rti:s cf Sup:rhoct:d Steam
- q Y= specific volume, cubic feel per pound "
h,= total heat of 5 team, Blu per pound Pressure Sat.
- Lbs.
sq. n.
Temp Total Temperature-De8rees Fahrenheit (t) ~
Q Abs.
P' Case P t 350* 400* 500* 600* 700* 800* 900* 1000* 1100* 1300* 1500*
D 15.0 0.3 213.03 V
, A, 31.939 33.963 37.985 41.986 45.978 49.964 53.946 57.926 61.905 69.858 77.807 1216.2 1239.9 1287.3 1335.2 1383.8 1433.2 1483.4 1534.5 1586.5 1693.2 1803.4 10.0 3.3 227 % V A, 23.900 25.428 28.457 31.466 34.465 37.458 40.447 43.435 48.420 3
$2.388 58.352 1215.4 1239.2 1286.9 1334.9 1383.5 1432.9 148J.2 1534.3 1586.3 1693.1 1803.3 30.0
- 15.3 250.34 7 A, 15.859 16.892 18.929 20.945 22.951 24.952 26.949 28.943 30.936 34.918 38 8 %
1213.6 1237.8 1286.0 13J4.2 1383.0 1432.5 1482.8 1534.0 1586.1 1692.9 1803.2 40.0 15.3 267.25 V
. . A, 11.8381236.4 1231.7 12.624 14.165 1285.0 15.685 1333.6 1382.5 17.195 1432.118.699 20.199 21.697 23.194 26.183 29.168 50.0 33.3 281.02 7 A,
9.424 1209.9 10.062 !!.306 12.529 13.741 1482.5 153J.7 1585.8 1691.7 1803.0 14.9471482.2 16.1501533.4 17.350 18.549 20.942 23.332 g:=g 1234.9 1284.1 1332.9 1382.,0 1431.7 1585.6 1692.5 1802.9 60.0 45.3 292.71 7 7.815 8.354 9.400 10.425 11.438 12.446 A, 1208.0 1233.5 13.450 14.452 15.452 17.448 19.441 1283.2 1332.3 1381.5 1431.3 1481.8 153J.! 1585.3 1692.4 1802.8 70.0 55.3 302.93 7 6.664 7.133 8.039 8.922 9.793 10.659 11.522 A, 12.381 13.240 14.952 16.661
, 12,06.0 1232.0 1282.2 1331.6 1381.0 1430.9 1481.5 1532.9 1585.1 1692.2 1802.6 40.0 65.3 312.04 Y 5.801 6.218 7.018 7.794 8.560 A, 9.319 10.075 10.829 11.581 13.081 14.577 1204.0 1230.5 1281.3 1330.9 1380.5 1430.5 1481.1 15J2.6 1584.9 1692.0 1802.5 90.0 75.3 320.28 7 5.128 5.505 6.223 6.917 7500 A, 8.277 8.950 9.621 10.290 11.625 12.956 1202.0 1228.9 1280.3 1330.2 1380.0 1430.1 1480.8 1532.J 1584.6 1691.8 1802.4 100.0 85.3 327.82 P 4.590 4.935 5.588 6.216 6.833 A, 7.443 8.050 8.655 9.258 10.460 11.659 1199.9 1227.4 1279.3 1329.6 1379.5 1429.7 1480.4 15J2.0 1584.4 1691.6 1802.2 120.0 105.3 341.27 7 3.7815 4.0786 4.6341 5.1637 5.6813 6.1928 6.7006 A, 1195.6 7.2060 7.7096 8.7130 9.7130 1224.1 1277.4 1328.2 1378.4 1428.8 1479.8 1531.4 1583.9 1691.3 1802.0 140.0 125.3 353.04 V ... 3.4661 3.9526 4.4119 4.8588 6.2995 5.7364 6.1709 1120.8 6.6036 7.4652 8.3233 A' ... 1275.3 1326.8 1377.4 1428.0 1479.1 1530.8 1583.4 1690.9 1801.7 160.0 145.3 363.55 A
V ...
3.0060 1217.4 3.4413 1273.3 3.8480 1325.4 4.2420 1376.4 4.6295 1427.2 5.0132 1478.4 5.3945 1530.J 5.7741 6.5293 7.2811 B=in 1582.9 1690.5 1801.4 180.0 165.3 373.08 7 ... 2.6474 3.0433 3.4093 3.7621 4.1084 4.4508 4.7907 A 1213.8 5.1289 5.8014 6.4704
... 1271.2 1324.0 1375.3 1426.3 1477.7 1529.7 1582.4 1690.2 1801.2 200.0 185.3' 381.80 V ... 2.3598 2.7247 3.0583 3.3783 3.6915 4.0008 4.3077 4.612'8 5.2191 5.8219 A ... 1210.1 1269.0 1322.6 1374.3 1425.5 1477.0 1529.1 1581.9 1689.8 1800.9 220.0 205.3 389.88 7 2.1243
... 2.4638 2.7710 3.0642 3.3504 3.6327 3.9125 A, ... 1206.3 1266.9 4.1905 4.1426 5.2913 1321.2 1373.2 1424.7 1476.3 1528.5 1581 4 1689.4 1800.6 ,
240.0 225.3 397.39 7 1.9268
.. 2.2462 2.5316 2.8024 3.0661 3.3259 3.5831 A, ... 1202.4 1264.6 3.8385 4.3456 4.8491 1319.7 1372.1 1423 8 1475.6 1527.9 1580.9 1689.1 1800.4 260.0 245.3 404.44 V ... .. 2.0619 2.3289 2.5808 2.8256 3.0663 3.3044 A, 3.5408 4.0097 4.4750
... ... 1262.4 1318.2 1371.1 1423.0 1474.9 1527.3 1580.4 1688.7 1800.1 280.0 265.3 411.07 9 ... ... l.9037 2.1351 2.3909 2.6194 2.8437 3.0655 A, ... 1260.0 3.2855 3.7217 4.1543
... 1316.8 1370.0 1422.1 1474.2 1526.8 1579.9 1688.4 1799.8 300.0 285.3 417.35 7 ... ... 1.7665 2.0044 2.1263 2.4407 2.6509 A, ... 1257.7 2.8585 3.0643 3.4721 3.8764
... 1315.2 1368.9 1421.3 147J.6 1526.2 1579.4 1688.0 1799.6 320.0 305.3 413.31 7 .. .. l.6462 1.8725 2.0823 2.2843 2.4811 A, ,. ... 1235.2 1313.7 IJ67.8 1420.5 2.6774 2.8708 3.1538 3.6332 1472.9 1525.6 1578.9 1687.6 1799.3 340.0 325.3 418.99 9 ... ..,
A, ... ... 1.53991312.2 1252.8 1.7561131.9532% .7 2.1463 2.3333 2.5175 2.7000 3.0611 3.4186 1419.6 I472.2 1525.0 1518.4 1687.3 1799 0 360.0 345.3 434.41 9 ... ...
s A, ... ... 1.4454 1.6525 1.842I 2.0237 2.2009 2.3755 2.5482 2.8898 3.2279 1250.3 1310.6 1365.6 1418.7 1478.5 1542.4 1577.9 1686.9 1798.8
' American Abstracted society of from ASME Mechanical SteamEast Ensincers,34t Tables 11%7) 47th street. New with permnieon of the publisher. the feeaa m d ea E=3 ork. N. Y.10017
- w esel
.. , - . 7 . ,... f. ... s ..,
_ . , . . ...%._,,._. g, ,.
~ 2 _w "' -,,,
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E
%NE -
CRANE Arrrwiin A-PwesicAt raceraties c, eturos Awo etnw cuanactenistics or vatves pittiwes. Awo pier A - 17
,, 1 T Properties of Superheated Steam continued hspecific volume, cubic feet per pound
- h,= total heat of steam,8tu per pound ' )
{
Pressure Sat.
500*
Lbs.per Temp. Total Temperature-De8rees Fahrenheit (t)
Sq.In.
Abs. Cage 801 500* 600* 700* 800*
po p g 900* 1000* 1100* 1200* 1300* 1400* 1500*
340.0 365.3 439.61 y 1.3606 1.5598 IJ410 1.9139 2.0825 2.2484 ' 2.4124 2.5750 2.7366! 2.8973 3.0572 A 1247.7 1309.0 1364.5 1417.9 1470.8 1523.8 1577.4 1631.6 1686.5 1742.2 1798.5 400.0 385.3 444.60 1.2841 1.4763 1.6499 1.8151 1.9759 2.1339 2.290 t 2.4450 2.5987 2.7515 2.9037 DJ.2 .- -
As 1245.1 1307.4 1363.4 1417.0 1470.1 1523.3 1576.9 1631.2 1686.2 1741.9 1798.1 m m .
gm 420.0 405.3 449.40 F 03 I 1.2148 1.4007 1.5676 1.7258 1.8795 2.0304 2.1795 2.3273 2.4739 2.6196 2.7647
- g A, 1242.4 1305.8 1362.3 1416.2 1469.4 1522J 1576.4 1630.8 1685.8 1741.6 1798.0 331 440.0 425.3 454.03 57 1.1517 1.3319 1.4926 1.6445 1.7918 1.9363 2.0790 2.2203 2.3605 2.4998 2.6384 02.9 -
As 1239.7 1304.1 1361.1 1415.3 1468.7 1522.1 1575.9 1630.4 1685.5 1741.2 1797J 44g 460.0 445.3 458.50 F l.0939 1.2691 1.4242 1.5703 1.7117 1.8504 1.9872 2.1226 2.2569 2.3903 2.5230 02.8 -
As 1236.9 1302.5 1360.0 1414.4 1468.0 1521.5 1575.4 m .= 1629.9 1685.1 1740.9 1797.4 480.0 465.3 462.82 V 1.0409 1.2115
"')g 2.6g 1234.1 1300.8 1.3615 1.5023 1.6384 1.7716 1.9030 2.0330 2.1619 2.2900 2.4173 A, 1358.8 141J.6 1467.3 1520.9 1574.9 1629.5 1684.7 1740.6 1797.2 577 500.0 485.3 467.01 9 0.9919 1.1584 1.3037 1.4397 1.5708 1.6992 1.8256 f.9507 2.0746 2.1977 2.3200 12.5 - -
A, 1231.2 1299.1 1357.7 1412.7 1466.6 ru a 1520.3 1574.4 1629.1 1684.4 1740.3 1796.9 956 i - 520.0 505.3 471.07 V 0.9466 1.1094 1.2504 1.3819 1.5085 1.6323 g,4 _ l _ 1.7542 1.8746 1.9940 2.1125 2.2302 A, 1228.3 1297.4 1356.5 1411.8 1465.9 1519.7
= a -
157J.9 1628J 1684.0 1740.0 1796J 65g 540.0 525.3 475.01 7 0.9045 1.0640 1.2010 1.3284 1.4508 1.5704 1.6880 1.f042 1.9193 2.0336 12.2 2.1471 m
-~
=,
~
A, 1225.3 1295.7 1355.3 1410.9 1465.1 1519.1 1573.4 1628.2 168J.6 17J9J 1796.4 130 52.0 560.0 545.3 478.84 7 0 8653 1.0217 1.1552 1.2787 1.3972 1.5129 1.6266 1.7358 1.8500 1.9603 2.0699 m A, 1222.2 1293.9 1354.2 1410.0 1464.4 1518.6 1572.9
-~
1627.8 168J.3 17J9.4 1716.1 233 880.0
'l J 565.3 482.57 V 0.8287 0.9324 1.1125 1.2324 1.3473 1.4593 1.5693 1.6780 1.7855 A, 1219.1 1.8921 1.9980 m .
1292.1 1333.0 1409.2 1463.7 1518.0 1572.4 1627.4 1682.9 17J9.1 1795.9 til 600.0 585.3 486.20 V 0.7944 0.9456
' t .4 1.0726 1.1892 1.3009 1.4093 1.5160 1.6211 1.7252 A, 1215.9 1290.3 1.8284 1.9309
- 1351.8 1408.3 1463.0 1517.4 1571.9 1627.0
.- 1682.6 1738.8 1795.6 104 1.2 650.0 635.3 494.89 F 0.7173 0.8634 0.9835 1.0929 1.1969 1.2979 1.3969 1.4944 1.5909
- . A, 1207.6 1285.7 1345.7 1406.0 1461.2 1.6864 1.7813
~
1515.9 1570.7 1625.9 1681.6 17J8.0 1794.9 119 700.0 685.3 503.08 9 0.9 ... 0.7928 0.9072 1.0102 1.1078 1.2023 1.2948 A, 1.3858 1.4757 1.5647 1.6530 n = 1281.0 1345.6 1403.7 1459.4 1514.4 1569.4 1624.8 1680.7 17J7.2 1794.3 11 3 6 750.0 735.3 510.84 V 0.7313 \
0.6 I
... 0.8409 0.9386 1.0306 1.1195 1.2063 1.2916 A, 1.3759 f.4592 l 1.5419
... 1276.1 1342.5 1401.5 1457.6 1512.9 1568.2 162J.8 1679.8 1736.4 i 1793.6 n92 3.4 800.0 785.3 518.21 9 ... 0.6774 0.7828 0.8759 0.9631 1.0470 1.1289 1.2093 A, 1271.1 1339.3 1.2885 1.3669 I.4446
.. 1399.1 1455.8 1511.4 1566.9 1622.7 1678.9 17J5.7 1792.9
'50 f.8 .,1
, 850.0 835.3 525.24 7 .. 0.6296 0.7315 0 8205 0.9034 0,9830 1.0606 1.1366 A, 1265.9 1336.0 1.1115 1.1855 1.3588
- 2
.. 1396.8 1454.0 1510.0 1565.7
~
1621.6 1678.0 1734.9 1792 3 43
'8 900.0 885.3 531.95 7 . 0.5869 0 6858 0.7713 0.8504 0.9262 0.9999 pq A, 1332.7 1.0720 1.1430 1.2131 1.2825 1260;6 1394.4 1452.2 1508.5 1564.4
~~
1620.6 1677.1 17J 4.1 1791.6 64 t6 950.0 935.3 538.39 9 0 5485 0.6449 0.7272 0 8030 0.8753 0.9455 g A, . 1255.1 1319.3 1392.0 1450.3 1507.0 1563.2 I.0142 1.0817 1.1484 1.2143 31 1619.5 1676.2 1733.3 1798.0
'3 g 1000.'0 985.3 544.58 7 0.5137 06080 0 6875 0.7603 0 8295 0.89 %
A, 1249.3 1315.9 0.9622 1.0266 1.0901 1.1529 1389.6 1448.5 1505.4 1561.9 1618.4 1675.3 17J2.5 1790.3
] l 1050.0 1035.3 550 53 F . 0.4811 0.5745 0 6515 0.7216 07881 A, 0 8524 0 9151 0.9767 1.0373 1.0973
. 1243.4 IJ22.4 1387.2 1446.6 1503.9 1560.7
~9 1617.4 1674.4 17J1.8 1789.6 g 1100.0 1085.3 556.18 7 0.4531 0 5440 0.61R8 0 6865 0.7505 0 8121 A, 1237.3 1318.8 0.8723 0.9313 0.9894 1.0468
_ IJ84.7 1444.7 1502.4 1559.4
- 1616.3 167J.5'17JI.0 1789.0 d l 1150.0 1135.3 561.82 7 . 0 4163 0 5161 0 5489 0 6544 0.7161 0 7754 A, 1230.9 1315.2 0 8332 0 8899 0 9456 1 0007
.. 1382.2 1442.8 1500.9 1558.1 1615.2 1672.6 j 1730.2 1788.J
~_.al.,
- e. A
. L .
-. s l -s%.- .---_ .L I A 18 Apetuoi 4 pmsic:a ,*oetaties o stuits Ano now c anicsinis,ies o, vitvis Pittiwes two ripe . . Cit A N E Properties of Superheated Steam concluded D
Y= specific volume, cubic feet per pound h,= total heat of steam, Btu per pound M
s.
Pressure Sat.
Ls.gr Temp.
Total Temperature--Degrees Fahrenheit (e)
- s. Gage
, 650* 700* 750' 800* 900*
- 1000 1100*
- 1200 1300 1400* 1500* M 1200.0 1185.3' A, 567.19 V 0.4497 0.4905 0.5273 0.5615 0.6250 0.6845 M 01418 1300.0 '1285.3 577.42 9 1271.8 1311.5 1346.9 1379.7 1440.9 1499.4 1556.9 1614.2 1671.6 1729 A, 0.4052 0.4451 0.4804 0.5129 0.5729 0.6287 0.6822 0.7341 0.7847 M0.8345 0
' 1400.0 1385.3 587.07 V 1261.9 1303.9 1340.8 1374.6 1437.1 14 %.3 1554.3 1612.0 1669.8 1727.9 A, 0.3667 0.4059 0.4400 0.4712 0.5282 0.5809 0.6311 0.6798 01272M 0.7737 0.8 1500.0 1485.3 5%.20 V 1251.4 12 %.1 1334.5 1369.3 1433.2 1493.2 1551.8 1609.9 1668.0 1726.3 17 0.3328 A, 1240.2 0.3717 1287.9 0.4049 1328.0 1364.0 0.4350 1429.2 0.4894 0.5394 0.5869 0.6327 0.6773 0.7210 1490.1 1549.1 1607.7 1666.2 1724.8 1783.7 M 0.76 1600.0 1585,3 604.87 9 0.3026 0.3415 0.3741 0.4032 0.4555 0.5031 A, 1218.3 1279.4 1321.4 1358.5 1425.2 0.5482 0.5915 0.6336 0.6748 0 7153 1486.9 1546.6 1605.6 1664.3 172J.2 1782.3 M
1700.0 1685.3 613.13 P 0.2754 0.3147 0.3468 0.3751 0.4235 0,4711 A, 1213.3 1270.5 1314.5 1352.9 1421.2 0.5140 0.5552 0.5951 0.6341 0.6724 1483.8 1544.0 1603.4 1662.5 1721J 1781.0 M
1800.0 1785.3 621.02 7 0.2505 0'.2906 0.3223 0.3500 0.3988 0.4426 A, 1201.2 1261.1 1307.4 1347.2 0.4836 1417.1 1480.6 1541.4 0.5229 0.5609 0.5980 0.6343 1601.2 1660.7 1720.1 1779J N 1900.0 1885.3 628.56 V 0.2274 0.2687 0.3004 0.3275 0.3749 A, 1185.7 1231.3 1300.2 1341.4 0.4171 0.4565 0.4940 0.5303 1412.9 1477.4 153A.8 1599.1 1658.8 05656 0.6001 1718.6 1778.4 M
. 2000.0 1935.3 635.80 V 0.2056 0.2488 0.2805 0.3072 0.3534 A, 1168.3 1240.9 1292.6 0.3942 0.4320 0.4680 0.5027 0.5365 1335.4 1408.7 1474.1 1536.2 1596.9 1657.0 1717.0 1777.1 0.5695 M 2100.0 2085.3 642J6 Y 0.1847 0.2304 0.2624 0.2888 0.3339 0.3734 0.4099 0.4445 0.4778 A, 1148.5 1229.8 1284.9 1329.3 1404.4 1470.9 15JJ.6 1594.7 0.5101 0.5418 1655.2 1715.4 1775.7 M
2200.0 2185.3 649.45 7 0.1636 0.2134 0.2458 0.2720 0.3161 A, 1123.9 1218.0 1276.8 0.3545 0.3897 0.4231 132J.! 1400.0 1467.6 1530.9 1592.5 0.4551 0.4862 0.5165 165J.3 1713.9 1774.4 M
2300.0 2285.3 655.89 7 ... 0.1975 0.2305 0.2566 0.2999 0.3372 0.3714 0.4035 0.4344 0.4643 AA ... 1203.3 1268.4 1316.7 1395.7 1464.2 1528.3 1590.3 1651.5 1782.3 0.4935 1773.1 d
2400.0 2385.3 662.11 Y ... 0.1824 0.2164 0.2424 0.2850
- 0.3214 0.3545 0.3856 0.4155 0.4443 A, ... 1191.6 1259J 1310.1 1391.2 1460.9 1525.6 1588.1 1649.6 1710.8 0.4724 1771.8 d
1500.0 2445.3 668.11 P ... 0.1681 0.2032 0.2293 0.2712 0.3068 0.3390 0.3692 0.3980 0.4259 A, ... 1176.7 1250.6 1303.4 1386.7 1457.5 1522.9 1585.9 1647.8 1709.2 0.4529 1770.4 d
2600.0 2585.3 673.91 V ... c.1544 0.1909 0.2171 0.2585 A, 0.2933 0.3247 0.3540 0.3819 0.4088
... 1160.2 1241.1 1296.5 1382.1 1454.1 1520.2 1583.7 1646.0 1707.7 0.4350 1769.1 d
2700.0 2685.3 679.53 7 ... 0.1411 0.1794 0.2058 0.2468 A, 0.2809 0.3114 0.3399 0.3670
... 1142.0 1231.1 1289.5 1377.5 1450.7 1517.5 1581.5 1644.1 0.3931 0.4184 1706.1 1767.4 d
2800.0 1795.3 644.% 9 ... 0.1278 0.1685 0.1952 0.2358 0.2693 0.299t 0.3268 0.3532 A, ... 1121.2 1220.6 1282.2 1372.8 1447.2 1514.8 1579.3 1642.2 0 3785 0.4030 1704.5 1766.5 d
2900.0 28h.a 690.22 Y ... 0.1138 0.1581 0.1853 0.2256 0.2585 ,
A, ... 1095.3 1209.6 1274.7 1368.0 1443.7 0.2877 0.3147 0.3403 0.3649 0.3887 1512.1 1577.0 1640.4 1703.0 1765.2 D
3000.0 1985.3 695.33 9 ... 0.0982 0.1483 s
0.1759 0.2161 0.2484 0.2770 0.3033 0.3182 A, ... 1060.5 !!97,9 1267.0 IJ6J.2 1440.2 1509.4 1574.8 1638.5 0.3512 0.3753 1701.4 1763.8 M
3100.0 3085.3 700.28 7 ... ... 0.1389 l
A, ... ... 1885.4 0.1671 0.2071 0.2390 0.2670 0.2927 0.3170 1259.1 IJ58.4 1436.7 1506.6 1572.6 16J6.7 0.3403 0.3628 1699.8 1762.5 M
3200.0 3185.3 705.08 9 .. ... 0.1300 A, .,, .., !!72.3 0.1588 0.1987 0.2301 0.2576 0.2827 0.3065 0.3291 0.3510 1250.9 1333.4 14JJ.! 1503.8 1570.3 1634.8 1698.3 1761.2 M 3300.0 3245.3 ...' 3 7 .., ... 0.1213 A, ... ... 1138.2 0.1510 0.1908 0.2218 0.2488 0.27J 4 0.2966 0.3187 0.3400 1241.5 1348.4 1429.5 1501.0 1568.1 1623.9 1696J 1759.9 d
3400.0 3365.3 ... 7 ... ...
A, ,,, ... 0.1129 1143.2 0.1435 0.1834 0 2140 0.2405 0.2646 0 2872 0 3088 0 d 32 %
1233.7 1343.4 1425.9 1498.3 1565.8 16J1.1 1695.1 1758.5 B:=5
r imur.g_ _ ..____ ... .m& =au em - - - - -- -
CRANE AretNois A-PeslCAL PtOPitHt! OF PLul05 AND FLOW CMARACittilflCS Cf Vatvtl. finiNC1. AND PtPt A.19
'A . Properties of Superheated Steam and Compressed Water
- V= specific volume, cubic feel per pound h,-total heat of steom, Blu per pound bso Total Temperature-.-Degrees 8:ahrmheit (t) s r 200* 400* 500* 600* 700* 800* 900* 1000* 1100* 1200* 1300*
, 1400* 1500*
zu:= 3500 7 0.0164 0.0183 0.0199 0.0225 0.0307 0.1364 0.1764 0.2066 0.2326 0.2563 0.2784 0.2995 0.3198 584 A, 176.0 379.1 487.6 608.4 779.4 1224.6 1338.2 1422.2 1495.5 1563.6 1629.2 1693.6 1757.2 5
3600 V 0.0164 0.0183 0.0198 0.0225 0.0302 0.12 % 0.1697 0.19 % 0.2252 0.2485 0.2702 0.2908 0.3106
$36 A, 176.3 379.3 487.6 604.1 775.1 121,5.3 1333.0 1418.6 1492.6 1561.3 1627.3 1692.0 1755.9 3800 7 0.0164 0.0183 0.0198 0.0224 0.0294 0.1169 0.1574 0.1868 0.2116 0.2340 0.2549 0.2746 0.2936 195 7 ; A, 176.7 379.5 487J 607.5 768.4 1195.5 1322.4 1411.2 1487.0 1556.8 1623.6 1688.9 1753.2 4000 7 0.0164 0.0182 0.0198 0.0223 0.0287 0.1052 0.1463 0.1752 0.1994 0.2210 0.2411 0.2601 0.2783 63, A, 177.2 379.8 487J 606.9 763.0 1174.3 1311.6 1403.6 1481.3 1552.2 1619.8 1685.7 1750.6 4200 V 0.0164 0.0182 0.0197 0.0222 0.0282 0.0945 0.1362 0.1647 0.1883 0.2093 0.2287 0.2470 0.2645 153 A, 177.6 380.1 487.8 606.4 758.6 !!51.6 1300.4 13 %.0 1475.5 1547.6 1616.1 1682.6 1748.0 i-
4400 7 0.0164 0.0182 0.0197 0.0222 0.0278 0.0846 0.1270 0.1552 0.1782 0.1986 0.2174 0.2351 0.2519 724 7 A, 178.1 380.4 487.9 605.9 754.8 1127.J 1289.0 1388.3 1469J 1543.0 1612J 1679.4 1745.3 4600 7 0.0164 0.0182 0.0197 0.0221 0 0274 0.0751 0. !!86 0.1465 0.1691 0.1889 0.2071 0.2242 0.2404 343 7 A, 178.5 380.7 487.9 605.5 751.5 1100.0 1277.2 1380.5 1463.9 1538 4 1608.5 1676.3 1742J
. 4800 7 0.0164 0.0182 0.0196 0.0220 0.0271 0.0665 0.1109 0.1385 0.1606 0.1800 0.1977 0.2142 0.2299 002 A, 179.0 380.9 488.0 605.0 748.6 1071.2 1265.2 IJ72.6 1458.0 1533.8 1604.7 167J.I 1740.0 I 5200 7 0.0164 0.0181 0.0196 0.0219 0.0265 0.0531 0.0973 0.1244 0.1458 0.1642 0.1810 0.1966 0.2114 695 A, 179.9 381.5 488.2 604.3 743.7 1016.9 1240.4 1356.6 1446.2 !$24.5 1597.2 1666.8 17J4.7 5600 7 0.0163 0.0181 0.0195 0.0217 0.0260 0.0447 0.0856 0.1124 0.1331 0.1508 0.1667 0.1815 0.1954 418 A, 180.8 382.1 488.4 603.6 739.6 975.0 1214.8 IJ40.2 1434.3 1515.2 1589.6 1660.5 1729.5 6000 7 0.0163 0.0180 0.0195 0.0216 0.0256 0.0397 0.0757 0.1020 0.1221 0.1391 0.1544 0.1684 0.1111 7
- 165 A, 181J 382.7 488.6 602.9 736.1 945.1 !!88.8 1323.6 1422.3 1505.9 1582.0 1654.2 1724.2 6500 7 0.0163 0.0180 0.0194 0.0215 0.0252 0.0358 0.0655 0.0909 0.1104 0.1266 0.1411 0.1544 0.1669 6935 A, 182.9 383.4 488.9 602.3 732.4 919.5 1856.3 1302J 1407.3 1494.2 1572.5 1646.4 1717.6 I 7000 7 0.0163 0.0180 0.0193 0.0!!3 0.0248 0.0334 0.0573 0.0816 0.1004 0.1160 0.1298 0.1414 0.1542 1724 A, 184.0 384.2 449.3 601.7 729.3 901.8 1124.9 1281.7 1392.2 1482.6 1563.1 1638.6 1711.1 7500 7 0.0163 0.0179 0.0193 0.0212 0.0245 0.0318 0.0512 0.0737 0.0918 0.1068 0.1200 0.1321 8529 A, 185.2 384.9 489.6 601.3 0.1433 726.6 889.0 1097J 1261.0 1377.2 1471.0 1553J 16J0.8 1704.6 8000 V 0.0162 0.0179 0.0192 0.0211 0.0242 0.0306 0.0465 0.0671 0.0845 0.0989 0.I115 1350 A, 186.3 385J 490.0 0.1230 0.1338 I 600.9 724.3 879.1 1074.3 1241.0 1362.2 1459.6 1544.5 162J.1 1698.1 9000 V 0.0162 0.0178 0.0191 0.0209 0.0237 0.0288 0.0402 0.0568 0.0724 0.0858 0.0975 1884 A, 188.6 387.3 0.1081 0.1179 490.9 600.3 720.4 864.7 1037.6 1204.1 1333.0 1437.1 1526.J 1607.9 1685.3 10000 7 0.0161 0 0177 0.0189 0.0207 0.0233 0.0276 0.0362 0.0495 0.0633 0.0757 0.0865 4030 A, 190.9 388.9 0.0963 0.1054 491.8 600.0 717.5 854.5 101I.3 1872.6 IJ05.3 1415.3 1508.6 1593.1 1672.8 11000 7 0.0161 0.0176 0.0188 0.0205 0.0229 0.0267 0.0335 0.0443 0.0562 0 0676 0.0776 1187 A, 193.2 390.5 0 0868 0 0952 492.8 599.9 715.1 846.9 992.1 1846.3 1280.2 1394.4 1491.5 1578J 65,2 1660.6
!!000 7 0.0161 0.0176 0.0187 0.0203 0.0226 0.0260 0.0317 0.0405 0.0$08 0.0610 0.0704 5753 A, 195.5 392.1 0.0790 0.0869 63.8 493.9 599.9 71J.3 84l.0 977.8 1124.5 1258.0 1374.7 1475.1 1564.9 1648.8 .
13000 V 0.0160 0 0175 0.0186 0.0201 0.0223 0.0253 0.0302 0 0376 0 0466 0.0$$l 0.0645 0 0725 1628 . A, 197.8 J9J.8 495.0 0 0799 600.1 711.9 836.3 966.8 1806.7 1238.5 IJ56.5 1459.4 1551.6 62.5 1637.4 14000 7 0.0160 0 0174 0.0185 0.0200 0.0220 0.0248 0.0291 0.0354 0.0432 0.0515 0.0595 0 0670 1510 A, 200.1 395.5 496.1 600.5 0.0740 68.2 710.8 832.6 958.0 1092.J l221.4 1340.2 1444.4 153s.8 1626.5 15008 7 0.0!$9 0.0174 0 0184 0.0198 0.0!!8 0.0244 0.0282 0.0337 0 0405 0.0419 0.0552 0 0624 0 0690 34 A, 102.4 397.2 497.4 600.9 710.0 829.5 950.9 1050.6 1206.8 1326.0 1430.3 1526.4 1615.9 15500 7 0.0159 0.0173 0.0184 0.0198 0.0217
!!*6 0.0242 0.0278 0.0329 0.0393 0 0464 0 0534 0.0603 0.0%8 A, 203.6 398.1 498.1 601.1 709.7 828.2 947.8 58.5 - 1075.7 1200.3 IJi9.6 142J.6 1520.4 1610.8
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MA S Ylifs -A0 q
, . ANSWER KEY J
U.S. Nuclear Regulatory Commission Reactor Operator License Examination
{
p,ggjjgy. San Dnofre Units 2/3 Reactor Type: Combustion., Engineering Date Administered: March 31. 1987 1
i -
Examiner: Grv W. Johnston Candidate: ,
INSTRUCTIONS TO CANDIDATE:
l 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 1
indicated in parentheses after the question. The passing grade requires at least 705 in each category and a final grade of at least 405.
Examination papers will be picked up six (6) hours after the examination starts. ~' -
X of Category X of Candidate's Category i Value Total Score Value Catecory '
- e s. z %
1 25.0 Mr:- 1. Principles of Nuclea. Power l Plant Operation, Tha..nodynamics, Heat Transfer and Fluid Flow 42.0 X ye 2. 3 %
2ay ,5 l 2. Plant Design Inc1tuting safety and j -
Emergency Syste n -
4 - 2 9. t Yo . .
- 2 J.f 2 5. 0 -25'r- -
3.
- Istruments tid Controls z o.21, i 25.0 25 4. Procedures - Normal, Abnormal.
Emergency, and Radiological Control -
'/ J~. f JMMT" -
TOTALS j Final Grade X .
- , All work done on this examination is my own. I have neither given nor received aid.
1 j Candidate's Signature i
4 -
l l . .
l l
L .
._ . - - - - _ . . . . - - - - . _ . - - - . - - . - - - _ _ _ . - _ , . . _ _ _ . , , . _ - . . _ , _ _ - . , _ . _ _ . _ , , - - _ . . . . . _ , , _ . . . - - , _ _ - , _ - ~ ~ _ -
, . I l
!l . .
l -
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1 r .
I REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS I -
' 1. A single room shall be provided for completing the written examina --- l_ l tion. The location of this room and. supporting restroom facilities '.
' ' " ~ ~
l
, shall be such as to prevent contact with all other facility and/or l j contractor personnel during the duration of the written examination. <
i If necessary, the facility should make arrangements for the use of l' i
- -- a suitable room at.a local school notel, or other building. 0b- ~ ~ ~ '
taining this room is the responsib111ty of the licensee.
~'
l i? 2. Mintaus spacing is required to ensure examination integriti as determined by.tne chief examiner. Minim e spacing should be one ..
! '}
t candidate per table, with a 3-ft space between tables. No wall '
} charts, models, and/or other training materials shall be present in 5 o l
jg the examination room. .
j
! 3. Suitable arrangements shall be made by the facility if the candi-i dates are to have lunch coffee or other refreshments. These ,
i :
arrangementsshallcompIywithItem1above. These arrangements ~
shall be reviewed by the examiner and/or proctor.
! 4. The facility staff shall be provided a copy of the written examination !
I and answer key after the last candidate has completed and handed in -
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. .
l 1
!' 5. . The licensee 'shall provide pads of 8-1/2 by '11 in. lined paper in i (. unopened packages for each candidate's use in completing the exam- l 1 .
ination. The examiner shall distribute these pads to the candidates. l
} . , All reference material needed to complete the examination shall be i furnished by the examiner. Candidates can bring pens i J' calculators, or slide rules into the examination room,, and pencils, no other equipment or reference asterial shall be allowed. .!
1
! 6. Only black ink or dark penctis should be used for writing answers '
1 i to questions. '-
k .
j . -
l 1 .
1 i
l g. Examiner Standards
. 6 l I . .
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- - , . . ~ - - - - . . - - - - . , - . - - - , . , _ . .
i o l .
NRC RULES AND GUIDELINES FOR LICENSE UAMINATIONS l During the administration of this' examination the following rules apply: '
1.
Cheatigudresultinmoreseverepenalties.on the. examination means an auto l and co .
- -2. Restroom trips are to be limited and only one candidate at a time may f.
11 eave. "You must avoid all contacts with'anyone outside the ciasination [ -
room to avoid even the appearance or possibility of cheating.
- 3. Use black ink er dark pencil g1y to facilitate legible reproductions.
r .. .
l 4. -Print your name in.the blank provided en the cover sheet of the
~
. .amasination.
. g. . . . .. ......w.. .. - . . . . .. ..
., 5. Fill in the' data en the' cover sheet of the: examination (if necessary). ..
- ) 5. Use only the paper provided for answers. e
~
- 7. Print your name in the upper right-hand corner of the first page of ggh,,
', section of the answer sheet.
[* 5. Consecutively number each answer sheet, write "End of Category
- as .
appropriate, the paper, andstart writeeach "Last categor{
Page on thTTast answer shee,t.onanewpage,writeg
- 9. Number each answer as to category h number, for example,1.4 S.3. -
- 10. 5 kip at least ih,tsg lines between each answer.
- 11. separate answer sheets fros
- down on your desk or table. pad and pla,ce finished answer sheets face i.
i 12. Use abbreviations only if they are commonly used in facility literature.
l 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. -
L
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question er not.
.I
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER'SLANK..
- 15. If parts of the examination are not clear as to intent, ask questions of
'. the examiner only.
l 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 i ,
completing the examination. This must be done after the examination has ji been completed. . .
l k Examiner Standards .s l1 l' .
i l
9
- 28. When you complete your examination, you shall: s. .
- a. Assemble your examination as follows: - I
. (1) Exam questions on top. .
(2) Exam aids - figures, tables, etc.
l
- (3) Answerpagesincludingfigureswhichareapartoftheanswer.l.[-
, b. Turn.in your copy of the examination and all pages used to answer 1
the examination questions. ,. ,
! c. 3. Turn in all. scrap paper and the balance of the. paper that you did -
I not'use for answering the questions.
'5- .
! d. Leave the examination area, as defined by the examiner. If after ..
1 leaving you are found in this area while the examination is still
. in progr,ess, your license amy be denied or revoked. .s .
I l
.i i .
}> . .
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- l
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- j l
- I
. . I
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)
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4 .
ll I
- Examiner Standards ..
i i
. l j
L-. -. -- _.
.r
- EQUATION SHEET f = ma y . ./g v = ms a= t+ g.t 2 Cyci efficiency = Net Work (out) 2 o Energy (in)
E = aC a = (vg - y )/t .
KE = uv 2 vf = v, + a A = AN "
A = A,e PE = agh w = 6/t A = In 2/cg = 0.693/tg W = v&P eg (eff) = (tq)(ts) i AE = 931Aa ,
(g 4g)
Il=[nCAT p k *
- Ak I = I . IX
~
k=UAAT 4 mYl%(br I = I
~
DX Pwr = Ug a I=I g to-x/ M
. P=P 10 SUR(t)* TyL = 1,3/g y=y HVL = 0.693/u o .t/T SUR = 26.06/T T = 1.44 DT SCR = S/(1 - K,gg) fX*ggo \
SUR = 26 g, CR, = S/(1 - K,ggg)
~
- T = '(t*/p ) + [(f *p)/A,gg ] p 1( eff)1 " 2(1 *K,gg)2 7 = 1*/ (p - D M " I/(I ~ Eeff) = CR /CR g 0
~ 8}! eff" M = (1 - K,gg)0 II ~ Eeff)1
- II eff ~I)/Eeff = AK,gg/Kaff SDM = (1 - K,gg)/K,gg p= [1*/TK,gg .] + [E/(1 + 1,ggT )]
~
g* = 1 x 10 seconds '
F = I(V/(3 x 10 0) A gg = 0.1 seconds
- E = Na - '
l .
Idgg=122
! WATER PARAMETERS Id =1022
' g l 1 gal. = 8.345 lba 2 R/hr = (0.5 CE)/d (meters) 1 gal. = 3.78 liters R/hr = 6 CE/d (feet)
I ft = 7.48 gal. MfSCEt.t.ANEOUS CONVERSIONS i Density = 62.4 lbm/ft 1 Curia = 3.7 x 10 dps 10 I
Density = 1 gm/cm 3 1 kg = 2.21 lbe Heat of varorization = 970 ttu/lba 1 hp = 2.54 x 10 3BTU /hr
- , Heat ofsfusica = 144 Btu /lba 0 1 Hw = 3.41 x 10 Btu /hr
) 1 Atm = 14.7 psi = 29.9 in. Ig. 1 Bt.u = 778 fe-lbf i ,
1 ft. H 2O = 0.4333 lbf/in 1 inch = 2.54 cm I '
4 *F = 9/5*C + 32
- C = 5/9 (*r - 32) '
le es
. . Table 1. Saturetect Steam: Tempoteture Teiste ,
Aesruss. steofic volwne fathaler Entrety Tomt tb per Sat Set. Set Set Sat ianr Sat. feet g $g hL best Evet Vapor Uqed Liged tvet Veter Fahr t 0 -
v, vfa 't ne Evat,g h Vaper ng s, sen 8a t
- *~.+ m e' 0 0s:59 0 016022 Hoe 7 3304 7 - 4 0179 ic75 5 Isn t 6 0000 2.1473 2 1073 3:0 *
. 38 4 00N00 0 016028 3061 9 30si t 1 996 .074 4 1076 4 0 004 2 1762 f leet MS NO 010M5 0 016020 MMO 20M 0 4 me 073 2 80772 S ett 2 1663 18732 20
... 24 4112 9 4 016019 2LM t 26M 2 t elt .01& & le7t! 40122 itM1 2.1443 384
- . 44 O!!I63 4 016019 M.6 0 24.$ $ 0 02, 871 0 079 0 0 0162 2 .432 'lles 44 43 8 01 0 016019 22724 2272 4 IO NS #90 079 1 0 0702 2 JM '1527 42 3 013143192 0 016019 2112 0 til2 0 12 081 054 F 008 7 6 0242 2 21, 8 90 est e.s 00 t O lH14 0 016020 IMS7 IMSF I 087 0874 Wie 0 0702 2 1111 1393 als
. as e neste 6 01602I lent 14Jte 16 51
- 086 4 10023 00HI 1 ,005 1327 #4 24 91U96 0 014023 704 0 fee t 18 064 :0H3 ' :083 4 GONI 2 0:01 21M2 00 0 St 0 0 19165 0 016074 Sat 2 Set 2 'Je OS T 004 2 .004 2 0 0800 ;'0798 t97 81 0
, W4 0 20675 00160M 402 4 402 4 22 068 0631 00s 1 00sM : 06M IM N0 1 . Ste t utt) 0 016024 343 6 Mit 20 0H G10 008 0 0 0s70 4 sta 4' 070 sta K4 8 23 # 3 0 014431 IM22 M22 N 000 etta 406 9 00616 . Gell.1:,0E0 SLA 90 0 02Wil 0 016433 207 8 :M16 N ote 10H , 007 , S MS$ 0MI 20N8 tie e f fete 0 0160M 179 2 IM 2 30 069 060 S 010 8 S Mt! 0791 2 0005 Nt 61 s 88 8 4 29897 0 016 139 OM S OW S 0674 cell 0 06M to t I
M4 Ita 0 31674 433809 0 016083 0 0160s4 9M 0 9M S 900 1 9MS N.054 3
N 064 060 OW J
.0ta.J 090 4 0 0870 '0098
'0192 2 0024 0 4100 . 9MS 1 0704 2 07H 06 8 0012 SLO MS O M?t2 0 016050 084 3 080 4 30 M2 '064 0 007 5 9000 Me l
n Omm 0= m, #,21 01 00: f tpl, nt
- . - u 0. m 0 Omm f.i4
.i 3 m. 3 .no. mM u.
t n.
MA 0im 44764M Omy 0 016061 me 673 0 1
m .i 673 9 42os.,
o 46 000 Ou m
est
- 09. 1 Ott o i.n me
,i 0 0895
.ie SlM . 0815 '
0 2 M.
Me 18 8 0 $06a3 0 0160 sil 633.1 40 037 WM ; N8 n=}, m 094 4 10912 I
088 4
- m: m -
m' = :m 'm:
0e99
- m. ., ::m
.. =l,
.. Dum Omm ms = esio e miol .m . 0iu ..
- Smu tam .n 4 == m Sim 0iM =
m g.,m Omm um m, in m0 sm.
- m lm:lij "l: :ti j nm tiL 00 0 0
li! 'fti M
.e 4 M
- l:N!! n O 13 m m: = = 1:!) L= la a ::.
- . a.m,0 em,6,m.4 l40. l,l0.
6, ,,,
m
,0,7 4a,
, ,0, iM,
, m 0,30 , , 0
.. I 0,,,,k 0
,n,l 1,l = =c mu m 8.-
.n. :%
ap 1 .0 e
, HBS 2030 0164b ,,0020 2 M f$ mf ,lk l[ h h hl gj I! M 11 'I itu ':g
, 1: 1 "17; 4a => +
. Lii.l !!! llll! L!U'll :!!H in h iE w[ Ut JW ll I
= = mm mu ma un su mn apJj[ h:>>.
!!! . O lll!!0 l00 l0.h llI ll!i t'l- d j-f
.: o,0 3 0,,,4, 0, , ,
I : Ib". ll! !!h lhh bl ,k $ ,g senn 6
- l :n am nu ::n ne h !! r It
=
a m
l!! $ 5 r
i i.
E
!E
. ,1,,
4,.i4
,$E.!
0le 4 Omni ny
.E.lE .3 l Wi
, y .,
E.34L 0
it,, ,
"E,; a
.,4 TIim, g li m;
,~ 0 ms n,- g n
tot
,g> om 6.s. 6 00 u, t.
, ,, m:
its am m m 1, s .,.,0.
. ,,n,,0 , ,,, a g.6 s 3;.m, ,g:
" 0 ,,
,,,o nm ,m ,,
.g.f ai u = i.. 4 ,,. ,,, n, 1,.
.;,0 .0, ,. u lin g; Ji
'1- im "m'n il: 13! g t :b, ;,t g ...,s.
i
- j.
c
,, Table 1. Se.ure.ed Steem: Tempeesture Table--Com.t seat j,
, A.s Press. . $. colic Valuene Enthalpy Entr.py ,'
Tem. Sat. Sat. Sat. Sa Sat. $st Tem.
fahs Lb.per
$ In, .Lge. [v Vapor Lage. Iva. Va.i. or Lged Vap t Fahr i .- p- -- vg veg vg -- . hg A fg hg .g fu.e.
,a 8a I
,m. mmm n .n ., .nn
.in g.
.2! lini! Eiil nin lU!. 2! yl n Inu "
E, 112 !
i tuf M !an a n! n a lun liu #1 tiiil 11!! JRi !!!
.. .. .mm .. .. m. i l., i .= m.
. nll..it.9.!.!.!nn i
.m.i.
m.
.n ui.m R.m Ifui '!*n!!=
i :inR.io
==
E.!.
mi t.i.ni.
un. i.m.uti.i
.i,nt E..!
=,
=. . ..n . .. m. m . i m
= 1,i m . .i u m.
n nn m n, .
. i m.,),
in io
.. n. .u , ..
.mn. ==
== m
.ru.
m m n 1, m.
1 ni m
i
- n. umo nm n m nn un . In,m. m.
- ==. == w .i m um . nu
- m. .mm an. m.
Ifm in ni =
m2n, I in m.e
.. n.
i . nm .. .. .m.i n 7 m.
i 4
mi m.
Rui um lin. '1,A.t. Rf!!
ui. inn .ini.! .
2!. i tii n, !!!il '"t"lis mi.i!n m um 2.:
- . m m
nm nm
.m. < = . ., m m. 3 nn m n
- m. ,
. nm. .m a ln.. mI
. \m.
m um,,
n, . m, m 1
m,
.5 .
m 30 un m,.,,
.i n .
3 M. 3 2.3,5 i
un ,
. . .1..., .,
.3 2m.
2M
= ,. m.
IM 1m m. n .i m u,u w .nl m 1 .
.. nm .m. Ii, m m :i m mn m ,. w ., um i , m
.. unn, in,. ., w ma .m . um i"I,> n . m
! .v. . .m m m .m =.
m.
m
. um . unu uni . n. .m m m.u. .ui .. in, in um.o, u:2n, . = m.
.uu onna .. .. == mi mi .. m i4
.m. um
. .mn .m u mn n. . .. ..
- m. .m 8mwu ., .u. u m .=n l . i s. i.m ..
u a.iw m. .,
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0.,l !!!! n,,!
n ::!!! M. : E!
i .
hlmm .!.!nm .i,a.lti
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9 tm.
1,. !:::
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=l .i .
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m => n m
.n .. . mi
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4
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.m.. 2! 12.n.l.1 lil)'
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in.
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n m>
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.nI m . .,m. .m
.in m.,
m m
- m. .
.,. .m.. .n, sm .
i
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.u.m. m m ..
m m m
mn
.m mn m. ,, n.u. R,a . un =.
o nn m f nm. .i.n un m.
- nin.
I.m.i.
.,m mu nn ml m, ,o
.m um w. ,m
.nm ni tom .m u n. un u .m
.n n...
. n M.i m, m uti m
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u,.n, is.
. tu. m. .
lli!
,!m im , .
a
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=
=t .lno, i.n . m. m,
, llini uti ## n!! llif 151 iW lim ulu :lii
. u .,
o u til i
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i mm. 8 ii m. m. .m = ..
.. i, . 1 WW la l m; =}
in l"s.m 1"
.m..t m. t'olmm Imuu In.ift mo mI m of . !: 8131 :l n, .i .
. m 3., u m. m.
... m.n i m,.i I. n. ,16 ,m .,n
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3,. [,
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. - . Table 1. Saturated Steam: Temperature Table-continued b
, Aas Prest Spechc Volume EnthalpF (ntropy Temp tb per Sat. Sat. Sat. Sat. Sat Sat. Teme Fahr sq In. -
Liamd tvan Va0er Lituuf Eva0 Vapor Lited Evan Vapor Fahr
. t ._ _0 ___v, via 't - he hg f hg . _ s, . s,a la I
=
ese t 466 87 0 0lMI 0 97453 0 90824 481 5 763 2 204 8 O WO5 04299 1 4704 400 0 ese 8 445 56 0 CM6m 0 13580 09H57 484 I 154 4 20s 7 0 6454 04213 1 4647 40s 8
...* ese t 508 83 4 01976 88405 0 91462 450 7 '754 0 204 6 0 6502 08t27 146M 40Be 472 8 524 67 0019se 0 8E345 0 44329 455 2 741 3 2045 4 6551 0 8062 3 4592 472 8 4764 54118
- 0 01992 6 82958 4 44950 "4599 744.5 204.3 5H99 8 7956 I 45 % ella det8 544 15 0 02000 0 79716 0 81717 464 5 739 6 204 I e 5648 0 7871 1 4518 4084 408 8 .567 8; & 02009 0 76413 0 18622 , det i 7H 7 203 8 0M9C 0 7785 8 4441 40s e
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j l SECTION 1 i
Principles of Nuclear Power Plant Operation,
-Thermodynamics, Heat Transfer and Fluid Flcw OUESTION 1.01 i If the speed of a centrifugal pump that is operating in a closed j system is reduced by a factor of two (2), what will happen to the
]
power consumption of the pump? (1.0)
- ANSWER
- Decrease by a factor of 8. (1.0)
- REFERENCE l Genera 1' Physics page 322.
QUESTION 1.02 The equation Q = m (h 2 -h g) is used to perform the caliormetric calculation of Reactor Thermal Power. Based on this calculation the power range nuclear instruments are adjusted to read in l percent rated power. If the heat input from the Reactor Coolant j pumps were neglected in the calculation, how would indicated j . power from the power range nuclear instruments differ from actual l thermal power? (1.0) l a
- ANSWER q The nuclear instrumentation would indicate higher than the actual 4 thermal power. (1.0) i
- REFERENCE General Physics pages 158, 159, and Caliormetric procedure.
QUESTION 1.03 A relief valve on a pipe opens at 885 psig. The temperature of the steam exhausted to the atmosphere is 320 deg. F. The fluid within the pipe is saturated steam. Using the steam tables provided. What is the approximate temperature of the fluid within the pipe, in the immediate vicinity of the relief valve? (1.0)
(Select one response from below.)
- a. 530 deg. F
- b. 400 deg. F
- c. 320 deg. F
- d. 212 deg. F
- ANSWER _
i
- a. (Saturated steam at 885 + 15 psia.) (1.0)
- REFERENCE CE Steam' Tables, General PhysicsSection II.
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QUESTION 1.04 In the Condenser the latent heat of vaporization is being extracted from the Turbine exhaust converting it to a liquid.
- a. What is the condensate depression for a condenser operating at 1.0 psia and a condensate temperature of 97 F? (1.5)
- b. Why is condensate depression important in the operation of the Condensate system? (1.0)
- ANSWER
- a. 1.0 psia saturation temperature = 101.74 F (0.5) condensate depression = difference between saturation temperature and condensate temperature = 101.74 - 97 =
4.74 F (1.0)
- b. To maintain sufficient Net Positive Suction Head (or to prevent cavitation) for the condensate pumps. (1.0)
- REFERENCE General Physics pages 182 to 185.
. QUESTION 1.05 Why will a positive reactivity insertion at End of Core Lif e (EOL) cause a greater reactor Startup Rate (SUR) response than the same positive reactivity insertion at Beginning of Core Life (BOL)? (1.0)
- ANSWER At EOL the delayed n fraction is smaller so that Beta is -
smaller thus SUR is larger.
- REFERENCE Reactor Theory, Nuclear Physics, and Core Operating Characteristics pages 148 to 157.
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QUESTION 1.06 If a reactor has been at a stable power level for a number of weeks, an equilibrium concentration of Xenon will exist. If a reactor trip then takes place:
- a. What changes occur in the the production and removal of Xenon following the reactor trip. (1.0)
- b. Why will there be an increase in Xenon concentration over the equilibrium concentration? (1.0)
- ANSWER
- a. The terms for production from fission and burnup by neutron absorbtion are nonexistent since fission and neutron production cease (1.0).
- b. The half-life of I-135 is shorter than that of Xe-135 (0.5),
thus, more Xenon is being produced than is decaying away (0.5).
- REFERENCE Reactor Theory, Nuclear Physics, and Core Operating Characteristics pages 106 to 110 and 204 to 218.
QUESTION 1.07 Regarding Nucleate Boiling:
- a. What are the FOUR Reactor Coolant System parameters that the DNB Heat Flux (CHF) is dependent upon? (1.0) .
- b. Why is the Departure from Nucleate Boiling Ratio (DNBR) the largest at the bottom of the core, under normal operating conditions? (1.0)
- ANSWER
- a. Flow Temperature Pressure Power C O.25 each3
- b. Because this is where the temperature is the lowest and pressure the highest. (1.0)
- REFERENCE 1 CE - Thermal Hydraulics, p 14 l Gz n <>< Asmik1, not'f 1it ~~22I e
QUESTION 1.08 You have just completed a reactor startup and power level is above the point of adding heat (POAH). In the following situations, EXPLAIN in terms of Reactivity Coefficients, why the Reactor Power changes?
(Assume the core is at mid-life, no other operator action and treat each situation separately).
- a. The Steam Dump pressure setting is raised by 20 psig resulting in a lower final Reactor power. (1.0)
- b. A 1% steam leak develops outside of containment resulting in a higher final Reactor power. (1.0) i
- ANSWER
- a. The steam dump pressure setting increase causes an RCS temperature increase. MTC and FTC (Doppler) both add negative reactivity to lower reactor power. (1.0)
- b. The increased flow will result in a lower RCS temperature.
MTC will add positive reactivity and power will rise. (1.0) v d"# r rc
- REFERENCE CE- Nuclear Physics, Reactor Theory and Core Operating Characteristics, pg 162-166, 178 QUESTION 1.09
- What is the purpose of the recirculation path of a centrifugal pump that is running with its discharge valve closed? 41.0)
- ANSWER When there is no flow through a pump running at shutof f head the continued rotation of the impeller churns the fluid that is in the casing and heats it up. The heated fluid may damage the moving parts (and cause it to seize) (1.0).
- REFERENCE General Physics page 320.
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QUESTION 1.10 Over the life of a typical core the flux distribution changes due to the redistribution of the fissionable fuel. On the following page there is a graph of the fuel distribution at Beginning of Core Life (BOL). Draw on the graph provided (Figure 1.10) the distribution of fissionable fuel at End of Core Life (EOL). (1.0)
- ANSWER Graph on Figure 1.10 with point distribution. (1.0)
- REFERENCE Reactor Theory, Nuclear Physics, and Core Operating Characteristics pages 181 to 203.
QUESTION 1.11 For each of the factors listed below, does the magnitude of the negative Power Coefficient increase or decrease as the factor is changed in the direction described?
- a. Moderator temperature decreases (0.5)
- b. Core age increases (0.5)
- c. Baron concentration increases (0.3)
- d. Control rods inserted (0.5)
- ANSWER
- a. Decrease (0.5)
- b. Increase (0.5)
- c. Decrease (0.5)
- d. Increase (0.5)
- REFERENCE Reactor Theory, Nuclear Physics, and Core Operating Characteristics pages 159 to 101.
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l QUESTION 1.12 The Charging pumps are positive displacement pumps:
- a. What will happen to the discharge flow rate if a manual valve is_ throttled partially closed (50%) in the discharge line? (0.75)
- b. What will happen to the flow rate of the same pump if the head at the suction of the pump were increased?
(0.75)
- ANSWER
- a. The flow rate will not change substantially. (0.75)
- b. Nothing, flow rate is independent of head. (0.75)
- REFERENCE General Physics page 329.
QUESTION 1.13 While operating at 50% of full power all rods out (ARO), a rod located very close to the middle of the core radially, drops all the way into the core with no resultant reactor trip.
- a. What will happen to the LOCAL Radial flux distribution shape? (1.0)
- b. What will happen to the LOCAL Axial flux distribution shape? (1.0)
- ANSWER -
- a. Radial flux distribution will be skewed away from the dropped rod, (Peak flux will increase) and the flux at the point of the dropped rod will be near zero. (1.0)
- b. Axial flux distribution will decrease and shape remains the same. (1.0)
- REFERENCE Reactor Theory, Nuclear Physics, and Core Operating Characteristics pages 181 to 204. The text material does not discuss this topic in any depth.
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l QUESTION 1.14 During normal plant operations certain chemical additions have to be made periodically. What Reactor Coolant System chemistry parameters are controlled by'the additives? (1.5)
- a. Hydrazine (0.5)
- b. Hydrogen (0.5)
- c. Lithium Hydroxide (0.5)
- ANSWER
- a. Hydrazine controls Oxygen concentration (at low-temperature conditions to limit corrosion). (0.5) '
- b. Hydrogen controls Oxy'en g concentration (at operating temperatures to limit corrosion). (0.5) ,
- REFERENCE Standard PWR chemistry.
QUESTION 1.15
. During a reactor startup a Reactor Operator adds positive reactivity with rods sufficient to raise Keff from 0.94 to 0.97.
- a. What will the new Source Range count rate be if the previous count rate was 50 counts /second? (0.5)
- b. What will happen if the same amount of positive reactivity is again added to the reactor? (1.0) -
- ANSWER
- a. The new count rate will be 100 cps. (0.5)
CR (1 - Keff,)
-- l- -
- =
CR = (50) x (0.06/O.03}
CR 2 2 (i ~ K*ff1) = 100 cps
- b. The reactor will be just critical or slightly supercritical (the latter more likely as per the following).. (1.0)
Delta Keff 0.03 rho = --------- = -- = 0.0309 Keff 0.97
-1 -1 Keff = ------ = ----------- = 1.03 rho - 1 0.0309 - 1
- REFERENCE Genera 1' Physics pages 146 and 147.
r -- -
QUESTION 1.16 The Main Generator proeduces both Reactive Power and Real Power:
- a. When the Main Generator is supplying power to the grid with a normal load, what type of power factor is being supplied? (0.75) b.- How is Apparent Power derived from Reactive Power and Real Power? (0.75)
- c. For both of the following what acronym (KVA, KW, or KVAR) is ccmmonly used for each type of Power? (0.5)
- 1. Real Power
- 2. Apparent Power
- ANSWER
- a. Lagging (0.75)
- b. By a vector sum. (0.75)
- c. 1. KW (Kilowatt) (0.25)
- 2. KVA (Kilo volt ampere) (0.25)
- REFERENCE
. SD-SO23-105 APPENDIX C page c-3 and figure C-5 End of Section 1 Go on to Section 2 .
e e
e , - __ _ _
r SECTION 2 Plant Design Including Safety and Emergency Systems QUESTION 2.01 The 'J' tubes on the Steam Generator feedwater sparger ring direct feedwater flow downward between the Steam Generator Vessel wall and the baffle assembly. What event are the 'J' tubes designed to prevent? (1.0)
- ANSWER Severe water hammer transients. (1.0)
- REFERENCE SD-SO23-160 page 11.
QUESTION 2.02 Regarding the Control Element Drive Mechanism Control Systems
- a. What is the function of the Upper Electrical Limit?
(1.0)
- b. What is the function of the Upper Group Stop? (1.0)
- ANSWER
- a. This prevents further individual CEA motion when in Manual Individual (or subgroup motion when in other modes) when the first CEA in that subgroup reaches this extreme limit. (1.0)
- b. Prevents further group withdrawal when the lowest CEA in the .
group reaches this limit. (1.0) to.5 each]
- REFERENCE CEDMCS SD-SO23-510 page 37.
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QUESTION 2.03 Regarding RCS letdown: Why are the CVCS letdown backpressure control. valves needed during operations in Mode 1? (TWO reasons required). (1.5)
- ANSWER Protect downstream purification equipment from overpressurization/ limit transients CO.753. Prevent upstream letdown flow from flashing to steam EO.75]. (1.5)
- REFERENCE CVCS SD QUESTION 2.04 Per Technical Specification LCD 3/4.4.8, PRESSURE / TEMPERATURE LIMITS, the RCS temperature and pressure shall be limited in accordance with the limit lines shown on attached Figure 6.9.a for specific operating conditions:
MATCH the LIMIT LINE (A-D) with its associated OPERATING CONDITION by selecting its specific operating condition from the choices given below ( 1-6 ).
(1.5, 0.75 pts. each)
LINE Condition # OPERATING CONDITION (choices):
(A) #_____ (1) Cooldown 30 deg/hr below 280 deg F (B) #__ (2) Core Critical ,
(3) Lowest service temp (heat up)
(4) Lowest service temp (cooldown)
(5) Inservice Tests (6) Heatup 30 deg/hr below 280 deg F
- ANSWER
( 1.5, 0.75 pts. each )
(A) #3 (B) #5
- REFERENCE Technical Specification LCO 3/4.4.0, PRESSURE / TEMPERATURE LIMITS
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' 7 AMEN P.E.iT NO
QUESTION 2.05 While the power plant is operating at a constant 100% power level, a reactor operator causes an inadvertent baration which causes Tave to drop 10 degrees F. Will the following parameters INCREASE, DECREASE, or REMAIN THE SAME immediately after the boration?
- a. Steam Generator temperature (0.5)
- b. Steam Generator pressure (0.5)
- c. Steam Generator Level (0.5)
- d. Unit Electrical Output (0.5)
(Assume that no operator action is taken and that all systems function normally, Manual Sequential for the rods and CVOL is not limiting.)
- ANSWER
- a. The Steam Generator temperature will decrease (f rom the
. Iower Tave). (0.5)
- b. The Steam Generator pressure will decrease (Tave drop lowers saturation temperature in S/G). (0.5)
- c. Steam-generator water level will initially increase (Swell in riser section). (0. 5) . .
- d. , Unit electrical load will remain the same. (0.5)
- REFERENCE SD-SO23-180 Main Turbine System -
System Description 42, RCS System Description 21, Feedwater Regulating System QUESTION 2.06 During 100% equilibrium power conditions, Carbon Dioxide gas is inadvertently valved into the main generator replacing the Hydrogen gas. How would this action affect the generator rotor temperature? (1.0)
- ANSWER
, Rotor temperature would increase because CO ~ ,is not as good a heat-transfer gas as H . (1.0) 2
- REFERENCE
- 1. SD-SO23-100 Main Gen. and 22 KV System
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n --n---- -
The Sta Transfer Switch in the 120 VAC system is desi fprovideav ual zero-time transfer to an alter e p6w r source in the case of Inverter failure. Beside e Manaual Pushbutton, what ar he other three (' inputs that can cause a Static Transfer Switch tranfer an alternate power source?
(3.0) f
- ANSWER
( 1. Failure deterioration of the in nal Inverter square j way ill accept internal fault of rter.) (1.0)
{ 2. lure or deterioration of the Inverter ou t voltage.
! (1.0)
- o. Overload which exceed the Inverter current capacity. 1.0) g ,
- REFERENCE SD-SO23-130 REV. O PAGE 9 QUESTION 2.08 What are the busses and motor control centers associated with ESF
. Load Group A for Unit 2 from 4160 Volts through 480 Volts (seven items required)? (2.0)
- ANSWER
- 4160 V Bus 2A04 (0.25)
- 480 V load center 2BO4 (0.25)
- 480 MCC 2BD (0.25) .
- 480 MCC 2BE (0.25)
- 480 MCC 2BY (0.25)
- 480 MCC 2 BRA (0.25)
- Common - 480 MCC BQ (0.5)
- REFERENCE SD-SO23-120 REV. O PAGE 89 QUESTION 2.09 What are the two (2) purposes of the small bypass flow path around the spray control valves? (1.0)
- ANSWER
- 1. To minimize thermal shock by (keeping spray lines relatively hot and spray nozzles relatively cold. (0.5)
- 2. Circulate PZR water with RCS to maintain uniform chemistry.
(0.5)
- REFERENCE SD-SO23-360 page 69, and RCS PLID. The reference material did not clearly indicate flow path for the bypass flow, the examiner f eels this is an oversight.
r GUESTION 2.10 Technical Specification Bases B3/4 5-2 through 5-3 establish three limits for the Refueling Water Tank minimum volume and boron concentration.
- a. What is the purpose for maintaining minimum volume in the Refueling Water Storage Tank? (1.0)
- b. What is the purpose for maintaining minimum boron concentration? (1.5)
- ANSWER
- a. To ensure that sufficient water is available within the containment to permit recirculation cooling flow to the core in the event of a LOCA. (1.0)
- b. To ensure that the reactor will remain subcritical (in the cold condition following mixing of the RWST and the RCS water volumes) following a LOCA (with all control rods inserted, except for the most reactive control assembly.)-
(1.5)
.
- REFERENCE Technical Specifications, B 3/4 5-2 through 5-3 SD-SO23-740 QUESTION 2.11 A small, but not insignificant, amount of flow in the Reactor Coolant Systen bypasses the Reactor Core.
- a. What is the most significant of the bypass flow paths?
(0.5)
- b. What are four (4) of the six other flow paths that bypass the core? (1.0)
- ANSWER ,
- a. Through outlet nozzle clearances.
- b. 1. Alignment keyways
- 2. Support cylinder holes
- 3. Core shroud clearances
- 4. Empty guide tubes
- 5. Rodded guide tubes
- 6. Instrumented guide tubes (any 4 0 0.25 each)
- REFERENCE SD-SO23-360 page 100.
r 1
QUESTION 2.12 l What are the two purposes of the Excess Flow Check Valve in the l Instrument Air System? (2.0)
- ANSWER Two primary purposes are:
1 Prevent overpressurization of the Containment during a LOCA or MSLB inside contaiment if an Instrument Air line broke in conjunction with the event. (1.0)
Prevent excessive flow demand from depressurizing the entire Instrument Air System if a line broke in the Containment.
(1.0)
- REFERENCE SD-SO23-570 page 15.
QUESTION 2.13 What flow path is provided to ensure that Salt Water Cooling flow can be maintained to the Component Cooling Water heat exchangers in the event the outfall for Unit 2 becomes blocked? (2.0)
- ANSWER The Emergency Discharge Line can be used, from the outlet of CCW heat exchangers (EOO1 and EOO2) [1.03 through valves (HV6496 and HV6494) to the overflow at the seawall E1.03. (2.0)
- REFERENCE SD-SO23-410 page 16, and 19. .
QUESTION 2.14 The Fire Protection System utilizes several different kinds of active suppression sub-systems. These include wet pipe sprinklers, pre-action sprinklers, carbon dioxide deluge systems, and Halon systems.
- a. What type of system is utilized for fire suppression around the Main Turbine-Generator bearings? (0.5)
- b. What type of system is utilized for fire suppression around the Emergency Diesel Generators? (0.5)
- c. How does Halon suppress combustion? (1.0)
- ANSWER
- a. Carbon dioxide (0.5)
- b. Pre-action sprinklers (0.5)
- c. By smothering (excluding oxygen) and by interfering with the combustion process directly. (1.0)
- REFERENCE SD-SO23-590'page 37, and table 5.
End of Section 2 Go on to Section 3 e
/ I SECTION 3 Instruments and Controls QUESTION 3.01 Regarding the Steam Bypass Control System (SBCS):
- a. What happens to the Steam Bypass Control Valves when the Emergency Off pushbutton is depressed? (1.0)
- b. What is the purpose of the 60 psia margin in the Master Steam Header Setpoint Program (60 psia > normal steam pressure)? (0.5)
- c. The steam flow signals to the Main Calculator are processed through a " Lag Circuit" prior to being sent
- to the steam pressure versus steam flow program. What two purposes does this " Lag Circuit" serve? (1.5)
- ANSWER
- a. All of the valves that are open[ fast close 4TII econds) and
. prevents the re-opening of the valves. ( L O)
- b. To provide a deadband to allow minor purturbations to occur without requiring GBCS operation. (0.5)
- c. 1. Allows the SBCS time to react more quickly to a load rejection than if the actuation setpoint kept getting higher as load was being rejected. (1.0)
- 2. The circuit fliters out high frequency noise that accompanies flow signals. (0.5)
- REFERENCE .
SBCS System Description.
QUESTION 3.02 Fouling of the surface of the throat of the Feedwater Venturi commonly occurs during extended operation. What will be the effect on indicated feedwater flowrate with respect to actual flowrate? (1.0)
- ANSWER The effective inside diameter (from increased friction and actual narrowing) of the throat will be decreased, this will raise the differential pressure being measured, and thereby give a higher than than actual flowrate indication. (1.0)
- REFERENCE General Physics. Plant experience with venturi fouling.
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GUESTION 3.03 What are the five (5) parameters that COLSS can display in the Control Room? (2.5)
- ANSWER C##')
- 1. Core power operating limit, based on peak linear heat rate.b'"#'## pYl
- 2. Core power operating limit based on margin to DNB. (~4pwS po4)
- 3. Total core power.
- 4. Margin between core power and the nearest core power operating limit (" digital margin meter").
- 5. Axial Shape Index ASI. (5 at 0.5 each)
- REFERENCE Plant Com re -ros] puter
- +'7 System description, 0 , p or is GUESTION 3.04 Regarding the Safety Channel Excore Instrumentation:
- a. For what event is the HI LOG POWER trip provided? (0.5)
- b. What is the trip setpoint for the HI LOG POWER trip
. (0,5)
- c. The linear channel of the Safety Channels is converted to a " Raw Linear Power" signal for use by the Core Protection Calculators. What is this signal used for by the Core Protection Calculators? (1.0)
- ANSWER
- a. This trip provides protection for a reactivity excursion at the end of core life with the plant shutdown or at low power. (Will accept Main Steam Line Break at EOC as answer.) (0.5)
- b. 0.89 % power (0.5)
- c. The Raw Linear Power signal is compared to the CPC's calculated Excore Power. This comparison will generate a Linear Power deviation Signal if any channel deviates more than 5%. ( 1. 0 ) A i r e s ur'r (Seco re- Desjstsuo W O ,,,se,y ,,,n)'
- REFERENCE
. SD-SO23-470 pages 11, 12.
7 0 - 10 2 3 - 7/ d , pser 17 l
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QUESTION 3.05 The following Reactor Trip Breakers are opened manually:
- TCB-5
- TCB-6
- TCB-7
- TCB-8
- TCB-9 Why would this not affect the the Control Element Drive Mechanism Control System (CEDMCS)? EXPLAIN! (2.0)
- ANSWER The five breakers provide only two of the four sources of power to the main power buss bars. With only one source to each of the buss bars affected (1.0), no power will be lost to CEDMCS thus the rods would not trip and all CEDMCS would be operable (1.0).
- REFERENCE SD-SO23-510 page 53.
QUESTION 3.06 Diesel Fuel Oil Storage tanks are afforded level ins mentation. Three level switches are provided for inform 'on and protective features. For each of the f lowing setpoints, hat are the indications both locally ( the tank) and remotely 'n the Control Room)? (1.5)
- a. 11 ft. n. (0.5)
- b. 9 ft. 10 in. 5) -
- c. 6 in. (0.5)
- ANSWER
- a. Diesel Fuel T,pn' HI/LO - CR o g25)
Main Fuel ank HI - LOCAL (O..
- b. Diesel el Tank HI/LO - CR (0.25)
Maip uel Tank LO - LOCAL (0.25)
- c. Ddesel Fuel Tank HI/LO - CR (0.25)
,f/ Main Fuel Tank LOLO - LOCAL (0.25)
- REFERENCE .
f t I _'SD-SO23-750 page 63.
.i
QUESTION 3.07 The operability of the main steam isolation valves ensures that no more.than one steam generator will blow down in the event of a steam line rupture. What are the two reasons for limiting the effect of a steam line rupture to the blow down of one steam generator? (2.0)
- ANSWER
- 1. Minimi:e the positive reactivity effects of t5e RCS cooldown associated with the blowdown. (1.0)
- 2. And limit the pressure rise within the containment in the event that the eupture occurs inside the containment. (1.0)
- REFERENCE Technical Specifications B 3/4 7-3 SD-9023-160 QUESTION 3.08 Concerning EXCORE instrumentation Safety Channels A,B,C,and D:
(a) The TROUBLE BISTABLE for each Safety Channel is initiated by ,
. a Loss of Drawer Low Voltage. What are three (3) of the four other conditions that will trip this TROUBLE BISTABLE?
(1.0, 0.33 pts. each)
(b) Why may each drawer Trouble Light NOT come on upon an associated Loss of Drawer Low Voltage? (1.0)
- ANSWER (a) (1.0, 0.33 pts. each for any three)
(1) calibration switch out of OPERATE (2) trip test switch out of OFF (3) removal of any circuit card (will accept " pulled card / channel")
(4) l'oss of detector HIGH voltage (b) (1.0)
The drawer trouble light may not come on upon a loss of drawer LOW voltage since drawer low voltage supplies power to the TROUBLE LIGHT.
- REFERENCE.
SD-SO23-470
QUESTION 3.09 The particular combination of credible input parameters into the CPC's is known as the CPC " Operating Space". Any input that falls outside its associated specified range gives DNBR and Local Power Density channel trips. Two of these input parameters are:
(1) No core protection calculator failure, and (2) Quality Margin < 0 .
What are four (4) of the five remaining credible input parameters that define the normal CPC operating space (specify the range for each stated parameter) 7 (2.5 , 0.625 each)
- ANSWER (2.5, 0.625 pts. each for 4)
(a) 1825 psia < pressure < 2375 psia (b) 495 deg.F < Tc < 580 deg.F (c) >2 RCPs running (d) 1.28 < Radial Peaking Factor < 4.28 (e) .5 < Axial Shape Index < +.5
- REFERENCE SD-SO23-710 Technical Specifications OUESTION 3.10 A Reactor Coolant Pump (RCP) shaft shearing, causes a low flow condition that could cause a DNBR or Local Power Density safety limit violation. What condition initiates the trip? (1.0)
- ANSWER When delta P across primary side of either S/G goes below a variable setpoint. (1.0)
- REFERENCE Technical Specifications SD-SO23-710 1
e
f QUESTION 3.11 The Toxic Gas Isolation System automatically terminates the supply of outside air when a toxic hazard is detected. What are the three gasses the system is designed to detect? (1.5)
- ANSWER
- 1. Chlorine (0.5)
- 2. Ammonia (0.5)
- 3. Butane / Propane (fuel gasses) (0.5)
- REFERENCE SD-SO23-720 page 29.
QUESTION 3.12 Unit 2 has just recieved a Safety Injection Actuation Signal (SIAS). Would this actuation affect any system that is associated with Unit 3 or common to both units? (1.0)
- ANSWER Yes, Control Room Isolation Signal is actuated from an input from both units from a SIAS (1.0).
- REFERENCE
. SD-SO23-720 QUESTION 3.13 Several Reactor Protection System trips are provided for events not associated with the Design Basis Accident. These include High Seismic Acceleration, Loss of Load, and High Steam Generator Level.
- a. Where are +ra triaxial accelerometers for the detection of seismic events located? (0.5)
- b. The Loss of Load trip would normally occur if the Main Turbine tripped when power is greater than 55%. What condition would require the setpoint to be reduced?
(1.0) ,
- c. What is the setpoint for the High Steam Generator Level trip? (0.5)
- ANSWER
- a. In the tendon gallerys of the containments. (0.5)
- b. If the operable number of Steam Bypass valves were reduced ,
from normal. (1.0)
- c. 90% wede range. (0.5)
- REFERENCE fi2"f" SD-SO23-710 pages 15, 16, 18.
S 0 - 702 3 - sco , ts a c s t a
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QUESTION 3.14 Pressuricer level transmitter LT-110X fails low (OX level). What would happen to the Pressurizer heaters (non 1E and 1E) if the Heater Cutoff Channel Selector switch had been 1 set to "Y" (LT-110Y) before the event occured? (1.0)
- ANSWER The non 1E heaters would be the only ones still energized. (1.0)
(The 1E heaters cutoff at 27% from either channel from separate bistables. If the channel selector is taken to Y before the event the non IE will still be energized.)
- REFERENCE Reactor Coolant System SD, Pressurizer Level Control System End of Section 3 Go on to Section 3 4 .
o a
f SECTION 4 Procedures - Normal, Abnormal, Emergency, and Radiological Control QUESTION 4.01 While operating in accordance with Operating Instruction 5023-5-1.3 " Plant Startup from Cold Shutdown to Hot Standby":
- a. Why is there a precaution that would preclude the starting of a Reactor Coolant Pump with Pressurizer level less than 33% and the RCS is 25 deg. F cooler than the Steam Generators? (1.0)
- b. The plant is in MODE 5 with Shutdown Cooling Train 'A' running, and Shutdown Cooling Train 'B' out of service, what additional prerequisite of the procedure must be met with the plant in this condition? (1.0)
- ANSWER
- a. Analysis shows that the LTOP setpoint can be challenged with
, a difference in temperature of (20 deg. F) regardless of the size of the pressurizer bubble. (1.0)
- b. The secondary side of the S/G's shall be greater than 50%
wide range (to provide an adequate heat sink). (1.0)
- REFERENCE SO23-5-1.4 pages 9 and 10.
~
QUESTION 4.02 The Reactor is at 55% of full power after just having been shutdown for the past two weeks for a repair of the Main Generator. The plant is to be brought to full power as soon as praticable. What is the MINIMUM time it will take to get to 100%
power using the Maximum Core Power Escalation Rate for these conditions. (1.0)
- ANSWER 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 15 minutes. (1.0) This is the Maximum Core Power Escalation Rate (20% per hour) allowed from these conditions.
^ " k " 0 )3
- REFERENCE (nr sun"re' vn 6 2#-1#% M " "*"" M # M m' SO23-5-1.7 page 25 " Maximum Core Power Escalation Rate" Attachment 1 j' 0 2 J - r - /. 7 , M Gr s 3 s
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5 DUESTION 4.03
( ,W hat are the Administrative exposure limits set by procedure
'SO123-VII-4.0 " Personnel Monitoring Program" for the following areas?
- a. Quarterly Whole Body (0.5) b.-Quarterly Extremity (0.5)
- c. Quarterly Skin (0.5)
- d. Annual Whole Body (0.5)
- ANSWER
- a. 900 mrem (0.5)
- b. 4700 mrem (0.5)
- c. 3750 mrem (0.5)
- d. 2500 mrem (0.5)
- REFERENCE SO123-VII-4.0 page 7.
QUESTION 4.04 Concerning Radiation Exposure Permits (REPS):
- a. What REP expires in one month and is issued to cover routine or repetitive work with low hazards? (0.5)
- 6. What REP is issued to cover performance of-assigned duties for HP or other groups and expires after three months? '(0.5)
- ANSWER
- a. Extended REP (0.5)
- b. Blanket REP (0.5)
- REFERENCE 4 SO123-VII-9.9 pages 11, 12, 13.
QUESTION'4.05 Regarding the Containment Purge System:
i
- a. When' running the Mini-Purge Exhaust unit why must the Supply Unit also be running? (1.0)
- b. Whet action is required if RT-7828 becomes inoperable during the purge? (1.0) -
- ANSWER
- a. TheminimumContainmentpressure(of-0.3psig)couldbe violated. (1.0)
- b. Containment purge must be stopped immediately. (1.0)
- REFERENCE
- SO23-1-4.2 page 4
QUESTION 4.06~
After a Reactor Trip has occured~you are proceeding through the Standard Post Trip Actions in SO23-12-1. In step 7 you determine that all the RCP's have stopped. What are the four parameters that are monitored to determine that Natural Circulation is occuring? (3.0)
- ANSWER
- 1. Operating loop delta T less than 58 deg. F. (0.75)
- 2. T and T are not rising. (0.75)
- 4. Reactor Vessel level greater than 82%. (0.75)
- REFERENCE SO23-12-1 PAGE 6.
QUESTION 4.07 During a Loss of All AC Power (Station Blackout) the 125 VAC Vital Busces have to have certain selected loads removed.
. a. What is the primary reason for reducing the loading on the 120 VAC Vital busses? (1.0)
- b. Prior to the de-energi:ation of the selected loads the following 480 VAC Breakers are opened.
- 1. BE 29 to HV-9367 Cont. Spray Header #1 Isa. Valve
- 2. BE 24 to HV-9303 Cont. Emer. Sump outlet valve
- 3. BE 35 to HV-9305 Cont. Emer. Sump outlet valve-
- 4. BJ 25 to HV-9368 Cont. Spray Header #2 Iso. Valve
- 5. BJ 33 to HV-9302 Cont. Emer. Sump outlet valve
- 6. BJ 34 to HV-9304 Cent. Emer. Sump outlet valve Why are these breakers opened prior to removing the loads selected for reducing loading on the 125 VAC I busses? (1.0) ,
I
- ANSWER
- a. This is r$qu' red to ensure adequate instrumentation is !
availloida F< monitor natural circulation if the blackout i lasts ch g+ .- a n (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />). (1.O)Al>'OA"<F 6* e W M '# N y rrexy sawrx I
- b. This is to ensure that an inadvertcnt CSAS or RAS does not occur with the return to' power. (All ESFAS Aux Relay cabinets for Train B will generate all ESF actuation signals when the loads are de-energized). (1.0)
- REFERENCE" SO23-13-1 page 15.
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l QUESTION 4.08 What six (6) conditions or events require that Eniergency Boration be initiated immediately? (3.0)
- ANSWER
- 1. Failure of 2 or more CEAs to drop following a Reactor trip.
(0.5)
- 2. One or'more regulating groups below PDIL. (0.5)
- 3. Shutdown Margin is determined to be < 5.44% Delta K/K when T is > 200 F. (0.5) //
ave
- 4. Shutdown Margin is determ'ined to be ,<3% Delta K/K when T,y, is < 200 F. (0.5)
- 5. Uncontrolled cooldown of the RCS with T ,
> 25 F below T ,j , (caused by excessive feedwater addition or excessive steam withdrawal.) (0.5)
- 6. During refueling with K,ff > O.95 or baron concentration
. less than (1720 ppm). (0.5)
- REFERENCE SO23-13-11 page 2.
QUESTION 4.09 During the conduct of a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> surveillance on the Safety Injection Tanks at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> March 31 you determine that the last surveillance done was at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> this morning March 31.
The surveillance performed prior to that time was at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> .
the evening of March 30. When will the NEXT surveillance be due,if you perform the surveillance now (2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />)7 (2.0)
- ANSWER 1800 to 0900 = 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> 0900 to 2300 = 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> The next surveillance would be performed at 3.25 X 12 = 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> per the Technical Specifications (1.0) from the 1800 surveillance, or 0900 M ;;. 16 (1.0).
- REFERENCE d '# #
Technical Specifications definitions
, s
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i l
QUESTION 4.10 Regarding valve operations:-
- a. When checking a manual valve's position, it must always
-be operated in what direction? (0.5)
- 6. Why must a normally closed Motor Operated Valve be declared inoperable when it is manually backseated?
(1.0)
- ANSWER
- a. In the closed direction. (0.5)
- b. The torque to come off the backseat may be more than the torque switch setting. (1.0)
- REFERENCE S0123-0-23.1 pages 2,3,4.
QUESTION 4.11 You are filling the position of Unit Control Operator 21. What are the boundaries of the area you required to be in whe'n_you are "at the controls" per S0123-0-30 ?-(1.0)
- ANSWER He must be in either area A or area B as defined in procedure-S0123-0-30. Area A is that area directly covered by the panels for Unit 2, area B includes the common area between the units' separate panels (1.0).
- REFERENCE S0123-0-30 page 14. ,
OUESTION 4.12 During operation in MODE 5 the Reactor Coolant System is drained-down to mid loop to enable entry into the primary side of the Steam Generators. The running Low Pressure Safety Injection pump loses flow. If the loss of flow is due to inadvertent lowering of the level or loss of SDC inventory:
- a. How, per procedure 5023-13-15 " Loss of Shutdown Cooling", is a gravity fill from the RWST aligned quickly to recover the level? (1.0)
- b. Why, per the Loss of Shutdown Cooling procedure, would it be inadvisable to start the other LPSI pump to restablish Shutdown Cooling? (1.0)
- ANSWER
- a. The integral bypass valve on a LPSI pump suction can be opened to allow gravity fill of the RCS. (1.0)
- b. It also may experience loss of flow (due to air binding). l (1.0)
- REFERENCE _~~
SO23-13-15 pages 3, 4, 5.
l
1 f~
QUESTION 4.13 Regarding the Reactor Coolant Pump starting operations:
- a. Precaution 4.4 of Procedure SO23-3-1.7 " Reactor Coolant Pump Operation" states that the fourth RCP should not be started until the RCS temperature is greater than 500 F. What is the reason for this precaution? (1.0)
- b. A RCP is sitting at rest, warm, at normal operating temperature having just been tripped after running for one hour. When may the pump be restreted? (0.5)
- ANSWER
- a. The potential exists for core uplift at lower temperatures, this precludes that possibility. (1.0)
- b. Immediately.(0.5) (With the motor running for 60 minutes an immediate consecutive start can be done.)
- REFERENCE SO23-3-1.7 pages 3, and 4.
QUESTION 4.14
, It is necessary to initiate Auxiliary Spray in MODE 3 with the RCS pressure at 500 psig. Why would the Technical Specifications require that the Charging System be declared INOPERABLE 7 (1.0)
- ANSWER The Charging System has to be valved out to allow Auxiliary Spray to be used making the charging flow path unusable. (1.0)
- REFERENCE .
SO23-3-1.10 pages 3, 8, and 9.
End of Section 4 End of Examination l
.? ~
^
79,, c i: , i . s.m n .5
. . pu s r c.r: F.y m s.e w.eior.
ES-302-3 SIMULATOR SCENARIO FORM Facility / Simulator: SONGS 2,3 Scenario No. IA
!*. * *a .
Examiners: Meadows Candidates: -
Defferding Upton Event No. Time Malf. No. Description
.s, ., a .r/ ,-
1 0 IC14 100% power Xe-equil -Bet. tife ppm
- [ ,,. . Need to lower power to 50%--maintenance on one e ",
feed pump.
< 2 10-15 CWO5 Loss of one circ. water pump (use CWO1 if 05 r uW ...-)
(f,i '~ can't be used).
-p*
'h' 3 20 N108 See if linear-middle detector can be failed.
~ '
If not, use N108. 6 2 ' '- ~'"' ' ' '
./
r**-
- d P ..
W 4 25 FWO9 Hi vib--MFW pump send A0--very bad FW21 Trip one pump for vib: second pump discharge V
valve closes FWO2 M-AFW seizure
-t<.' .,-
( /
(. , T-AFW overspeed (resettable) f fe M f 9 ff (cP 1
. I
ES-302-5 i
I
~
SIMULATOR ADMINISTRATION FORM
- Scenario No. IA Event No. 1 Page 1 of 4
'Brief
Description:
IC14--100% power - BOL - Xe equil Boron 1170^* lower power to 50% maintenance on feedwater pump.
Plant Conditions Position Candidate Actions / Behavior 100% ACO Prepare for power reduction Establish communication with CRS & C0 on rate and any coordination needed CO Calculate boron addition i Establish rate of reduction with CRS and ACO l (rate not to exceed 11 MWe/ min) i i
CRS Notify dispatch and chemistry of power reduction CRS or designee follow operatino procedure 5023-5-1.4 6"M- .~~ , -
. )
i i
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i
'ES-302-5 SIMULATOR ADMINISTRATION FORM -
Scenario No. IA Event No. 2 Page 2 of 4
' ~ ~
Brief
Description:
Loss of one circ water pump -
Plant Conditions Position Candidate Actions / Behavior
~90% ACO Identify problem Watch condenser vac May need to lower load to keep cond vac in limits C0 May have to borate a little faster to keep rod within limits CRS Work with CO & AC0 to stablize plant (if load from event has been reduced significantly, condenser vac may hold)
)
i
+ . l i
ES-302-5 I SIMULATOR ADMINISTRATION FORM .
.I l
.- I Scenario No. IA Event No. 3 Page 3 of 4 .
l 3...
n.tef
Description:
NIO8 - (try to fail linear channel midrange'dttector (50%) which affect linear and log range)
- - if not possible, linear amp failure CH2 mid j detector Plant Conditions Position Candidate Actions / Behavior (90% C0 Detemine problem--Note both linear and loa readings off 1
i CRS Aid CO to diaanose problem
! Identify Tech Spec actions I Bypass 100, DNBR, linear power level, local power 1 dens 1ty re w rm r: 3/v. y s, ,- r...~.-r w "
i l
I
. . ~ . , , . _ _ , . _ . . ~ _ . _ . _ _ . . . . _ . _ , _ _ _ _ , , _ . . . _ . . , . , _ . . - . . _ - - , _ - _ _ __ .- . _ - . , , _ . . _ . - . ~ . . ~ . , - , . - , . . . _ . ._.-- _ _ _ . . . - _ - _ _ _ _
ES-302-5 SIMULATOR ADMINISTRATION FORM ,
Scenario No. IA Event No. 4 Page :4 .of. 4
. r. . -
Brief
Description:
FWO9 Hi vib Feedwater pump >3 (5 mils il pump FW21 Feed pump discharge valve closes on No. 2 pump (after shutdown of #1)
FWO2 M-AFW seizure T-AFW trips overspeed (locally reset ok)
Plant Conditions Position Candidate Actions / Behavior
~80% ACO Note alarm - inform CRS Send PE0 to check PE0 informs bad vib CRS He may request quick load reduction to 60% then trip pump. The second FW pump trips and No Aux feed available until a PE0 resets overspeed.
reor 'r)
Enter 5023-12-1 posttrip. Diagnose--LOFW--Go to S023-12-6 LOFW--send PE0 to reset overspeed.
Evaluate per emergency plan. [E& f : fr,c rr y:I.. )
~
SIMULATOR SCENARIO FORM
. Facility / Simulator: SONGS 2,3 Scenario No. IB , , ,
" ~
Examiners: Meadows Candidates:
Defferding Upton Event No. Time Malf. No. Description xn 610
, . g< ' ' 1 0 IC13 50% Bet M7+ ppm boron Xe-equil y
(maintenance complete) ready to increase power cra a - - - ~ /- sa, u a, o u 6' 2 10-15 SG04 SG level control Instruments drifts Hi F,,
P ',,e 8 c,,,-sa cv:';
e r
l ','
3 15-20 CV05 Nonregen. Hx leak (if not possible, use GVM)c, "
leak in letdown line isolatable 9 fffJ,.5.TM17.1 r
,1. [/w-no a.- e < o < < s n - e s .- + n .- - - .'. n)
'" 4 25 SG02 S/G tube leak 5 apm--300 - 10 min
.r
_g
,, . 'e ) MS01 = . . . . , .
^"
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+- =
W_._m
~ , -
_m . + - _ - - -
m-- --. _ _ _ .
I.
ES-302-5~.
SIMULATOR ADMINISTRATION FORM 4
Scenario No. IB Event No. 1 Page 1 of 4 IC13 _50% power BOL Boron 1224--Xe Equil ' I" Y ~
Brief
Description:
j Maintenance complete-2nd FW pump not running but preparation complete Plant Conditions Position Candidate Actions / Behavior i
50% ACO Use procedure to start FW pump and prepare for power increase. (S~ #2 T *- * ~ f, F W LC 9 s'9 2 1 .' -l rk ' O i
.i I
j CO Calculate dilution, establish rate of power increase with ACO and CRS.
A d
9 i
j CRS Review procedure for power increase. Make notifications to dispatch etc. (h-v4 Cen--, O'z 7-r-/. h i
i 4 ,
I l
4 I
l
ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 1B Event No. 2 Page 2 of 4
~
Brief
Description:
SG04 S/G level instrument drifts Hi, feedflo - I' reduces, level starts dropping Plant Conditions Position Candidate Actions / Behavior 50-60% ACO Note S/G level change or respond to alarm S/G #1 Hilo (5023-5-2-16, ARP). Take manual control of FWCS and manually control level.
CRS Aid ACO to diagnose problem. He may reduce rate of power increase so S/G level control can be 1 maintained. (r e z 1 - r - 2 ~ ' t , s ^* /' )
i a
D ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. IB Event No. 3 Page 3 of 4
~
Brief
Description:
Leak in nonregen Hx into CCW. Surge tank leve WIl'1 increase. Rad monitor will increase. Mismatch charge letdown or CV05 leakin letdown line.
Plant Conditions Position Candidate Actions / Behavior
~60% CO Will note letdown - charge mismatch. Radiation monitor will increase output.
Diagnose problem, isolate letdown.
t i
CRS Aid in diagnosis. Classify leak for Tech Specs.
O n.v.s as w~~r) 1 l
- _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ . , ,_r. _ , , . . - _
ES-302-5 SIMULATOR ADMINISTRATION FORM
, Scenario No. 1B Event No. 4 Page 4__ of 4 Brief
Description:
SG02SG+leakrampinginrupture5-300gpmi mid ~
MS01 safety opens 10% - 5 min into event Plant Conditions Position Candidate Actions / Behavior
~60-70% ACO Respond to alarms (cond air eject or blowdown) il Note feedflow changes (when leak increases).
Reduce power when requested.
CRS Will probably start plant down at fairly high rate. Make notifications.
i
., C0 Start boration for power reduction. Sta'rt added
- charge pumps as needed.
i
~~
/: ~
CRS Enter S023-13-14-RCS leak after trip S023-12-1/Ir p' '
< -l then S023-12-4.( re r . t Ne* )
Classify event per emergency plan. ($~c2 3 -/271 - / )
i l
ES-302-3 SIMULATOR SCENARIO FORM -
Facility / Simulator: SONGS 2,3 Scenario No. 1C
.s... "'
Examiners: Meadows Candidates: '.i.
Defferding Upton Event ,
No. Time Mal f. No. Description p M[ 1 0 IC19 85% 530 ppm boron. Just came down from 100%
ya for a turbine valve test. Yalves failed.
Need to shut down to repair valves.
-> ~ rr sa ne e- ,,- - < x r e, .- c w . n :.: -
w r- en -s ,, y c c a ni~ c. .
U ,,/ I' 2 10 CV03 RCP middle seal fail. pump 2B yr .
e> * ,
f/*
.jr ,c ?,p ,, ,rve,.x an , m . . s , . a n . . . ,g. _, . . _ ,_. .
D , ( <' 3 15 FWM- Et well icvel suni..vl fei'; L= , , , .
8#
2 n . " , . c #'4 20 E001 LOSP EDG fail to start L37 ^'< '
}pe 5 EG08 Auto transfer fails 3 min after A0 send to EDG start Give them one DG
ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 1C Event No. 1 Page _1 of 4 Brief
Description:
IC19 MOL 85% pwr. 530 ppm boron Turbine valve test failed-shutting down for maintenance Plant Conditions Position Candidate Actions / Behavior h5% CO Calculate boron, establish rate with CRS & ACO.
ACO Prepare for power reduction. Coordinate with CO to maintain Tave-Tref.
CRS Review procedure 5023-5-1.4, check for special procedures at 60 and (50% power. Notify dispatch Notify chemistry. [ "" ~ # - ' ' ' W# ' " ' " ' ' '
f -
r ,,; ,. , i. y vi r~ s.~ < ~'
/> )l 1
l
5 ES-302-5 SIMULATOR ADMINISTRATION FORM -
Scenario No. 1C Event No. 2 Page 2 of 4
~
Brief
Description:
CV03 RCP middle seal fail pump 2B 7' AOI S023-13-6 Plant Conditions Position Candidate Actions / Behavior 2 CO Identify failed seal, notify CRS. Watch bearing temps.
Other indications CB0 temp above normal.
CB0 header press increasing PI 0215.
I CRS Review procedure. Note if 2nd seal fails start plant shut down. 3 seals immediate Rx trip.
(* s c 13 -- s :. - : , K .~ *
- un -:- )
l I
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- - - . . . ~ - , . .. - . . .
ES-302-5 SIMULATOR ADMINISTRATION FORM .
Scenario No. 1C Event No. 3 Page 3 of 4
?. . .
Brief
Description:
Hot well level control drifts Lo - Hot well Mvel; ^
FW16, will increase (ARP S023-5-2.18)
Plant Conditions Position Candidate Actions / Behavior
~70% ACO Note Hi/Lo level alarm. Hi level indication on LI 3245A & B. Notify CRS.
ACO Take manual control and make adjustment to brina hot well level back to normal (maintain level 50-75%). May have to manual open overboard valve.
CRS Note problem - look for cause (could be salt water leak into hot well or control problem)
(snn rozJ-r-2.st) 4
- e-um
,-- .-,7 . ,, -n. ,-.
l l
l ES-302-5 l SIMULATOR ADMINISTRATION FORM Scenario No. IC Event No. 4 Page 4 of 4 Brief
Description:
ED01 LOSP & auto transfer fails EG08 EDG fails to auto start Plant Conditions Position Candidate Actions / Behavior 50-65% C0 Respond to Rx trip alarm. Immediate action.
ACO Immediate actions - Rx trip.
CRS Procedures: S023-12-1 Rx Trip (A. o . n ) (*" '
- )
Also S023-13-1 LOSP [c ~<ert ~ ' ' - -
f Step 3.5.2.2--send PE0 to start EDG
ES-302-3 SIMULATOR SCENARIO FORM -
Facility / Simulator: SONGS 2,3 Scenario No. 2A Examiners: Meadows Candidates: - Y' Defferdina Upton Event No. Time Mal f. No. Description pet. .r' f 0 IC14 100% power. Xe-equil 80t. -tt70 ppm boron ggge 1
Power lowered 50% for maintenance
.,c'" 2 10 CWO5 Circ water pump failure
+'#7O2""/
< / r*
3 _ 15 NIO8 NI failure ,
s* s 4 4 9* *.- ',
(
r
,,<e 4 20 CV15 Hi AP purification filter
'e , .'s
,,,r# 5 25 FW15 Heater drain tank level failure Lo e i e " 6 30 FWO9 Hi vib MFW pump t' FW21 Operators trip Hi vib pump. Trip the 2nd pump
<ee>~ ^'^ FWO2 M-AFW seizure
,,,,,'f T-AFW overspeed (resettable) re.o -ik state 7~
ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 2A . Event No. -1 Page 1 of 6 4 Brief
Description:
IC14--100% power - BOL - Xe equil Boron 1170 2 ower power to 50% maintenance on feedwater pump Plant Conditions Position Candidate Actions / Behavior 100% ACO Prepare for power reduction Establish communication with CRS & CO on rate and any coordination needed 1
CO Calculate boron addition Establish rate of reduction with CRS and ACO (rate not to exceed 11 MWe/ min) !
=i CRS Notify dispatch and chemistry of power reduction CRS or designee follow operating procedure 502 3 - 5 ' . 4 0 > - ~ r IA' / ~ ~ ~ '- ~ '
l ww- - - -
1 ES-302-5 1 .
!' SIMULATOR ADMINISTRATION FORM i
! Scenario No. 2A Event No. 2 Page 2 of 6 i- ,.
3 Brief
Description:
Loss of one circ water pump i !
i Plant 4
Conditions Position Candidate Actions / Behavior j
~90% ACO Identify problem Watch condenser vac May need to lower load to keep cond vac in limits-i C0 May have to borate a little faster to keep rod
! within limits 1
e i
i i
j CRS Work with CO & ACO to stablize plant (if load j from event has been reduced significantly. -
condenser vac may hold) d ess ve r - - ve u, r to: .7 - s r - s o )
1 4 ,
i I j
i t I
- . - . - . ~ - . . - - , . . - - - - . - - - - . - . , - . . - , . . , . .
ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 2A Event No. 3 Page 3 of 6 Brief
Description:
NIO8 - (try to fail linear channel midrange detector (50%) which affect linear and log range)
- if not possible, linear amp failure CH2 mid 1
Plant Conditions Position Candidate Actions / Behavior (90% C0 Determine problem--Note both linear and log readinas off J
CRS Aid CO to diaanose problem Identify Tech Spec actions Bypass loa, DNBR, linear power level, local power density OrcN f, c c. .1//. r .rar~ m c+ whn) 1
, _ . . .-m -. . - _ . _ _ _ _ . _ ., _ _ _
ES-30?-5
~
SIMULATOR ADMINISTRATION FORM Scenario No. 2A Event No. 4 Page 4 of 6 Brief
Description:
CV15 purification filter Hi AP - slow ramp to"
50% in 10 min Plant Conditions Position Candidate Actions / Behavior
~80-85% C0 Respond to alarm - Hi AP purification filter.
Notify CRS.
f CRS Note problem. Have operator backwash filter, when clean return flow to normal. 6 ve r r/-A A" )
J I
_~ -_.- . . _ _
ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 2A Event No. 5 Page 5 of 6 Brief
Description:
FW15 Heater drain level lo normal +10% ' l' ~
Plant Conditions Position Candidate Actions / Behavior
~80% ACO Respond to alarm--notify CRS--take manual control diagnose problem.
CRS Aid ACO to diagnose problem. Ask for I&C help.
(<<ci i i. ., . i s u n/ Or)
r ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 2A Event No. 6 Page 6 of 6 Brief
Description:
FWO9 Hi vib Feedwater pump >3 (5 mils #1 pump -
FW21 Feed pump discharge valve closes on #2 pump (after shutdown of #1 pump)
FWO2 M-AFW seizure T-AFW trips overspeed (locally reset ok) 0 Plant Conditions Position Candidate Actions / Behavior
~80% ACO Note alam - inform CRS Send PE0 to check i PE0 infoms bad vib i
CRS He may request quick load reduction to 60% then trip pump. The second FW pump trips and No Aux feed available until a PE0 resets overspeed.
Enter S023-12-1 posttrip. Diagnose--LOFW--Go to S023-12-6 LOFW--send PE0 to reset overspeed.
1 Evaluate per emeraency plan.
l i
, , , . . . . - - , , , , , - . _ . . . - - - , - - . , . _, ,.,_.,c- - . , -, r, ., _ _ , , , , , . , . , , - . , -
ES-302-3 SIMULATOR SCENARIO FORM Facility / Simulator: SONGS 2,3 Scenario No. 2B Examiners: Meadows Candidates: - - -
Defferding Upton Event No. Time Malf. No. Description
- t cz o
.e,
1 0 IC13 50% Bet 4074' boron Xe-equil (maintenance complete, power up)
, ,. - r e' 4 - 2 10 SG04 S/G level instr. drifts Hi N "-/m + )
aswon j , .* ;. 3 15 CV05 "en, ega;, 'N 1;;k 'if :t ;;;;;ible, :e (M&)
we',[',s '
leak in letdown line-isolatable C '
s y-si-i= ~
/
,e p*
- " 4 20 RP03 Inadvertent CIAS
+ t
"#ni S 30 SG02 SG tube leak ramp 5--300 apm in 10 min 9 501 SC ::fet; L.ek 1G; i
r,<e--m-- - - - - - ----i- - e- r --a .m .y -- t
ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 2B Event No. 1 Page 1 of 5 Brief
Description:
IC13 50% power BOL Boron 1224--Xe Equil - -
Maintenance complete-2nd FW pump not running but preparation complete Plant Conditions Position Candidate Actions / Behavior 50% ACO Use procedure to start FW pump and prepare for
[r 0.: 7-; ~ 7ev - G- 2 -#
l power increase.
CO Calculate dilution, establish rate of power increase with ACO and CRS.
CRS Review procedure-power increase make notifications.
, Classify event. Cr-- - ..o .< a s s~ a ,r n ws* .J e A t ' '* l
... . ... _- ._ . . - - - ._ _ = . . . . - - -._ ._-
k ES-302-5 SIMULATOR ADMINISTRATION FORM i
Scenario No. 2B Event No. 2 Page 2 of 5
~
Brief
Description:
SG04 S/G level instrument drifts Hi, feedfloC -
reduces, level starts dropping l
I . Plant
], Conditions Position Candidate Actions / Behavior 50-60% ACO Note S/G level chanae or respond to alam S/G #1 Hilo (5023-5-2-16, ARP) . Take manual control of l
FWCS and manually control level.
l 4
d i
5
(
r CRS Aid ACO to diacnose problem. hemayreducerate of power increase so S/G level control can be
)
ma1ntained. (ro t 3 - v - f. ra. - . . v. . : u .
t s .
. 4
ES-302-5 i
t SIMULATOR ADMINISTRATION FORM ,
I Scenario No. 2B Event No. 3 Page 3 of 5
, Brief
Description:
Leak in nonregen Hx into CCW. SurgetankleN1 hill increase. Rad monitor will increase. Mismatch charge letdown or CV05 leakin letdown line.
Plant i Conditions Position Candidate Actions / Behavior
~60% CO Will note letdown - charae mismatch. Radiation j monitor will increase output.
e i
Diagnose problem, isolate letdown.
1 i _
CRS Aid in diagnosis. Classify leak per Tech Specs. j (vA, . ./. c /c c i : .: ~ u )
e 1
y . . _ _ , ..
_v, _-.-v-y,.-.,.c. , _ ,, , _ . _ , .,
l ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 2B Event No. 4 Page 4 of 5 Brief
Description:
RP03 Inadvertent CIAS (A) .+ l~ ~
Plant Conditions Position Candidate Actions / Behavior
~50% ACO Respond to alarm - notify CRS of CIAS - A Review boards for indications to determine if real or inadvertent Check to make sure valves operated as required (n.,. 7 .;y.i;-<? z. - n < r a ' > ' ' c.x s .c)
CRS Aid ACO to determine if CIAS is real or inadvertent. S023-13-17 step 3.1 trip Rx. Go to l l
S023-12-1. l l
1 l
l CO Proceed with immediate actions.
Qcn .s dr s-s3-sr r . - : - i ,,.r -',,.- ,-< o - *. ...
7 c:
. . * &. .)
l l
1
ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 2B Event No. 5 Page 5 of 5 Brief
Description:
SG02 SG + leak ramping in rupture 5-300 gpm 10 min i MS01 safety opens 10% - 5 min into event Plant Conditions Position Candidate Actions / Behavior
~60-70% ACO Respond to alams (cond air eject or blowdown)
Note feedflow changes (when leak increases).
Reduce power when requested.
CRS Will probably start plant down at fairly high rate. Make notifications.
C0 Start boration for power reduction. Start additional charge pumps as needed.
J CRS Enter 5023-13-14-RCS leak after trip 50bTI-1 1 A - ' -)
then5023-12-4.65- r-e e e d4- )
e,, * -- - " "- v
l ES-302-3
~
SIMULATOR SCENARIO FORM Facility / Simulator: SONGS 2,3 Scenario No. 2C Examiners: Meadows Candidates:
Defferdina Upton Event No. Time Half. No. Description
, ,- i 1 0 IC19 85% 530 ppm boron MOL
- Power just down from 100%
~, , ,,- f
Turbine valve test failed Need to shutdown for repairs r a' ' ' 2 10 CV03 _RCP middle seal fail pump 28 s a s <. s r m s rc w -
,. , , a s 9, ni a.e i e n.-
'*"' 3 15 FWMr et will iWvel u.ntic,1 f i h L: - -
i ~ f ' ' ' 4 20 NIO3 Safety channel failure--loa c' #" ' ' ' .5 r 25 ED01 LOSP j ,, , . , - F EG08 EDG fails to start [I ~~ o /e "< - )
Auto transfer fails 3 min after SRO send A0 to start DG--Give them one diesel l
ES-302-5 SIMULATOR ADMINISTRATION FORM E
Scenario No. 2C Event No. 1 Page 1 of 5 Brief
Description:
IC19 MOL 85% pwr. 530 ppm boron Turbine valve test failed-shutting down for maintenance l
Plant Conditions Position Candidate Actions / Behavior-85% CO Calculate boron, establish rate with CRS & ACO.
ACO Prepare for power reduction. Coordinate with C0 to maintain Tave-Tref.
CWV) l CRS Review procedure 5023-5-1.4, check for special j procedures at 60 and (50% power. Notify dispatch
]
Notify chemistry.
l i
i
ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 2C Event No. 2 Page 2 of 5 Brief
Description:
CV03 RCP middle seal fail pump'28 -
AOI S023-13-6 Plant Conditior,s Position Candidate Actions / Behavior 2 CO Identify failed seal, notify CRS. Watch bearing temps.
. Other indications C80 temp above nomal.
CB0 header press increasing PI 0215.
4 i
[Ad/ C* J / 7.; )
CRS Review procedure. Note if a 2nd seal fails, start plant shut down; if all 3 seals fail, immediately trip Rx.
t
.s l
ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 2C Event No. 3 Page ,3 of 5
.,..'~^
Brief
Description:
Hot well level control drifts Lo - Hot well level, FW16, will increase (ARP S023-5-2.18)
Plant Conditions Position Candidate Actions / Behavior
~70% ACO Note Hi/Lo level alarm. Hi level indication on LI 3245A & B. Notify CRS.
ACO Take manual control and make adjustment to bring hot well level back to nomal (maintain level ,
50-75%). May have to manual overboard.
l l
1 l
4 l 1
) CRS Note problem - look for cause (could be salt water leak into hot well or control problem) l
[ ,.s- c..c,c-:.is) l 4
4 1
ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 2C Event No. 4 Page 4 of 5
^ ~ -
Brief
Description:
NIO3 Log channel failure Plant Conditions Position Candidate Actions / Behavior
~60-65% CO Respond to alarm and note channel failure.
CRS Identify Tech Spec requirements (Table 3.3.1).
Have CO or ACO bypass channel.
l l
, - - - , _--m--, ,-e-, , . , _ _ - . - -
-r- -= w -<m , -
W-- - - - - - - - ,--e -- -
~
SIMULATOR ADMINISTRATION FORM Scenario No. 2C Event No. 5 Page .5 of 5 Brief
Description:
ED01 LOSP & auto transfer fails EG08 EDG fails to auto start Plant Conditions Position Candidate Actions / Behavior 50-65% CO Respond to Rx trip alarm. Immediate action, ACO Immediate actions - Rx trip.
j l
CRS Procedures: S023-12 Rx Trip Also 5023-13-1 LOSP Step 3.5.2.2--send PE0 to start EDG I
1 4
_ _ _ _ _ . -. _. ,, - . - . , , , , _ _ , ,, .4
April 2, 1987 ES-302-3 SIMULATOR SCENARIO FORM Facility / Simulator: SONGS 2,3 Scenario No. 3A
- 3. . .
Examiners: Meadows, RT Candidates: 's- 'I '
Defferding, LJ Upton, JW Jr.
Event No. Time Half. No. Description zu xe rr y to x<xc-z
/c sr e .L v~? . . ,, 7. vr y . .- ,.. 1 1 0 min ICF Core age =-80t; boron concentration =-4589 -
' ,, . e s ,
yp... ;---- ---i-( 10 'f- - ^' e; PZR pressure = 2250 psia; RCS Tava = 545*F CEA> o,c belew the Lung Ter= Ste:dy St:te in: Ort 4^n limit (Tech S;;cs). Unit 2 is returning to operation after a refueling outaqe. Unit 3 is shutdown for refueling.
System needs power ASAP. S023-5-1.3.1 has been completed through step 6.5. Blowdown rad monitor is out-of-service. All other ,
components / systems are operable. (CA.a << - -
,, , 7.s-?< . ,. a 7 . - e )
'"'r (* ' 2 10 min NIO1 A or B DC-power supply to either channel 1 or 2 '
1 Startup detector fails.
<~ 3 12 min RD06 Position indicator fails for CEA in Group 6 due to reed-switch failure.
April 2,1987 ES-302-3 SIMULATOR SCENARIO FORM (contd)
Scenario No. 3A (contd) ,,,
Event No. Time Half. No. Description
- ' ' Chemistry reports back that the RCS dose t.'- 4 10'I%
131 equivalent 1 is 1.8 sci /cc.
c e 5 18 min CV20 VCT outlet isolation valve fails closed; loss of charaina on low suction pressure to charaina pumps.
ys,i " 6 25 min MS03 Main steam line break inside containment.
.l 1
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1 April 2, 1987 ES-302-5 l SIMULATOR ADMINISTRATION FORM Scenario No. 3A Event No. 1 Page ;.1 of 6 Brief
Description:
Complete approach to critical Plant Conditions Position Candidate Actions / Behavior CFT IC9 4HL The SS will coordinate and direct actions to take the reactor critical. S023-5-1.3.1 should be used with checking of the procedure copy vs the control copy. Candidate should understand ASI control and CEA Insertion Limits. The candidate should check on any limitations caused by the rad. monitor failure.
co ffP The candidate should follow S023-5-1.3.1. He should change the reactivity and know how to determine when the reactor is critical.
/co
-4MMr The candidate should understand 5023-2-4, " Aux Feedwater System Operation" and S023-2-1, " Main Feedwater Pump Operation." He should assist as directed in the approach to critical.
April 2, 1987 ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 3A Event No. 2 Page 2 of 6 Loss of one channel of excore startup ' 'I' Brief
Description:
Plant Conditions Position Candidate Actions / Behavior
-4
~10 % PO, BOP The candidates should be responsive to the annunciator indication (50A47 or 57) and to the instrumentation indications. The startup channel indications should be compared with each other and with the safety channel indications of power level. The candidates should know how to obtain such information from the plant computer and the OSPDS.
SS The SS should confirm the instrument-failure diagnosis and see to it that I&C is requested to trouble shoot the problem. He should verify that he can continue into Mode 2. (LI V7 ~ -
-r5
April 2, 1987 ES-302-5 4
SIMULATOR ADMINISTRATION FORM i
Scenario No. 3A Event No. 3 Page y 3 _ ,
of 6
' ' ' ~
l, Brief
Description:
CEA position indication fails Plant
- Conditions Position Candidate Actions / Behavior PO, BOP The candidates will respond to the deviation alarm. Team coordination will be required to respond to the two instrument failures. The ,
event must be diaanosed as an instrument failure and not a stuck CEA.
4
) SS The SS must coordinate the control room response to the' situation. He must confirm the diagnosis of this failure. He must be aware of the actions he would need to carry out if the rod were stuck j
j and untrippable (shutdown margin). Tech Specs should be consulted on CEA indications.
l [ s o .- ; - i .] -s 3 s , n a..m <. o i t
( r. . . W*/ . s . w c ?' < 'r e-- J l
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April 2, 1987 ES-302-5 l
I SIMULATOR ADMINISTRATION FORM Scenario No. 3A Event No. 4 Page 4 of 6 Brief
Description:
Approach to the point of adding heat Plant Condit: Sns Position Candidate Actions / Behavior about 10-I% SS(~c) c The candidate should be monitorina the increase in power according to S023-5-1.3.1. The chemistry report will require that maximum chargina and letdown be initiated.
P06C d) The primary operator should perform the steps to increase charaina and letdown.
BOP [Jed The candidate should maintain board control while the PO is chancing the CVCS. S/G levels must be monitored and maintained. [r o z 3 / - / -
'l
April 2, 1987 ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 3A Event No. 5 Page 5 of 6 Brief
Description:
Loss of all charging pumps ~ '" T ~
Plant Conditions Position Candidate Actions / Behavior about 10-I% P0(co) With the closina of VCT outlet isolation valve, suction pressure to the chargina pumps will be lost.Mhecandidatemustdiagnosethesystem problem and promptly and accurately transmit the informationtotheSS)ThedecreaseinPZRlevel will result in the loss of letdown.
SO (Sco) The 50 must function to control S/G levels with the aux feedwater pump durina the transient.
SS (cefl The SS must confirm the diagnosts and act to correct the situation; i.e., to get the valve opened.
April 2, 1987 ES-302-5
~
SIMULATOR ADMINISTRATION FORM Scenario No. 3A Event No. 6 Page 6 of 6 Brief
Description:
Main steam line break inside containment Plant Conditions Position Candidate Actions / Behavior
~10-I% power BOP [eco) The candidate should note the blowdown of S/G #1 and report the fact that a trip will come on low S/G #1 level. He should note the containment parameters. Carry out SPTAs.
PO[bO-) The candidate should note and report the decreasing RCS pressure and temperature. Carry out SPTAs.
SSdbet) The candidate should provide a diagnosis of a main steam line break and enter the Emergency Operating Procedure 5023-12-5.
I
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l April 2,1987 ES-302-3 SIMULATOR SCENARIO FORM Facility / Simulator: SONGS 2,3 Scenario No. 3B ,, ,
- '~
Examiners: Meadows, RT Candidates:
Defferding, LJ Upton, JW Jr.
Event No. Time Malf. No. Description
,,,-,-i 1 0 min IC30 Core age = EOL; boron concentration = 50 ppm; reactor level = 100%; equilibrium zenon concentration, PZR pressure = 2250 psia; RCS Tava = 581 F. ASAP, decrease power to enable 2 circulating water pumps to be turned off.
r* '2 0 min CV11 MOV 2HV9247 seat erosion causes leak into RCS 100% and an extra increase in the boron concentration. [d/ - re ~ ' ' &~~ m 4~
ks y C ~ < * - a* rkr) 3 5 min CV16 The volume control tank level transmitter fails, indicating that the level is below the auto makeup demand level.
l 1
April 2,1987 ES-302-3 SIMULATOR SCENARIO FORM (contd)
Scenario No. 3B (contd)
Event No. Time Malf. No. Description
,,,... r ' 4 20 min CWO4A NE tube sheet is 37% plugged due to intake of ,
) 1 ,. ,. , n ,. -<- :L 50% trash. (&" - C vo r J /re- . u - ?. *
- r CWO4B NW tube sheet is likewise plugged (add CWO4C and D as necessary to result in a trip at t = 25 min).
,,a*
p
5 25 min FWO4 ,Feedwater piping is broken inside' containment FWO2B and downstream of check valves on S/G #1 P504 vill not start. '
-n , - - -
April 2,1987 ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 3B Event No. 1 Page 1 of 6 Brief
Description:
Decrease reactor power level,100% to 65% -
Plant Conditions Position Candidate Actions / Behavior 100%
(cPOoBOP no) The candidates should determine the amount of boration to make this maneuver: the plant data book should be used for the EOL conditions.
S023-5-1.7, Section 6.5, " Preparation for Power Descention," should be used.
(c PO0 ) The candidate should properly start the power-down by setting uD the CVCS for boration.
i (A c o) l SO The candidate should properly decrease the steam ;
flowrate to the turbine.
I
April 2,1987 ES-302-5
~
SIMULATOR ADMINISTRATION FORM Scenario No. 3B Event No. 1 (contd) Page 2.
of 6
"~
Brief
Description:
Plant Conditions Position Candidate Actions / Behavior
$S The candidate should determine (see Attachment 6 of S023-5-1.7) that the power level must be reduced to 65% and also use Attachment 5 to determine the maximum unloading rate.
l April 2, 1987 ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 3B Event No. 2 Page 3 of 6 Brief
Description:
Inadvertent boration Plant Conditions Position Candidate Actions / Behavior 100% power (P0,BOPco,s cThe o) additional boration will be at a rate of and less 10 Opm. Over the next 20 minutes or so, the operators will note a power decrease that exceeds what they expect.
(cer)
SS The shift supervisor should assist in trying to diagnose the malfunction.
~
April 2, 1987 ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 3B Event No. 3 Page 4 ,o f, 6 Brief
Description:
VCT level transmitter fails L0 Plant Conditions Position Candidate Actions / Behavior 90% power
('c o) The correct diagnosis is that transmitter P0 2LT0226 has failed afvina a low level indication.
This will produce alarms and automatic makeup.
(sco)
BOP The candidates should note the Tava/ Tref mismatch and continue to reduce the loads on the turbine accordina to the procedures.
(cnc)
SS The candidate should confirm the diaanosis and should continue to be concerned about the decrease in the power level.
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April 2, 1987 ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 3B Event No. 4 Page 5 of 6 Brief
Description:
Condenser tube sheet blockage Plant Conditions Position Candidate Actions / Behavior (ACC) 80% power B0P The candidate should note the increase in circulating water temperature. The circulating water flowrate will have decreased. The candidate should observe and report the loss of vacuum. The candidate should properly carry out his SPTAs.
(co)
P0 The candidate should carefully monitor his boards during the event and then properly carry out his SPTAs.
(ca)
SS The candidate should assist in the event diaanosis (increased ap across the water box).
He should instruct the team to reduce power and then to trip the plant.
April 2, 1987 ES-302-5
~
SIMULATOR ADMINISTRATION FORM Scenario No. 3B Event No. 5 Page 6 of 6 Brief
Description:
Feedwater pipe break, loss of P504 Plant Conditions Position Candidate Actions / Behavior
('A cc) The candidate should note the problem with S/G tripped BOP plant #1 and the fact that P504 will not start. He should ensure that the steam driven AFW pump is feeding S/G #1. S023-12-1, " Standard Post Trip Actions" should be followed.
("c o)
PO The candidate should monitor his boards and report to the SS on the primary parameters, especially Tc.
(exSSt) The SS should guide the team in response to the AFW problem and feedwater leak into containment.
He must diaanose the event and classify it properly. S023-12-6 should be entered, " Loss of Feedwater."
1 l
l April 2,1987 ES-302-3 ;
SIMULATOR SCENARIO FORM Facility / Simulator: SONGS 2,3 Scenario No. 3C - ,, .
Examiners: Meadows, RT Candidates:
Defferding, LJ Upton, JW Jr.
Event No. Time Malf. No. Description 3,,, . J 1 0 min IC28 Core age = EOL; boron concentration = 190 ppm; power level = 50%; equilibrium zenon concentration, PZR pressure = 2250 psia; RCS Tavo = 562'F. Increase power to 90% ASAP.
/ 2 10 min RD03 A Group 6 CEA drops into the core. RD03 is then removed: 1.e., the CEA is recoverable.
f*',
- ,,,- 3 15 min --
A bomb threat call comes into the control room--a lunch box next to the main generator, set to explode in 30 minutes. Cre , .- e - --
- -c w . cp ,..,c.
. .c . . . , .,
-)
,e ', r -
4 20 min RC03 RCS piping ruptures at SDC connection--initial leak = 50 apm and increases to 1000 apm.
,- 5 21 min EC08 HPSI pumps will not start due to faulty relay contacts. (a n r Z - ' 9 )
April 2,1987 ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 3C Event No. 1 Page 1 of 5 Brief
Description:
Increase power from 50% to 90%
i Plant Conditions Position Candidate Actions / Behavior (co, /COSRS 501 Dower P0, BOP, SS The candidate should prepare for power increase operations according to 5023-5-1.7, Sections 6.1 " Preparation for Power Ascension" 6.2 " Guidelines During Power Ascension" 6.3 " Power Ascension" L:&: 0)
P0 The candidate should make the proper calculations using the plant data book for the power change of 50% to 90%. 5023-3-2.2 provides the guidelines for the calculation of the deletion volume.
S023-3-2.1 on CVCS operation.
I (sco)
BOP The candidate should properly raise the power level of the T/G.
1
.= --
I j 1
1
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April 2, 1987 ~ ~
~
SIMULATOR ADMINISTRATION FORM
- r Scenario No. 3C Event No. 1 (contd). Page 2 o 5 Brief
Description:
Plant Conditions Position Candidate Actions / Behavior ,
[ car) The candidate should coordinate the power SS ascention, including the monitorina of ASI (see ctep 6.1.8).
i l
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April 2, 1987 ES-302-5 SIMULATOR ADMINISTRATION .;JA Scenario No. 3C Event No. 2 Page 3 of 5 Brief
Description:
Dropped CEA Plant Conditions Position Candidate Actions / Behavior 60% power (P0co) The candidate should note and report the dropped CEA. He should be alerted by alarms SOA 36, 50A 37, 50A 38, 56C 53, and 50A 02 and CEA bottom 11aht, lower electrical limit lamp, RSPT on the CRT and a CEAC point-ID indication.
O c.7)
BOP The candidate should monitor the secondary plant and control T/G power if necessary to respond to the pcrer change (2-4%).
(csr)
SS The candidate should assist in and confirm the diagnosis. He should instruct the P0 in recoverina the rod. See 5023-13-13. Tech Specs should be consulted on time limits to alian the CEAs.
April 2,1987 ES-302-5 SIMULATOR ADMINISTRATION FORM l
Scenario No. 3C Event No. 3 Page 4 ,f 5
) Brief
Description:
Bomb threat Plant-Conditions Position Candidate Actions / Behavior (co, no,cxS 60% power PO, BOP, SS Whoever takes the call should follow instructions to obtain as much information as possible from the caller.
i i
i' cstf l SS The SS must then determine the actions required ,
a by the Emergency Plan procedures. [re-nJ-ka7-h 4
1 6
s 4
L 4
- April 2, 1987 ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 3C Event No. 4,5 Page 5 of 5
'^~
Brief
Description:
LOCA with no HPSI pump capability Plant Conditions Position Candidate Actions / Behavior 60% and (car)
SS The candidate should assist in the diagnosis of tripped the event and then make correct use of LOCA Procedure S023-12-3, RCS Inventory procedure S023-12-10, and the Classification procedure 50123-VIII-1.
(co)
PO The candidate should note the drop in PZR pressure / increase in charging flow / charging letdown mismatch and clearly report to SS. The candidate should report that the leak becomes greater than the charging capacity.
(ca,/c.:>,c M)
P0, BOP, SS The candidates should properly carry out his SPTAs (S023-12-1)-P N rf " '# # # "" #
l April 3, 1987 ES-302-3 SIMULATOR SCENARIO FORM ,
Facility / Simulator: SONGS 2,3 Scenario No. 4A f-. ,
Examiners: Meadows, RT Candidates: stand-in as BOP Defferdina, LJ Upton, JW Jr.
Event No. Time Malf. No. Description i,sr '" 1 0 min - 109 Core aae = BOL: boron concentration = 1580 NIO2A ppm; power level ( 10~4% ; # = 0.96 Ak/k; PZR w ri. a t ', ,,
pressure = 2250 psia; RCS Tava = 545'F CEAs are below the Lona Tern Steady State Insertion Limit (Tech Specs). Unit 2 is returning to operation after a refueling outaae. Unit 3 is shutdown for refuelina.
System needs power ASAP. 5023-5-1.3.1 has been completed through step 6.5. Channel 1 excore safety is out-of-service and will be worked on. I&C has requested that the channel not be bypassed until they get to inspect it.
All other components / systems are operable.
I T' 2 10 min ED07 Loss of inverter occurs.
- , , ,. . . J ' ' ' 3 10-I% Chemistry reports back that the RCS dose equivalent I I3I is 1.8 sci /cc.
w- ,e - -
+--a -r -n,-- , , - - + <w ,m-,,-g-w,,,- veav n e r,---,---sav --,-m==- tw-v,--*<-*~ w-rw-wr , -~~~v +--~',w~~v-+ ~---v=-w - ,w -- me-~
1 i
i April 3,1987 ES-302-3
~
SIMULATOR SCENARIO FORM (contd) .
Scenario No. 4A (contd) f .. . __
I Event
, No. Time Malf. No. Description a
' c , ,,t F'it 4 12 min CV19 CVCS temperature control valve fails.
.i j NIO2B Loss of excore safety channel 2 occurs with no i
y " < r6 25 min MS03 Main steam line break inside containment iye; i
occurs.
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- - . - - - - . ~ - . _ , - - -
.1 April 3, 1987 ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 4A Event No. 1 Page 1 of 6 Brief
Description:
Complete approach to critical Plant Conditions Position Candidate Actions / Behavior (car) The SS will coordinate and direct actions to take IC9 SS the reactor critical. S023-5-1.3.1 should be used with checking of the procedure copy vs the control copy. Candidate should understand ASI control and CEA Insertion Limits. The candidate should check on any limitations caused by the loss of I channel of excore safeties.
c'C 0 )
P0 The candidate should follow S023-5-1.3.1. He should change the reactivity and know how to determine when the reactor is critical.
sco The candidate should understand S023-2-4, " Aux BOP Feedwater System Operation" and S023-2-1, " Main Feedwater Pump Operation." He should assist as directed in the approach to critical.
1
,, . . , - , . , ~ - . , , - - - . ,
, , . , , e-,--- - - - - -- - . - - , - - ,-
I l
April 3, 1987 ES-302-5 l
i SIMULATOR ADMINISTRATION FORM ,
Scenario No. 4A Event No. 2 Page 2 of 6 Brief
Description:
Loss of inverter I]',' - -
Plant Conditions Position Candidate Actions / Behavior
~10~4%
cPO, e 'sBOP e0 The candidates should be responsive to the annunciator indication and to the instrumentation indications. An alternate power supply should be selected to restore the AC power. The manual transfer switch should be used. .
(c a ) The SS should confirm the instrument-failure SS diaanosis and see to it that I&C is requested to trouble shoot the problem. He should verify that he can continue into Mode 2. C'# MV 1 )
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April 3, 1987 ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 4A Event No. 3 Page 3 of 6
~ '
Brief
Description:
Approach to the point of adding heat I' Plant Conditions Position Candidate Actions / Behavior
- '-]
about 10-1% l 'SS The candidate should be monitoring the increase in power according to 5023-5-1.3.1. The chemistry report will require that maximum charging and letdown be initiated.
(c o) The primary operator should perform the steps to PO increase charging and letdown.
(s e c )
BOP The candidate should maintain board control while .
the PO is changing the CVCS. S/G 1evels must be monitored and maintained.
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l April 3, 1987 ES-302-5 SIMULATOR ADMINISTRATION FORM l Scenario No. 4A Event No. 4 Page 4 'of 6 l
Brief
Description:
CVCS temperature control valve fails resulting ^ * -
in low temperature Plant Conditions Position Candidate Actions / Behavior
( '0 )
about 10-1% P0 The candidate should respond to the alarms and power the CVCS instrumentation. The candidate should be aware of the potential impact of a lower charaina temperature, includina the fact that the demineralizers will be more efficient in removing boron.
re r) The SS must coordinate the control room response SS to the situation. He must confirm the diaanosis of this failure and insure that maintenance has been contacted.
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f l April 3,1987 ES-302-5
~
SIMULATOR ADMINISTRATION FORM Scenario No. 4A Event No. 5 Page 5 of 6 t' .
Brief
Description:
High voltage power supply.is last to excore sifety channel 2--no response of RPS i
! Plant Conditions ~ Position Candidate Actions / Behavior CO ACO 4 about 10~I% P0. BOP The candidate should note the loss of a second channel and no trip.
i 4
1 i
e n.r SS The SS must confim the diagnosis and respond by
- manually tripping the plant.
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+
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- , . . . , _ - . - . _ _ _ , - - . . , _ - - ~ . . . - _ . _ , - - - . _ . . . _ . . ~ _ - ~ _ _ , . - _ , . - - . _ _ - - _ _ , . - - . , . - . - - - - - - - - .
April 3, 1987 ES-302-5 SIMULATOR AD"INISTRATION FORM '
l Scenario No. 4A Event No. 6 Page 6 ' of 6 i Brief
Description:
Main steam line break inside containment /."
Plant Conditions Position Candidate Actions / Behavior
~10-11 power Oco) The candidate should note the blowdown of S/G fl.
BOP He should note the containment parameters. He
! should correctly and promptly carry out his SPTAs.
(co) The candidate should note and report the PO decreasino RCS pressure and temperature. He should correctly and promptly carry out his SPTAs.
(orr.) SS The candidate should provide a diagnosis of a main steam line break and enter the Emergency Operatina Procedure 5023-12-5. He should i classify the event (s). He should respond to the failure of the RPS to trip the plant.
i
April 3,1987 ES-302-3 l
SIMULATOR SCENARIO FORM 4
Facility / Simulator: SONGS 2.3 Scenario No. 48 i Examiners: Meadows, RT Candidates: stand-in as PO -
Defferdino, LJ Upton, JW Jr.
Event No. Time Mal f. No. Description 0 min IC30 Core age = EOL; boron concentration = 50 ppm;
, , ,,,.. 1 p<
r reactor level = 100%; equilibrium zenon
- '" concentration, PZR pressure = 2250 psia; i
RCS Tava = 581'F. ASAP, decrease power to 50%. Unit 3 is shutdown for refuelina. D/G A l
was declared " inoperable" 10 minutes ago due j to Chemistry's report on suspended solids in the diesel fuel oil.
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r "r 6 2 10 min SG04 SG 1evel control instruments drifts Hi j 100% __
. . ,. e t " ' ' 2 15 afn CV05 ? Letdown HX leak i
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_ _ . . - . . ~ . _ - - . . . _ .
. . . _ . -. __ . _ _ . _ ~ ._ .-_ _ _ _ _ _ - - - _
d April 3, 1987 ES-302-3 l t
} SIMULATOR SCENARIO FORM (contd) .
l Scenario No. 48 (contd) ;
- 3.,.. ,
- Event ~ ' . ',. . T ~
No. Time Mal f. No. Description l r# r'gr . 4 25 min FWO4 Feedwater pipina i t broken inside containment pe
- FWO28 and downstream of check valves on S/G #1.
turbine trip P504 will not start. Steam driven pump trips 1
! on overspeed.
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_ ._ _ _. _. _ _ . __ _ ~ _-- _ _ . _ . _. _ _ _ _ _ - _ _ _ _ _ _ _ . . . _ . _ _ _ . _
k April 3, 1987 ES-302-5 a
SIMULATOR ADMINISTRATION FORM i
Scenario No. 4B Event No. 1 Page 1 ' of 5
]
i Brief
Description:
Decrease reactor power level,100% to 505 -/'. ' . . ' -
1 i
Plant l Conditions Posttion Candidate Actions / Behavior
.l (co, A coicM) l 100% P0, 80P, SS The candidates should determine the amount of i
j boration to make this maneuver; the plant data -
book should be used for the EOL conditions.
! 5023-5-1.7. Section 6.5, " Preparation for Power i
Descention " should be used.
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1 (c o ) The candidate should properly start the power-P0 down by settina up the CVCS for boration. ;
i i
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i oco) 50 The candidate should properly decrease the steam 4
flowrate to the turbine. [raz 7 f- /
- w')
i l 3 o 1 -so-) ,7w~eaw co i
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,,,--~.-r~..-~ ~ n n.,-w ,-m -r~, -,,--,,n-,--_ ,m., -,,n,_.,,-,,_,-,n.,- e.,~..-,, ,-n__,r,.e-.n,.,,<..,v-,
April 3,1987 ES-302-5 SIMULATOR ADMINISTRATION FORM ,
Scenario No. 4B Event No. 2 Page 2 of 5 Brief
Description:
SG04 S/G level instrument drifts Hi, feedflod"-- " ~
reduces, level starts dropping Plant Conditions Position Candidate Actions / Behavior reco) Note S/G level change or respond to alarm S/G #1 50-60% BOP HILo (5023-5-2-16 ARP). Take manual control of FWCS and manually control level.
cxs SS Aid BOP to diaanose problem. He may reduce rate of power increase so S/G level control can be maintained.
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April 3, 1987 ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 4B Event No. 3 Page 3 of 5 Brief
Description:
Leak in nonregen Hx into CCW. Surge tank levek will, increase. Rad monitor will alarm. Mismatch in- -
charging / letdown or CV05 leak in the letdown line.
Plant Conditions Position Candidate Actions / Behavior (co P0
) The candidate should note charaing/ letdown mis-
~60%
match. Radiation monitor will increase output.
He should diagnose the problem. He should isolate letdown.
(cs SSS } Aid in diagnosis. Classify leak for Tech Specs.
[.n .r. .7 / v . v. s me.- << n u x )
S h_,
April 3, 1987 ES-302-5 SIMULATOR ADMINISTRATION FORM Scenario No. 4B Event No. 4 Page 4 ' of 5 Brief
Description:
Feedwater pipe break, loss of P504 I'-l,' ; -
Plant Conditions Position Candidate Actions / Behavior tripped (A40P CO) The candidate should note the problem with S/G plant #1 and the fact that P504 will not start. He should note that the turbine driven pump has tripped. S023-12-1, " Standard Post Trip Actions" should be followed.
co P0 The candidate should monitor his boards and report to the SS on the primary parameters, especially Tc.
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April 3,1987 ES-302-5
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SIMULATOR ADMINISTRATION FORM Scenario No. 4B Event No. 4 (contd) Page 5 of 5 Brief
Description:
Plant Conditions Position Candidate Actions / Behavior (cA.r)
SS The SS should guide the team in response to the AFW problem and feedwater leak into containment.
He must diagnose the event and classify it properly. 5023-12-6 should be entered, " Loss of Feedwater," or the candidate may enter the functional if he is still concerned about the leak in the CVCS.