Text

Exam Rept 50-309/87-21OL on 870915-17.Exam Results:Three of Four Senior Reactor Operator Candidates Passed Exams & Received Licenses.Exam & Answer Key,Facility Comments & NRC Response to Comments Encl
	ML20236R469
Person / Time
Site:	Maine Yankee
Issue date:	11/09/1987
From:	Keller R, Norris B; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20236R461	List: ML20236R460; ML20236R469;
References
	50-309-87-21OL, NUDOCS 8711230301
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{{#Wiki_filter:, . .. U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT N0. 50-309/87-21(0L) FACILITY DOCKET NO. 50-309 FACILITY LICENSE. NO. OPR-36 < LICENSEE: Maine Yankee Atomic Power Company I 83 Edison Drive Augusta, Maine 04336 FACILITY: Maine Yankee EXAMINATION DATES: September 15-17, 1987 . jll4lf} C& ' ' 'C W u oya Barry S. Norris Date Senior Operations Engineer (Examiner / Inspector) l l Gj f y .,; c., n : '.p II I APPROVED BY: II Robert M. Keller, Chief, PWR Section Date Operations Branch Division of Reactor Safety l SUMMARY: Written and operating examinations were administered to four Senior Reactor Operator (SRO) candidates. Three of the candidates passed all portions of the examinations and received their licenses. One candidate failed the written examination. 1 8711230301 071116 , PDR ADOCK 05000309 ' V PDR i 0FFICIAL RECORD COPY .0L EXAM MAINE YANKEE - 0003.0.0 11/29/80

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\\ REPORT DETAILS ! l TYPE OF EXAMINATIONS: Replacement I EXAMINATION RESULTS: ] l SR0 l l Pass / Fail l .. } l l l l l l J l Written l 3/1 l i l l l l l l l Operating l 4/0 l l l l l l 1 ' l Overall l 3/1 l . I l I _ CHIEF EXAMINER AT SITE: B. S. Norris, USNRC - l OTHER EXAMINERS: R. M. Keller, USNRC i L. S. Defferding, PNL j q 1. The following is a summary of generic strengths and deficiencies noted on

the operating examinations. This information is being provided to aid the i , licensee in upgrading license and requalification training programs. No l licensee response is required. ' STRENGTH All four of the candidates were knowledgeable with respect to the l administrative requirements of a senior reactor operator at Maine Yankee. DEFICIENCIES All four of the candidates appeared unsure when discussing operations a. regarding fuel handling. b. Two of the candidates were " Instant SR0s"; that is, not previously licensed as Reactor Operators (R0s) at Maine Yankee. The other two candidates were " Upgrade SR0s"; that is, an RO who upgraded his license to an SRO. _ _ _ _ _ _ _ _- - -Y

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1 The two Instant SR0s were reluctant to make a decision during the simulator portion of the examinations. This was especially obvious when compared to the two Upgrade SR0s who were very decisive. i c. As the panel operators, all four of the candidates were slow to j silence /acknowlege alarms when involved in an evolution that was I not an abnormal or emergency condition. During emergencies, the panel operators would silence the alarms without determining which

annunciator (s) were alarming. ] ! 2. The following is a summary of generic deficiencies noted .from the grading l of the written examinations. This information is being provided to aid the licensee in upgrading license and requalification training programs. No licensee response is required. l l a. The candidates were unable to determine the resultant system flow and pressure for pumps in parallel and in series. The candidates were provided the system curve and_the pump characteristic curves. l b. The candidates were unable to state the fail position of air operated ' valves on a loss of air pressure, i c. The candidates were unable to list the immediate action steps in the l " Response Not Obtained" column for emergency boration in accordance with the Emergency Operating Procedures. d. The candidates were unable to identify unexplained leakage from the reactor coolant system when provided with the latest leakage reports. e. The candidates were unable to state what actions should be taken when I a Safety Injection tank isolation valve was logged as shut for greater l than two hours. (This is a one-hour action statement in the Technical Specifications.) 3. Personnel Present at Exit Interview: , NRC Personnel B. S. Norris, Chief Examiner R. J. Freudenberger, Resident Inrpector NRC Contractor Personnel L. S. Defferding, PNL OFFICIAL RECORD COPY OL EXAM MAINE YANKEE - 0005.0.0 11/29/80

1 . -4- . Facility Personnel W. Ball, Operations Coordinator, Simulator Group M. Evringham, Operations Training Section Head J. Frothingham, Manager, Operations Department J. Kirsch, Supervisor, Operations Training B. O'Brien, Senior Instructor A. Shean, Manager, Training 4. Summary of comments made at the exit interview: a. The NRC discussed the generic strenthgs and weaknesses noted on the operating examinations, see paragraph 1. for details. With respect to the candidates actions regarding the alarms, the facility stated that this is not normal; and that they, in fact, emphasize the importance of acknowledging alarms in a timely manner and knowing which alarms are being silenced. b. The NRC noted that the plant was clean from both a radiological and j housekeeping standpoint. c. The NRC raised a concern with respect to the availability of the keys to the remote shutdown panels and the vital switchgear. The keys are , , I stored in yellow boxes near the respective panels, these boxes are I ' neither locked nor alarmed. Two adverse conditions could arise from i this situation: i 1. The keys would not be available when they are needed in an l emergency. 2. The keys would be used by an unauthorized individual to take control of vital equipment away from the Control Room. This has been discussed with and will be tracked by the NRC Resident Inspector. d. The NRC noted that a possible plant design deficiency was noticed during one of the simulator scenarios. Vital 120 volt AC buses 2 l and 3 were cross-connected to the same power supply in accordance l with the operating procedures, that power supply was subsequently deenergized. The simulator instructors stated to the NRC examiners that there was not a worse combination of buses to be deenergized for affecting the plant controls and indications. By design, these two buses can only be cross connected to each other. The facility noted the concern and committed to research the condition. . The NRC Resident Inspector will track this concern. ' __ - - - -. -- . - _

. -5- . e. The NRC stated that two concerns from a requalification program inspection conducted in June, 1987 were re-inspected and are considered closed. These concerns were: 1. During simulator evaluations, all SR0s were not evaluated in a- supervisory position on their ability to use the Emergency Operating Procedures (E0Ps) to mitigate the consequences of an accident. Subsequently, the Maine Yankee Simulator Evaluation Guidelines (CRS-1) have been changed to require all SRO's to be evaluated using the E0P's while in a supervisory position. l 2. After a facility administered written requalification examina- tion, a potential weakness was identified in the area of Instrumentation and Control (I&C) that was not factored into the next requalification cycle. Subsequently, a review of the Licensed Operator Decertification Course for 87/88 indicated that the I&C portion of the appropriate systems (nuclear instrumentation, feedwater control, etc.) would receive increased emphasis. Additionally, the program has been revised to require a statistical analysis of the examination results and, as necessary, incorporated into the next requalification cycle. 5. The written examination was reviewed by the facility, their comments are enclosed as Attachment 2. The NRC response to the comments is enclosed as Attachment 3. l 6. Maine Yankee has certified their simulator to the NRC in accordance with l 10CFR55.45(b)(5)(i). Attachment 4 is the Simulator Facility Fidelity Report as required by the Examiner Standards, ES-104. l l Attachments: i 1. SRO Written Examination and Answer Key l 2. Facility Comments on Written Examination 3. NRC Response to Facility Comments 4. Simulation Facility Fidelity Report 0FFICIAL RECORD COPY OL EXAM MAINE YANKEE - 0007.0.0 11/29/80

. l - i ATTACHMENT 4 l SIMULATION FACILITY FIDELITY REPORT j Facility Licensee: Maine Yankee Facility Licensee Docket No. : 50-309 Facility Licensee No.: DPR-36 Operating Examinations Given At: Maine Yankee Simulator Operating Examinations Given On: September 16-17, 1987 ( During the conduct of the simulator portien of the operating examinations , identified above, the following performance discrepancies were observed: ' 1. The smallest leak rate for a steam generator tube leak is 10 gpm. By Maine Yankee procedures, a munual reactor trip is required. To train on a small tube leak, the facility states that thty can " work around" the problem with the leak being elseshere and everriding the alarms for the secondary process radiation monitors. l 2. The simulator does not have the ability to mimic manual operation of ali the valves on the main control board. An example is FW-M-19 and FW-fi-20,

the discharge valves on the motor driven main feed pumps. During one of ' the scenarios, it was not possible for the candidater to implement the Emergency Operating Procedure for a loss of heat sink (FR-H.1). Enclosed as a part of this attachment are the ES-302 " Simulator Scenario Events" forms. 1 0FFICIAL RECORD COPY OL EXAM MAINE YANKEE - 0008.0.0 11/29/80 . - _ _ _ _ _ _ -

. ! . U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT 1 EXAMINATION REPORT NO. 50-309/87-21(OL) FACILITY DOCKET NO. 50-309 FACILITY LICENSE NO. DPR-36 LICENSEE: Maine Yankee Atomic Power Company 83 Edison Drive j Augusta, Maine 04336 ~ FACILITY: Maine Yankee l 1 EXAMINATION DATES: September 15-17, 1987 ^ CHIEF EXAMINER: ~ ~ r y S. No'rris ' Date' W 9, /f F 7 j nior Operations Engineer (Examiner / Inspector) APPROVED BY: ) . M[kd7 ~ l Robert M. Kel1er, Chief, PWR Section Date a Operations Branch j Division of Reactor Safety i l SUMMARY: Written and operating examinations were administered to four Senior Reactor Operator (SRO) candidates. Three of the candidates passed all portions of the examinations and received their licenses. One candidate failed the written examination. 4 i ! l 1 !

. . REPORT DETAILS TYPE OF_ EXAMINATIONS: Replacement , l l EXAMINATION RESULTS: l 1 SR0 l . l Pass / Fail l ' I l l 1 I I l Written l 3/1 l l l 1 1 I I ! l Operating l 4/0 l l l l l l l l Overall l 3/1 l l l 1 l i CHIEF EXAMINER AT SITE: B. S. Norris, USNRC j OTHER EXAMINERS: R. M. Keller, USNRC L. S. Defferding, PNL 1. The following is a summary of generic strengths and deficiencies noted on the operating examinations. This information is being provided to aid the licensee in upgrading license and requalification training programs. No licensee response is required. , STRENGTH All four of the candidates were knowledgeable with respect to the administrative requirements of a senior reactor operator at Maine Yankee. DEFICIENCIES All four of the candidates appeared unsure when discussing operations a. regarding fuel handling. b. Two of the candidates were " Instant SR0s"; that is, not previously licensed as Reactor Operators (Ros) at Maine Yankee. The other two candidates were " Upgrade SR0s"; that is, an R0 who upgraded his license to an SRO. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ . _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ - _ ___-_ _-_________ _ _ _ ___ -

___ ____ _-- -- , . ! -3- ! . l The two Instant SR0s were reluctant to make a decision during the simulator pcrtion of the examinations. This was especially obvious when compared to the two Upgrade SR0s who were very decisive. , 1 l c. As the panel operators, all four of the candidates were slow to silence /acknowlege alarms when involved in an evolution that was not an abnormal or emergency conditicn. During emergencies, the panel operators would silence the alarms without determining which annunciator (s) were alarming. , 2. The following is a summary of generic deficiencies noted from the grading ~ , of the written examinations. This information is being provided to aid ' the licensee in upgrading license and requalification training programs. No licensee response is required. i a. The candidates were unable to determine the resultant system flow and pressure for pumps in parallel and in series. The candidates were provided the system curve and the pump characteristic curves. b. The candidates were unable to state the fail position of air operated l valves on a loss of air pressure. ' c. The candidates sere unable to list the immediate action steps in the " Response Not Obtained" column for emergency boration in accordance , with the Emergency Operating Procedures, i d. The candidates were unable to identify unexplained leakage from the 4 reactor coolant system when provided with the latest leakage reports. ' e. The candidates were unable to state what actions should be taken when a Safety Injection tank isolation valve was logged as shut for greater than two hours. (Thi: is a one-hour action statement in the Technical Specifications.) l l 3. Personnel Present at Exit Interview: NRC Personnel B. S. Norris, Chief Examiner R. J. Freudenberger, Resident Inspector NRC Contractor Personnel L. S. Defferding, PNL 1 l l L__._..____ _ _ _ _ _ . _ . _ _ _ . _ _ _ . . _ _ . _ _ _ . _ _ _

4 , . _4 . Facility Personnel W. Ball, Operations Coordinator, Simulator Group , M. Evringham, Operations Training Section Head ' J. Frothingham, Manager, Operations Department J. Kirsch, Supervisor, Operations Training B. O'Brien, Senior Instructor A. Shean, Manager, Training 4. Summary of comments made at the exit interview: a. The NRC discussed the generic strenthgs and weaknesses noted on the operating examinations, see paragraph 1. for details. j With respect to the candidates actions regarding the alarms, the ) facility stated that this is not normal; and that they, in fact, emphasize the importance of, acknowledging alarms in a timely manner 1 and kno' ing which alarms are being silenced. w i b. The NRC noted that the plant was clean from both a radiological and housekeeping standpoint. l The NRC raised a concern with respect-to the availability of the keys j c. to the remote sh0cdown panels and the vital switchgear. The keys are I stored in yellow boxes near the respective panels, these boxes are ! neither locked nor alarmed. Two adverse conditions could arise from 1 this situation: ' 1. The keys would not be available when they are needed in an emergency. ' , 2. The keys would be used by.an unauthorized individudl to take I control of vital equipment away from the Control Room.

i This has been discussed with and will be tracked by'the NRC Resident l Inspector. ! d. The NRC noted that a possible plant design deficiency was noticed ! during one of the simulator scenarios. Vital 120 volt AC' buses 2 and 3 were cross-connected to the same power supply in accordance with the operating procedures, that. power supply was subsequently l deenergized. The simulator instructors stated to the NRC examiners that there was not a worse combination of buses to be deenergized for affecting the plant controls and indications. By design, these two buses can only be cross-connected to each other. l j The facility noted the concern and committed to research the conditio . The NRC Resident Inspector will track this concern. ./ _---___-_-_--_--L_-- - - - - . - - - - - - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - -

i . ' -5-. l . i e. The NRC-stated that two concerns from a requalification program inspection candacted in' June, 1987 were re-inspected and are considered closed. These concerns were: j ! l 1. During simulator evaluations, all SR0s were not evaluated in a ) I supervisory position on their &bility to use the Emergency l Operating Procedures (EOPs) to mitigate the consequences of an i accident. ., Subsequently, the Maine Yankee Simulator Evaluation Guidelines (CRS-1) have been changed to require all SR0's to be evaluated I using the E0P's while in a supervisory position. \\ 2. After a facility administered written requalification examina- j tion, a potential weakness was identi F,ed in the area of i Instrumentation and Control (I&C) that was not factored into l the next requalificati-on cycle. i Subsequently, a review of'the Licensed Operator Decertification j Course for 87/88 indicated that the I&C portion of the ) appropriate systems (nuclear instrumentation, feedwater control, i etc.) would receive in:reased emphasis. Additionally, the

program has been revised to require a statistical analysis of l the examination results and, as'necessary, incorporated into ! the next requalification cycle. 5. The written examination was reviewed by the facility, their comments are i enclosed as Attachment 2. The NRC response to the comments is enclosed ae 1 i Attachment 3. ' s l 6. Maine Yankee has certiff ed their simulator to the NRC in accordcnce with ! 10CFR55.45(b)(5)(i). Attachment,4 is the Simulator Facility Fidelity Report as required by the Examiner Standards, ES-104. l l Attachments: i 1. SRO Written Examination and Answer Key 2. Facility Comments on Written Examination i 3. NRC Response to Facility Comments 4. Simulation Facility Fidelity Report a i

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- - - _ _ _ _ __ _ _ . _ _ L ggt, gygao. 0 , stop iv a* ' ./ , U. S. NUCLEAR REGULATORY COMMISSION - /M8/J . SENIOR REACTOR OPERATOR L.ICENSE EXAMINATION f ! FACILITY: _MAINg_XONKEE____________ REACTOR TYPE: _P L48 -C E_ _ __ __ ___ _ __ _ _ _ _ DATE ADMINISTERED: _QZZ@241g________________ ] . i EXAMINER: _NQRRI@z_@._@t___________ CANDIDATE: _ @,,$h_b_ (E ,, i INSIBUCIlgN@_Ig_C6NDID81El j Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing ,! grade requires at least 70% in each category and a final grade of at least 80% Ex ami nati on papers will be picked up six (6) hours after the examin-cian starts. % OF DATEGORY % OF CANDIDATE'S CATEGORY _Y86UE_ _IQIOL ___SCQBE___ _YGLUE_,,_ ______________C@IE@gBX_____________ 1 .:t . .t 5" 3 _2E._20d _2E_@@ .________ 5. THEORY OF NUCLEAR POWER F'LANT ___________ OPERATION, FLUIDS, AND THERMODYNAMICS _25-@@__ _25t@@ ___________ __.____ 6. PLAN 7 SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION M, cd _EE EE Y _252.99 ______.__ 7. PROCEDURES - NORMAL,, ABNORMAL, ___________ EMERGENCY AND RADIOLOGICAL CONTROL _25-@9__ _2@z@@ ________ 8. ADMINISTRATIVE PROCEDURES, _..______ __ CONDITIONS, AND LIMITATIONS - 97 J.* iSC - CE_7_ ________% Totals ___________ Final Grade i 1 All work done on this examination is my own. I have neither given nor received aid. ' , -____ ____-________-_______-_ __ C :q ,u eA%,ge4a Candidate >s Signature -l S~ of". 6 (c', l7 ) s~to. 6 (f. per 2 0.r b (f.cm ,af & AfVT7 , , , , .. t. ./' ' .- 6 ,, l ~6 3 . _ c '0+ 'I y ,, A .'-_ \\ ' 4 _-

. . . _ ..-.w... - . . . - - . . .. a NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS Suring the administration of this examination the following rules apply: 1. Cheating on the examination means an automatic denial of your application - and could result in more severe penalties. 1 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating. ' 3. Use black ink or dark pencii gnl'y to facilitate legible reproductions. 4. Print your name in the blank provided on the cover sheet of the examination. 5. Fill in the date on the cover sheet of the examination (i f necessary). 6. Use only the paper provided for answers. 7. Print your name in the upoer right-hand corner of the first page 7f each j section of the answer sheet. 8. Consecuti vel y nun.ber each answer sheet, write "End of Category _,_" as appropriate. start each category on a new page, write gnly gn gne side of the paper, and write "Last Page" on the last answer sheet. 9. Number each answer as to category and number, for example, 1.4, 6.3. 10. Skip at least three lines between each answer. 11. Separate answer sheets from pad and place finished answer sheets f ace l down on your desk or table. ll 17. Use abbreviations onl y if they are commonly used in f acili ty literatur,.e 1 13. The point value for each question is indicated in parentheses after the i question and can be used as a guide for the depth of answer required. assumptions used to obtain 14. Show all calculations, methods, or an answer , to mathematical problems whether indicated in the question or not. t 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE DUESTION AND DO NOT LEAVE ANY ANSWER BLANK. I 16. If parts of the examination are'not clear as to intent,'ask questions.of the eg3 miner onl y. i 17. You must sign the statement on the cover, sheet that indicates that the work is your own and you have not received or been given assistance in compl eting the examination. This must be done after the examination has been completed. < i v . m ' ? , ' > xx , ._ _ c . . . w _

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.. ! . . 18. When you complete your examination, you shall: i a. Assemble your examinatter as follows: ) (1) Exam questions on cop. (2) Exam aids - figures, tables, etc.

(3) Answer pages including figures which are part of the answer. l b. Turn in your copy of the examination and all pages used to answer

the examination questions. l c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions. I d.. Leave the examination area, as defined by the examiner. If after

I leaving, you are found in this area while the examination is still in progrecs, your license may be denied or revoked. I l i ) 1 . s l l

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. _ . - . . . _. _ PAGE 2 ,5..' THEORY'OF NUCLEAR POWER PLANT OPERATION _ FLUID @z_AND i IHEBdODYN601CS. . QUESTION 5.01 (3.00) TRUE or FALSE a. The reactivity value of equilibrium xenon at 100% power is double the reactivity value at 50% power. Justify your answer. (1.50) b. The time to reach equilibrium xenon from 0% to 100% power is less than the time to reach equilibrium xenon from 100% to 0% power. Assume step changes in power. Justify your answer. (1.50) QUESTION 5.02 (1.00) As a result of core burnup, Beta-bar (eff) will chance; subsequently, this change in Dula-bar will result in a change in the Start-up Rate. How will Beta-bar and the Start-up Rate change if a small amount of posi ti ve reactivity were added at DOC and EOC. Assume the amount of reactivity added is equal at BOC and EOC? Choose the best answer below. (A) Beta-bar (eff) will increase and the Start-up Rate will be larger. (B) Beta-Bar teff) will increase and the Start-up Rate will be smaller. (C) Beta-bar (eff) will decrease and the Start-up Rate will be larger. (D) Beta-bar (eff) will decrease and the Start-up Rate will be smaller. QUESTION 5.03 (2.00) During a natur al circulation cooldown, the pressure in the steam generator is 835 psig. What is the minimum pressurizer pressure that would ensure that the RCS i s 45 deg F subcooled? Show your work and state all assumptions. 1 1 (***** CATEGORY 05 CONT:NUED ON NEXT PAGE *****) v ,.4 - , . , 5 . 13 9p f, ?^ I- n ':/l 'A .1 % a _ _

. - - - Sv__ISE98Y_9E_ NUCLE 68_EgWEB_E6GNI_gEEB8IlgN _ELUIDS _8ND PAGE 3 x 1 ISEBMgDYN6MICS . QUESTION 5.04 (3.50) The reactor is at 25% power, equilibrium Xenon and Samarium, baron. concentration is 1200 ppm, BOC, Group 5 rods are at 150 steps. Using the attached figures from the Maine Yankee Technical Data Book: What will be the final boron concentration if power is raised to 100%, ARD, equilibrium Xenon and Samarium? State which figure you use as I applicable. State all assumptions and show all work. . QUESTION 5.05 d(_. 50? J,7i You are in the process of a plant start-up, reactor power is steady at 10E(-2)% power. The reactor operator inadvertently moves the CEAs IN for 30 seconds. Assume rod worth is 0.0077 %drho/ step, an average decay constant of 0.07 sec-1, and a effective delayed neutron fraction of 0.006. Answer the tallowing assuming no f urther operator action: ) i a. Calculate the SUR immediately AFTER rod motion stops. Show all your work. (1.25) b . C :. _ p _ d te pert -bover-HGW-end-WHV--weuki thc CUn change ulICHCR t EOC" Me calcM etierw g ' /1;- ' O! ' " . the :m$ 4 cc-nditic" ' - -40.75) ' e a:__ = ,. c. Compared with part (a) tbove, HOW and WHY would the SUR change if it were j ust BEFORE rod motion is stopped? No calculation ,are nececsary. (0.75) d. What is the power 60 seconds AFTER ROD MOTION STOPS 7 (0.75) QUESTION 5.06 (3.00) In accordance with the Maine Yankee' Technical Specifications, there are FOUR parameters that are monitored and can be controlled by the reactor ' operator to ensure that the Specified Acceptable Fuel Design Limit (SAFDL) on the Departure from Nucleate Boi,1ing Ratio (DNBR) is not enceeded. Briefly explain HOW (Increase, Decreane, No Change) and WHY an INCREASE in ea:h of these parameters affects the DNBR. Assume ot.her parameters remain constant. l l (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) l l l l +4 > '

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Sta_IHEQBY_QE_NUGLE86_EgWEB_ELONI_QEEB8IlgN _ELQlgS _8Ng PAGE 4 ) 1 t D IHEBMggyN8 MIG 3 a 4 QUESTION 5.07 (2.50) i l 1 Describe HOW and WHY reactor power and Tavg will change after 2 minutes of Emergency Boration at each of the below initial powers. Assume no operator action is taken. Consider each case separately. Extend your answer to the point where stable conditions are again restored. NO numerical values are required, state whether the parameter will increase or decrease. NOTE: If power and/or temperature do NOT change, so state and explain why no change will occur. a. 100% power (1.50) b. .10E-3% power (1.00) l DUESTION 5.08 (2.00) a. For a reactor operating at a constant power and temperature, the THERMAL neutron flux near EOC will be (GREATER THAN, SMALLER THAN, or THE SAME AS) the flux near DOC? Justify your answer. 1 ! operatin a constant power and temperature, the FAST l b. For a reactor near EOC$g at be (GREATER THfiN, SMALLER THAN, or THE SAME AS) neutron flux the flux near BOC? (Assume the prompt / delayed neutron ratio remains constant.) Justify your answer. QUESTION 5.09 (2.00) Refer to Figure 5.1 attached: l l Determine the resultant system flow and discharge pressure for the below l combinations of centrifugal pumps. You may write on the figure and attach it to your answer sheets. , i a. Pump #1 in SERIES with Pump #2 b. Pump #2 in PARALLEL with Pump #3 , I l l l l ! (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) + a.

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. . . _ . ~ . . . . .. . 5ttlIHEQBY_QE_UyGLE88_EQUEB_EL8UI_QEESGIlgds_ELylDS _GNQ PAGE 5 t T_ H_ E_ R M_ _O_D Y N_ A M_ _I.C_ S_ . __ __ _ . QUESTION 5.10

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a. What condition is prevented from occurring by tripping Reactor Coolant Pumps (RCP) when subcooled margin drops below 25 F? (0.50) b ,. D u n c . i b s_- .J,y

ubcoolir,g: : u;cd to detr mir:c c:CP t r i p cri+"H n

g ~ t e rm roegs preccur- c- g ccund2 y r ocacter ceci7,t i.c c t c 2 d c y , D dept,;dcit I;CC pr..,;urc. ( 1. PP '- 9 c. State FOUR advantages of continued RCP operation during a Steam Generator tube rupture. (1.00) . I l (***** END OF CATEGORY 05

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- - _ _ _ , , - . . . . 6saieL@NI_Sy@IEMS_ DESIGN _COUI6Q6t_@ND_1NSI6pdENI@IlgN PAGE 6 t l . -QUESTION 6.01 (2.50) Answer the following concerning the Containment Isolation' System: < a. With the control switch in AUTO, state the logic required to generate a CIS "A" signal. (0.75) b. With the control switch in BLOCK, state the logic required to generate q a CIS "A" signal. (1.00) i c. State which valves receive a close command from a CIS "A" si g n a'l but not from an SIAS "A" or "B" sign &1. (0.75) . j l . l QUESTION 6.02 (2.80) Refer to the at.tached Figure NS-4-1: i How do the below CVCS valves fail on a loss of air pressure? Answer either l FAILS OPEN, FAILS CLOSED, or FAILS TO ______ POSITION ] a. Letdown Dr ag Valve (LD-A-9) l b. Letdown Pr essure Control Valve (LD-F-16) c. Deminera iner Bypass Valve (LD-T-36) d. Volume Coitrol Tank Diversion Valve (LD-A-51) e. Charging Pump Discharge to Charging Pa Seal Water Supply (CH-A-32) l f. Boric Acid to Charging Pump Valve (BA-A-80) 9 Seal Water Supply Pressure Control Valve (SL-P-3) 1 QUESTION 6.03 (2.00) Describe the automatic control signals provided by the below area radiation monitors. If applicable, include in your discussion when the control signal is in service. a. RM-6105 Containment Low Range Area Monitor b. RM-6107 Fuel Pool Area Moniter l l (***** CATEGORY 06 CONTINUED ON'NEXT PAGE *****) di'a ,, _ l

, . , _ . _ _ _ _ ._ > PAGE 7 j ,16i3_PLSNI_SYSIEMS_ DESIGN _CQNIBg61_GND_INgIBUMENI6I1ON z i , . QUESTION 6.04 (3.00) Explain'the effect on'the plant as a result of the below malfunctions. j Include in your explanation any automatic actions and setpoints, continue the explanation until steady state conditions are reached. Assume all systems operate normal except as stated and NO oper.ator action. Consider each case separately. a. The plant is in hot standby (Condition 6). The steam pressure setpoint for the Steam Dump and Turbine Bypass System is slowly reduced by 110 (1.00) psi from normal. b. Reactor power is 50%. The sequencing controller for THREE of the steam . dump valves f ails such that all three valves go full open. (1.00) c. Power is 100%. A turbine trip occurs while the Signal Interrupt Switch (1.00) is i n the TEST position. GUESTION 6.05 (2.50) 5 The plant was initially in Condition 7 with all systems aligned and operating normally. One hour ago a Safety Injection Actuation Signal was received on low pressurizer pressure. Using Figure NS-5-14 as a reference, and given the following current plant- conditions, state the status / position of the below listed pumps and val ves. (PUMPS: injecting, on recirc, or secured; VALVES: open or closed) Assume no operator action. NOTE: ignore the valve open/close indications on Figure NS-5-14. Conditions: RCS pressure == 500 psig, decreasing slowly Containment pressure = S psig, decreased f rom 27 psig 150,000 gallons RWST volume = i a. P-12A b. P-14A c. P-61A d. LSI-M-40 e. HSI-M-50 f. HSI-M-54 g. SIA-M-54 h. HSI-M-40 i. HSI-M-42 j. LSI-M-11 k. HSI-M-11 1. CS-M-91 i m. CS-M-1 n. CH-K-1 c. SIA-M-11 p. LSI-F-59 ) q. CS-M-66 r. CH-A-33 s. CS-A-55 t. SIA-A-47 i (***** CATEGORY 06 CONTINUED ON NEXT PAGE *****) J tl, % 'h f , y;3 4 ' Nb5:$b b) . > _ _ _ _ . . _ _ _ _ _ _ _ _______ . __ __

/

6tt_EL@NI_@Y@IEd@_DE@lGN _CONIB06t_6ND_lN@IBUdENI@IlON PAGE 8 t . QUESTION 6.06 (2.45) Describe the automatic response to a decreasing pressure in the water a. fire protection system. Include setpoints. ( 1 ', 00 ) b. Where can the fire pumps be manually started and stopped? (0.75) Why are the two fire pumps separated by a concrete enclosure? (0.70) c. 1 QUESTION 6.07 (2.75) For the below Reactor Protection System trips, list: 1. The trip setpoint l 2. The basis for the trip 3. Any automatic or manual inhibit, enable, or bypass signals a. Steam Generator pressure b. Pressurizer pressure i OUESTION 6.08 (3.00) Answer the following questions regarding the CEA Position Indicating circuits: a. The Reed Switch Assembly is used for what purpose (s) other than actual position indication? . Include setpoint(s), as appropriate. (1.80) b. The plant is at power and CEAs are being slowly inserted in manual ' sequential with Tavg being maintained by changing the baron concentration. Assume CEAs are inserted until Group Four becomes the onl,y group being moved. What alarms and/or interlocks would be expected from the Pulse Counting Indication System? (1,20) , (***** CATEGORY 06 CONTINUED ON NEXT PAGE

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..~.. - . . .....-.- - . . 6 2;ELeNI_@Y@IEd@_DE@lGN _GQNIBQLt_eND_IN@IBUdENI8IlON PAGE 9 t % b QUESTION 6.09 (2.00) a. What is the purpose of the Sudden Pressure Relay on the Unit Station Service Transformers? What automatic action is initiated if this relay actuates? (0.80) b. You just took the' breaker control switch for 4U to CLOSE but the. , breaker did not close; the synchronizing 0 switch is ON, and the synch selector switch is selected to 40. List the FOUR ather conditions that must be satisfied to allow the breaker to close. (1.20) l DUESTION 6.10 (2.00) Using the Highliter and the attached Figure AS-13-1, show the normal Fuel Pool Cooling System lineup for the below conditions: The plant completed a refueling 1 week ego Fuel Pool temperature 140 F iit l J t (***** END OF CATEGORY 06

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. _ _ . . . _ , , . , ] 2ct_BBOGEpuBES_;_NOBUGL1_8BNOBd863_EUEBGENQY_GNQ PAGE 10 BGDIO60 GIG 66_QONIBQL . QUESTION 7.01 (2.00) The following note is from Maine Yankee procedure 1-7 " Plant Cooldown": When performing a Natural Circulation cooldown consideration should be given to designating a dedicated operator to quickly mitigate potential , consequences of an inadvertent charging or HPSI flow event. a. What condition is this note hoping to prevent? b. One of the actions to be taken in the event of an inadvertent flow event is to trip any running Reactor Coolant Pumps. What is the reason ,for this action? ! QUESTION 7.02 (2.25) The " Loss of Power Supply to Instrument Bus DP/ PAC" annunciator alarms, and.

the control board indications confirm the alarm. If the manual immediate ' actions did not correct the c ondi ti on , and no further operator action is taken, explain WHY the plant will or will not trip. ] j QUESTION 7.03 (2.50) The plant has just had a reactor trip, group SA rods did not fall on the receipt of the trip signal; the SOS has announced that he is transitioning to FR-5.1. The sixth immediate action step of FR-S.1-is to initiate Emergency Boration. List the SIX actions (including sub -steps) if the BAST is not available. QUESTION 7.04 (1.50) In accordance with Maine Yankee procedure 1-15-1, " Primary Component Cooling System", what is the basis for the minimum water level in the surge tank? t (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****) } > Y .q 1 i ~ _ - _ . - . . . _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -. L . __ g

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , . , PAGE 11 Z 1_ESQgEpyBES_;_NOBd861_GDNgBd863_EMEB@ENgy_8NQ 60919699IG66_G9 NIB 96 . QUESTION 7.05 7 ( 3. 90 F 4. ro Answer the following in accordance with Maine Yankee procedure AOP 2-10 4 " Loss of Pressure Control /RCS Leak": a. If pressurizer pressure is decreasing, what FOUR valves / sets of valves would you check to ensure they were closed? (2.00) p-ier to +-ippire Mhy deet ++ e precedu c direct yev te trip #1 + 3 RCor g/,42 OSP L- t '1.03F h j . l QUESTION 7.06 (1.S0) ( l Prioritize the below li sted Critical Safety Function Status Trees from l highest to lowest: l l 1. Containment - Red l 2. Core Cooling - Yellow 8 3. Heat Sink - Red 4. Integrity - Orange ! 5. Inventory - Green l 6. Subcriticality - Orange l DUESTION 7.07 (2.50) ! 1 a. In accordance with ECA-0.0, what are the immediate actions for a , ' Loss of All A/C Power? Substeps are not required. (1.75) b. What is the basis for the following quotati on f rom ECA-0. 07 (0.75) "CSF Status Trees should be monitored for information only. FRP's should not be implemented." l l l l l l l l 1 (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****) i l I nFk . . _ _ s

- % Zzt_PBggEQUBES_;_UgBd861_89NgBd863_EdEBGENCy_8Ng PAGE 12 SeDIOLOG1ceL_cgNIBg6 ! .

QUESTION 7.08 (2.45) In order to maintain the plant.at 100% power, work must be performed inside I the. containment in a radiation field of 100 MREM /HR gamma and 100 MRAD /HR neutron. You will be accompanying the maintenance man into the work area. Assume you are 27 years old and have a lifetime exposure through last quarter of 29 REM on your NRC Form 4. So far this quarter, you have ) accumulated 1.0 REM. j a. How long may you stay in this area without exceeding the Maine Yankee administrative limits? Show all assumptions and calculations. (1.55) b. ,What three individuals, by position, must approve the Radiation Work Permit befare work may begin? (0.90) QUESTION 7.09 (2.50) Answer the f ol low;ng in acccrdance with Maine Yankee procedure 1-12-6 ' " Control Room Ventilation." I a. If power is lost to Bus 5, what affect will this have on the control room ventilation and air conditioning? Justify your answer. (2.00) j b. With respect to the control room ventilation and air conditioning 3 is j the plant in a lechnical Specification Action Statement? (0.50) l J

QUESTION 7.10 (2.50) Answer the f oll owi ng in accordance with the Maine Yankee Emergency Operating Procedures: a. How is a faulted Steam Generator identified? (1.00) b. List six actions taken to isolate a faulted steam generator. (1.50) l l l (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****) 1 , _-_- - _ _ - - - _. -_ -- - - - .-__ _-____ __-_

_ _ _ _ . Z121ESgCEpuBED_;_NQBd@L1_OBNgBd@L1_gMEBGENgY_GN9 PAGE 13 6091960 GIG 86_GQNIBg6 . QUESTION 7.11 (2.00)' Answer the f ollowing in accordance with the Maine Yankee Technical Specifications for refueling operations, consider each case separately: a. Certain conditions within the containment must be maintained if the reactor has been subcritical for less than 210 hours. What is the basis for the time limit? (1.00) b. Both RHR trains shall be operable when the water level above the top of the irradiated fuel assemblies seated within the reactor vessel is less ,than 23 feet of water. Why must BOTH trains of RHR be available? (1.00) l l l l l

I ' I , (***** END OF CATEGORY 07

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=Bu_iODMINISIB@IlyE_PSOCEQUBESx_CONDlllON@1_6NQ_LIMlI@IlONS PAGE' 14 . QUESTION 8.01 (2.50) Answer the following in accordance with Maine Yankee Technical. Specifications and procedure 1-26-5 " Shift Manning and overti'me Requirements". Assume the plant is in Condition 7: a. What actions must be taken if operating with a minimum. crew composition 4 and one of the Reactor Operators becomes incapacitated? (1.25) b. Is the following rction proper by the Plant' Shift Supervisor? Justify (1.25) your answer. Fifteen minutes before scheduled arrival on the on-coming shift, one of. .the three on-coming RO calls in sick. The on-shift PSS decides, due to the shift's present overtime condition, to call in a replacement. The PSS also decides that since the replacement should arrive shortly.after shift change (about 30 minutes) to send his people home and let the next shift start with aniy two ROn. QUESTION 8.02 (2.25) Define Shutdown Margin in accordance with the Maine Yankee Technical Specifications. l QUESTION 8.03 (2.25) The plant is in Condition 6 and the latest leakage r eports show: 0.8 gpm - leakage past the incore instrumentation assemblies 1.8 gpm - leakage past c h r-c k valves from the RCS to the SI Tanks 1.2 gpm primary to secondary leakage (all three generators) 5.8 gpm - total leakage Explain which TS limits, if any, are exceeded; include in your explanation what the limit is that was exceeded, if applicable. l 'l l l t 1 1 1 I , i (***** CATEGORY 08 CONT INUED ON NEXT F' AGE * * * * * ) l l \\ l ._ - - _ . - - _ _ - _ - _ _ _- -_w

. - _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ . 1 b l8DM1BISIBOIIVE_PRgCEDUBESt_CgNDlI19USg_8ND_(.1[111011gNg PAGE 15 . .. QUESTION 8.04 (3.00) It is discovered today, 15 September day shift, that'a monthly surveillance on the Reactor Protective System due last Wednesday, 9 September mid shift, was not performed. The surveillance has been performed satisfactorily for the last six months on the following dates: 10 Aug, 7 Jul, 2 Jun, 4 May, 29 March, and 27 Feb. (A calendar is attached for your use) J In accordance with Maine Yankee Technical Specifications and procedure 1-200-8 " Operations Department Surveillance Schedul e, Impl ementati on and Records" is the system considered operab.le? Justify your answer. . l QUESTION 8.05 (3.00) In accordance with Maine Yankee Operations Memo 9-E-10 " Actions Which Depart from License Conditions and Technical Specifications": l a. When may licensed operators depart from requirements of the Technical ] (1.50) Specifications? 6. WHO must give approval for the departure and WHEN must this approval be ob t a i n ed'? (1.50) < QUESTION O.06 ( 1. 50 ) Answer in accordance with Maine Yankee Operati ons Memo 9-L-21 "Special Security Areas /Two-Man Rule": a. List the THREE areas within the plant where two-man control is (0.75) required. b. Li st. the onl y all owed exception to the two-man rule and the responsibility of the NSE. (0.75) (***** CATEGORY 08' CONTINUED ON NEXT PAGE *****)

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ sg ;eDMlulgIgellyE_EBgCEDUBE@2_CQUDlllOUS1_GNDllMlIOllgNS PAGE 16 i . -OUESTION 8.07 (3.00) Answer the following questions TRUE or FALSE in accordance with Maine Yankee procedure 0-14-1 " White Tagging Procedure": a. A maintenance irdividual was removed from the Tagging and Switching I List last week due to a minor viol ation of the procedure. He has been retrained on the importance of verbatim compliance of'the procedure from both the maintenance supervisor and you, the on-shift PSS. The Plant Manager must approve reinstatement of the individual. b. A trained Control Room Operator (RO licensed) may be in charoe of

issuing the White Tag Order. l A QA Blue Hold Tag may be placed on a Tagging Order even though the OA c. i ndi vi dual is not on the Tagging and Switching List. I d. A second LICENSED operator must validate that the tagging order will perform its intended function. l 1 k QUESTION 8.08 (3.00) Answer the following in accordance with Maine Yankee Technical Specifications: a. When is a CEA cons 1dered ta be misaligned? List TWO conditions. (1.00) b. What action must be taken within one hour of identification of the I misalignment? (2.00) 1 QUESTION 8.09 (3.00) You are the on-coming PSS and the plant is in Condition 7. During a pre-shift review of the logs, you note that SIA-M-21 (S1 Tank i sol a ti on val ve) was shut two hours ago for minor maintenance; no 1og entry was made for the val ve being reopened. What actions should be taken by the on-shift PSS? , DUESTION 8.10 (1.50) It is 2 o' clock in the mor ni ng and the planL in in Condi tion A ,. Procedure Change Report (PCR) for 1-15-3 "Servir:e Water System" is brought to you for approval by one of your ads. What r equi r emen t s must be met for the PCR to be approved? (***** END OF CATEGORY 08

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- 4 JANUARY JULY i S M T W T F S S- M T W- 'T. F S .i 1 2 3 1 2 3 4 i 4 5. 6 7 8 9 10 .5 6 7. 8 9 10 ~ 11 l ! 11 12 13 14 15 16 17 ~ 12 13 14 15 16 '17 18 18 19 20 21 22 23 24 19 20 - 21 22 23 24 25 25 26 27 28 29 30 31 26 27 28' 29 30 -31 l FEBRUARY AUGUST S M T W T F S S 'M 'T W T F S q t 1 2 3 4 5 6 7 30 31 1 l 8 9 10 11 12 13 14 2 3 4 5 6 7 8 l 15 16 17 18 19 20 21 9 10 11 12 13 14- -15 l - 22 23 24 25 26 27 '28 16 17 18 19 20 21 22 ] 23 24 25 26 27 28 29 MARCH SEPTEMBER S M T W T F S S M T W T F .S 1 2 3 4 5 6 7 1 2 3 4. 5 8 9 10 11 12 13 14 6 7 8 9 10 11 12 15 16 17 18 19 20 21 13 14 15 16 17 18 19 1 22 23 24 25 26 27 28 20 21 22 23 24 25 26 29 30 31 27 28 29 30 APRIL OCTOBER I S M T W T F S S M T W T F S 1 2 3 4 1 2. 3 5 6 7 8 9 10 11 4 5 6 7 8 9 10 12 13 14 15 16 17 18 11 12 13 14 15 16 17 ll ' 19 20 21 22 23 24 25 18 19 20 21 22 23 24 ', ' l 26 27 28 29 30 25 26. 27 28- 29 30 31 I MAY NOVEMBER , lj, S M T W T F S S M T W T F S i 31 1 2 1 2 3 4 5 6 7 3 4 5 6 7 8 9 8 9 10 11 12 13 14- ! 10 11 12 13 14 15 16 15 16 17 18 19 20 21 H 17 18 19 20 21 22 23 22 23 24 25 =26 27 28 24 25 26 27 28 29 30 29 30 , JUNE DECEMBER l S M T W T F S S M T W T F S 1 2 3 4 5 6 1 2 3 4 5 7 8 9 10 11 12 13 6 7 8 9 10 11 12 14 15 16 17 18 19 20 13 14 15 16 17 18 19 21 22 23 24 25 26 27 20 21 22 23 24 25 26- 28 29 30 27 28 29 30 31 , i ).
, . . . - .a '6u_1IUE98Y_9E_ NUCLE 68_EQWEB_EL@NI_OEEB8IlgN,_El=glph_GND PAGE 17 1 ISEBL1gQyN8MICS ' ANSWERS -- MAINE' YANKEE -87/09/15-NORRIS, B. S. l 1 . j ANSWER 5.01 (3.00) I a. False E 0. 50 3 - At the higher power, the burnout term is more dominant than at the lower power. EO.503 Thus, the reactivity warth for xenon is not linear. E0.50] i I (NOTE: Equilibrium Xe at 50% power i s '80% of that at 100% power) l b. True E0.50] The time to reach equilibrium xenon 0% to 100% is ~40 hours, i .from 100% to 0% is ~70 hours. E1.00] 1 I REFERENCE MY , NUS t/o] 3, IJni t 10, pgs 10.2-1 to 10.4-6, 84 Ques No 10.3-1 l RO Rx Theory LP No RO-L-1.12. ELO# CRC-101-90 J. R. LaMar sh, Intro to Nuclear Engineering, 2nd Edition, pgs 317-322 192006K105 192006K106 ...(KA"S) , i h ANSWER 5.02 (1.00) (C) E1.00] REFERENCE j MY, RO Rx Theory LP, R D - L - 1 . 9 ., pgs 5-8 84 RO-L-1.10, pgs 3-6

001000K547 192003K106 ...(KA'S) i l ANSWER 5.03 (2.00) 835 psig = 850 psia E0.50] 525.24 + 45 =DCC. s'If0,50J 850 psia =: 525.24f for Th EO.25] "'I 1 C L . 2 E' " LO: p ;1. f6% * => l2py. p a pu r 4??.2^ c -' C0 2"2 [p..ts)' fpr. A y%> 77 ^7L.*^ CCO pat. 7.A * ==74 yt, .2 4 p.fr r " ' - c L 7. 92 p - , ' rT' 02 p;;g; E tm [p. $~".] 7I * M2% 3p1la (/At'f dpasf t REFERENCE MY, RO Heat Transfer L.P , RD-L-7.1, EOL# PPM-101-178418 193003K117 193003K125 ...(KA'S) , ,.I' k' h y

r, ' '!1 *i .' d is ' _ __ _ _ _ _ _ _ _ __ _ _
. _. . . . . . . _ . .. 1 ~5. ' THEORY OF NUCLEAR POWER PLANT OPERATION _ FLUIDS AND PAGE 18 z t J T H E R M O D. Y N A_ M _I C S - - - - - - - - , , - a ANSWERS -- MAINE YANKEE -87/09/15-NORRIS, B. S. ' 1 l I ! I 1 ANSWER 5.04 (3.50) 1 ) Reactivity due to FTD: -1.00 - (-0.28) = -0.72 %drho E0.403 I (Fig 2.1.2.1) o.og o,of _o, o g l E0.403 Reactivity due to MTD: g-0-im - 0.10 7 -02-90 %drho (Fig 2.2.2.1) Reactivity due to Xenon: -2.65 - (-1.45) = -1.20 %drho EO.403 ) (Fig 2.3.1.2) Reactivity due to Samarium: at power, equilibrium is constant [0.403

> (Fig 2.3.1.2) Reactivity due to rods: 1.36 - 1.20 -= +0.16 %drho E0.403 (Fig 2.6.2) f, <gg Total reactivity change: Sum of the above g 2,07 %drho CO.403 Baron worth at 1200 ppm: / (Fig 2.7.1.2) (-11.2 %drho)/(1200 ppm) = -0.0093 %drho/ ppm E0.40] j, gf New baron c onc ent r at i on :: =g;2.27 %drho EC.303 q r,2gro , ppm) (-0.0093 %drho/ ppm) (Cb - 1 erc9 %drho + (1200 ppm) (-0.0093 "'.drho/ ppm) Cb n . - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - f , g.r (-0.0093 %drho/ ppm) C b = /( i . vi - 11.16)/(-0,0093) ppm =4- ilid pp n e /voo o am E0.403 fj l NOTE: figure number is not required for full credit. , j REFERENCE . MY RO Rx Theory LP, RO-L-1.13, T L.OM C RC- 101. c 3 MY proc. No. 1-4 " Operations at Power" Sect 5.0 MY Tech Data Break, Figures 1.2.5.1, 1.2.6.1, 2.1.1.1, 2.1.1.2, 2.1.2.1, 1 2.2.2.1, 2.2.2.2, 2.3.1.1, 2.3.1.2, 2.3.2.1, 2.6.1, 2.6.2, & 2,7,1,2 l \\ 192008K120 ...(KA'S) t t l l I m e - > 5 hf 4 I _ _ _ _ _ _ .__.m._ __ .J
1 b

'5. CTHEORY OF NUCLEAR POWER PLANT OPERATION _,FL.UIDS _AblD PAGE 19 z t ISERUOQyNOd1CS A41SWERS -- MAINE YANKEE -87/09/15-NORRIS, B. S. ! l - ANSWER 5.05 ~/ -i 3. DG ) /*,7# I a. Lambda = 0.07 sec-1 E0.25] Beta eff =_0.006 E0.25] Rho = (30 sec) (1 min /60 sec) (-0.0077 %drho/ step) (40 steps / min) = -0.154 %drho 00.25] ) After rod motion stops: SUR = 26 (l ambda (rho) ) / (beta eff - rho) [0.25] = 2600.07(-1.54E-3)]/06E-3 - (-1.54E-3)J = 26(-1.08E-4)/(7.54E-3) =-0.37 dpm E0.25] . IJOTE: deduct 0.1 if candidate does not use negative rho in calculation b. At r g,___g gn;_ _rr ;g; 77.
, ; 77 3--
g
g,gg3
++.1 h git . ' Sicky E' % T4 /4 ? E0.25] 47 , E0.50] c. Duo to the rho dot factor the EUR would be h i g her (vrf o re 'rAyc<bv'\\- EO.25] d. P = Po10E(SUR*t) E0.25] W E 10E (-2) ] E 10E (-0. 37dpm) (1mi n 9 E0.25] = E10E(-2)]EO.43] [10E(-2)]E10E(-0.37)J = = = 4.3E(-3) % power E0.25] NOTE: deduct 0.1 if candidate does not use negative SUR in cal cul ati on REFERENCE MY RO Rx Theory LP RO-L-1.10 ELOMCRC--101-63 MY TDB, Fig 2.6.2 192008K124 ...(KA'S) I t O .>
_ _ _ _ _ _ __ .. .. '5,,_lIHEQBY_QE_NUCLEGB_EQWEB_[66NI_QEEB@IlgNg_ELylDS _GND PAGE 20 g IHEBMQQYNOMICS ANSWERS -- MAINE YANKEE -87/09/15-NORRIS, B. S. . t ANSWER 5.06 (3.00) ' i 1. Reactor Power E0.25] Increasing reactor power results in increased heat flux E0.25] and DNBR decreases E0.25]. 2. RCS Temperature E0.253 Increased temperature will decrease the subcooling EO.25] therefore the heat flux required to reach CHF will decrease and the DNBR will decrease E0.253 l 3. Pressurizer Pressure E0.25] l Increased pressure increases the subcooling CO.253 and therefore DNBR increases. E0.253 4. RCS Flow EO.25] Increased flow decreases the blanketing of steam bubbles E0.25] thus increasing the CHF and increasing DNBR E0.25]

REFERENCE ,- MY RO Heat Transfer LP RO-L-7.3, pg 15 f< ELO# PPM-103-9,10,11 MY TS pgs 2.2.1-2.2-2 l 193008K105 ...(FA'S) ANSWER 5.07 (2.50) i ' a. Reactor power decreases initially [0.25] due to the negative reacti vi ty of the baron addition [0.25]. The primary to secondary mismatch E0.253 causes Tave to decrease EO.253. The decrease in Tave inserts positive reactivity [0.253 and restores power to 100% (or slightly lower) [0.25] b. Tave is determined by the amount of pump heat and the setting on the decay heat release valve (or the steam dump and bypass system) E0.25] thus Tavg will not change EO.253. (NOTE: power is below the point of adding heat) Borcn addition will cause power to decrease LO.25] to the sub-critical multiplication source l evel E0.25]. i l REFERENCE

MY OP 1-1, Rev 36, pg 23 q c _i t
,,

dd'!;,
,J -r; c-a _ __________ _ _ _ _ r- m i _ _ _ . - - . _ _ _ _ _ _ . _ _ _ _ - . . - . _ . . - _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . - _ _ _ _ _ _ _ _ _ _ _ . _ _ . , 1 000024K101 000024K102 192008K120 ...(KA'S) i < ' n . _ - * ) 4 s
. - . , . ..A.. . . . , . % _lISEgBL gE_,NYCLEGB_EQWE8_EL6NI_QEEB@IlgNz_ELQ1pS _6ND PAGE 21 1 ISEBt]QDYN8MICS l <$NSWERS -- MAINE YANKEE -87/09/15-NORRIS, B. S. j l I ANSWER 5.08 (2.00) a. GREATER THAN E0.25] as the core ages (boron decreasing) the macroscopic cross section of the fuel will decrease; to maintain the same power level the thermal neutron flux must increase E0.75]. , ! b. SAME AS E0.25] fast neutron flux is directly proportional to power E0.75]. REFERENCE MY RO Rx Theory LP RD-L-1.5 pgs 18-24 & ELO# CRC-101-21&33 l MY NET Vol 2, pgs 14.5-1, 15.1-1 to 15.1-7 l 192001K108 ...(KA"S) - 1 ANSWER 5.0? (2.00) see attached Figure 5.1 KEY 109 ( + / -- 5) gpm [0.50] a. Flow = Pressure = 52 (+/- 3) psig E0.50] 122 (+/- 5) gpm [0.50] b. Flow = Pressure = 61 (+/- 3) psig E0.503 REFERENCE MY RO Heat Transfer LP RO-L-7.4 pgs 1 0 - 1'7 & ELOt) PPM-104-8,11,15 191004K109 191004K110 193005K115 ...(KA'S) ANSWER 5.10 ~f (2.50.5 /. f o a. Insures that pumps are tripped in the event of a SBLOCA EO.25] before the break becomes uncovered E0.25] t-ipp:rg PC'% &>-i y t + uptur _ E 0 . '~ 0 2 oc - PCE p cuur - q r ult :r y' Etc deper'k :t C "' ;wnmur - ._, tac-hard ta c al c ul at:c . [C.CO2- c. Available spray EO.25] Good core cooling EO.25] Cool down easier on RCPs than natural circulation E0.25] Prevents head voiding E0.253 REFERENCE Westinghouse Owner's Group Executive Volume, Generic issue - RCP Trip / Restart ' . , 1 m. , e..\\+'" Tr e s - , __ __

. 1
, . 4 ~5 ' THEORY OF' NUCLEAR POWER PLANT OPERATIONg_FL_UIQSg_ONQ PAGE 22 3 ' IUE6MQDYNSdlGS ANSWERS -- MAINE YANKEE -87/09/15-NORRIS, B. S. ] 000011K314 ...(KA'S) l l l l

I 1 ! l l . 1 1 i \\ .4 ' I " - 'M' '- I .L _ _ ___ m._ _ . .___m_. , , _
___ _ , - , _ . _ . . . _. PAGE23 . h E68NI_EY@IEM@_DE@l@N _,CQNISQL1_6ND_lN@lSUMENIBIlgN z ANSWERS -- MAINE YANKEE -87/09/15-NORRIS, B. S. s ANSWER 6.01 (2.50) a. containment pressure E0.50] 2/3 sensors E0.25] b. containment pressure sensors E0.25] (NOTE: no credit or deduction for containment logic since are same as above) pressurizer pressure E0.50] 2/4 sensors E0.25] 1 . ' c. PCC supply to RCPs E0.25] PCC return from RCPs CO.25] i l Seal return from RCPs E0.25] 1 REFERENCE Mn Yankee: STM, Chapter 6, "ECCS" NS-5, pgs 43-45

' 103000K102 103000K108 103000K406 ...(KA'S) ANSWER 6.02 (2.80) a bEhF* hil11- CIQLL$__ - l - - b. fails closed c. fails to bypass position d. f ails to PDT positi on j i e. fails closed f . d E-AF__[sqd _c[gha/___ ,_ , 9 d W [uYS_.vf&L ---- . l l REFERENCE MY GTM, Chpt 4 "CVCS" NS-4, pgs 21-67 T Objectives ELOHCVCS0101-5, -0102-5 & -0103-2 MY SRO & RO Program ! asks anda bJkm b5 / 5 he ?' IM rpC AGl* E*c? i . . . (K8S) 004$0eK114 07eee0K3e2 ' ! l l 'l ! ' l i l l 1 l \\ } ) ' 1
Y j#. . . .
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, l - 1 '

-'6 a_ _E60NI_ S Y SIE M S _ D E SIG d1_ C O NIB g 61_8N Q_ INSIB LJ M E N1811QN PAGE 24 i 1 4 ANSWERS -- MAINE YANKEE -87/09/15-NORRIS, B. S. j . I I 4 ANSWER 6.03 (2.00) ) l l a. Stops containment ventilation and purge (chuts VPA-1,2,3,4,5 & stops l fan HV-9) CO.75] l only during Refueling made E0.25] l l b. Stops fuel pool elevator UPWARD motion E1.00] NOTE: half credit deduction if candidate does not mention UPWARD REFERENCE MY STM Chpt 20 "RMS" AS-18, pgs 4, 35 MY SRO & RO Program Tasks and Objectives ELOitRMS-0101-7 072000K301 072000K302 ...(KA"S) ANSWER 6.04 (3.00) , 1 a. Normal steam pressure setpoint 865 psig (Tavg of 532 F) E0.50] l A decrease of 110 psi would cause the steam header pressure to drop to 775 psig which in the setpoint for automatic closure of all valves E O. G b. Secondary power would increase by "13.5% E0.25] Tavg would decreasy . due to no CEA motion EO.25] cc~..;g "A t: -t nor N. 20 c ..:s : n y ! e -b u r b ; ,' 1: .! ta d :.; r : -
u,y ap; aE: ,
- IM' "UT mad" T . 25. - l ' _.m WA @bf f fkar lC Inc4Je [G tf] &r/ c<. frrh ce,1 J/Gl[s'. 25] l c. The tLWbine trip signal directly causes a reactor trip E0.25]. The l turbine trip signal also closes a contact in the Quick Open Override 1 circuit which causes all dump and bypass valves to open EO.253. T.- t+m COTLC :n ,;t- i f:- 5 0 '. , tb ' cW-++d : rYldt h .::c t . '1 SM , di: s: pf ; :! c '= g ~vtr ;;a+et-y--val-v n t E-A-243.*~/ When the Tavg error signal girops bel ow 18 F, the override signal clears, closing Q$1ven [0.253. tar rema.;,cfr o- o f 5 elecay bed w,7/ be a&s'.riyhof al k"8 Wut- Ad C by byp ss sm fpFJ. [0.E$~] REFERENCE MY STM Chpt 24 " Main Turb & Turb Control" PGS4, pg 45 Chpt 25 " Steam Dump & Turb Bypass System" PGS-14, pgs 1-20 Chpt 11 "RPS" NS-12, pg 5 SRO & RO Tasks & Obj ectives, System 041 "SDTbS" ELOitSD-0101-4 041020K302 ...(KA'S) 1 .AA- J 9.&acA n af dyd 77.ND. i $ 6 ' .-_~-_--.Q~._n _a___U - _ - -
. - . . . , PAGE 25 ,'6ic_EL8NI_@YSIEMS_DEglGN _CONIB06t_6ND_INSIByMENIQIlgN z ANSWERS -- MAINE YANKEE' -87/09/15-NORRIS, B. S. . ANSWER 6.05 (2.50) (f ollowing signal s present SI AS, CSAS, CIS) a. recirc 6. injecting c. injecting d. open e. open f. closed g. open h. closed i. open j. open k. open 1. closed m. open n. closed o. open p. open q. open r. closed s. closed t. closed REFERENCE. , ' MY STM Chpt 6 "ECCS" NS-5 pgs 1-15, 23, 28, 35, & Fig NS-5-14 MY SRO & RO Tasks and Objectives, System 006 "ECCS" ELO#ECCS-0101-2,11,14 006000K102 006000K404 006000K405 026000K401 ...(KA'S) ANSWER 6.06 (2.45) a. The motor driven pump st ar t s, ,0 0.,25 3 when yard loog,g essure decreases to 90 puig E0.25] and the I F##6 riven pump starts wnDn pressure has % 3 decreased to 80 psig E0.25] c- 1" cf ol ' Mtc to tN " " -'"7 ' ' - pump EP.253 7 [o. w 1 -f Co. /S*,7 b. Started locally LE.;JJ or from the CR E D . 2L T7 Stopped 1 oc al 1 Y'1% E }3 oe a f f eral<er(for mDpump) [0 2'0 ~I c. The concrete wall is a fire enclosure EO.50] in case of a fire due to the diesel fuel oil system [0.203 REFERENCE MY STM Chpt 44 " Water Fire Protection System" AS-8, pgs 2 & 11 MY SRO & RO Tasks and Objectives System 86 " Fire Protection" ELOMFP-0101-4,5 086000A201 086000K402 ...(KA'S) < . j 'I . ..I . ' , _ _ _ t _.q ,.
, .-.....-.1 - J . PAGE 26 ,b _'EL@NI_Sy@IEL1@_DESl@N _CQNIBQLr,__@ND_lN@lBlMENIGIIQN z ANSWERS -- MAINE YANKEE -87/09/15-NORRIS, B. S. s1 .Il . ! . ANSWER 6.07 (2.75) a. 485 psig E0.25] < Protection against steam line break accident E0.501 ] Manual bypass below 585 psig E0.25] 1 g4 4. ej'ee e / o l 4 g'4e f g i A Automatic enable above 585 psig E0.251 tdt 64% i l b. 2385 psig E0.25] Protection against (a) excessive blowdown via a pressurizer r el i ef valve E0.50] or (b) prevent operation when ex power is greater than secondary power [0.50]
,./4o
480 g (ab > , .No automatic or manual signals E0.25] ' p a4 ' REFERENCE MY STM Chpt 11 "RP5" NS-12 pgs 4 8e 3 4 / .( 7 f ,f, /-J j MY SRO 8. RO Tasks and Objectives System 12' PS" ELOMRPS-0101-2 012000K402 012000K406 ...(KA"S) ANSWER 6.0S (3.00) 9 a. Upper limit stop E0.30] 3 134'k [0.10] ) I# (/, s%od) Lower limit stop E0.30] 9 2"gEO.10] - Devi at i on of highest to lowest within a group E0.30J & 5",E0.10] Shutdown group insertion permissive CO.30] F ul l y inserted E0.30] b. Power Dependent Insertion LO Limit. for Group 5 EO.303 Power Dependent Innertion LO-LO Limit for Grcup 5 CO.30J Lower Sequential permissive EO.30] Lower Group stop E0.30] , l REFERENCE MY STM Chpt 12 "CEA Control System" NS-9, pgs 34-37, Figs NS-9-4 8v 9to12 MY SRO 8< RO Tasks and Objectives System 001 ' Control Rod Drive" ELO#CEDS-0101-9, -0102-1,2,4 014000A102 014000A103 ...(KA*S) w I P , . . ' ! 'L ' - '-' - . - - - - - - _ _ . . - 2 -.c ___.__a .
_ _ _ ._ . 9'gj_ EL@NI_GYSIEUS_DE@lGN _COUIBQLt_@ND_lhSIBUdENIAllON PAGE 27 z ANSWERS -- MAINE YANKEE -87/09/15-NORRIS, B. S. . ANSWER 6.09 (2.00) a. 1. Purpose - to detect a major transformer fault CO.40] 2. Action - trips the generator E0.403 b. 1. Diesel generator breaker 1B selected for Normal control [0.30] 2. Generator primary and backup protection relays reset E0.303 3. No fault on bus 4U E0.303 4. 4T6 norm /emerg switch in normal E0.303 REFERENCE MY STM Chpt 32 "HV Electrical Systems" PGS-17, pgs 16 & 55, MY SRO & RO Tasks and Objectives ELOMAC-0101-11,14 062000K404 062000K405 ...(KA'S) ANSWER 6.10 (2.00) See att ached Fi gur e AS-13-1 KEY: " COOLING LOOP Suction with flange E0.253 Only ONE cooling pump EO.503 Heat Exchanger E0.25] PURIFICATION LOOP Skimmers to suction of purification pump E0.25] Suction to purification pump AFTER l-IX E0.45] Prefilter, Demi neral i z er , Postfilter EO.10 each3 REFERENCE MY STM Chpt 37 " Fuel Pool Cooling System" AS-13 pgs 1-3 & 13-14 MY Proc 1-17-1 " Fuel Pool Cooling & Purification" 033000K303 ...(KA'S) i l l l l P. .l . ' o s
- . . . . - . . s. 'Zu_iEB9GEgyBE@_;_NgBM8(s_8@NgBU@6t_EUEBGENgy_ONQ PAGE 28 . ' BBD196gGIC86_CgNIBQL ANSWERS -- MAINE YANKEE -87/09/15-NORRIS, B. S. ANSWER 7.01 (2.00) a. Low Pressure Over Temperature (LTOP) condition.[1.003 b. To minimize the chance of RCP seal degradation E1.003 REFERENCE MY Proc 1-7, pgs 9 & 27 MY SRO & RO Tasks and Objectives ELO#RCS-0101-8,13 003000A202 006000A101 006000K105 006050A201 ...(KA'S) . ANSWER 7.02 (2.25) l All feed train pump recirculation valves open EO.753 causing a low suction ( pressure trip on the main feed pumps [0.753 thereby causing a low SG 1evel trip [0.753.

REFERENCE MY Pan-Alarm Book, Window No. SS-5-7 NY Proc AOP 2-11, pg 3 MY SRO & RO Tasks and Objectives ELOMMFW-0101-11 & ELOMAC-0101-19,28 000037A219 000057K301 ...(KA'S) i l ANSWER 7.03 (2.50) Emergency borate using the RWST 1 1. Maintain at least one charging pump running CO.403 f 2. Open valves from RWST to operating charging pumps E0.403 l 1 3. Close VCT outlet i sol ati on valve E0.403 4. Adjust charging header to at least 150 gpm (0.403 , 9 5. Adjust letdown flow controller E0.403 l ! If the RWST cannot be used, then emergency borate with the BAMT. CO.503 d REFERENCE MY Proc FR-S.1, pg 4 i MY SRO & RO Tasks and Objectives ELO#EAS-0101-8 & ELOMCVCS-0103-1 000024G010 000029G010 ...(KA'S) j l I - ;,; 3 J i 5 - '3 r ' < - .i. _. _._:_ . _ _ _. _ . . _ . ,. - - . j .
_ _ _ - _ _ _ _ _ _ _ _ _ _ _ _- . _ _ _ _ . P '7.. PROCEDURES - NORMALt_ABNORL1AL _EMERGENg'(_ANQ PAGE '29 1 8@plOLO@lG@L_GONTBg6 . ANSWERS -- MAINE YANKEE -87/07/15-NORRIS, D. S. a ANSWER 7.04 (1.50) To ensure sufficient makeup capacity to the PCC system E0.50] during the shutting of PCC-M-219 E0.50] on the receipt of a SIAS/CIS E0.503. REFERENCE MY Proc 1-15-1, pg 1 MY SRO & RO Tasks and Objectives ELO#CC-0101-1 & ELOWEAS-0150-4 000026K302 ...(KA'S) . g ANSWER 7.05 7 C.00)J.60 . "gy A:alcY&W a. 1. PR-A-1 & 2 (spray valves) E0.50] ,[,( gy[ l 2. PR-S-14 & 15 (PORVs) [0.503 3. PR-M-89 6 90 RC-M-54 & 56 (Pzr & Rx head vents) [0.50] 3 4. Pr safety valves [0.50] ~]- NG+E: a h+-ek a'. f2L: 1itc h ,. ' k+*. .a , : . -9 w a y a l w-+r c- c1. . g i > .g i; ici 5 -- -

'n +' 1 1_-: t . y included O MM CAF- b. __. Y___g______ Y_? - _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ . . _ _ _ . _ _ . _ _ _ _ ( 1 BW _____ __________.__________.__________.____________._._ __ _.______ ______ REFERENCE MY Proc AOP 2-10, pgs 3-4 MY SRO & RO Tasks and Objectives ELOMPPC-0102013 000027A2.1 010000A107 ...(KA'S) ANSWER 7.06 (1.80) Priority: highest to lowest 2. Cr. Co ul : r. ; ' :c a 1 3. Heat Sink - Re;d , __ g ,g 6. Subtriticality - Orange 4. Integrity - Orange ' 2. Core Cooling - Yellow EO.25ieach, correct order required 5. Inventory - Green 0. A o REFERENCE Westinghouse Executive Volume, User's Guide, pgs 10-11 MY SRO & RO Tasks and Objectives ELOWEAS-0101-1,2,3 194001A102 ...(KA'S) > , '_ A N .- -~_ ___ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ '
_ - . - _ _ _ _ _ _ _ - - - -- - _ _ - - . . _ . . _ .. - 'Zzt_ PROCEDURES - NORMALg_ABNQRMAL1_ EMERGENCY _6ND PAGE 30 BBDIOLOGICBL_ggNIBOL ANSWERS -- MAINE YANKEE -87/09/15-NORRIS, B. S. ANSWER 7.07 (2.50) a. 1. Manually trip reactor CO.253 and turbine E0.253 2. Ensure reactor trip E0.25] 3. Ensure EFCVs closed E0.25] 4. Check RCS isolated CO.25] 5. Establi sh total EFW flow E0.25] - greater than 490 gpm CO.25] b. FRP's are written on the premise that at least one AC emergency bus (0.75) is energized. . i REFERENCE MY Proc ECA-0.0, pgs 2 - 3 I MY Step Description Table for ECA-0.0, Step 1 - Note 3 MY SRO L RO Tasks and Objectives ELO#EAG-0101-6,7 000055G007 000055K302 062000A201 ...(KA'S) m,{ i ANSWER 7.08 (2.45) I 45 REM E0.257 a. 5(N-18) = Total lifetime to date -- 29 + 1 = 30 REM E0.25] I I Total lifetime available = 4 5 - 30 = 15 REM E0.25] 1 REM E0.253 2- 1 Total this quarter available = = Quarterly limit is more restrictive than annual limit [0.15] total gamma + neutron = 1.1 REM /HR done rate EO.25] 0.1 REM /HR + (0.1 RAD /HR) (10 QF) = 1.0 HR/1.1 REM /HR = 0.91 HRS = 53 MIN E0.153 l b. Work Party Leader E0.30] Radiological Controls technician E0.30] . Shift Operating Supervisor (or Nuclear Safety Engineer) EO.303 REFERENCE MY Radiation Protection Manual, pgs 2-2, 2-6, 3-12 MY SRO & RO Tasks and Objectives ELOMAD-0103-1,8 & TLOMM-0303 194001K103 194001K105 ...(KA'S) . I l l v i 'f ' ' %22' ' ^ 1 ._. . ._
- . ~ . . . - , - - - - - .. . 1 > . I 'Zze_EBgCEpgBE@_;_NgBM862_8pUgBM862_EDEB@ENCy_6ND PAGE 31 i l 88D196091C66_CgNIBQL ~ .! l ' ANSWERS -- MAINE. YANKEE ~B7/09/15-NORRIS, B. S.

ANSWER 7.09 (2.50) a. Air conditioner AC-1 A i s powered f rom MCC-7A (Bus 5) E0.50] Cooling to air conditioner AC-1B is from SCC which is powered from Bus 6 [0.50] Air conditioning will be lost E0.50] but not ventilation EO.50] ] b. Yes EO.503 REFERENCE MY Proc 1-12-6, pgs 1 &2 ' 009000K102 ...(KA'S) ANSWER 7.10 (2.50)

1 < a. 1. Any SG pressure decreasing in an uncon troll ed manner E0.50] 2. Any SG completely depressurized E0,503 I b. 1. Stop RCP in loop with affected SG Cany 6 a 0.25 each] H 2. Ensure ADV closed , 3. Ensure MFW train pumps tripped and in Pull-To-Lock 4. Manually close MFRVs to affected SG 5. Manually close MFRV bypass valve to af f ected SG l 6. Close EFW flow isolation valve for affected SG 7. Ensure SG blowdown valves closed 8. Locally close affected SG atmospheric steam supply i sol ati on valves 9. Close EFCV for affected SG i REFERENCE MY Proc E-2, pgs 1,2,4-5 j ' l 000040A201 000040K304 ...(KA'S) ! l ANSWER 7.11 (2.00) ! a. The fuel has decayed sufficiently [0,50] (to maintain dose levels I within 10CFR limits) in the event of a fuel handling accident CO.50] , b. Both trains are required iri the event of a single f ailure [1.00] REFERENCE MY TS, pgs 3.13-1 to 3.13.4 ...('A's) K '033000A203 033000K404 . 1 -/ aL g 97 ' ! eu .

' ' .x +
-
, . 'Mi . t __ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . . , _,_R_ _]
-
- -
_ . . . . . . 9 '8 __'GDMINISIBQIlyE_BBQCEDUBE@s_CgNDLIlgN@z_GND_61MlI@IlgN@ PAGE 32 3 ANSWERS -- MAINE YANKEE -87/09/15-NORRIS, B. S. . ANSWER 8.01 (2.50) a. Obtain a qualified relief E0.75] within two hours E0.50] b. Yes CO.50] the number of RO qualified personnel present would still meet TS requirements CO.75] REFERENCE MY TS, pg 5.2-1 MY proc 1-26-5, pgs 1-2 MY SRO & RO Tasks and Objectives ELO#AD-0104-11 194001A103 ...(KA'S) ANSWER 8.02 (2.25) SDM shall be the sum of: a. t. h e reactivity by which the reactor is subcritical in its present condition, and E0.75] b. the reactivity associated with the withdrawn t'rippable CEAs E0.75] less E the reactivity associated with the highest worth withdrawn trippable i l CEA E0.75]. l REFERENCE ! MY TS pg 2 of definitions i MY SRO b RO Tasks and Obj ecti ves TLOttCRC-0101. b l 192002K110 ...(KA'S) ANSWER 8.03 (2.25) Leakage to SGs is exceeded C E;. 2 5 : CP*?Y-fCoff[ limit is 1.0 gpm E P . 5:" C o 73') -f gg.572] Unexplained leakage is exceededT: 0.2C 5 o "d - , gy total identified is 0.8 + 1.8 + 1.2 = 3.8 gpm 4.-77 unex pl ai ned is total leakage - identified = 5.8 - 3.8 = 2.0 gpm T b2d'I 7 /Sif if 'l-kffn! [p.b'0 l l bc c L:mg c to Ecsctor c c, . t s i co ,m. L Jum Lu u u l u. . i crc! .cr c' p ccct n bounderf7' l mt: : 'l e (-p :: c c h ^c '- n: 2 t - tu EI T='t m .5E" 7 4 . rg_g53 ,7 Mnne .Li d t 't l REFERENCE MY TS pg 3.14-1 , l MY SRO & RO Tasks and Objectives ELOMAD-0104-10 000009K320 ...(KA'S) AOw_ - _ . _ - _ - w
. _ _ g . . '83__89d1NISIBQIlVE_BBQCEDUBEQs_CQNQlllQNSz_BNQ_LldlI@IlgNS PAGE 33 ' ANSWERS -- MAINE YANKEE -87/09/15-NORRIS, B. S. . . ANSWER 8.04 (3.00) The system is NOT operable E1.00] ,. Three consecutive surveillance intervals may not exceed 100.75 days [1.00] 7_) x 31 days = 100.75) Total 2nterval since 2 Jun is 105 days. E1.00] REFERENCE l MY TS pgs 4&7 MY proc 1-200-8 pg 2 MY SRO & RO Tasks and Objectives ELO#SURV-0301-1, ELOMSNO-0303-5.c.1 012000G005 ...(KA'S) l ANSWER 8.05 (3.00) a. When immediately needed to protect public health and safety E0.753 and no alternate action is immediately apparent E0.75]. b. Must receive prior approval E0.503 from a licensed SRO EO.50J and ( ' highest level of company management available EO.50] ! REFERENCE MY Ops Memo 9-E-10 , MY SRO & RO Tasks and Objectives ELOMSNO-0302-9 ] 194001A102 ...(KA'S) ANSWER 8.06 (1.50) a. Locked steam driven AFW pump (P-25B) enclosure EO.25] Two locked enclosures E0.25] at the cable penetration areas in the Rx MCC room E0.253 [0.370Y b. Operations department personnel onl y { 0. 25] Itay enter in response to an emergency {0. 2521 'Sc "SE sc to lag thc rntry E O . 25 2 .~/ [o.375] REFERENCE MY Ops Memo 9-L-21 ' MY SRO & RO Tasks and Objectives ELOMSNO-0302-9 194001K105 ...(KA'S) _= - :a _ . - .
_. mM 'St__'GDMINI@ISBIIME_PBgCEDgBE@s_CgNDlligN@t_8ND_bldlI811gN@ - PAGE 34 ANSWERS -- MAINE YANKEE -87/09/15-NORRIS, B. S. . ANSWER 8.07 (3.00) a. True [0.75 each] b. False c. True d. True REFERENCE MY proc 0-14-1, pgs 2 - 5 MY SRO b RO Tasks and Objectives ELO#M-0302-6,7,8,11 194001K102 ...(KA'S) . ANSWER 8.08 (3.00) e a. 1. A CEA in misaligned if it is more than 10 steps out of position from the rest of its group or subgroup. [0.503 2. If indicated positions of subgroups SA or 5B differ by more than 15 steps. [0.503 1 b. If the misalignment is not corrected within fifteen minutes [0.503; power must be reduced by at least 10% of rated power within one-half hour [0.503 and by at least 20% of rat r_d power within one hour [0.503 (of identification of the misalignment). CEA insertion limits specified for the initial thermal power must be maintained [0.503. REFERENCE MY TS pg 3.10-1 MY SRO & RO Tasks and Objectives ELOMAD-0104-10, ELOMCEDS-0102-6 001050A203 ...(KA*S) ANSWER B.09 (3.00) 1. Attempt to open the valve if it is not already open [0.503; if the valve will not open, then commence a plant shutdown [0.503. 2. If the valve was shut for more than one hour [0.503,an action statement has been violated (3.19.A.1) [0.503. The'on-shift PSS should notify the NRC [0.503 within one hour [0.253 (in accordance with 10CFR50. 72 (b ) ( 1 ) <(i i ) B ) and have his NSE complete an Unusual Occurrence Report [0.25] REFERENCE MY TS pg 3.19-1 MY Ops Memo 9-E-6 MY Proc 1-26-1, pgs 2-3, 6 - ____ _A - a.
. PAGE 35 ,'9=__'89MINIEIB011ME_EgggEQgBEgt_gggg1IlgNS _gNQ_LIMll@IlgNg t ANSWERS -- MAINE YANKEE -87/09/15-NORRIS, B. S. -. MY SRO & RO Tasks and Objectives ELO#AD-0104-10 006000G011 ...(KA*S) ANSWER 8.10 (1.50) 1. The intent of the procedure must not be changed CO.503 2. An SRO licensed i ndi vi dual must approve the procedure E0.503 3. An employee of the department responsible for the procedure must also approve the procedure CO.253; if necessary, telephone approval from the department may be obtained E0.253. REFERENCE MY Proc 0-05-1, pg 4 MY Proc 0-06-2, pg 8 MY SRO & RO Tasks and Objectives ELOMAD-0102-6 194001A102 ...(KA'S) -__-__- _-_. -_ _
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Attachment 3 . . NRC Resolution of Facility Comments on SRO Written Examination Question NRC Number Resol ut i on 5.01 Comment noted, this will be considered in grading. 5.03 Comment accepted, answer key changed accordingly. 5.04 Comment accepted with respect to MTD and samarium, answer key modified accordingly. Note: answers will be graded allowing for some tolerance in reading the figures. 5.05 Comment noted with respect to the lack of a standard equation sheet, will be considered in grading. l 5.05.a.1 Per discussion with M. Evringham during the review of the comments, the reactor should not be critical at 10E(-2)% power while still withdrawing the shutdown rods. Comment not accepted. 5.05.a.2 Comment accepted, as long as final answer is a negative SUR. 5.05.a.3 Comment noted, answer key modified to a negative SUR. 5.05.b Comment accepted, part "b" of the question deleted.

1 5.05.c Comment accepted, will be considered in grading. l 5.05.d Comments noted, will be considered in grading. 5.10.a Comment not accepted, question specifically asked about RCPs with respect to subcooled margin. 5.10.b Comment accepted, part "b" of the question deleted. l 5.10.c Comment noted, valid alternate answers will be accepted. ! I ' 6.01.b Comment noted, will be considered in grading based'on any l assumptions made by candidate; if no assumptions are stated, question will be graded as shown. 6.02 Answer key modified to reflect correct answers. 6.04.a&b Comment noted. 6.04.c Comment accepted, answer key modified accordingly. l l 6.06.a Comment accepted, answer key modified accordingly. 6.06.b Comment accepted, answer key modified accordingly. 6.07 Comment accepted, answer key modified accordingly. 1 Page 1 , l 1
__ Attachment 3 , e , Question NRC j Number Resolution d 6.08.a Comment accepted, either answer will be accepted. 7.02 Comment noted, question will be graded cased on valid j assumptions stated by candidate. 7.05.a Comment noted, will be considered in grading. 7.05.b Question based on old information, deleted f rom examinati on. I 7.06 Comment noted, original intent of the partial credit. 7.09.a Comment noted. 7.10.a Comment noted. i ! 7.10.b Comment noted, question is testing candidate's understanding of a faulted steam generator. j 8.01.b Comment noted, will be considered in grading. I 8.03 Comment accepted, answer key modified accordingly. 1 8.04 Comment accepted, answer key corrected. 8.06.b Comment accepted, answer key modified accordingly. 8.09 Comment noted. 8.10 Comment noted. ' Page 2 __-_- _ _ - _ -
_ -__ _ ______ __ _ _ . . -_ _ _ . i i l l r I i ES-302 ATTACHMENT 3: SIMULATOR SCENARIO EVENTS I SCENARIO No: D - Maine Yankee, Sept 16 '87 i ! Examiners: Norris Candidates: SRO , _ _ _ _ , 1 Defferding RO _ BOP _ Synopsis: 80% Power, 0% BUP LOCA with a loss of plant computer Malfunctions inserted prior to start of scenario: I

Summer, all cooling water temperatures high j RP04B Failure of auto SIAS on Lo-Lo PZr Pres 6 II Equipment Out-Of-Service , MFP 2A for motor replacement

l RX01B Non-controlling pZr pres channel (PIC 10lY) - failed detector i Event / l j Time Malf No. I Description i Initial Conditions: 1 0 IC#16 Plant at 80% power, 0% BUP, Xenon increasing (came dowm from 100% late last shift per dispatch) . j Expect to go back to 100% sometime this shift i Watch the temperatures on the cooling water systems, l expected high today close to 100F l Thunderstorms forecast for this afternoon , ARO ) Scenario: +4 (1)/RX01A Failure LOW of second pZr pres channel (PIC 101X) => manual control of RCS pres j \\ --+12 (2)/RC07A Vibration on #1 RCP - start at 0% and ramp to j ' 50% (25 mils above normal) over 20 minutes i => expected rapid power reduction to secure pump l NOTE to sim inst: when called as PSS, order a ! rapid plant shutdown and then secure the pump { +15 (3)/PC01 Loss of Plant Computer j NOTE: insert after power reduction begun j Ouestion: .a failure to update or loss of power j => Manual sequential control lost to CEAs l /IO Fail LSI-M-41 shut I ( (suction to A-train LPSI & CS pumps) ) ! +20 (4)/CV17A Vapor Seal failure on #1 RCP l +22 /CV14A Lower Seal failure on #1 RCP j +24 /CV15A Middle Seal failure on #1 RCP l l +26 /CV16A Upper Seal failure on #1 RCP l ' => progressive failure give 500 gpm leak

/RPO4B Failure of auto SIAS on Lo-Lo pZr pres ! , => manual SI required j +30 (5)/RC03A Cold leg rupture , ! => Containment spray, only one train
_ _ _- . e ES-302 ATTACHMENT 3: SIMULATOR SCENARIO EVENTS SCENARIO No: B - Maine Yankee, Sept 16 '87 Examiners: Defferding Candidates: SRO _ Norris RO BOP Synopsis: 75% Power, 0% BUP Steam Generator Tube Rupture with failed fuel Malfunctions inserted prior to start of scenario: Summer, all cooling water temperatures are high

CR01 Failed fuel - 100% severity No alarms or indications for about 15 minutes after shift RD02 The following CEAs are stuck (due to fuel binding) -
27, 47, 55, & #34
l Equipment Out-Of-Service MFP 2A for motor replacement l l RX01B Non-controlling pZr pres channel (PIC 10lY) due to failed '

detector l l l l Event / Time ! Malf No. Description

' Initial Conditions: 0 l IC#16 l Plant at 75%, 0% BUP, Xenon increasing (came down l l from 100% late last shift per dispatch request) ] l l Expect to go back to 100% sometime this shift j l Watch the temperatures on the cooling water ! ! systems, expected high today close to 100F ' l Thunderstorms forecast for this afternoon l ARO Scenario: +3 (1)/ --- Plant Manager calls up and orders load decreased to 50% ASAP, the dispatcher has called him and said there are problems on the grid +7 (2)/RD02 Stuck CEA #34 (Grp SA) found on power decrease +12 (3)/ Chemistry reports an increase in SG#3 activity => should also give indications of fuel failure l +18 (4)/ED06B Failure of #2 Inverter => Loss of #2 Vital AC Bus +25 (5)/ED06C Loss of Vital Bus #3 => Rx trip /SG01C Increase SGTL to 10% (~100 gpm) => enough to ensure SI on or shortly after trip NOTE TO EXAMINERS: PROCEDURE ONLY ALLOWS 25 MINUTES FROM TRIP TO EITHER EQUALIZE PRESSURES IN SG AND PZR OR ELSE SHUT RCS LOOP ISOLATION VALVES (E-3, STEP 19) - 3-
, . I l - ES-302 ATTACHMENT 3: SIMULATOR SCENARIO EVENTS 1 SCENARIO No: C - Maine Yankee, Sept 16 '87 f Examiners: Norris Candidates: SRO _ _ _ _ _ RO , Defferding BOP Synopsis: 80% Power 0% BUP 2 Loss of Feed with loss of all RCPs Malfunctions inserted prior to start of scenario: Summer, all cooling water temperatures high

RD08 Failure of all RPS auto trips

1 ' ( Equipment Out-Of-Service MFP 2A for motor replacement

i RX01B Non-controlling pzr pres channel (PIC 101Y) - failed detector i Event / j Time Malf No. ! Description Initial Conditions: 0 l IC#16 Plant at 80% power, 0% BUP, Xenon increasing (came ! I down from 100% late last shift at dispatch request ! l ! Expect to go back to 100% sometime this shift l Watch the temperatures on the cooling water , ~~ I systems, expected high today close to 100F Thunderstorms forecast for this afternoon I ARO , Scenario: +3 (1)/---- Dispatch calls up and requests 100% ASAP due to loss of another plant on the grid /AN01F Loss of annuciator panel for SG alarms +10 (2)/CV12A Charging pump P-14A trips ' Ensure that the RUNNING pump is the one that trips /CV08B Failure of charging flow low +20 (3)/RX09A Failure of Tavg instrument - fail slowly to 0% => loss of Tavg signal to SDTBS - +25 _(4)/ED02B Loss of Station Service Transformer X26 /RX11 Failure of SDTBS controller - 0% severity l => all valves fail to open in automatic /RD08 Failure of auto Reactor trip +26 /ED03B Loss of Station Auxiliary Transformer X16 => loss of all MFPs & RCPs +28 (5)/FW15 Rupture of AFW header upstream of AFW-100 QUESTION: what is AFW-100 => Total loss of feed I -a- - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ . __ _ _ _ _ _ - _- ___ _ - - _ _ ~
_- e e 'ES-302 ATTACHMENT 3: SIMULATOR SCENARIO EVENTS SCENARIO No: A - Maine Yankee, Sept 16 '87 Examiners: Defferding Candidates: SRO RO , Norris BOP ._ Synopsis: 80% Power, 0%'BUP Loss of all electrical power followed by stuck open SG safety Malfunctions inserted prior to start of scenario:

Summer, all cooling water temperatures are high EG03A DG-1A trips due to failure of speed relay l l Equiement Out-Of-Service MFP 2A for motor replacement

RXO_B Non-controlling pzr pres channel (PIC 101Y) due to failed detector Voltage regulator mode switch - tagged out after it caused a

a trip during beginning of scenario the first time l Event / I Time Malf No. Description Initial Conditions: 0 IC#16 Plant at 80%, 0% BUP, Xenon increasing (came down from 100% late last shift por dispatch request) Expect to go back to 100% sometime this shift l Watch the temperatures on the cooling water j systems, expected high today close to 100F Thunderstorms forecast for this afternoon ' All CEAs our (ARO) __ l l Scenario: +2 l (1)/----- 1 Dispatch calls up and requires 100% ASAP l l +15 (2)/RM02C1 RM-1701 SCC fails high => shuts surge tank vent valve +20 (3)/? Loss of Offsite Power WITHOUT unit trip (transformer failure l n I +22 (4)/CWO1C Circulating water pump P-26C trips ' l => reduce power to continue operation I possible manual reactor / turbine trip 1 +25 (5)/MS05C SG#3 Safety Valve fails open - 100% Severity => Reactor / turbine trip /EG03A DG-1A fails to start => only Bus 6 available +28 (6)/EG03B DG-1B trips l l Loss of all Power l l 1 -2-
_ _ _ - _ _ _ - _ J e ATTACHMENT 4 SIMULATION FACILITY FIDELITY REPORT Facility Licensee: Maine Yankee Facility Licensee Docket No. : 50-309 i Facility Licensee No. : DPR-36 l Operating Examinations Given At: Maine Yankee Simulator Operating Examinations Given On: September 16-17, 1987 During the conduct of the simulator portion of the operating examinations identified above, the following performance discrepancies were observed: 1. The smallest leak rate for a steam generator tube leak is 10 gpm. By Maine Yankee procedures, a manual reactor trip is required. To train on a small tube leak, the facility states that they can " work around" the problem with the leak being elsewhere and overriding the alarms for the secondary process radiation monitors. 2. The simulator does not have the ability to mimic manual operation of all the valves on the main control board. An example is FW-M-19 and FW-M-20, the discharge valves on the motor driven main feed pumps. During one of the scenarios, it was not possible for the candidates to implement the Emergency Operating Procedure for a loss of heat sink (FR-H.1). Enclosed as a part of this attachment are the ES-302 " Simulator Scenario Events" forms. i ! l l , l ! I - - - - - --- -- - --- }}

ML20236R469

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sas rrx ==

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ML20236R469

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=

'

sas rrx ==

==

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