IR 05000416/1993300
| ML20057A117 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 08/30/1993 |
| From: | Bartley J, Lawyer L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20057A116 | List: |
| References | |
| 50-416-93-300, NUDOCS 9309130078 | |
| Download: ML20057A117 (200) | |
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_, ,7 c t y.....} Report No.: 50-416/93-300 Licensee: Entergy Operations, In Jackson, MS 39205
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Docket No.: 50-416 License No.: NPF-29 ; Facility Name: Grand Gulf ! Examination Conducted: July 26 - August 6, 1993 !
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I Chief Examiner: 8 ~ 8/24 /9 3 JonapnH.Bartg Date Signed ! Examiners: E. Lea, NRC Region II i J. Hanek, EG&G E
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Approved By: D ' '
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Lawrence L. Lawyer, Chief (/ .Date Signed Operator Licensing Section . Operations Branch 'l Division of Reactor Safety !
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SUMMARY d Scope: NRC examiners conducted regular, announced operator licensing requalification i examinations during the period July 26 - August 6,1993. Examiners
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administered examinations under the guidelines of the Examiner Standards (ES),. NUREG-1021, Revision 7. Seven Senior Reactor Operators (SR0s) and six Reactor . Operators (R0s) received written and operating examinations. For the simulator portion of the examination, operators comprised three crews. Seven-stand-in operators were used during the simulator portion of the examination ' to complete the crew complemen ! t
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Results: ,
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Operator Pass / Fail: ;
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SR0 R0 Total Percent Crews Percent Pass 7 4 11 84.6% 3 100% l Fail 0 2 2 15.4% 0 0%
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Examiners judged the Grand Gulf Nuclear Station requalification program as satisfactory based on the results of the examination ; Examiners identified weaknesses regarding written examination time validation (paragraph 2.c(1)) and identification of critical steps in Job Performance Measures (JPMs) (paragraph 2.c(2)).
Examiners identified a strength regarding the licensee's pro-active stance in incorporating NRC feedback into other facility requalification examinations >
(paragraph 2.c).
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' Ho violations or deviations were identifie ! a
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REPORT DETAILS-i Persons Contacted ' Licensee Employees ,
. *C. Cresap, Senior Operations Instructor *J. Czaiku, Corporate. Representative, Mississippi Power Cor *L. Daughtery, Superintendent, Plant Licensing M. Dietrich, Manager, Nuclear Training l *C. Dugger, Manager of Operations *C. Elisaesser, Assistant Plant Manager of Operations *C. Hicks, Superintendent, Operations *D. Hintz, Chief Executive Officer, Entergy Operations *R. Hutchinson, Site Vice President , *H. McDowell, Operations Assistant ! *H. McKnight, Senior Operations Instructor > *C. Roberts, Senior Operatiens Instructor t *R. Ruffin, Licensing Specialist * Shelley, Superintendent, Operations Training ;
other licensee employees contacted included instructors, engineers, ' technicians, operators, and office personne , NRC Personnel
: *R. Bernhard, Senior Resident Inspector C. Hughey, Resident Inspector *L. Lawyer, Chief, Operator Licensing Section 1 ; *M. Sykes, Intern ; * Attended exit interview ! Discussion Results and Program Evaluation The Grand Gulf Nuclear Station Requalification Program was determined I to be satisfactory. A requalification examination was ~ administered under the guidelines of NUREG-1021, Revision 7. Seven of seven Senior Reactor Operators (SR0s) and four of six Reactor Operators (R0s)
passed the examination. Three of three crews evaluated passed the simulator portion of the examination. Based on the examination results, the Grand Gulf Nuclear Station Requalification Program meets the guidelines established in NUREG-1021, ES-601. " Scope NRC examiners conducted regular, announced operator licensing requal-ification examinations during the period July 26 - August 6, 199 l Examiners administered examinations under the guidelines of the . Examiner Standards (ES), NUREG-1021, Revision Seven SR0s and six
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Report Details 2 1 R0s received written and operating examinations. For the simulator portion of the examination, operators comprised three crews. Seven
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stand-in operators were used during the simulator portion of the ! examination to complete the crew complement. The examiners also , reviewed the licensee's 1992 requalification operating examinations l under the guidelines of the NUREG-1021, Revision 7, and determined 't they were adequat ; Examination Development k The proposed examinations were acceptable with the exception of the written examinations. The examination team also r.oted some problems with the identification of critical steps in the Job Performance , Measures (JPMs) and the development of alternate path JPMs. The examiners performed a detailed review of the proposed simulator, walk- ; through and written examinations in accordance with the guidelines in ES-601, ES-602, ES-603, and ES-604. The licensee's staff did a good job responding to the examination team's feedback which resulted in a i minimum number of changes during the onsite review. The team noted : the licensee's pro-active stance in incorporating the examination i team's feedback into the other four weeks of requalification examination (1) Written Examination The written examinations were very broad in scope and effectively covered the sample plan, but did not meet the guidelines of ES-602. The licensee submitted a set of examinations for each of the two weeks. Each examination set consisted of 3 written examinations with 15 questions each, a common Part A, an R0 Part B, and an SR0 Part B. The combined written examinations met the '
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minimum of 30 questions identified in ES-602. _ a The examiners reviewed the questions for cognitive level, technical content, importance, discrimination,-and time validation. Approximately 30 percent of the initially proposed questions were modified or replaced. The examiners identified many questions on each examination as memory level or lists of true/ false statements. The majority of the modifications encompassed significant revisions to the stem or distractors of the questions. Based on time validation problems identified in the 1991 NRC administered requalification examination and the in office review of the proposed examinations, the examiners directed the licensee to add 10 questions to the examinatio This increased the length to the maximum of 40 questions identified in ES-602. The licensee added the 10 questions to the Part B examinations for each week. The examiners determined the revised 40 question examination was appropriate as evidenced by the time required by the operators to complete the examinatio Report Details 3 (2) Job Performance Measures The examiners determined the walk-through examinations were adequate. The examiners identified two problem areas during the review of the JPMs per ES-603. The licensee identified non-critical steps as being critical and JPMs designated as alternate path did not meet the guidelines for alternate path JPM All of the JPMs proposed for this examination contained instances of verify, check, and ensure steps being designated as critical steps. These types of steps did not require the operator to take action and therefore were not critical for completion of the tas The examination team's review of the proposed alternate path JPMs revealed that the operator was not required to take actions based on the fault in order to successfully complete the task. An example of this was CRO-C41-F02. This JPM required injecting Standby Liquid Control (SLC) by initiating trains A and B. The JPM was designed so that the train A pump failed to start. The alternate path required by the JPM consisted of the operator noting that SLC pump A had not started and of reporting that to the Plant Supervisor. The JPM did not require the operator to take any positive steps due to the fault, nor would missing the fault have changed the outcome of the JPM. The licensee developed four alternate path JPMs in response to the examination team's feedback. The new JPMs met the guidelines of ES-60 (3) Simulator Scenarios : The examiners reviewed nine scenarios selected for the examin-ation weeks and determined that they were thorough, covered the Emergency Operating Procedures (EOPs) in depth, and met the guidelines of ES-60 .
' Examination Administration The examinations were administered in accordance with the guidelines of NUREG-1021, Revision 7. Both of the examination weeks were well i organized and coordinated. The licensee minimized operator stress by '
developing several walk-through examinations so that operator sequestering was nat required. The examiners evaluated the licensee evaluators in accordance with ES-603 Attachment 3 and ES-604 and determined they were satisfactory. During the simulator examinations, the evaluators were thorough and asked probing follow-up question The performance of the evaluators during the walk-through examinations met the guidelines of ES-603 Attachment .- _ _ _ _ _ _ _ _ _ _
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! Operator Performance Operator performance during the operating test was satisfactor However, two R0s failed the written examination (1) Written Examination ;
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Overall, two R0s failed the written examinations. SR0 performance ; on the written examinations was satisfactory. The R0 combined Part : A and Part B examination scores ranged from 74.4 to 100 percent l with an average score of 85.6 percent. The SRO combined Part A and ! Part B examination scores ranged from 87.5 to 97.4 percent with an i average score of 92.1 percent. The examiners determined that the written examinations were sufficiently discriminating, j
' (2) Job Performance Measures Overall, the operators performed well during the JPMs. The examiners noted a significant improvement in operator performance of JPMs compared to the last examination. Of the 13 operators taking the walk-through examinations, only 3 failed JPMs. None of i the operators failed more than one JP i (3) Simulator :
Crew performance in the simulator part of the examination was . satisfactory. The examiners identified two significant weaknesses ! in one crew in the areas of E0P implementation and Emergency Plan event classification. The examiners reviewed the licensee's ; . remediation plan for the operators and determined the remediation ; plans dequately addressed the weaknesses identifie l (a) During scenario ESC-029, the Plant Supervisor incorrectly l directed emergency depressurization based on two areas being above maximum safe operating values. EP-4, " Auxiliary Building and Radioactive Release Control," required emergency depressurization if more than one area temperature or more ' than one area radiation level was above its maximum safe operating value as listed in EP-4 Table 3. The Plant i Supervisor made the emergency depressurization call based on one area temperature and one area radiation level being above the maximum safe operating values. Although this was incorrect, it did not unnecessarily degrade the plant or , complicate the recovery because emergency depressurization was . necessary later in this scenario. This same incorrect action ; in other circumstances could have caused unnecessary plant ' degradation or recovery complication !
Report Details 5 (b) During scenario ESC-029, the Shift Superintendent (SS) did not upgrade the Site Area Emergency to a General Emergency when , site boundary radiation levels rose to 60-70 mr/hr with containment breached. Initially the crew knew containment was i breached based on steam issuing from the blowout shafts through the Auxiliary Building roof. When the survey teams reported radiation levels at the site boundary of 60-70 mr/hr, the SS did not upgrade the classification because steam was not issuing from the Auxiliary Building Roof and he therefore concluded that containment was no longer breached. This was : incorrect. Steam stopped exiting the Auxiliary Building roof due to the depressurization and cooldown of the reactor; not
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because containment integrity had been restore Simulator Facility The simulator performed well during the examinations. No hardware or software failures occurred. The examiners noted one simulator fidelity problem witn the Reactor Core Isolation Cooling (RCIC) system during the administration of Scenario ESC-030. This scenario consisted of a loss ' of offsite power compounded by the loss of injection sources other than RCIC. An emergency depressurization was required due to RCIC being unable to maintain level greater than -197 inches. The crew overrode the RCIC isolation at 60 psig in the reactor by procedure to allow RCIC to continue to provide water to the reacto Following the crew's emergency depressurization and their bypassing of the RCIC low reactor pressure isolation, an examiner noted that RCIC was injecting at 600 gpm with reactor steam pressure at 8 psig. The examiners felt that 600 gpm with 8 psig steam pressure was not accurate and requested the licensee staff to research the RCIC turbine operating characteristics. The licensee's research revealed that the RCIC turbine would stall at a steam pressure between 10 and 50 psig depending on the plant piping configuration. This confirmed the examiners' suspicions that RCIC would l not be capable of pumping 600 gpm with 8 psig steam pressur j 3. Action on Previous Inspection Findings (CLOSED) IFI 416/92-07-02, Failure of Segment Examination To Provide Discriminatio This item concerned the failure of segment examinations administered to initial licensing candidates to adequately identify , candidates' weaknesses. The failure of the licensee to identify poor l performers prevented the candidates from receiving needed remediation prior to the NRC initial examination. During this examination, the examiners reviewed documentation pertaining to the IFI. The following corrective actions were identified: s The required minimum grade for written examinations has been raised from l ) 70 percent with an 80 percent average to a minimum of 80 percen _- _ . - - . - .-.
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l Two comprehensive written examinations were added to the evaluation l program. One examination is scheduled to be administered at the ! conclusion of the fundamentals section and the second examination is
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scheduled to be administered at the end of the systems sectio Periodic written examinations have been incorporated into the simulator . trainin l A review of training records indicated that the licensee training staff had I identified weaknesses in individual performance as a result of the : corrective actions implemented by the licensee. The licensee identified 1 operator weaknesses during requalification training and initial license trainin Examiners considered the licensee's corrective action to be l adequate, and this Inspector Follow-up Item is close (Closed) VIO 416/92-07-03, Failure To Provide Remediation For Candidates Who j Fail Examinations. This item concerned the licensee's failure to provide i adequate remediation to an SR0 candidate following failure of a written examination. The candidate was required to self study with no significant ' instructor contact as a form of remediation. There was no preplanned or i organized contact with the training instructors. As a result of the inadequate remediation training, the candidate failed the retake examinatio During examination 93-300, the examiners reviewed the licensee training procedures and training records of licensed operators and initial licensing candidates. The examiners found that the licensee had incorporated changes j addressing remediation into Ol-S-04-1, " Licensed Operator Training and i Qualification Program," Revision 12. Attachment 1 of that document provided { the guidelines that were to be used when remediation was required, and ! Attachment 2 documented the remedial training plan. The examiners reviewed 'j l the training records of those candidates who received remediation. The i licensee did an adequate job of documenting the reason for remedial training, topic to be discussed during remedial training, schedule of remedial training, and the results of the training. Examiners considered the licensee's corrective action to be adequate and this Violation is close . l (Closed) VIO 416/92-07-04, Failure To Perform Technical Competence and I l Instructional Certification For Contractors. This item concerned the licensee's failure to perform a technical competence and instructional , skills certification for contractor instructors as required by 14-S-01-9, l
" Instructor Training, ')ualification and Certification," Revision 12. During l this examination the examiner: reviewed 14-S-01-9 and the training records of seven contract instructors hired by the licensee since the March 3, 1992, i operator training inspection. The examiners found the procedure had been '
' revised to delineate all areas where new instructors needed to be evaluated and trained. Records reviewed indicated that all contractor instructors have received training and have been evaluated as required by procedur Examiners considered the licensee's corrective action to be adequate and this Violation is closed.
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Report Details 7 4. Exit Interview . At the conclusion of the site visit, the examiners met with representatives ! of the plant staff listed in paragraph I to discuss the results of the ! examinations. The licensee did not identify as proprietary any material : provided to, or reviewed by the examiners. Dissenting comments were not ' received from the license t
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ENCLOSURE 2 SIMULATOR FACILITY REPORT-Facility Licensee: Grand Gulf Nuclear Station Facility Docket No.: 50-416-Operating Tests Administered On: July 28 - AugustL 6,1993 This form is to be used only to report observations. These observations do not constitute, in and of themselves, audit or inspection findings and are not, without further verification and review, indicative of noncompliance with 10 CFR 55.45(b). These observations do not affect NRC certification or approval of the simulation facility other than to provide information that may be used in future evaluations. No licensee action is required solely in response to these observation While conducting the simulator portion of the operating tests, the following items were observed (if none, so state): ITEM DESCRIPTION RCIC RCIC pumped 600 gpm with reactor steam pressure at 8 + psig (paragraph 2.f).
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Ak a3 de *, cJ) Gul+ 953n GRAND GULF NUCLEAR STATION ANNUAL REQUALIFICATION EXAMINATION EXAM NAME: 93 LOR A3/RO I DATE ADMINISTERED: RO OPERATOR: l SECTION OPERATOR CATEGORY PERCENTAGE SCORE POINTS PLANT & CONTROL 1 SYSTEMS All work done on this exam is my ow I have neither given nor received ai Operator's Signature - _ _ _ _ _ _ _ _ _ _ _ _ _ _ i
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GUIDELINES 1. Read each question carefully and thoroughly. Identify the number of parts. Highlight and separate key points. If you have questions, ask the instructor for clarificatio . Carefully review each of the four choices and select the one that most completely and correctly answers the question. Unless determined otherwise during the post-examination review process, only one choice is correc . Answer the questions you know first. Pace yourself to allow a set time for harder questions. Allow time to check your answer . Use a # 2 or # 2.5 lead pencil to completely fill in the blocks on the automated answer form. If you have to change your answer, ensure that you completely erase all marks from the undesired bloc RULES 1. All examinations are open reference, using materials that would normally be available to you in the Control Room. Other materials may also be provided if required to answer the question . To pass the examination, you must achieve a combined grade of 2 80.0% for Parts A and . You have a total of 90 minutes to complete this section of the examinatio . No talking during the examination is allowed. Do not disturb the class - raise your hand if you have a question. Talking or trading answers with other members of the class will result in an immediate failur . Only one student may leave the room at a time. Ask the instructor for permissio . After you complete your examination, assemble the questions, aids, answer form and all scrap paper into a package and give it to the proctor. Remember to sign the statement on the cover i shee . Af ter you have turned in your examination, leave the examination area. If you are found in this area while the examination is still in progress, your license may be denied or revoke _ _ _ _ _ - _
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The plant was operating at = 100% power near EOC with no inop l
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equipment when the following events occurred during previous shifts: o Approximately 10 hours ago, Reactor Recirc Pump "A" trippe The cause was a faulty protective relay in CB-5A. Estimated time of repair is two more hours. All Tech Spec-required ' actions have been take o Four hours ago I&C calibrated the Standby Liquid control bulk solution tank's level instrumen All other events and changes to plant statuh occurred on this shif Consider the following: o All data from the Control Room and Tech Spec rounds should be considered valid and within their periodicity for the Day Shif The Day Shift rounds have not yet been reviewe o All indications (meters, indicating lamps, annunciators, etc.) should be considered vali No spurious indications unless otherwise note No burned-out indicating or annunciator lamp ** ***** a. Questions 1-11 ARE related to this scenario and are marked
* * * SCENARIO 93/3 *** at the to ) Answers should be based on actual conditions that may be observed in the simulator NO ) Some questions MAY refer to past or future conditions within this scenario. In such cases, this information will be provided in the question, b. Questions 12-15 ARE NOT related to this scenario. Answers should be based on information given in the question ONLY, unless otherwise note :
O O .- QUESTIONS 1-11 , ARE SPECIFICALLY RELATED TO THIS SCENARIO
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ANSWERS SHOULD BE BASED ON ACTUAL INDICATIONS OBSERVED IN THE SIMULATOR i l' P s e
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***** ANNUAL REQUALIFICATION EIAM *****
93 LOR A3/RO QUESTION NO. 1 PT. VALUE: 1.00 REC ID: 1382
* * * SCENARIO 93/3 * * *
Choose from below the one statement that correctly describes the proper EMERGENCY PROCEDURE response to present Suppression pool temperature condition a. BOTH loops of Suppression Pool Cooling should be in service until Suppression Pool temperature decreases to < 95* b. Only one loop of Suppression Pool Cooling is required to to be in service at this tim c. The Reactor should immediately be scrammed and both loops of Suppression Pool Cooling placed in servic d. The Reactor should immediately be scrammed and rapidly depressurized, and both loops of Suppression Pool cooling placed in servic <
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/RO QUESTION NO. 2 PT. VALUE: 1.00 REC ID: 1384
* * * SCENARIO 93/3 * * *
The Duty Manager is concerned about the present Condensate /Feedwater System configuratio Considering procedural AND operational limitations under PRESENT plant circumstances, is his concern justified? Why? a. Yes. All three Condensate Pumps are procedurally required to be in service at the present power leve i b. Yes. Feedwater pump suction pressure is dangerously lo c. No, as long as total feedwater flow remains below 16 albm/h d. No. Removing one Condensate Pump and Condensate Booster Pump from service is permitted at this power level anywa i e r 4 ,
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/RO QUESTION NO. 3 PT. VALUE: 1.00 REC ID: 1369
* * * SCENARIO 93/3 * * *
i The STA reports the following results of the latest MON edit from the Powerplex computer: i MTPF = 3.17 FDLRX = 0.87
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MAPRAT = 0.63 MFLCPR = 0.91 Regarding reactor power, what actions, if any, should be taken NOW in response to this report? a. No action required (the edit indicates normal parameters for the current plant conditions), b. Recirc. flow should be further reduced to approximately 56 mlbm/hr to exit the Power-to-Flow regio c. Insert control rods to exit the current Power-to-Flow regio d. Immediately scram the reactor and enter the Scram ONE : j i l
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/RO QUESTION NO. 4 PT. VALUE: 1.00 REC ID: 1371
* * * SCENARIO 93/3 * * *
Choose from below the correct setpoint (in % rated thermal power) for the APRM flow-biased scram function under the present plant circumstance a. 40 b. 77 c. 100 d. 111
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/RO , QUESTION NO. 5 PT. VALUE: 1.00 REC ID: 1383
* * * SCENARIO 93/3 * * *
Choose the one statement below that best describes Emergency Procedure implementation requirements under the present plant condition a. MUST enter the EPs; MAY exit when it is determined that the emergency no longer exist b. MUST enter the EPs; MAY exit when Suppression Pool Cooling is in servic c. Entry into AND exit from the EPs is optional under these condition d. Entry into the EPs is optional, but once entered MUST remain until all entry conditions have cleare , l l I i I
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/RO QUESTION NO. 6 PT. VALUE: 1.00 REC ID: 1370
* * * SCENARIO 93/3 * * * ;
Choose from below the one correct statement regarding operation of the Reactor Recirculation System under the present circumstance a. B33-F067A should remain shut to prevent reverse flow through the "A" Recirc. loo b. "B" Recirc. loop flow should be at Icast 40,000 gpm flow (but less than 44,600 gpm) to prevent excessive delta-t's with the "A" loo c. B33-F067A can be opened, but the "A" Flow CoJtrol Valve should be closed to prevent excessive reverse flow while allowing enough flow to clear the temperature interloc d. B33-F067A should be re-opened to keep the delta-t's as 10~1 as possibl t
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/RO
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QUESTION NO. 7 PT. VALUE: 1.00 REC ID: 1374
* * * SCENARIO 93/3 * * *
Choose from below the one statement that describes the correct action regarding SSW B recirc valve P41-F006B if the operator were to start RHR Pump B right NO a. Valve will go FULL CLOSED automatically on valve position interlock b. Valve must be manually close , c. Valve will remain FULL OPEN and cannot be remotely closed as long as SSW B is running, d. Valve will go FULL CLOSED automatically when SSW flow is increased beyond the minimum flow setpoin i ,. PAGE 8 l
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ANNUAL REQUALIFICATION EXAM CONTINUED 93 LOR A3/RO l i QUESTION NO. 8 PT. VALUE: 1.00 REC ID: 1373
* * * SCENARIO 93/3 * **
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Concerning the C34 Narrow Range level instrumentation, what procedural actions, if any, are required? ; P a. No action required. All readings are within spe _ b. Immediately initiate an MNCR on the discrepant items and ensure that it is reviewed for operability within 24 hour c. Circle the discrepant item (s), initiate an immediate investigation to determine the cause of the discrepancy and describe the investigation and its results in the
" Comments" sectio d. IMMEDIATELY write a Priority 1 CI to have the discrepant item (s) restored to operability since inoperability requires a plant shutdown within 24 hour , !
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***** ANNUAL REQUALIFICATION EXAM CONTINUED ***** i 93 LOR A3/RO , !
QUESTION NO. 9 PT. VALUE: 1.00 REC ID: 1400 l l l
* * * SCENARIO 93/3 * * *
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Given ALL available information and present plant indications, choose from below the correct status of the Standby Liquid Control j System regarding Tech Spec SBLC is fully OPERABLE SBLC is INOP because it does not meet the minimum required concentration limi ' SBLC is operating in the LIMITED OPERATION region of Tech Spec Figure 3.1.5- d. SBLC is operating in the UNACCEPTABLE OPERATION region of Tech Spec Figure 3.1.5- ;
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93 LOR A3/RO QUESTION NO. 10 PT. VALUE: 1.00 REC ID: 1420
* * * SCENARIO 93/3 * * *
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Chemistry has requested that the Control Room perform the proper lineup for taking a PARS sample from the P.eactor Recirculation-pump discharge sample poin What valve manipulations, if any, need be performed? a. No additional manipulations required (system is in the correct lineup). l Send an operator to Area 10, 119' to open B33-F12 , c. CLOSE B33-F127 and B33-F128. OPEN B33-F125 and B33-F12 d. Requested sampling lineup is OK, but B33-F019 and B33-F020 should be CLOSE t
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/RO QUESTION NO. 11 PT. VALUE: 1.00 REC ID: 1377
* * * SCENARIO 93/3 * * *
SELECT the one correct statement concerning how the LPCS injection valve would respond under present plant conditions if a manual Di I LOCA signal were initiated NO The valve will NOT open automatically NOR can it be opened manually from P601, with OR without the LOCA signal, The valve will NOT open automatically. It CAN be opened manually from P601, with OR without the LOCA signa The valve will open automatically with the LOCA signa It CANNOT be opened manually from P601, with OR without the LOCA signa The valve can be opened manually from P601 NOW, but it will close automatically with the LOCA signa , . - . . .. . - . . . . . . .. - ..c . . O O ;
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QUESTIONS 12-15 j i i ARE NOT l r SPECIFICALLY RELATED-
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TO THIS SCENARIO _____________________________ l
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ANSWERS SHOULD BE BASED ON SYSTEM KNOWLEDGE AND- ANY : INFORMATION GIVEN IN THE QUESTION-
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***** ANNUAL REQUALIFICATION EXAM CCNTINUED *****
93 LOR A3/RO QUESTION NO. 12 PT. VALUE: 1.00 REC ID: 1200 When raising the MHC START DVC to reset the Main Turbine after a trip, the operator must stop momentarily when the (1) begin to open and wait for (2) to stabilize before continuin (1) HP Stop valves; (2) HP control fluid pressure b. (1) HP Stop valves; (2) LP control fluid pressure c. (1) LP Stop valves; (2) HP control fluid pressure d. (1) LP Stop valves; (2) LP control fluid pressure
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93 LOR A3/RO QUESTION NO. 13 PT. VALUE: 1.00 REC ID: 1191 The reactor mode switch is in "STARTUP".
SELECT the one statement that describes a condition in which the Intermediate Range Monitoring (IRM) system is not functioning correctly, IRM "A" indicates 110/125 of scale on range 7 and no rod block or scram signal is presen b. IRM "B" indicates 122/125 of scale on range 6, a rod. block and a half scram is presen c. IRMs "D" and "A" both fail upscale and a reactor scram occurs, d. IRM "C" mode switch is placed to " STANDBY" ; a rod block and half scram occurs.
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/RO QUESTION NO. 14 PT. VALUE: 1.00 REC ID: 9L1 If the handswitch for SRV B21-F051A on Remote Shutdown Panel H22-P151 were taken to OFF, which of the following statements would be true? Consider the signals given as the ONLY signals presen B21-F051A will NOT open if ONLY Division 1 ADS logic initiate b. B21-F051A will open in the Safety mod B21-F051A will NOT open on a Division 1 Relief signa B21-F051A will open ONLY if the Division 2 ADS logic initiate o
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PAGE 15 ANNUAL REQUALIFICATION EXAM CONTINUED ***** . 93 LOR A3/RO i
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QUESTION NO. 15 PT. VALUE: 1.00 REC ID: 1367 ; which of the fellowing PASS system pathways has a valve in the sample flowpath that has an automatic isolation from NSSSS? a. Drywell atmosphere ; b. Suppression pool a c. RHR A
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d. Recirc jet pump
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 IDR A3/RO
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GRAND GULF NUC* EAR STATION ANNUAL REQUALIFICATION EXAMINATION EXAM NAME: 93 LOR B3/RO DATE ADMINISTERED: RO OPERATOR: SECTION OPERATOR CATEGORY PERCENTAGE SCORE POINTS B. ADMINISTRATIVE CONTROLS / 2 PROCEDURAL LIMITS All work done on this exam is my ow I have neither given nor received ai Operator's Signature
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GUIDELIT.ES 1. Read each question carefully and thoroughly. Identify the number of parts. Highlight and separate key points. If you have I questions, ask the instructor for clarificatio . Carefully review each of the four choices and select the one that most completely and correctly answers the question. Unless determined otherwise during the post-examination review process, only one choice is correc . Answer the questions you know first. Pace yourself to allow a set time for harder questions. Allow time to check your answer . Use a # 2 or # 2.5 lead pencil to completely fill in the blocks on the automated answer form. If you have to change your answer, ensure that you completely erase all marks from the undesired bloc RULES 1. All examinations are open reference, using materials that would normally be available to you in the Control Room. Other materials may also be provided if required to answer the question . To pass the examination, you must achieve a combined grade of 2 80.0% for Parts A and . You have a total of 90 minutes to complete this section of the examinatio . No talking during the examination is allowed. Do not disturb the class - raise your hand if you have a question. Talking or trading answers with other members of the class will result in an immediate failur . Only one student may leave the room at a time. Ask the instructor for permissio . After you complete your examination, assemble the questions, aids, answer form and all scrap paper into a package and give it to the proctor. Remember to sign the statement on the cover shee . After you have turned in your examination, leave the examination area. If you are found in this area while the examination is still in progress, your license may be denied or revoke m
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93 LOR B3/RO QUESTION NO. 1 PT. VALUE: 1.00 REC ID: 328 The plant is in Operational Mode 4 with RHR Shutdown Cooling A in servic E12-F009 closes on a spurious isolation signal. The valve cannot be re-opened either manually or electrically due to thermal bindin Which one of the following describes an approved, valid method of removing decay heat under these conditions? Operate HPCS to circulate coolant between the Suppression Pool and the reactor via the head ven Inject with LPCS to circulate coolant through the reactor from the Suppression Pool through two open SRV Circulate coolant between the Main Condenser and the reactor using the Condensate Pumps and main steam line Line up and operate RHR B in the shutdown cooling mod o
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 2 PT. VALUE: 1.00 REC ID: 1118
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An ALERT was declared due to loss of the plant's ability to maintain reactor coolant temperature < 200*F while in Mode Adequate decay heat removal has now been restored and coolant temperature is = 142*F and stabl Prior to terminating the ALERT, the Emergency Director should: consult with offsite state and local organization receive permission from the local NRC Resident Inspecto c. consult with all emergency facility coordinator receive permission from the Corporate CE *
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 3 PT. VALUE: 1.00 REC ID: 1348 The Offgas Pretreatment Radiation Monitor is required to be operable . a. at all times b. ahen the Offgas system is in service and flow is going through the charcoal adsorbers c. when a St aam Jet Air Ejector is in service d. whenever the Offgas Post-treatment Radiation Monitoring system is inop l
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 4 PT. VALUE: 1.00 REC ID: 1060 When the Condensate precoat filters are in service, it is possible that could result if more than Condensate Pumps are runnin a. high feedwater conductivity due to spent resin; one b. Condensate Pump runout; two c. lifting relief valves in the precoat filters' piping; one d. exceeding the flow capacity of the precoat filters; two
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 5 PT. VALUE: 1.00 REC ID: 1232 The reactor is operating in Mode 1 with the "B" IRM failed upscale and bypasse While conducting surveillance 06-OP-1C51-W-0003, an unexpected Di II half-scram was receive Which one of the following events could have caused the half-scram under these conditions? APRM B's mode switch was taken to POWER / FLOW with the APRM not bypasse IRM F's mode switch was mistaken for the APRM F mode switch and was taken out of OPERAT APRM F's meter selector switch was taken to COUNT with the APRM not bypasse The operator inadvertently bypassed IRM D when he meant to bypass APRM ' O
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 6 PT. VALUE: 1.00 REC ID: 864 In which one of the following plant conditions is the Alternate Decay Heat Removal System procedurally allowed to be operated? The plant is in Refueling, with the head removed and the RPV cavity flooded. All pool gates have been remove No Shutdown Cooling loop is in servic The plant is in Hot Shutdown. No Shutdown Cooling loop is in servic The plant is in Refueling with the RPV head removed. The RPV cavity is drained. Shutdown Cooling B is in servic The plant is in Cold Shutdown. RHR A trips while in Shutdown Cooling. RHR B is tagged out. RHR "C" is in the Suppression Pool Cleanup mod O . S - PAGE 7
***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 7 PT. VALUE: 1.00 REC ID: 1283 A LOCA has occurre All control rods went FULL I Drywell temperature has been observed to be greater than saturation for the current reactor pressure, so the operator has decided that level cannot be determine Only LPCS and RHR C will start. As a result, the operator is able to establish a maximum Rx pressure of 42 psig greater than Containment pressure with six SRVs ope What Emergency Procedure should be used to establish and maintain adequate core cooling? a. Pressure and Level Control section of EP- b. Pressure and Level Control section of EP-2 c. RPV Flooding contingency of EP- d. Containment Flooding contingency of EP- * O
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 8 PT. VALUE: 1.00 REC ID: 1136 An operator is placing FPCCU Filter /Demin "A" in service with FPCCU Pump "B" operatin After placing the Mode Switch in FILTER, he increases flow STEADILY at the rate of 1% every two seconds as the RO closes the bypass valv While the filter is being placed in service, the following system system conditions exist:
- FPCCU delta-flow = 35 gp SFP return flow = 740 gpm - FPCCU Drain Tank level = 14% - UCP return flow = 340 gpm Which one of the following describes the expected system response under these conditions?
a. The "A" F/D will automatically swap back to the " HOLD" mode because flow is not being increased fast enoug FPCCU Pump "B" will trip on low drain tank leve The FPCCU system will automatically isolate on high delta-flo The system is operating normall . M O mer ~ , PAGE 9
***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 9 PT. VALUE: 1.00 REC ID: 1053 In order to verify the operability of the Standby Liquid Control System's suction piping heat tracing, must be verified at least once every 24 hour a. no alarms present on the panels b. correct temperature setpoint c. power available to at least one division d. all four heating elements warm to the touch
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93 LOR B3/RO QUESTION NO. 10 PT. VALUE: 1.00 REC ID: 1190 A station blackout has occurre The Div. III D/G is the only available source of 4.16KV powe Which one of the following conditions alone would prevent the use of Division 3 diesel generator to energize the Division 1 ESF bus? a. HPCS High Drywell Pressure Initiation signal is sealed i b. Annunciator "15AA UNDERVOLT LOCKOUT TRIP" (P864-1A-A3) is alarme RPV water level is -50" on Wide Range instrument Electricians have reported bus damage on ESF bus 16A & w O
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93 LOR B3/RO QUESTION NO. 11 PT. VALUE: 1.00 REC ID: 225 Which one of the following is required to red tag an air operated, fail open valve in the closed position? Jack the valve closed with an installed jacking device, Tag the hand switch for the valve in the closed positio Tag the valve's air supply ope Install an air bottle instead of normal operating ai !
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 12 PT. VALUE: 1.00 REC ID: 1139 The reactor is exactly critical with reactor power on Range 7 of the Intermediate Range Monitor Control rods are inserted such that - 0.0010 delta K/K is inserted in the cor Reactor pressure is 915 psi The reactor depressurizes through the main steam line drains to 815 psi (Assume the temperature coefficent of reactivity is 0.0001 delta K/K per degree F and all other reactivity factors stay cunstant.)
The reactor core will: become prompt critica become supercritica remain exactly critica become subcritica l
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 13 PT. VALUE: 1.00 REC ID: 894 During a special test, the Turbine Building NOB is controlling Hotwell level in manual from the 1H22-P171 pane The NOB should be communicating his actions to the Control Room via the . a. telephone b. portable radio c. Turbine Building auxiliary sound-powered phone
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 14 PT. VALUE: 1.00 REC ID: 852 A plant shutdown from 100% power is in progres The Reactor Recirculation pumps will automatically downshift to slow speed when Feedwater flow decreased to less than: %. % after a 15-second time dela %. % after a 15-second time dela i e M M w w PAGE 15
***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 15 PT. VALUE: 1.00 REC ID: 956 The Control Room is abandoned and the Control Rod Drive Hydraulic System (CRD) is being utilized for RPV level contro CRD flow to the Reactor Vessel procedurally should be controlled by: Manually opening / closing the CRD Drive Water Filter Outlet valve C11-F083 at Area 10, 139' Aux. Bld Manually opening / closing the CRD Drive Water Pressure Pressure Control Valve C11-F003 from the P151 panel, Local manual control of the CRD Flow Control valve (C11-F002A/B). Throttling the CRD pump discharge valve (C11-F217A/B).
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93 LOR B3/RO QUESTION NO. 16 PT. VALUE: 1.00 REC ID: 1 Static inverter 1Y79 momentarily lost power from its normal DC sourc The alternate AC source automatically switched in to supply the loa What happens when normal DC power is restored? a. The inverter will re-energize but remain in the ALTERNATE SOURCE SUPPLYING LOAD mode until the local INVERTER TO LOAD button is depresse b. The inverter is " locked out" and will not re-energize and supply the load until it is manually rese c. The inverter will switch back to its normal DC source within about two second d. The inverter will re-energize, but will not accept the load until the local transfer switch is returned to the NORMAL OPERATION position _. . _ _ .
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 17 PT. VALUE: 1.00 REC ID: 1423 The handswitches for SRV B21-F051D on panels P150 and P151 have been taken to OF What would be the response of the Safety Relief Valve system if reactor pressure were to momentarily increase to 1105 psig? a. Six SRVs would ope b. SRVs F051B and F051D would ope SRV F051B would ope NO SRVs would ope I
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 18 PT. VALUE: 1.00 REC ID: 1202 The plant is operating in Mode 1, 100% powe Chemistry reported a Reactor Water conductivity of 2.0 ymho/cm at 0100 on 7/27/9 Condensate demins were changed out, reactor water conductivity was found to be 1.5 ymho/cm at 0100 on 7/28/9 All other chemistry parameters remain within their allowed limit Up until now no chemistry limit has been exceeded this yea Which one of the following describes the correct required action? a. Continue to search for source of chlorides. No additional action is required for another 48 hours, b. Commence a normal plant shutdown, and proceed to Cold Shutdown within 16 hour c. Reduce power per IOI-2, scran at step 6.14 and continue to cool down to Cold Shutdown d. Be in at least Startup within the next 6 hours
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 19 PT. VALUE: 1.00 REC ID: 1076 A reactor cocidown is in progress, with RHR "A" in Shutdown Coolin Reactor pressure is 95 psi E12-F008 goes shut due to a spurious isolatio E12-F008 was subsequently re-opened and RHR "B" was placed in Shutdown Cooling The crew is preparing to align RHR "A" for LPCI Standb What special precaution should be considered in doing this? a. This evolution requires prior NRC concurrenc . RHR A and B are particularly susceptible to an inter-system LOCA in this conditio c. A sudden loss of RPV level inventory may occu d. Opening the LPCI A suction valve could result in excessive water hamme _ _ _ _ - - _ - _ - _ .
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PAGE 20 ANNUAL REQUALIFICATION EX)Ji CONTINUED ***** 93 LOR B3/RO QUESTION NO. 20 PT. VALUE: 1.00 REC ID: 1228 Select from below the one event which is a Safety Limit violatio Reactor startup is in progress with two bypassvalves full open when an APRM spike causes a Division I scram signal. The operator overreacts and manually inserts a full scram. All rods insert fully. Reactor pressure decreases to 700 psig due to subsequent cold water injection and lack of decay hea b. The reactor is operating at 55% power when both recirculation pumps trip off. RPV level increases to +55 inches and the Reactor fails to auto-scram. The operator-at-controls inserts a full scra The reactor is operating at 55% power when a pressure regulator failure causes the bypass valves to fully open. RPV pressure decreases to 700 psig and the MSIVs fail to close. Reactor power is 42% when the operator manually closes the MSIVs. The reactor scrams and RPV level is restored to normal with RCI d. The reactor is operating at 55% power when both RFPTs tri The reactor scrams on low R2V level and HPCS & RCIC receive start signals, but HPCS fails to start. RPV level decreases to-125 inches before RCIC is able to begin increasing leve i
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 21 PT. VALUE: 1.00 REC ID: 876 ESF Transformer 21 output breaker 152-1501 to ESF Bus 15AA tripped open (reason unknown) and de-energized ESF Bus 15A . The Division I diesel generator started and is now supplying power to ESF Bus 15A Which one of the following conditions, if it occurred, WOULD NOT trip OPEN the Division I diesel generator output breaker (152-1508)? a. Generator ground overcurrent b. LOCA c. Generator differential overcurrent d. Engine low lube oil pressure
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 22 PT. VALUE: 1.00 REC ID: 1251 In establishing the calibration conditions for the five RPV level ranges used at GGNS, Containment temperature is assumed to be for all range a. 80*F b. 85'F c. 90*F d. 95'F
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 23 PT. VALUE: 1.00 REC ID: 1285 A is a symbol within the Emergency Procedures that should be returned to whenever its answer changes during the execution of the procedur a. black diamond b. red diamond c. black rectangle d. rectangle with an arrow on one end
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90 LOR 33/RO QUESTION NO. 24 PT. VALUE: 1.00 REC ID: 383 The Standby Liquid Control (SLC) System test tank is being used to add water to the RP Which one of the following components is in the OPEN position? Power supply breaker for MOV F001A, 52-15211 Power supply breaker for MOV F001B, 52-16313 Storage tank outlet valve F001 Test tank outlet valve F031.
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO QUESTION NO. 25 PT. VALUE: 1.00 REC ID: 1197 The Main Turbine is rolling at 1800 rpm and ready for synchronizatio The setting of the MHC Speed Setter should NOW be . a. 100% b. 0% c. 5% above actual turbine speed d. 5% below actual turbine speed
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/RO
**** END OF EXAM ****
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64 /4 - 9 J - 3 0 0 GRAND GULF NUCLEAR STATION ANNUAL REQUALIFICATION EXAMINATION EXAM NAME: 93 LOR A4/RO DATE ADMINISTERED: RO OPERATOR: i i SECTION OPERATOR CATEGORY PERCENTAGE I SCORE POINTS A. PLANT & CONTROL 1 SYSTEMS All work done on this exam is my ow I he're neither given nor received ai Operator's Signature
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GUIDELINES 1. Read each question carefully and thoroughly. Identify the number of parts. Highlight and separate key points. If you have questions, ask the instructor for clarificatio ~ 2. Carefully review each of the four choices and select the one that most completely and correctly answers the question. Unless determined otherwise during the post-examination review process, only one choice is correc . Answer the questions you know first. Pace yourself to allow a set time for harder questions. Allow time to check your answer . Use a # 2 or # 2.5 lead pencil to completely fill in the blocks on the automated answer form. If you have to change your answer, ensure that you completely erase all marks from the undesired bloc RULES 1. All examinations are open reference, using materials that would normally be available to you in the Control Room. Other materials may also be provided if required to answer the question . To pass the examination, you must achieve a combined grade of 2 80.0% for Parts A and . You have a total of 90 minutes to complete this section of the examinatio . No talking during the examination is allowed. Do not disturb the class - raise ycur hand if you have a question. Talking or trading answerr, with other members of the class will result in an immediate '.ailur . Only one student may leave the room at a time. Ask the instructor for permissio . After you complete your examination, assemble the questions, aids, answer form and all scrap paper into a package and give it to the proctor. Remember to sign the statement on the cover shee . After you have turned in your examinat ion, leave the examination area. If you are found in this area while the examination is still in progress, your license may be denied or revoke l
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The' plant was operating at 98% power, BOC, at Step 181 on Control- -! Rod Sequence Document #-1-6-000-A2-15_when the shift. bega !
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The following events are scheduled for your shift: _I
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j o Conduct surveillance 06-OP-1N32-V-0001
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I All other events and changes to plant status actually occurred on I j this shif i
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o All data from the Control Room and Tech Spec rounds should
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be considered valid and within their periodicity for the' Day; i Chif l
- The Day Shift rounds have not yet been reviewe ,
o All indications (meters,-indicating lamps, annunciators,_ l etc.) should be considered vali l
! - No spurious indications unless otherwise note ! - No burned-out indicdcing or annunciator lamp .I * ** **** f
M 7-14 . ! N l a. Questions 1-tr ARE related *** to this scenario and are marked -{
* * * SCENARIO 93/4 ,
at the to * t t 1) Answers _ should be based on actual conditions that may be i observed in the simulator NO ) Some questions MAY refer to past or future conditions within -I this scenario. In such cases, this information will be l provided in the questio l
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IR 71-13 b. Questions -FF-15 ARE NOT related to this scenario. Answers should -; be based on information given in the question ONLY, unless i otherwise note # i
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TO THIS SCENARIO j _____________________________ :
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ANSWERS SHOULD BE BASED ON l ACTUAL INDICATIONS l OBSERVED IN THE SIMULATOR '
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,.1 QUESTION N . PT. VALUE: 1.00 -REC ID: 1389- ;
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* * * SCENARIO 93/4
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Choose from below the correct flow-biased APRM ROD.. BLOCK TRIP 1
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SETPOINT under the present plant circumstance , i a. 86% i
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t- - ANNUAL REQUALIFICATION EXAM CONTINUED -j - - 93 LOR A4/RO d
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LQUESTION NO. 2 PT..VALUE 1.00 REC ID 1394 .l
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=* * * SCENARIO 93/4 ** * ,
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ASSUME that'the' Operator-at-the-controls reduces core flow to'50%.
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core flow in order to reduce offgas activity.below present' levels.-
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Chemistry and HP have been notified to take reactor coolant sample What action, if any, should be taken.next? : i
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a. Continue reducing core flow to stay below the MSIV isolation' j ; setpoint agai l l r b. No further~ action required since the power reduction to.50% ),
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core flow caused offgas pretreatment activity to decrease = ;
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below present level i c. Manually insert a. Group I isolation due to its failure to' fi automatically initiat . I d. Insert control rods and continue monitoring offgas .i-g pretreatment radiation level .j
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# ***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A4/RO QUESTION NO. 3 PT. VALUE: 1.00 REC ID: 1392
* * * SCENARIO 93/4 * * *
Which one of the choices below most COMPLETELY describes the action that the Operator-at-the-Controls should NOW take regarding the reactor control rods? a. Scram the reacto Fully insert the drifting rods and reduce core flow to 60%. c. Attempt to stop the outward drift of the control rods by momentarily applying a INSERT signa d. Attempt to WITHDRAW the drifting rods back to their original position. If they won't stay there, then locally scram the rods and valve them ou I i
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- ***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A4/RO QUESTION NO. 4 PT. VALUE: 1.00 REC ID: 1391
* * * SCENARIO 93/4 * * *
The Plant Supervisor directs the ACRO to cancel ALL the FAULT and CRITERIA lights associated with the ATT test problem without de-energizing the ATT program itsel What should the operator do? a. Depress the CANCEL pushbutton on the ATT Control Panel b. Depress the ATT SUBGROUP SEL MSCV RESET PRGM pushbutton on P680 and the CANCEL pushbutton on the ATT Control Pane c. Turn the ATT Control Panel power keyswitch on P870 to OFF then back to O d. Depress the ATT SUBGROUP SEL MSCV AUTO OFF/AUT ON pushbutto .
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93 LOR A4/RO QUESTION NO. 5 PT. VALUE: 1.00 REC ID: 1395
* * * SCENARIO 93/4 * * *
Given present plant indications, which one of the following is the most significant risk being posed by the Fuel Pool Cooling and Cleanup System? a. FPCCU Pump auto-tri b. FPCCU filter /demin isolatio c. Overflow into Fuel Pool Sweep ventilation ductin d. High Spent Fuel Pool temperatur q,3 - PAGE 6
***** ANNUAL REQUALIFICATION EXAM CONTINUED ***** *
93 LOR A4/RO QUESTION NO. 6 PT. VALUE: 1.00 REC ID: 1396
* * * SCENARIO 93/4 * * *
Choose from below the one condition that could be the cause of the present RPV level indication status, a. Build-up of non-condensible gases in a level instrument reference le b. Make-up valve to the affected level instruments' condensing pot is close c. Packing leak from instrument root valve B21-FXO7 d. Drywell temperature lower than instrument calibration condition O
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93 LOR A4/RO QUESTION NO. 7 PT. VALUE: 1.00 REC ID: 1397
* * * SCENARIO 93/4 * * *
After Security reported steam coming from the 185' elevation of the Aux. Bldg., the Shift Superintendent directed Chemistry to monitor
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radiation levels at the site boundary and offsit Radiation levels were found to be norma The Roving NC' reports that recorder E31-R608/R611 indicates the following Aux. Bldg. steam tunnel temperatures: Ambient = 162*F delta-T = 58'F Choose the one statement below that best describes what action should be taken NOW per the Emergency Procedure a. Scram and emergency depressurize the reacto b. Scram the reactor and close the MSIV c. Manually isolate the Fuel Handling Area and Fuel Pool Sweep ventilation system d. Operate all Aux. Bldg. steam tunnel cooler i
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PAGE 8 ANNUAL REQUALIFICATION EXAM CONTINUED ***** 93 LOR A4/RO QUESTION NO. 8 PT. VALUE: 1.00 REC ID: 841
* * * SCENARIO 93/4 * * *
h one of the following would explain current status of the Reactor Feed .p system (including controls and protective devices)? a. The RFP's\ e failed to respond to a valid trip signal and should be manually trippe b. The system is operatin normall N N The system is responding too slowly to the reduction in reactor powe b
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d. One of three parallel RFP discharge presFu witches has has failed hig P
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A4/RO QUESTION NO. 9 PT. VALUE: 1.00 REC ID: 1419
* * * SCENARIO 93/4 * * *
If a valid LSSS LOCA were to occur NOW, DG Cooling Water Inlet valve P41-F018B would . a. remain closed b. open open but then close when no subsequent diesel start occurred d. remain closed until the diesel achieves rated speed, then it would open
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 IDR A4/RO
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QUESTION NO. 10 PT. VALUE: 1.00 REC ID: 1245
* * * SCENARIO 93/4 * **
How will SSW A RECIRC valve P41-F006A respond if a valid LSSS LOCA actuation were to occur right now? Valve will ope Valve vill remain close Valve will open until P41-F014A opens, then it will close, Valve is interlocked closed for one hour. It may then be manually opene i .
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93 LOR A4/RO QUESTION NO. 11 PT. VALUE: 1.00 EEC ID: 858
* * * SCENARIO 93/4 * * *-
Which one of the following accurately describes the present status of the Reactor Feedwater Level Control System? a. The "B" Narrow Range level instrument has been automatically prevented from being able to control level regardless of selection status, b. A comparator circuit has recognized a level difference among the three Narrow Range level instruments, but no other automatic actions have taken plac c. A comparator circuit has automatically selected the "C" Narrow Range instrument to replace the "B" instrument if the "B" instrument should be selected for level contro d. The "B" Narrow Range level instrument should be manually de-selected from the level control averaging circui .-. . .- . ,- - . , - . . .
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SPECIFICALLY RELATED TO THIS SCENARI . i
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I _____________________________ , I ANSWERS SHOULD BE BASED ON SYSTEM KNOWLEDGE AND ANY INFORMATION GIVEN IN THE QUESTION j i
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93 LOR A4/RO QUESTION NO. 12 PT. VALUE: 1.00 REC ID: 1386 The NOB sent to investigate an inverter 1Y97 trouble alarm observed the following: DC INPUT = 112 VDC AC OUTPUT = 112 VAC INVERTER SUPPLYING LOAD light = On ALTERNATE SOURCE SUPPLYING LOAD light = Off IN SYNC light = Off PRECHARGE light = On He asks if the Control Room wants him to manually transfer source What should he be told? Why? a. No. UPS sources should never be swapped when they are not in synchronizatio b. No. Equipment damage would occur due to an incomplete precharg c. Yes. Inverter failure is imminen d. Yes, as long as he does it ONLY by depressing the AL, TERNATE SOURCE TO LOAD pushbutto .
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A4/RO ! l QUESTION NO. 13 PT. VALUE: 1.00 REC ID: 353 l ' Evaluate the control room indications provided below (NOT on the simulator) and determine the present status of the Standby Liquid Control System: SLC operation is required due to an ATWS conditio White SQUIB VALVE READY lights are OFF SLC SYS A and B OOSVC alarms received Amber SQUIB A and B LOSCONT OR PWR LOSS lights are ON 1C41-F031 is OPEN 1C41-F008 is OPEN SLC A and B pumps are running SLC is operating normall SLC would not be inop if E22-F036 was close SLC is inop because C41-F001A/B cannot ope SLC is operable since C41-F031 can be closed from the control roo &
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93 LOR A4/RO QUESTION NO. 14 PT. VALUE: 1.00 REC ID: 955 At what point in the SSW systems do the SSW flow indicators on the Remote Shutdown Panels measure system flow? a. System discharge flow b. System return flow c. RHR A heat exchanger flow d. The sum of RHR A heat exchanger and D/G 12 Jacket Water Cooler flo ,
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- ***** ANNUAL REQUALIFICATION EXAM CONTINUED ***** .
93 LOR A4/RO QUESTION NO. 15 PT. VALUE: 1.00 REC ID: 1387 Which of the following would occur if inverter 1Y97 failed without transferring to the ALTERNATE source? a. TSC would lose powe b. CAS would lose powe c. SAS would lose powe d. The Aux. Bldg. would isolate agai (. -
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* ***** ANNUAL REQUALIFICATION EXAM CONTINUED ***** *
93 LOR A4/RO
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**** END OF EXAM ****
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C uf f 'l 3 .S eo GRAND GULF NUCLEAR STATION , ANNUAL REQUALIFICATION EXAMINATION EXAM NAME: 93 LOR B4/RC DATE AOMINISTERED: RO OPEr<ATOR: SECTION OPERATOR CATEGORY PERCENTAGE SCORE POINTS B. ADMINISTRATIVE CONTROLS / 2 PROCEDURAL LIMITS All work done on this exam is my ow I have neither given nor received ai Operator's Signature
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GUIDELINES 1. Read each question carefully and thoroughly. Identify the l number of parts. Highlight and separate key points. If you have l questions, ask the instructor for clarificatio . Carefully review each of the four choices and select the one that most completely and correctly answers the question. Unless determined otherwise during the post-examination review process, only one choice is correct.
' 3. Answer the questions you know first. Pace yourself to allow a set time for harder questions. Allow time to check your answer . Use a # 2 or # 2.5 lead pencil to completely fill in the blocks on the automated answer form. If you have to change your answer, ensure that you completely erase all marks from the undesired bloc RULES 1. All examinations are open reference, using materials that would normally be available to you in the Control Room. Other materials may also be provided if required to answer the question . To pass the examination, you must achieve a combined grade of 2 80.0% for Parts A and . You have a total of 90 minutes to complete this section of the excminatio . No talking during the examination is allowed. Do not disturb the class - raise your hand if you have a question. Talking or trading answers with other members of the class will result in an immediate failur . Only one student may leave the room at a time. Ask the instructor for permissio . After you complete your examination, assemble the questions, aids, answer form and all scrap paper into a package and give it to the proctor. Remember to sign the statement on the cover shee . Af ter you have turned in your examination, leave the examination area. If you are found in this area while the examination is still in progress, your license may be denied or revoke ,
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,, ***** ANNUAL REQUALIFICATION EXAM *****
93 LOR B4/RO QUESTION NO. 1 PT. VALUE: 1.00 REC ID: 1105 An ALERT is declared at 122 The Communicator begins ti;e initial notification at 1224 and completes it at 122 The first Followup Notification MUST begin NO LATER THAN: a. 1251 l i l
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93 LOR B4/RO QUESTION NO. 2 PT. VALUE: 1.00 REC ID: 1251 In establishing the calibration conditions for the five RPV level ranges used at GGNS, Containment temperature is assumed to be for all range a. 80*F b. BS*F c. 90*F d. 95*F i i
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B4/RO QUESTION NO. 3 PT. VALUE: 1.00 REC ID: 1228 Select from below the one event which is a Safety Limit violatio Reactor startup is in progress with two bypassvalves full open when an APRM spike causes a Division I scram signal. The operator overreacts and manually inserts a full scram. All rods insert fully. Reactor pressure decreases to 700 psig due to subsequent cold water injection and lack of decay hea b. The reactor is operating at 55% power when both recirculation pumps trip off. RPV level increases to +55 inches and the Reactor fails to auto-scram. The operator-at-controls inserts a full scram, c. The reactor is operating at 55% power when a pressure regulator failure causes the bypass valves to fully open. RPV pressure decreases to 700 psig and the MSIVs fail to close. Reacter power is 42% when the operator manually closes the MSIVs. The reactor scrans and RPV level is restored to normal with RCI d. The reactor is operating at 55% power when both RFPTs tri The reactor scrams on low RPV level and HPCS & RCIC receive start signals, but HPCS fails to start. RPV level decreases to-125 inches before RCIC is able to begin increasing leve . A w
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B4/RO QUESTION NO. 4 PT. VALUE: 1.00 REC ID: 1289 An inadvertent SRV lift has increased Suppression Pool temperature to 95'F and level to 18.75 fee The SRO subsequently entered EP- Which one of the following best describes how the Emergency Procedure should be implemented? a. Only the Suppression Pool Temperature leg need be entere b. BOTH the Suppression Pool temperature AND Suppression Pool Level legs must be entere c. ALL legs of EP-3 must be entered and their appropriate parameters monitored and controlled, d. ALL legs of EP-3 must be entered except for the Hydrogen Control le A
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B4/RO QUESTION NO. 5 PT. VALUE: 1.00 REC ID: 1224 One of the immediate actions in the Reactor Scram ONEP is to place the Mode Switch in SHUTDOW However, the operator is cautioned to NOT perform this step if the Pressure Control System cannot maintain reactor pressure greater than 850 psi In this case, placing the Mode Switch in SHUTDOWN: will cause the MSIVs to CLOSE when pressure decreases to < 850 psig, thus removing pressure control capability through the Bypass valve I i bypasses the automatic MSIV closure at < 850 psig, and thus may cause further undesirable reactor depressurizatio , i bypasses ALL Group I isolations and thus may cause further undesirable reactor depressurizatio will close the MSIVs automatically, regardless of pressure, causing an SRV lift and a further reduction in reactor temperature and pressur . r i .
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93 LOR B4/RO
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QUESTION NO, 6 PT. VALUE: 1.00- REC ID: 1201 l While resetting the Main Turbine,.the "B" HP Stop Valve closed -j i after partially openin The other three HP stop valves came full'ope ! What must the operator do next? !
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' Return the MHC START D7C to 0% and immediately attempt to i
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b. Return the MHC START DVC to 20% and immediately attempt to- ! re-open the HP Stop valve ! c. Return the MHC START DVC to'O%, wait for about-one minute
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and attempt to re-open the HP Stop valve : r
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~h d. Return the MHC START DVC to 20%, wait for about one minute and attempt to re-open the HP Stop valve .
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***** ANNUAL REQUALIFICATION EXA14 CONTINUED *****
93 LOR B4/RO QUESTION NO. 7 PT. VALUE: 1.00 REC ID: 1130 An operator is placing FPCCU F/D "B" in servic After placing the Mode Switch in FILTER at time zero, flowrates are established per the below schedule: TIME (seconds
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F/D FLOW (gpm) BYPASS FLOW (gpm)
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0 0 1090 30 120 820
, 60 180 650 At time 60, the local operator tells the Control Room that he is stopping the flow increase for 30 seconds to allow it to stabiliz The RO stops closing the bypass valve at time 6 What will the impact of this evolution as described be on the FPCCU System?
a. The filter will automatically enter the BACKWASH mode, b. The filter will automatically enter the HOLD mod c. The operator has only 20 seconds left to increase flow above the pump trip setpoint after he resumes the flow increase, d. The FPCCU pump will trip on low flo ,
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B4/RO QUESTION NO. 8 PT. VALUE: 1.00 REC ID: 302 The reactor was operating at rated conditions when all offsite power was lost at 021 Divisions 2 and 3 diesel generators failed to automatically star Division 1 diesel generator was in " Maintenance" so that its fuel rack could be adjuste The operator returned Div. 1 D/G to " Operational" at 0220, and the diesel started immediatel Div. 3 D/G was nanually started at 023 Div. 2 D/G was made to auto-start at 024 What is the classification of this event? Unusual Event Alert Site Area Emergency General Emergency l
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. ***** ANNUAL REQUALIFICATION EXAM CONTINUED ***** l 93 LOR B4/RO QUESTION NO. 9 PT. VALUE: 1.00 REC ID: 1196 The plant is operating at 100% power when the "A" Reactor Recirculation Pump trip The following plant conditions result:
Reactor Power = 60% , Core Flow = 44% Feedwater flow = 8.6 albm/hr Reactor level = 34" Recirc Loop B Flow = 44,600 gpm Select the appropriate action that is required for these condition a. Immediately place the mode switch in shutdow b. Increase Recirc Loop B flow to raise core flow >50%. c. Insert rods to reduce power to reach region III OR IV within two hour d. Place both FCVs to the maxium OPEN positio I i
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B4/RO QUESTION NO. 10 PT. VALUE 1.00 REC ID: 1073 Feedwater shutoff valve B21-F065A is closed before RHR "A" is placed in shutdown cooling to prevent: exceeding limitation on the warm up of B21-F065A during system warmu opening of RHR "A" minimum flow valve (E12-F064A) during start up of the shutdown cooling loo exceeding Limitations of Tech Spec figure 3.4.6.1- draining of reactor water to the feedwater system.
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93 LOR B4/RO
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QUESTION NO. 11 PT. VALUE: 1.00 REC ID: 1195 An operator is performing the " Count" section of APRM surveillance r 06-OP-1C51-V-0003 for APRM "B" during Mode 1 operation ;
Enough LPRMs have been bypassed to make the APRM meter indicate 65% in
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the COUNT mod , One of the un-bypassed LPRMs fails downscal No operator actions are take Which one of the following sets of APRM signals would result?
, (Consider that the APRM is in Bypass per the surveillance).
. Decrease in indicated power l
- Meter reads 65%.
' No change in indicated power
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- Meter reads less than 65%
- INOP Decrease in indicated powe ,
- Meter reads 65%.
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B4/RO QUESTION NO. 12 PT. VALUE: 1.00 REC ID: 1346 Which plant effluent ventilation systems are required by Tech Specs to have an operable SPING noble gas monitor? a. All effluent system b. Containment /Drywell, Fuel Handling Area and SBGTS A and B systems onl c. Containment /Drywell and Fuel Handling Area systems onl d. SBGTS A and B systems onl , I
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B4/RO QUESTION NO. 13 PT. VALUE: 1.00 REC ID: 1059 The plant is being started up following a winter refueling outag As preparations are being made to feed the vessel with the Condensate / Feedwater system, the ACRO observes hotwell water temperature to be 68 degrees Which one of the following is the risk of feeding the vessel with water at this temperature? a. Damage to the flued feedwater heads, b. Exceeds the NDT of the Condensate /Feedwater system pipin c. Thermal shock to the RFV and shrou d. Possible inadvertent criticalit ! l l l l
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M M w w PAGE 14 . ***** ANNUAL REQUALIFICATION EXAM CONTINUED ***** 93 LOR B4/RO QUESTION NO. 14 PT. VALUE: 1.00 REC ID: 1252 The CRO is performing an ATT test of Main Turbine Stop and Control Valve N11-F026B during Mode Seconds after the test commences, SJAE steam flow becomes unstable, so the operator decides to abort the test no What should be done NEXT? a. The RO MUST wait for the valve to complete its test cycle before initiating the Reset progra b. Simultaneously depress the MSCV RESET PRGM and REL buttons on P68 c. Immediately turn the ATT Control Panel power keyswitch on P870 to OF d. Simultaneously depress the RELEASE and RESET buttons on the ATT Control Panel on P87 M M w w - PAGE 15
***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B4/RO QUESTION NO. 15 PT. VALUE: 1.00 REC ID 952 A red light illuminated for one of the six Safety Relief Valves on Remote Shutdown Panels 1H22-P150 and 1H22-P151 indicates: a. the tailpipe pressure switch for the associated SRV has actuate b. the SRV's "A" solenoid (P150) or "B" solenoid (P151) is energize c. a limit switch within the SRV has made contact to indicate that the valve is ope d. a limit switch within the SRV's air accumulator indicates a low pressure condition in the accumulato .. .
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93.LD:R B4/RO QUESTION NO. 16 PT. VALUE: 1.00 REC ID: 228 Valve N21-F016B is being-tagged for maintenanc The clearance is installed and the clearance holder signs the for The MWO is then Authorized to Star 'Upon commencing work, the clearance' holder notices that vent valve N21-F035B is closed and un-tagged, even though the clearance requires that it be ope What should he do? Stop work and notify the Plant Superviso Open the valve and resume wor Verify system conditions are adequate for scope of maintenance.and-continue wor Open the valve, complete a new red tag and install it on the valv .
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93 LOR B4/RO QUESTION NO. 17 PT. VALUE: 1.00 REC ID: 876 ESF Transformer 21 output breaker 152-1501 to ESF Bus 15AA tripped open (reason unknown) and de-energized ESF Bus 15A The Division I diesel generator started and is now supplying power to ESP Bus 15A Which one of the following conditions, if it occurred, WOULD NOT trip OPEN the Division I diesel generator output breaker (152-1508)? a. Generator ground overcurrent b. LOCA c. Generator differential overcurrent d. Engine low lube oil pressure
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B4/RO QUESTION NO. 18 PT. VALUE: 1.00 REC ID: 1044 SBLC storage tank level is 4,900 gallons. Tank temperature is 90* Which one of the following identifies the normal range of sodium pentaborate concentration that will prevent entering a Tech Spec action statement? a. 13.0% - 28.5% b. 13.6% - 20.0% c. 13.6% - 15.2% d. 12.6% - 14.4%
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93 LOR B4/RO QUESTION NO. 19 PT. VALUE: 1.00 REC ID: 1423 . The handswitches for SRV B21-F051D on panels P150 and P151 have been taken to OF What would be the response of the Safety Relief Valve system if reactor pressure were to momentarily increase to 1105 psig? a. Six SRVs would ope b. SRVs F051B and F051D would ope c. SRV F051B would ope d. NO SRVs would open.
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ANNUAL REQUALIFICATION EXAM CONTINUED ***** 93 LOR B4/RO QUESTION NO. 20 PT. VALUE: 1.00 REC ID: 1202 The plant is operating in Mode 1, 100% powe Chemistry reported a Reactor Water conductivity of 2.0 pmho/cm at 0100 on 7/27/9 Condensate demins were changed out, reactor water conductivity was found to be 1.5 gmho/cm at 0100 on 7/28/9 All other chemistry parameters remain within their allowed limit Up until now no chemistry limit has been exceeded this yea Which one of the following describes the correct required action? a. Continue to search for source of chlorides. No additional action is required for another 48 hour b. Commence a normal plant shutdown, and proceed to Cold Shutdown within 16 hour c. Reduce power per IOI-2, scram at step 6.14 and continue to cool down to Cold Shutdown d. Be in at least Startup within the next 6 hours
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B4/RO QUESTION NO. 21 PT. VALUE: 1.00 REC IL: 894 During a special test, the Turbine Building NOB is controlling Hotwell level in manual from the 1H22-P171 pane The NOB should be communicating his actions to the Control Room via the . a. telephone b. portable radio c. Turbine Building auxiliary sound-powered phone O w M w
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PAGE 22 . ANNUAL REQUALIFICATION EXAM CONTINUED ***** 93 LOR B4/RO QUESTION NO. 22 PT. VALUE: 1.00 REC ID: 852 A plant shutdown from 100% power is in progres The Reactor Recirculation pumps will automatically downshift to slow speed when Feedwater flow decreased to lens than: %. % after a 15-second time dela %. % after a 15-second time dela l
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93 LOR B4/RO QUESTION NO. 23 PT. VALUE: 1.00 REC ID: 383 The Standby Liquid Control (SLC) System test tank is being used to add water to the RP Which one of the following components is in the OPEN position? Power supply breaker for MOV F001A, 52-15211 Power supply breaker for MOV F001B, 52-16313 Storage tank outlet valve F001 Test tank outlet valve F03 i
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, *****- AlNUAL REQUALIFICATION EXAM CONTINUED *****
93 IDR B4/RO QUESTION NO. 24 PT. VALUE: 1.00 REC ID: 1285 A is a symbol within the Emergency Procedures that should be returned to whenever its answer changes during the execution of the procedur a. black diamond b. red diamond c. black rectangle d. rectangle with an arrow on one end
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93 LOR B4/RO QUESTION NO. 25 PT. VALUE: 1.00 REC ID: 1139 The reactor is exactly critical with reactor power on Range 7 of the Intermediate Range Monitor Control rods are inserted such that - 0.0010 delta K/K is inserted in the cor Reactor pressure is 915 psi The reactor depressurizes through the main steam line drains to 815 psi (Assume the temperature coefficent of reactivity is 0.0001 delta K/K per degree F and all other reactivity factors stay constant.)
The reactor core will: become prompt critical, become supercritica remain exactly critical, become subcritica c J
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93 LOR B4/RO
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Answer Key kG J !# '- O'" * Su/4 93-30,3 93 LOR A3/RO A D C 1 B i A i D A C D 10. A 11. B 12. D 13. A 14. B 15. C l i A l
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! -93 LOR B4/SRO . .\ A i B -j C ; . A C c l C i D j B ; A- :
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GRAND GULF NUCLEAR STATION ANNUAL REQUALIFICATION EXAMINATION EXAM NAME: 93 LOR A3/SRO DATE ADMINISTERED: SRO OPERATOR: SECTION OPERATOR CATEGORY PERCENTAGE SCORE POINTS A. PLANT & CONTROL SYSTEMS 1 All work done on this exam is my ow I have neither given nor received ai Operator's Signature I i i i I
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w r GUIDELINES 1. Read each question carefully and thoroughly. Identify the number of parts. Highlight and separate key points. If you have questions, ask the instructor for clarificatio . Carefully review each of the four choices and select the one that most completely and correctly answers the question. Unless determined otherwise during the post-examination review process, only one choice is correc . Answer the questions you know first. Pace yourself to allow a set time for harder questions. Allow time to check your answer . Use a # 2 or # 2.5 lead pencil to completely fill in the blocks on the automated answer form. If you have to change your answer, ensure that you completely erase all marks from the undesired bloc RULES 1. All examinations are open reference, using materials that would normally be available to you in the Control Room. Other materials may also be provided if required to answer the question . To pass the examination, you must achieve a combined grade of 2 80.0% for Parts A and . You have a tota. of 90 minutes to complete this section of the examinatio . No talking during the examination is allowed. Do not disturb the class - raise your hand if you have a question. Talking or trading answers with other members of the class will result in an immediate failur . Only one student may leave the room at a time. Ask the instructor for permissio . After you complete your examination, assemble the questions, aids, answer form and all scrap paper into a package and give it to the proctor. Remember to sign the statement on the cover shee . Af ter you have turned in your examination, leave the examination area. If you are found in this area while the examination is still in progress, your license may be denied or revoked.
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SCENARIO 93/3 The-plant was operating at z .100% ' power near . EOC with-no'ino equipment when the following events occurred during previous shifts: o Approximately 10 hours ago, Reactor Recirc Pump "A" trippe The cause was a faulty protective relay'infCB-5A. Estimated time of repair.is two more; hours.LAll-Tech spec-required
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actions have been taken, o Four hours ago I&C calibrated the Standby Liquid Control bulk solution tank's level instrumen All other events and changes to plant status occurred on this shif Consider the following: o All data from the Control Room'and Tech Spec rounds should-be considered valid and within their periodicity. for the Day Shif The Day Shift rounds have not yet been reviewe O All indications (meters, indicating lamps, annunciators,. etc.) should be considered vali No spurious indications unless otherwise note No burned-out indicating or annunciator lamps'.
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a. Questions 1-11 ARE related
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to this scenario and are marked
* * * SCENARIO 93/3 at the~ to ) Answers should be based on actual conditions that may be observed in the simulator NO ) Some questions MAY refer to past or future conditions within this scenario. In such cases,'this information will be provided in the questio b. Questions 12-15 ARE NOT related to this scenario. Answers should be based on information given in the question ONLY, unless otherwise noted.
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***** ANNUAL REQUALIFICATION EIAM ***** ,
93 LOR A3/SRO .- l QUESTION NO. 1 'PT. VALUE: 1.00 REC ID:.1382
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* * * SCENARIO 93/3 * * * !
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choose from below the one statement that correctly describes the proper :;
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EMERGENCY PROCEDURE response co present Suppression Pool temperatur [ condition i
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i BOTH loops of Guppression Pool Cooling should be in service j t until Suppression Pool temperature decreases to < 95' !
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b. Only one loop of Suppression Pool Cooling is required to to be in service at this tim ; l c. The Reactor should immediately be scrammed and both loops . of Suppression Pool Cooling placed in servic !
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d. The Reactor should immediately be scrammed and rapidly ; depressurized, and both loops of Suppression Pool cooling -!
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93 LOR A3/SRO QUESTION NO. 2 PT. VALUE: 1.00 REC ID: 1370
* * * SCENARIO 93/3 * * *
Choose from below the one correct statement regarding operation of the Reactor Recirculation System under the present circumstance a. B33-F067A should remain shut to prevent reverse flow through the "A" Recirc. loo b. "B" Recirc. loop flow should be at least 40,000 gpm flow (but less than 44,600 gpm) to prevent excessive delta-t's with the "A" loo c. B33-F067A can be opened, but the "A" Flow Control Valve should be closed to prevent excessive reverse flow while allowing enough flow to clear the temperature interlock, d. B33-F067A should be re-opened to keep the delta-t's as low as possibl . M A w w - PAGE 3
***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/SRO QUESTION NO. 3 PT. VALUE: 1.00 REC ID: 1372
* * * SCENARIO 93/3 * * * ----- SRO/STA/SE ONLY -----
Given ALL available information regarding the status of the Standby Liquid Control System, choose from below the correct action, if any, required by Tech Spec a. No action required (SBLC is fully OPERABLE).
b. Verify SBLC tank temperature to be within the limits of Figure 3.1.5-1 once every 4 hours, c. Restore SBLC tank parameter (s) to within the required limits within 72 hours, or be in at least Hot Shutdown within the next 12 hour d. Restore SBLC tank parameter (s) to within the required limits within 8 hours or be in at least Hot Shutdown within the next 12 hour . - _ .
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PAGE 4 ANNUAL REQUALIFICATION EXAM CONTINUED ***** 93 LOR A3/SRO QUESTION NO. 4 PT. VALUE: 1.00 REC ID: 1374
* * * SCENARIO 93/3 * * *
Choose from below the one statement that describes the correct action regarding SSW B recirc valve P41-F006B if the operator were to start RHR Pump B right NO Valve will go FULL CLOSED automatically on valve position interlock b. Valve must be manually close c. Valve will remain FULL OPEN and cannot be remotely closed as long as SSW B is runnin d. Valve will go FULL CLOSED automatically when SSW flow is increased beyond the minimum flow setpoin ! i
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***** AlNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/SRO l l QUESTION NO. 5 PT. VALUE: 1.00 REC ID: 1384 l * * * SCENARIO 93/3 * * *
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The Duty Manager is concerned about the present Condensate /Feedwater System configuration.
l l Considering procedural AND operational limitations under PRESENT plant circumstances, is his concern justified? Why? l Yes. All three Condensate Pumps are procedurally required to be in service at the present power leve Yes. Feedwater pump suction pressure is dangerously lo c. No, as long as total feedwater flow remains below 16 mlbm/h d. No. Removing one Condensate Pump and Condensate Booster Pump from service is permitted at this power level anyway.
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/SRO
i QUESTION NO. 6 PT. VALUE: 1.00 REC ID: 1369
* * * SCENARIO 93/3 * * *
l i The STA reports the following results of the latest MON edit from
i the Powerplex computer: MTPF = 3.17 FDLRX = 0.87 MAPRAT = 0.63 l MFLCPR = 0.91 Regarding reactor power, what actions, if any, should be taken NOW in response to this report? a. No action required (the edit indicates normal parameters for the current plant conditions).
b. Recirc. flow should be further reduced to approximately 56 mlbm/hr to exit the Power-to-Flow regio c. Insert control rods to exit the current Power-to-Flow regio l d. Immediately scram the reactor and enter the Scram ONE ; l
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****'* ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 IDR A3/SRO QUESTION NO. 7 PT. VALUE: 1.00 REC ID: 1371
* * * SCENARIO 93/3 ** *
Choose from below the correct setpoint (in % rated thermal power) for the APRM flow-biased scram function under the present plant circumstance a. 40 b. 77 c. 100 d. 111 i l l
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/SRO QUESTION NO. 8 PT. VALUE: 1.00 REC ID: 1383
* * * SCENARIO 93/3 * * *
Choose the one statement below that best describes Emergency Procedure implementation recuirements under the present plant condition a. MUST enter the EPs; MAY exit when it is determined that the emergency no longer exists, b. MUST enter the EPs; MAY exit when Suppression Pool Cooling is in servic c. Entry into AND exit from the EPs is optional under these condition , d. Entry into the EPs is optional, but once entered MUST remain until all entry conditions have cleare .
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PAGE 9 ANNUAL ~REQUALIFICATION EXAM CONTINUED ***** ! 93 LOR A3/SR !
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' QUESTION NO. PT. VALUE:.-l.00 REC ID: 1377 "!
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* * * SCENARIO 93/3 * *.*
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l SELECT the one correct statement concerning how the LPCS injection: ! I valve would respond under present plant conditions if-a manual Di [
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, The valve will NOT open automatically NOR can it_be opened' .
manually from P601, with OR without the LOCA signa !
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^t The valve will NOT open automatically. It CAN be opened -I manually from P601, with OR without the LOCA signa l
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l The valve will open automatically with the LOCA signa It CANNOT be opened manually from P601,'with OR without j! the LOCA signa ' The valve can be opened manually from P601 NOW, but it will ! close automatically with the LOCA signa I
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93 LOR A3/SRO QUESTION NO. 10 PT. VALUE: 1.00 REC ID: 1420
* * * SCENARIO 93/3 * * *
Chemistry has requested that the Control Room perform the proper lineup for taking a PASS sample from the Reactor Recirculation pump discharge sample poin What valve manipulations, if any, need be performed? a. No additional manipulations required (system is in the correct lineup).
b. Send an operator to Area 10, 119' to open B33-F12 CLOSE B33-F127 and B33-F128. OPEN B33-F125 and B33-F12 d. Requested sampling lineup is OK, but B33-F019 and B33-F020 should be CLOSE l
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***** ~ ~hNNUAL REQUALIFICATION EXAM CONTINUED ***** 'I i1 93 LOR A3/SRO- l
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i QUESTION NO. 11- PT. VALUE: 1.00_ REC ID::1424-l
* * * SCENARIO-93/3f* * * i
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-Which one of-the following best describes the Tech Spec' action (s'~, )
if any,-that are required NOW regarding the CRD. system?
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b. Verify operability of C11-F122 OR close the. penetration '!f within four hour t
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within four hours OR isolate the penetratio :
, Be in Hot Shutdown within the next 12 hours and in Cold i
Shutdown within the following 24 hour : i
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/SRO QUESTION NO. 12 PT. VALUE: 1.00 REC ID: 1191 The reactor mode switch is in "STARTUP".
SELECT the one statement that describes a condition in which the Intermediate Range Monitoring (IRM) system is not functioning l ' correctly, a. IRM "A" indicates 110/125 of scale on range 7 and no rod block or scram signal is presen IRM "B" indicates 122/125 of scale on range 6, a rod block and a half scram is presen IRMs "D" and "A" both fail upscale and a reactor scram occurs, IRM "C" mode switch is placed to " STANDBY" ; a rod block and half scram occur l l l
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/SRO QUESTION NO. 13 PT. VALUE: 1.00 REC ID: 951 If the handswitch for SRV B21-F051A on Remote Shutdown Panel H22-P151 were taken to OFF, which of the following statements would be true? Consider the signals given as the ONLY signals presen B21-F051A will NOT open if CNLY Division 1 ADS logic initiate B21-F051A will open in the Safety mod B21-F051A will NOT open on a Division 1 Relief signt: B21-F051A will open ONLY if the Division 2 ADS logic initiates, l i I
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/SRO QUESTION NO. 14 PT. VALUE: 1.00 REC ID: 1200 When raising the MHC START DVC to reset the Main Turbine after a trip, the operator must stop momentarily when the (1) begin to open and wait for (2) to stabilize before continuin a. (1) HP Stop valves; (2) HP control fluid pressure (1) HP Stop valves; (2) LP control fluid pressure (1) LP Stop valves; (2) HP control fluid pressure (1) LP Stop valves; (2) LP control fluid pressure l l I
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***** AIMUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A3/SRO QUESTION NO. 15 PT. VALUE: 1.00 REC ID: 1367 Which of the following PASS system pathways has a valve in the sample flowpath that has an automatic isolation from NSSSS? Drywell atmosphere Suppression pool RHR A Recirc jet pump l
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93 LOR A3/ShD
**** F* 7F EXAM ****
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6*u/-f 93-3cc GRAND GULF NUCLEAR STATION ANNUAL REQUALIFICATION EXAMINATION EXAM NAME: 93 LOR B3/SRO DATE ADMINISTERED: SRO OPERATOR: SECTION OPERATOR CATEGORY PERCENTAGE SCORE POINTS B. ADMINISTRATIVE CONTROLS / 2 PROCEDURAL LIMITS All work done on this exam is my ow I have nelcher given nor received ai Operator's Signature
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GUIDELINES Read each question carefully and thoroughly. Identify the number of parts. Highlight and separate key points. If you have questions, ask the instructor for clarificatio . Carefully review each of the four choices and select the one that most completely.and correctly answers the question. Unless determined otherwise during the post-examination review process, only one choice is correc . Answer the questions you know first. Pace yourself to allow a set time for harder questions. Allow time to check your answer . Use a # 2 or # 2.5 lead pencil to completely fill in the blocks on the automated answer form. If you have to change your answer, ensure that you completely erase all marks from the undesired , bloc RULES 1. All examinations are open reference, using materials that would normally be available to you in the Control Room. Other materials may also be provided if required to answer the question . To pass the examination, you must achieve a combined grade of 2 80.0% for Parts A and . You have a total of 90 minutes to complete this section of the examinatio . No talking during the examination is allowed. Do not disturb the class - raise your hand if you have a question. Talking or trading answers with other members of the class will result in an immediate failur . Only one student may leave the roc 3 ;c a time. Ask the instructor for permissio . After you complete your examination, assemble the questions, aids, answer form and all scrap paper into a package and give it to the proctor. Remember to sign the statement on the cover * shee ' 7. Af ter you have turned in your examination, leave the examination area. If you are found in this area while the examination is still in progress, your license may be denied or revoke .
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***** ANNUAL REQUALIFICATION EXAM *****
93 LOR B3/SRO QUESTION NO. 1 PT. VALUE: 1.00 REC ID: 1189 A LOCA has occurred, resulting in a decreasing reactor water level inventor When MUST the crew start to line up the plant firewater system, if it is available, as an alternate means of increasing reactor level? a. Level cannot be maintained > +11.4".
b. Level cannot be maintained > -167".
c. Level cannot be maintained > -167" AND less than two injeccion subsystems can be lined u d. Level goes below -167" AND less than one injection subsystem can be lined u _ _ - _ _ _ _ _ _ -
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 2 PT. VALUE: 1.00 REC ID: 1076 A reactor cooldown is in progress, with RHR "A" in Shutdown Coolin Reactor pressure is 95 psi E12-F008 goes shut due to a spurious isolatio E12-F008 was subsequently re-opened and RHR "B" was placed in Shutdown Cooling The crew is preparing to align RHR "A" for LPCI Standb What special precaution should be considered in doing this? a. This evolution requires prior NRC concurrenc b. RHR A and B are particularly susceptible to an inter-system LOCA in this conditio c. A sudden loss of RPV level inventory may occu d. Opening the LPCI A suction valve could result in excessive water hamme *
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***** ANNUAL REQUALIFICATION EXAli CONTINUED *****
93 LOR B3/SRO QUESTION NO. 3 PT. VALUE: 1.00 REC ID: 1249 Wide Range level instrumentation is calibrated for 20 BTU /lba of feedwater inlet subcooling, while Narrow Range instrumentation is not. Why? a. Narrow Range's variable leg tap is above the feedwater inlet nozzle, and thus does not see the subcooled water, b. Narrow Range compensates for inlet subcooling by adjusting reactor pressure calibratio c. Narrow Range does not consider the presence of feedwate d. Wide Range uses feedwater inlet subcooling as compensation for inaccuracy due to its relatively wide range compared to Narrow Rang .
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 4 PT. VALUE: 1.00 REC ID: 1190 A station blackout has occurre The Div. III D/G is the only available source of 4.16KV powe Which one of the following conditions alone would prevent the use of Division 3 diesel generator to energize the Division 1 ESF bus? a. HPCS High Drywell Pressure Initiation signal is sealed i b. Annunciator "15AA UNDERVOLT LOCKOUT TRIP" (P864-1A-A3) is alarme RPV water level is -50" on Wide Range instrument d. Electricians have reported bus damage on ESF bus 16A . M ww M ww _- PAGE 5
***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 5 PT. VALUE: 1.00 REC ID: 1344 Technical Specification 3.3.7.5 requires that the Fuel Handling Area Ventilation system have an operable accident monito Which one of the following describes what constitutes an operable accident radiation monitor? a. SPING Channel 5 and AXM Channels 2, 3 and b. AXM Channels 2, 3 and c. GE Constant Flow Monitor and all AXM channel d. All SPING channels and the GE Constant Flow Monito ,
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION No. 6 PT. VALUE: 1.00 REC ID: 327 The reactor is in Mode 5 with individual control rod coupling checks in progres The monthly surveillanne of the SLC storage tank concentration has just been complete The results of the chemical analysis indicate a boron concentration of 17.5%. The storage tank temperature is 80 degrees Storage tank level is 4,850 gallon Which of the following BEST describes the actions that are required under these conditions? The SLC Storage Tank is within limits; therefore no action is
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require Write a Tracking LC . If any control rod is withdrawn past position 02, manually scram the reacto Insert all insertable control rods within one hou ,
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 7 PT. VALUE: 1.00 REC ID: 1152 During an ATWS, the RHR Service Water crosstie can be used for level control and/or restoration at any time, to maintain level between -167" and +5 to control level between -197" and the level to which it was lowered for Level / Power Contro ONLY when in Containment Flooding, because of the poor water qualit to restore and maintain level above -197".
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****-
93 LOR B3/SRO QUESTION NO. 8 PT. VALUE: 1.00 REC ID: 1101 A Site Area Emergency was declared approximately four hours ag All appropriate emergency response facilities are OPERATIONA Responsibility for communications with offsite agencies now belongs to the: Control Roo b. Technical Support Cente Emergency Operation Facilit Corporate Emergency Cente ) i
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 9 PT. VALUE: 1.00 REC ID: 1202 The plant is operating in Mode 1, 100% powe Chemistry reported a Reactor Water conductivity of 2.0 pmho/cm at 0100 on 7/27/9 Condensate demins were changed out, reactor water conductivity was found to be 1.5 pmho/cm at 0100 on 7/28/9 All other chemistry parameters remain within their allowed limit Up until now no chemistry limit has been exceeded this yea Which one of the following describes the correct required action? Continue to search for source of chlorides. No additional action is required for another 48 hour b. Commence a normal plant shutdown, and proceed to Cold Shutdown within 16 hour c. Reduce power per 101-2, scram at step 6.14 and continue to cool down to Cold Shutdown d. Be in at least Startup within the next 6 hours
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 10 PT. VALUE: 1.00 REC ID: 1051 In order to meet all of the Federal requirements of the Standby Liquid Control System, the system must be able to pump at least 5,803 pounds of sodium pentaborate to the reactor cor The purpose of this quantity of sodium pentaborate weight is to: a. bring the reactor from full power to a cold, xenon-free shutdown condition given a rod density of at least 70%. b. produce a concentration of 660 ppm in the reactor core within 90 to 120 minute c. shut the reactor down under hot conditions onl d. meet the 3% shutdown margin requiremen . O
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 11 PT. VALUE: 1.00 REC ID: 1227 An Instrument Air header break in the Turbine Building has resulted in the total loss of the system in the Containmen Which one of the following correctly describes the how the control rods are affected?. Rods will drift in. Reactor will scram on high Scram Discharge Volume leve The scram inlet and outlet valves and the Scram Discharge volume vent and drain valves all fail open, resulting in loss of RPV water inventory to the Suppression Poo Backup scram valves fail open, causing rods to immediately scra Scram air header will dump when pressure decreases to 65 psig, causing an immediate scra i
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***** ANNUAL REQUALIFICATION EXAM CONTIlWED *****
93 LOR B3/SRO + QUESTION NO. 12 PT. VALUE: 1.00 REC ID: 1157 Why does EP-3 direct the operator to concurrently enter EP-2 - when Suppression Pool temperature reaches 110 degrees? ,
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a. To ensure that a manual scram is inserted in case a scram has not yet already occurre b. So that the emergency depressurization that is now required can be accomplishe c. To ensure that all available Suppression Pool cooling is placed in servic d. Because initiation of SBLC is ALWAYS required at this ' temperatur . F r
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 13 PT. VALUE: 1.00 REC ID: 450 The reactor was operating at rated conditions when a large-break LOCA occurre All automatic actions occurre Reactor water level is stable at -210".
Chemistry reports that the post-scram coolant sample indicates an I-131 dose equivalent activity of 310 pCi/m What is the event classification? Unusual Event Alert Site Area Emergency General Emergency
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PAGE 14 ANNUAL REQUALIFICATION EXAM CONTINUED ***** 93 LOR B3/SRO QUESTION NO. 14 PT. VALUE: 1.00 REC ID: 1084 While heating up the Second Stage Moisture Separator / Reheaters, t'.le operator is cautioned against increasing the heating steam controller's output to > 90% in order to prevent: a. exceeding the 100*F/hr heatup rate limit for the MS/R' b. causing a HI-HI level condition in the Second Stage MS/R Drain Tan c. causing a steam flow imbalance between the A and B Second Stage MS/R' d. rolling the Main Turbine off its turning gea . M M war w4sr .- PAGE 15
***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 15 PT. VALUE: 1.00 REC ID: 1197 The Main Turbine is rolling at 1800 rpm and ready for synchronizatio The setting of the MHC Speed Setter should NOW be . a. 100% b. 0% c. 5% above actual turbine speed d. 5% below actual turbine speed
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 16 PT. VALUE: 1.00 REC ID: 889 SRO/STA/SE ONLY A reactor scram occurred from 85% power during a startu I&C is investigating the cause of the scram but has not been able to find the caus Which one of the following is the correct POST-TRIP ANALYSIS classification? a. Class b. Class I c. Class II d. Class I . - PAGE 17
***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 17 PT. VALUE: 1.00 REC ID: 1139 The reactor is exactly critical with reactor power on Range 7 of the Intermediate Range Monitor Control rods are inserted such that - 0.0010 delta K/K is inserted in the cor Reactor pressure is 915 psi The reactor depressurizes through the main steam line drains to 815 psi (Assume the temperature coefficent of reactivity is 0.0001 delta K/K per degree F and all other reactivity factors stay constant.)
The reactor core will: become prompt critica become supercritical, remain exactly critica become subcritica . A h H W -
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PAGE 18 ANNUAL REQUALIFICATION EXAM CONTINUED ***** 93 LOR B3/SRO QUESTION NO. 18 PT. VALUE: 1.00 REC ID: 1 Static inverter lY79 momentarily lost power from its normal DC sourc The alternate AC source automatically switched in to supply the loa What happens when normal DC power is restored? The inverter will re-energize but remain in the ALTERNATE SOURCE SUPPLYING LOAD mode until the local INVERTER TO LOAD button is depresse b. The inverter is " locked out" and will not re-energize and supply the load until it is manually rese c. The inverter will switch back to its normal DC source within about two second d. The inverter will re-energize, but will not accept the load until the local transfer switch is returned to the NORMAL OPERATION position i I l l l
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***** ANNUAL REQUALIFICATION EXAM CONTINUED ***** i 93 LOR B3/SRO
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QUESTION NO. 19 PT. VALUE: 1.00 REC ID: 845 SRO/STA/SE ONLY The plant is in STARTUP, = 3% power and at rated pressur During the performance of 06-OP-1C34-R-0001, " MAIN TURBINE /RFPT LL8" surveillance, the A RFPT fails to trip due to a faulty auxiliary rela Select the MOST APPROPRIATE action to take per the Technical Specification a. Enter the action requirements of Tech Spec 3. b. Correct the problem prior to entering Mode c. Write an LCO per 3.3.8, and correct the problem within 7 day d. Write an LCO per 3.3.8, and correct the problem within 72 hours.
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***** ANNUAL REQUALIFICATION EY.AM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 20 PT. VALUE: 1.00 REC ID: 956 The Control Room is abandoned and the Control Rod Drive Hydraulic System (CRD) is being utilized for RPV level contro CRD flow to the Reactor Vessel procedurally should be controlled by: Manually opening / closing the CRD Drive Water Filter Outlet valve C11-F083 at Area 10, 139' Aux. Bld Manually opening / closing the CRD Drive Water Pressure Pressure Control Valve Cll-F003 from the P151 pane Local manual control of the CRD Flow Control valve (C11-F002A/B). Throttling the CRD pump discharge valve (Cll-F217A/B).
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 21 PT. VALUE: 1.00 REC ID: 1423 The handswitches for SRV B21-F051D on panels P150 and P151 have been taken to OF What would be the response of the Safety Relief Valve system if reactor pressure were to momentarily increase to 1105 psig? a. Six SRVs would ope b. SRVs F051B and F051D would ope SRV F051B would ope d. NO SRVs would open.
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 22 PT. VALUE: 1.00 REC ID: 225 Which one of the following is required to red tag an air operated, fail open valve in the closed position?
- Jack the valve closed with an installed jacking device, Tag the hand switch for the valve in the closed positio Tag the valve's air supply ope Install an air bottle instead of normal operating ai I i
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 23 PT. VALUE: 1.00 REC ID: 1366 ! While performing a surveillance on the Post-Accident Sampling System, the Plant Chemist was unable to open B33-F127 (RW POST-ACC SMPL CTMT OTBD ISOL) . Select the one statement that correctly describes the reporting requirement , No NRC notification is require NRC Region II must be notified within one hou The NRC Operations Center must be notified within one hour and NRC Region II must be notified if the valve remains stuck for ;
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72 hour NRC Region II must be notified within 24 hours after the ' valve has been stuck for 72 hour .
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 24 PT. VALUE: 1.00 REC ID: 1232 The reactor is operating in Mode 1 with the "B" IRM failed upscale and bypasse While conducting surveillance 06-OP-1C51-W-0003, an unexpected Di II half-scram was receive Which one of the following events could have caused the half-scram under these conditions? APRM B's mode switch was taken to POWER / FLOW with the APRM not bypasse . IRM F's mode switch was mistaken for the APRM F modt switch and was taken out of OPERAT APRM F's meter selector switch was taken to COUNT with the APRM not bypasse APRM D fails downscal .
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR B3/SRO QUESTION NO. 25 PT. VALUE: 1.00 REC ID: 864 In which one of the following plant conditions is the Alternate Decay Heat Removal System procedurally allowed to be operated? The plant is in Refueling, with the head removed and the RPV cavity flooded. All pool gates have been remove No Shutdown Cooling loop is in service, The plant is in Hot Shutdown. No Shutdown Cooling loop is in servic The plant is in Refueling with the RPV head removed. The RPV cavity is drained. Shutdown Cooling B is in servic The plant is in Cold Shutdown. RHR A trips while in Shutdown Cooling. RHR B is tagged out. RHR "C" is in the Suppression Pool Cl.anup mod i
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 IDR B3/SRO
**** END OF EXAM ****
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ffay/n C%< ~ /
Cia /-/ 9 ) - 3 to GRAND GULF NUCLEAR STATION ANNUAL REQUALIFICATION EXAMINATION EXAM NAME: 93 LOR A4/SRO DATE ADMINISTERED: SRO OPERATOR: SECTION OPERATOR CATEGORY PERCENTAGE SCORE POINTS A. PLANT & CONTROL SYSTEMS 1 All work done on this exam is my ow I have neither given nor received ai Operator's Signature i _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ,
- , . M M war we s GUIDELINES 1. Raad eaca question carefully and thoroughly. Identify the n'imber o2 parts. Highlight and separate key points. If you have questior4s , ask the instructor for clarificatio . Carefully review each of the four choices and select the one that most completely and correctly answers the question. Unless determined otherwise during the post-examination review process, only one choice is correc . Answer the questions you know first. Pace yourself to allow a set time for harder questions. Allow time to check your answer . Use a # 2 or # 2.5 lead pencil to completely fill in the blocks on the automated answer form. If you have to change your answer, ensure that you completely erase all marks from the undesired bloc RULES 1. All examinations are open reference, using materials that would normally be available to you in the Control Room. Other materials may also be provided if required to answer the question . To pass the examination, you must achieve a combined grade of 2 80.0% for Parts A and . You have a total of 90 minutes to complete this section of the examinatio . No talking during the examination is allowed. Do not disturb the class - raise your hand if you have a question. Talking or trading answers with other members of the class will result in an immediate failur . Only one student may leave the room at a time. Ask the instructor for permissio . After you complete your examination, assemble the questions, aids, answer f orm and all scrap paper into a package and give it to the practor. Remember to sign the statement on the cover shee . After you have turned in your examination, leave the examinati n area. If you are found in this area while the examination is still in progress, your license may be denied or revoke . . . - = . . . , . -
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.FCENARIO 93/4 f
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'i The plant was. operating at.98% power, BOC,- at. Step 181'on Cu sl- ,
Rod Sequence . Document # 'l-6-000-A2-15 %dlen the shift. bega ; t
.The following events are scheduled for your: shift:. l
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o Conduct surveillance 06-OP-1N32-V-0001
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All other. events and changes to plant status actually. occurred on 'I this shif i consider the following: ' s o All data'from the Control Room and Tech Spec rounds should' ' be considered valid and within their_ periodicity for the Da ! Shif t i
- The' Day Shift rounds have not yet been-reviewe '
o All indications (meters, indicating lamps, annunciators,. , etc.) should be considered vali ~
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- No spurious indications unless otherwise note No burned-out indicating or annunciator lamps.- !
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a. Questions 1-12 ARE related to this scenario and are marked l
* * * SCENARIO 93/4 *** at thel to .i
1) Answers should be based on actual conditions that may be' observed in the simulator NO t
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2) Some questions MAY refer to past or future conditions within' this scenario. In such cases, this information'will be provided in the questio J
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b. Questions 13-15 ARE NOT related to this scenario. Answers should ; be based on information given in-the question ONLY, unless , otherwise note * i
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QUESTIONS 1-12
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i ANSWERS SHOULD BE BASED ON' ACTUAL INDICATIONS . OBSERVED IN THE SIMULATOR , t I i P i
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***** ANNUAL REQUALIFICATION EIAN ***** . j 93 LOR A4/SR :
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QUESTION NO. 1 PT. VALUE: '1.00 REC ID: 1397~
* * * SCENARIO 93/4 *'* * j .After Security reported steam coming.from the 185' elevation of the =l Aux. Bldg.,.the Shift Superintendent directed-Chemistry to monitor' !
radiation levels at the site boundary and offsit , Radiation levels were'found to be normal.- i i t The Roving NOA reports that recorder E31-R608/R611 indicates the ; i following Aux. Bldg. steam tunnel temperatures:
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Ambient = 162*F
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delta-T = 58'F
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Choose the one statement below that best describes what action should be taken NOW per the Emergency Procedure l
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a. Scram and emergency depressurize the reacto j
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b. Scram the reactor and close the MSIV c. Manually isolate the Fuel Handling Area and Fuel Pool
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Sweep ventilation system ; d. Operate all Aux. Bldg. steam tunnel cooler ..
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***** ANNUAL REQUALIFICATION EXAM CONTIlmED *****
93 LOR A4/SRO QUESTION NO. 2 PT. VALUE: 1.00 REC ID: 1396
* * * SCENARIO 93/4 * * *
Choose from below the one condition that could be the cause of the present RPV level indication statu a. Build-up of non-condensible gases in a level instrument reference le b. Make-up valve to the affected level instruments' condensing pot is close c. Packing leak from instrument root valve B21-FXO7 d. Drywell temperature lower than instrument calibration condition .
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A4/SRO i QUESTION NO. 3 PT. VALUE: 1.00 REC ID: 1395'
* * * SCENARIO 93/4 * * *
Given present plant indications, which one of the following is the most significant risk being posed by the Fuel Pool Cooling and Cleanup System? a. FPCCU Pump auto-tri b. FPCCU filter /demin isolatio c. Overflow into Fuel Pool Sweep ventilation ductin d. High Spent Fuel Pool temperatur !
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A4/SRO QUESTION NO. 4 PT. VALUE: 1.00 REC ID: 1394
* * * SCENARIO 93/4 * * *
ASSUME that the Operator-at-the-Controls reduces core flow to 50% core flow in order to reduce offgas activity below present level Ten minutes later, offgas pretreatment equilibrium activity is determined to be 2.75 E+ Chemistry and HP have been notified to take reactor coolant sample What action, if any, should be taken next? a. Continue reducing core flow to stay below the MSIV isolation setpoint agai b. No further action required since the power reduction to 50% core flow caused offgas pretreatment activity to decrease below present level c. Manually insert a Group I isolation due to its failure to automatically initiat d. Insert control rods and continue monitoring offgas pretreatment radiation level ; l
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***** ndNUAL-REQUALIFICATION EXAM CONTINUED.~***** ~!
'93 IAR.A4/SRO 'i
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QUESTION NO. 5 PT.'VALUE: 1.00- RECLID:-1392- !
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* * * SCENARIO 93/4 * * *
't Which one of the choices below most COMPLETELY' describes'the action if that the operator-at-the-controls should NOW take regarding thel 'f
.: t reactor control rods? I i
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. Scram the reacto ~!
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.i i Fully' insert the' drifting rods and reduce core flow to 60%.
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c. Attempt to.stop the outward drift of the control rods
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d. Attempt to WITHDRAW the drifting rods back to their~ -j i original position. If they won't stay-there, then locally <[ scram the rods and valve them ou l
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***** : ANNUAL REQUALIFICATION1 EXAM CONTINUED = ***** .
. 93-LOR A4/SR {
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: QUESTION NO.--6 PT.'VALUE:.1.00 REC ID: 1391 '
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* * * SCENARIO 93/4 *- * * !
The Plant Supervisor directs the ACRO-to cancel ALL the FAULT and-CRITEitIA lights associated with'the ATT-test problem.without I f de-energizing the ATT program itsel ;
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~What should the operator do?-
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a. Depress the CANCEL pushbutton on the ATT Control Panel-. l
b. Depress the ATT SUBGROUP SEL MSCV RESET PRGM pushbutton.on ! P680 and the CANCEL pushbutton on the ATT Control' Pane !
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c. Turn the ATT Control Panel power keyswitch (n) P870 to OFF-then back to O ! i
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d.-Depress the ATT SUBGROUP SEL MSCV AUTO OFF/AUT.ON pushbutto !
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***** ANNUAL REQUALIFICATION EXA14 CONTINUED ****=
93 LOR A4/SRO QUESTION NO. 7 PT. VALUE: 1.00 REC ID: 1393
* * * SCENARIO 93/4 ** * -------- SRO/STA/SE ONLY --------
What Tech Spec actions would be required if the response to the control rod problem revealed the following:
-- Rod 12-37 is stuck and cannot be moved by either scram or normal drive method Control rod 08-41 was fully inserted and declared inoparabl a. Be in Hot Shutdown within the next 12 hour b. Check for adequate shutdown margin within 12 hours and restcre at least one rod to OPERABLE within 48 hours or be in Hot Shutdown within the next 12 hour c. Restore ALL rods to OPERABLE within 48 hours or be in Hot Shutdown within the next 12 hour d. Be in at least STARTUP within the next 6 hours, HOT SHUTDOWN within the following 6 hours and COLD SHUTDOWN within the subsequent 24 hour . . . . , ~ . . . . . . .., . . .- t r
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*****- ANNUAL.REQUALIFICATION_-EXAM CONTINUEDL ***** . l
, 93 LOR _A4/SRO !, QUESTION NO. 8 PT.-VALUE: 11.00 REC'ID:~ 138 ?!
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* * * SCENARIO 93/4 ** *J j r
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Choose from below the correct flow-biased APRM ROD BLOCK TRIP Li i SETPOINT under'the present plant' circumstance '! P
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a. 86% -' i b. 92% l t c. 106%
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A4/SRO QUESTION NO. 9 PT. VALUE: 1.00 REC ID: 1419
* * * SCENARIO 93/4 * * *
If a valid LSSS LOCA were to occur NOW, DG Cooling Water Inlet valve P41-F018B would . remain closed open open but then close when no subsequent diesel start occurred remain closed until the diesel achieves rated speed, then it would open
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 IAR A4/SRO QUESTION NO. 10 PT. VALUE: 1.00 REC ID: 841
* * * SCENARIO 93/4 *** \
Which one of the following would explain current status of the Reactor Feed to system (including controls and protective devices)? a. The RFP's ave failed to respond to a valid trip signal and should be ml1741 ally trippe ' b. The system is oper Nqrmall c. The system is responding to owly to the reduction in reactor powe One of three parallel RFP discharge pressure
%tcheshas has failed hig k
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e i QUESTION No.'11. 'PT.=VALUE: 1.00 REC ID: 1245! ! i
* * * SCENARIO 93/4* *.*
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i How will SSW A RECIRC valve P41-F006A respond if a valid LSSS i LOCA actuation ~were to occur right now? f
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. . Valve will ope !
b.- Valve will remain close l i
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' Valve is interlocked closed for one hour. It may then be manually opene q
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93 LOR A4/SRO~
:ij QUESTION NO. 12 PT. VALUE!.1.00 REC ID:-858 i * * * SCENARIO.93/4 * *-*' ,
i Which one of the following accurately' describes'the'present status i
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of the Reactor Feedwater Level Control System?
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prevented from being able to control.leve1'regardless of l selection statu !
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b. A comparator circuit has recognized a level difference l among the three Narrow Range level instruments, but no other j automatic actions have taken plac I c. A comparator circuit has automatically selected the "C"
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Harrow Range instrument to replace the "B" instrument'ifr-the "B" instrument should be selected for level contro ] I
. . i d. The "B" Narrow Range level instrument should be-manually .
de-selected from the level control averaging circui f e
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- QUESTIONS 13-1 , ARE NOT , a SPECIFICALLY RELATED I
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TO THIS SCENARIO : i _____________________________
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ANSWERS SHOULD BE BASED ON l SYSTEM KNOWLEDGE AND ANY: l INFORMATION GIVEN IN THE QUESTION j m
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93 LOR A4/SRO 1 i
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O QUESTION NO. 13 . PT . VALUE: 1.00- REC ID: 1353 (
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-Evaluate,the control room indications provided below'(NOT on the simulator); and determine . the present . status of the _ Stand'by Liquid -
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control System:
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SLC operation is required due to an^ATWS' condition.
g White SQUIB VALVE READY' lights are.0FF SLC SYS A and B OOSVC alarms received i l Amber SQUIB A and'B LOSCONT OR PWR LOSS lights are ON l
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'1C41-F031 is OPEN 1C41-F008 is OPEN ~!
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SLC A and B pumps are running
, SLC is operating normall ,
J SLC would not be inop if E22-F036 was close l
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' SLC is inop because C41-F001A/B cannot ope 'l l SLC is operable since C41-F031 can be closed from the ' control'
room.
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***** ANNUAL REQUALIFICATION EXAM CONTINUED *****
93 LOR A4/SRO QUESTION NO. 14 PT. VALUE: 1.00 REC ID: 955 At what point in the SSW systems do the SSW flow indicators on the Remote Shutdown Panels measure system flow? a. System discharge flow o. System return flow c. RHR A heat exchanger flow d. The sum of RHR A heat exchanger and D/G 12 Jacket Water Cooler flo <
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93 LOR A4/SRO QUESTION NO. 15 PT. VALUE: 1.00 REC ID: 1386 The NOB sent to investigate an inverter 1Y97 trouble alarm observed the following: DC INPUT = 112 VDC AC OUTPUT = 112 VAC INVERTER SUPPLYING LOAD light = On ALTERNATE SOURCE SUPPLYING LOAD light = Off IN SYNC light = Off PRECHARGE light = On He asks if the Control Room wants him to manually transfer source What should he be told? Why? a. No. UPS sources should never be swapped when they are not in synchronizatio b. No. Equipment damage would occur due to an incomplete precharg Yes. Inverter failure is imminen d. Yes, as long as he does it ONLY by depressing the ALTERNATE SOURCE TO LOAD pushbutto ..
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PAGE 16 ANNUAL REQUALIFICATION EXAM CONTINUED ***** 93 14R A4/SRO
**** END OF EXAM **** .
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/5'{c JSen - One W Skh/ 9.9-3 rv GRAND GULF NUCLEAR STATION ANNUAL REQUALIFICATION EXAMINATION EXAM NAME: 93 LOR B4/SRO DATE ADMINISTERED:
SRO OPERATOR: SECTION OPERATOR CATEGORY PERCENTAGE SCORE POINTS B. ADMINISTRATIVE CONTROLS / 2 PROCEDURAL LIMITS All work done on this exam is my ow I have neither given nor received ai Operator's Signature
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we Q GUIDELINES 1. Read each question carefully and thoroughly. Identify the number of parts. Highlight and separate key points. If you have questions, ask the instructor for clarificatio . Carefully review each of the four choices and select the one that most completely and correctly answers the question. Unless determined otherwise during the post-examination review process, only one choice is correc . Answer the questions you know first. Pace yourself to allow a set time for harder questions. Allow time to check your answer . Use a # 2 or # 2.5 lead pencil to completely fill in the blocks on the automated answer form. If you have to change your answer, ensure that you completely erase all marks from the undesired bloc RULES 1. All examinations are open reference, using materials that would normally be available to you in the Control Room. Other materials may also be provided if required to answer the question . To pass the examination, you must achieve a combined grade of 2 80.0% for Parts A and . You have a total of 90 minutes to complete this section of the examinatio . No talking during the examination is allowed. Do not disturb the class - raise your hand if you have a question. Talking or trading answers with other members of the class will result in an immediate failur . Only one student may leave the room at a time. Ask the instructor for permissio . After you complete your examination, assemble the questions, aids, answer form and all scrap paper into a package and give it to the proctor. Remember to sign the statement on the cover ' shee . Af ter you have turned in your examination, leave the examination area. If you are found in this area while the examination is ; still in progress, your license may be denied or revoke I l I i
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93 LOR B4/8RO QUESTION NO.1 1 PT. VALUE:_1.00 REC ID: 1345 Each plant ventilation system that releases to the environment is required by Tech Specs to have an operable effluent stack flow monito Each of these systems has two such monitors -- a normal channel _and a redundant channe . Which one of the following correctly describes the relationship of these monitors to Tech Spec requirements? a. The normal channel MUST be operable to meet the specificatio The redundant channel may only be used to estimate flow if the normal channel is ino b. EITHER an operable normal OR redundant channel meets the requirements of the specification, since one is entirely independent of the othe c. BOTH the normal AND redundant channels MUST be FULLY capable of generating an accurate stack flow signal in order to meet the requirements of the specificatio If the normal channel becomes inop, it is not necessary to enter the LCO for 72 hours as long as the redundant channel is operabl ,
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93 LOR B4/SRO 1 QUESTION NO. 2 PT. VALUE: 1.00 REC ID:-1194 zWhich one of the following correctly lists the equipment whose vacuum trips.-'can be bypassed without having_to install jumper wires , or pull relays? a. MSIVs,. Bypass Valves and the reactor feed pump b. MSIVs and the reactor feed pump c. Bypass Valves and MSIV d. Reactor feed pumps and the Main Turbin .,-
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*****- ANNUAL REQUALIFICATION EXAM CONTINUED ***** j 93 LOR-B4/SRO
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QUESTION NO. 3' PT. VALUE: 1.00 -REC ID: 1204'
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Before rolling the' Main Turbine to 1800 rpm, the Turbine Stress ?
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Evaluator should indicate a minimum temperature margin of' (1)
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! (1) 80 degrees; (2) prevent having to shut down1the turbin .
t (1) 55 degrees; (2)= avoid any speed' hold point l
: (1) 60 degrees; (2) avoid unnecessary thermal' stress on the HP l turbin ;
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93 LOR B4/SRO- ~E i
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QUESTION NO. 4 PT. VALUE: 1.00 REC ID: 1248 !
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f The plant _is at 55% powe ] SSW A was declared inop six hours ago when an'MWO to replace the motor' bearing was ATS'd. An LCO has been writte No other LCOs exis ;
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i The system responded normally except for O/A Fan 1Y47-C001B-B, which j
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failed to star : t The pump was shut down and placed in Standb j
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SELECT the one most correct requirement per Tech. Spec ;
, Be in at least HOT SHUTDOWN within 12 hours and in COLD !
i SHUTDOWN within the following 24 hour '!
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! Be in at least STARTUP within the next six hours, liOT_ SHUTDOWN !
l within the following six hours and COLD SHUTDOWN within the- j subsequent 24 hour l
! Restore SSW A to operable within 72. hours or be in at least j
- HOT SHUTDOWN within the next 12 hours and COLD SHUTDOWN l within the following 24 hour i
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'l HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the :
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l 93 LOR B4/SRO l l QUESTION NO. 5 PT. VALUE: 1.00 REC ID: 1110 A GENERAL EMERGENCY has been declared due to a LOCA with evidence of minor core damage with a potential loss of containment l The Shift Superintendent, acting as the Emergency Director, recommends that a 2-mile radius be evacuate What responsibility does he have regarding follow-up on his Protective i
Action Recommendation (PAR) until he is relieved by the on-call Duty Manager /Offsite Emergency Coordinator? a. Calls all responding agencies within 30 minutes to ascertain l l the status of the PAR.
l b. Must obtain concurrence from the Duty Manager on the PAR.
! l c. Calls the Mississippi and Louisiana state emergency operations directors within 30 minutes to ascertain the status of the PAR. ; i d. Must obtain concurrence from the Offsite Emergency Coordinator l on the PAR.
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93 LOR B4/SRO QUESTION NO. 6 PT. VALUE 1.00 REC ID: 1170 The plant was operating at rated conditions when an ATWS occurre Several SRVs lifted and increased Suppression Pool temperature above 110*F, so SLC was initiate The crew is now inserting rods by driving and scramming the Under which one of the following conditions may SLC be terminated? All rods are at position 02 except one at position 0 All rods are in except one at position 02 and one at position 0 All rods are in except one at position 4 The Reactor Engineer says that subcriticality can be guaranteed to 200* L
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93 LOR B4/SRO QUESTION NO. 7 PT. VALUE: 1.00 REC ID: 1366 While performing a surveillance on the Post-Accident Sampling System, the Plant Chemist was unable to open B33-F127 (RW POST-ACC SMPL CTMT OTBD ISOL) . Select the one statement that correctly describes the reporting requirement No NRC notification is require NRC Region II must be notified within one hour, The NRC Operations Center must be notified within one hour and NRC Region II must be notified if the valve remains stuck for 72 hour NRC Region II must be notified within 24 hours after the valve has been stuck for 72 hour i
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93 LOR B4/SRO QUESTION NO. 8 PT. VALUE: 1.00 REC ID: 1224
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One of the immediate actions in the Reactor Scram ONEP is to place the Mode Switch in SHUTDOW However, the operator is cautioned to NOT perform this step if the Pressure Control System cannot maintain reactor pressure greater than 850 psi In this case, placing the Mode Switch in SHUTDOWN: will cause the MSIVs to CLOSE when pressure decreases to < 850 psig, thus removing pressure control capability through the Bypass valve bypasses the automatic MSIV closure at < 850 psig, and thus may cause further undesirable reactor depressurizatio bypasses ALL Group I isolations and thus may cause further undesirable reactor depressurizatio will close the MSIVs automatically, regardless of pressure, causing an SRV lift and a further reduction in reactor temperature and pressur l l l
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93 LOR B4/SRO QUESTION NO. 9 PT. VALUE: 1.00 REC ID: 1185 Which one of the following best describes the reason why EP-2A directs that, during an ATWS, the recite. pumps be downshifted to slow speed before they are tripped? a. Prevent tripping the Main Turbine on high RPV leve b. Prevent damage to the Recirc. pump c. Prevent damage to the Recirc. Flow Control Valve , d. Prevent excessive thermal transient on the RPV lower plenu i l I l i L -
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93 LOR B4/SRO QUESTION NO. 10 PT. VALUE: 1.00 REC ID: 394 Which of the following statements best describes what specific effect(s) a Standby Liquid Control (SLC) initiation has on the RWCU System? Starting "A" SLC pump isolates G33-F004, G33-F001 and G33-F25 Starting "A" SLC pump isolates G33-F004 ; starting "B" SLC SLC pump isolates G33-F001 and G33-F25 Starting "B" SLC pump isolates of G33-F001, G33-F004 and G33-F251 Starting "B" SLC pump isolates G33-F004; starting "A" SLC pump isolates G33-F001 and G33-F251
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93 LOR B4/SRO QUESTION NO. 11 PT. VALUE: 1.00 REC ID: 1262 The plant was operating at 85% power when a LOCA occurre The Plant Supervisor entered the Emergency Procedures and is now deciding whether level can be determine Choose from below the one situation in which the Wide Range level instrument CANNOT be use SITUATION DW TEMP CTMT TEMP RX PRESS WR LEVEL
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_________ _______ _________ ________ ________ i a 205*F 106*F 100 psig -96" b 225*F 147'F 185 psig -135"
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c 150*F 120*F 312 psig -139" i d 215'F 145*F 75 psig -125" i
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93 LOR B4/SRO QUESTION NO. 12 PT. VALUE: 1.00 REC ID: 1061 When turbine-generator output is less than 50%, main condenser vacuum is restricted to 2 22.5" Hg to: a. prevent damage to the last stage turbine blade b. maintain a sufficient margin to the low vacuum trip setpoin c. prevent overpressurizing the main condenser if a prompt turbine load increase should occu d. maximize turbine-generator efficiency.
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93 LOR B4/SRO QUESTION NO. 13 PT. VALUE: 1.00 REC ID: 402 A General Emergency has been declared due to a DBA LOC There is evidence of minor core damage (4%). Engineering predicts that Containment pressure will peak at 16 psig within the next 15 minute One hour later, the Dose calculator projects the following dose commitments: Site boundary: Two miles: Five miles: 5270 mrem WB 1112 mrem WB 387 mrem WB 6215 mrem Thyroid 3618 mrem Thyroid 940 mrem Thyroid Which one of the following describes the Protective Action Recommendations that should be made to offsite agencies: No evacuation of surrounding areas require Evacuate a two-mile radiu Evacuate a five-mile radius, Evacuate a five-mile radius and ten miles downwin .i
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93 LOR B4/SRO QUESTION NO. 14 PT. VALUE: 1.00 REC ID: 1158 A major LOCA has occurred Emergency depressurization is required due to exceeding the Suppression Pool's Heat Capacity Level Limi Where are the steps that detail how this is to be accomplished? a. RPV Flooding leg of EP-2 b. Containment Flooding leg of EP- c. Steps 16, 17 and 18 of EP- d. In the B21 SO I i _ . _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - - - . . _ - .
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93 LOR B4/SRO QUESTION NO. 15 PT. VALUE: 1.00 REC ID: 1192 Given the following plant conditions: Mode Switch position: STARTUP Reactor power: 55/125 on IRM range 4 (average) IRM status: All selected to Range 4 SRM status: "B" bypassed . SELECT the one statement that describes an operating condition that will cause a rod bloc SRM channel A indicates 7.0 E + 04 cps and its detector is fully inserte SRM channel C indicates 5.0 E + 01 cps and its detector is partially inserte IRM channel B indicates 30/125 of scale and its detector is fully inserte IRM channel F indicates 8/125 of scale and its detector is partially inserte J
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93 LOR B4/SRO QUESTION NO. 16 PT. VALUE: 1.00 REC ID: 230 A Local Leak Rate Test is being performed on an RHR systea containment penetration during an RF The Technician performing the test notes that the valve lineup is not satisfactory for an accurate tes Which of the following statements best describes how the required change to the valve lineup can be made? Changes must be made through a 3-signature TC The LLRT must be stopped and the specific test has to be re-written and approved by the PSR A " pen and ink" change can be made by the LLRT Coordinator and reviewed by a qualified technical reviewe The technician performing the test can make a " pen and ink" change and notify the Shift Supt. when the test is complete
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93 LOR B4/SRO QUESTION HO. 17 PT. VALUE: 1.00 REC ID: 890 SRO/STA/SE ONLY Lightning struck in the vicinity of the switchyard, causing a generator tri An investigation shows that no damage was done due to the lightning strik During the event level was maintained between +15 and +47 inche Bypass valves operated to maintain pressure with no SRV actuation Choose the correct event classification in accordance with the Post Trip Analysis procedur Class Class I Class II Class IV.
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< 93 LOR B4/SRO QUESTION NO. 13 PT.'VALUE: 1.00 REC ID: 1045'
: Federal-regulations nominally require that the Standby Liquid Control System for'the size reactor vessel used at GGNS must maintaib-a 13%
solution of sodium pentaborate in its storage tan However, GGNS is specifically required to maintain a minimum 13.6% solutio GGNS is required to maintain a higher-than-normal boron concentration
'in order to compensate for:
a. mixing irregularity, since SLC is injected through'the HPCS sparge b. solution plating.in the unusually long run of injection pipin the SLC pumps not being able to pump the required 86 gp d. reduced shutdown margin for this operating cycl ~ L
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93 LOR B4/SRO QUESTION NO. 19 PT. VALUE: 1.00 REC ID: 952 A red light illuminated for one of the six Safety Relief Valves on Remote Shutdown Panels 1H22-P150 and 1H22-P151 indicates: a. the tailpipe pressure switch for the associated SRV has actuate b. the SRV's "A" solenoid (P150) or "B" solenoid (P151) is energize c. a limit switch within the SRV has made contact to indicate that the valve is ope d. a limit switch within the SRV's air accumulator indicates a low pressure condition in the accumulator.
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93 LOR E4/SRO QUESTION NO. 20 PT. VALUE: 1.00 REC ID: 876 ESF Transformer 21 output breaker 152-1501 to ESF Bus 15AA tripped open (reason unknown) and de-energized ESF Bus 15A The Division I diesel generator started and is now supplying power to ESF Bus 15A Which one of the following conditions, if it occurred, WOULD NOT trip OPEN the Division I diesel generator output breaker (152-1508)? a. Generator ground overcurrent b. LOCA c. Generator differential overcurrent d. Engine low lube oil pressure t
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93 LOR B4/SRO QUESTION NO. 21 PT. VALUE: 1.00 REC ID: 1423 The handswitches for SRV B21-F051D on panels P150 and P151 have been taken to OF What would be the response of the Safety Relief Valve system if reactor pressure were to momentarily increase to 1105 psig? a. Six SRVs would ope b. SRVs F051B and F051D would ope c. SRV F051B would ope d. NO SRVs would open.
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PAGE 22 l ANNUAL REQUALIFICATION EXAM CONTINUED- *****. i 93 LOR B4/SRO l Li l
. . . ~ QUESTION NO. 22 PT. VALUE 1.00 REC ID: 1202 .The plant is operating _in Mode.1, 100% power.- .
Chemistry reported a Reactor Water conductivity; of 2.0 ymho/cm at , l 0100 on 7/27/9 l
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Condensate demins were changed out, reactor water conductivity.was F found to be 1.5 pmho/cm at 0100 on 7/28/9 . .
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All other chemistry parameters remain within their! allowed limits.-. ,i Up until now no' chemistry limit has been exceeded this yea j Which one of the following ' describes the correct required action?:
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s a. Continue to search for source of chlorides. No additional-
:t action is required for another 48 hour !
b. Commence a normal plant shutdown, and proceed to Cold Shutdow i within 16 hour I
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c. Reduce power per IOI-2, scram at step 6.14 and continue to ! cool down to Cold Shutdown d. Be in at least Startup within the next 6 hours
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93 LOR B4/SRO QUESTION NO. 23 PT. VALUE: 1.00 REC ID: 1076 A reactor cooldown is in progress, with RHR "A" in Shutdown Coolin Reactor pressure is 95 psi E12-F008 goes shut due to a spurious isolatio E12-F008 was subsequently re-opened and RHR "B" was placed in Shutdown Cooling The crew is preparing to align RHR "A" for LPCI Standb What special precaution should be considered in doing this? a. This evolution requires prior NRC concurrenc b. RHR A and B are particularly susceptible to an inter-system LOCA in this conditio c. A sudden loss of RPV level inventory may occu d. Opening the LPCI A suction valve could result in excessive water hamme l l
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93 LOR B4/SRO QUESTION NO. 24 PT. VALUE: 1.00 REC ID: 1139 The reactor is exactly critical with reactor power on Range 7 of the Intermediate Range Monitor Control rods are inserted such that - 0.0010 delta K/K is inserted in the cor Reactor pressure is 915 psi The reactor depressurizes through the main steam line drains to 815 psi (Assume the temperature t iefficent of reactivity is 0.0001 delta K/K per degree F and all other reactivity factors stay constant.)
The reactor core will: f become prompt critica become supercritica remain exactly critica become subcritica l i l \. e
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***** ANNUAL REQUALIFICATION EXAM CONTINUED ***** i 93 LOR B4/SRO QUESTION NO. 25 PT. VALUE: 1.00 REC ID: 845 !
SRO/STA/SE ONLY The plant is in STARTUP, = 3% power and at rated pressur During the performance of 06-OP-1C34-R-0001, " MAIN TURBINE /RFPT LL8" surveillance, the A RFPT fails to trip due to a faulty auxiliary rela Select the MOST APPROPRIATE action to take per the Technical Specification Enter the action requirements of Tech Spec 3. Correct the problem prior to entering Mode 1.
} c. Write an LCO per 3.3.8, and correct the problem within 7 day d. Write an LCO per 3.3.8, and correct the problem within 72 hour ; I l
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93 IDR B4/SRO
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