IR 05000213/1987007

OL Exam Rept 50-213/87-07OL for Exams Administered During Wk of 870316-19.Exam Results:All Four Senior Upgrade Candidates Passed Written & Oral Exams

ML20213G320
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/07/1987
From:	Collins S, Crescenzo F, Keller R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20213G313	List: IR 05000213/1987007 ML20213G311
References
50-213-87-07OL, 50-213-87-7OL, NUDOCS 8705180231
Download: ML20213G320 (44)

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U. S.' NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO. 87-07 (OL)

FACILITY DOCKET NO. 50-213 FACILITY LICENG: NO. DPR-61 LICENSEE: Connecticut Yankee Atomic Power Company P. O. Box 270 Hartford, Connecticut 06141 EXAMINATION DATES: March 16-19, 1987 GHIEF EXAMINER: q 21 87 F. Cres6ahzo, Reac Engineer (Examiner) Date REVIEWED BY: )

R. Keller, Chief, P'roject Section 1C k

Date

APPROVED BY: laryuse f/(dll/y>! 5 1(B7

%muel J.' Collins, Deputy Director, DRP Date

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SUMMARY: OperatcklicensingexaminationswereadministeredtofourSenior Operator upgrade candidates during the week of March 16. All candidates passed the written and oral examination t 8705180 PDR A f500PDR 13

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REPORT DETAILS TYPE OF EXAMS: Replacement

' EXAM RESULTS:

l SRO l l Pass / Fail l .

l l l l 1 L l Written Exam l 4/0 I I I I I I I l Oral Exam l 4/0 l

I I I I I I l Simulator Exam l 4/0 l l l l l l l

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I OVERALL l 4/0 l t

i I i CHIEF EXAMINER AT SITE: F. J. Crescenzo, Reactor Engineer (Examiner) OTHER EXAMINERS: D. Silk, Reactor Engineer (Examiner)

R. M. Keller, Chief, Operator Licensing l SUMMARY OF GENERIC STRENGTHS OR DEFICIENCIES NOTED ON OPERATING EXAMS: No significant generic weaknesses were noted during the simulator

examinations. Generally, the candidates performed well.

' Some candidates had great difficulty locating PIDs using the micro-  !

fiche files in the control room. This problem may be indicative of a system problem rather than a candidate problem since an efficient method for indexing of the micro-fiche cards does not seem to exis Some of the candidates seemed disoriented in the control room due to

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recent control room modifications. All the candidates had spent considerable time as reactor operators on shift, however, it was apparent that some had remained detached from the control room during their upgrade training program. This was evidenced by the candidates having to conduct brief searches for selected logbooks, procedures, and prints during the examinations.

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3 SUMMARY OF GENERIC STRENGTHS OR DEFICIENCIES NOTED DURING GRADING OF WRITTEN EXAMS:

The candidates performed poorly on the following question This information is provided for'use in upgrading future requalification and initial operator training programs. No reply is require Question # Topic Class Average 5.I2 Discussion of Axial 33.3%

Flux Redistribution 7.05 Description of alternate 54.1%

RHR flow paths following normal RHR failure 7.06 Alternative methods for 38.7%

dose monitoring in high radiation area .13 Technical specifications 66.6%

regarding startup with inoperable containment valve EXIT INTERVIEW DETAILS Personnel Present at Exit Interview:

NRC Personnel F. J. Crescenzo, Reactor Engineer (Examiner)

S. Pindale, Resident Inspector Facility Personnel D. B. Miller, Plant Superintendent G. H. Bouchard, Unit Superintendent R. E. Brown, Operations Supervisor B. Ruth, Supervisor, Operator Training J. E. Deveau, Assistant Supervisor, Operator Training M. F Bray, Assistant Supervisor, Simulator Training SUMMARY OF NRC COMMENTS MADE AT EXIT INTERVIEW: The items noted in paragraph 3 above were discusse The facility was informed that results of the examinations would not be available until after the licensing process was complet Every effort would be made to have the results within 30 day , - - _ _ _ .__ .. - _ _ _ _ _ _ . . _ _ _ _ . ---_ _ __ _ _ _ .-___ _ _ __

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4 The facility was informed that that the exam review was efficient and well organized. -Comments on the exam were pertinent and well documente _The facility was informed that the simulator performed well with exception of two malfunctions (feedwater heater malfunction and 120vac malfunction). SUMMARY OF FACILITY COMMENTS AT EXIT INTERVIEW: The facility stated that the exams were well prepared and thanked the examiners for their efforts, In response to item 3.b above, the facility stated that many extra-neous prints were also filed in the microfiche file. Any prints which are required for control room use are available in hard copy for In response to item 3.c above, the facility stated that the control room had been reorganized in response to NRC comments in a previous inspection. The Station Superintendent stated that the candidates would be reoriented with the control room prior to performing further license function . RESOLUTIONS TO FACILITY COMMENTS ON WRITTEN EXAMS:

The " master answer copy" is marked and initialed to indicate resolution of questions raised during the two hour exam review on March 17 and is provided as Attachment 1 to this repor All comments were resolved to the satisfaction of the facility and the chief examiner during the post examination review. The following represent those comments which resulted in significant changes to the examination answer ke Facility Comments Question 5.05 - also accept power level as a parameter which can effect DNBR Resolution - comment accepted, acceptable alternate answer Question 5.06 - answer should be " decrease" Resolution - comment accepted, proper reference material provided to support comment Question 5.09 - also accept the five conditions of ES 0.1 for verifying the effectiveness of natural circulation Resolution - comment accepted, acceptable alternate answer Question 6.01b - answer should be FALSE since "any" implies all Resolution - comment accepted

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Question 6.02c - answer should be FALSE since SIAS would not be reset Resolution - comment accepte Question 7.11 - also accept.the alternate answers as described in CY-LO-MITCOR L75004 Resolution - comment accepte Question 7.12 - answer for method of verifying effectiveness of alternate heat sink methods per FR H-1 should be core exit Tc Resolution - comment accepte Question 8.01d - answer should be TRUE as question was unclear Resolution - comment accepte Question 8.04b,c - answers should be YES due to state requirements for one hour notifications and station administrative requirements to notify NRC whenever the state is notified Resolution - comment accepte Question 8.06c - delete this question since a recent procedure change deleted all time requirements Resolution - comment accepte Attachment 1: Written Examination and Answer Key (SRO)

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U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _USDDBM_NEGb'_____________ ,

REACTOR TYPE: _EWB-WEG4________________

DATE ADMINISTERED _DZZ9}/17 _______________

EXAMINER: _GBESCENZ92_E2 _ _ _ _ __ _ _ _ _ _ _ _

! [1 CANDIDATE:  ?

II?~ikd_________---

i.'d INSIBUGI19NS_ID_G6NDID6IE1 Use separate paper for the answer Write aiswers on one side onl Staple question sheet on top of the answer sheet Points for each question'are indicated in parentheses after the questio The passing grade requires at least 70% in each category and a final grade of at *

1 east 80%. Examination papers will be picked up six (6) hours after the examination start % OF CATEGORY % OF CANDIDATE'S CliTEGORY

__Y6LUE_ _IQI6L ___SGQEE___ _Y6LUE__ ______________G6IEGQBY_____________

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_2Dt99__ _25z00 THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS

_2Dx99__ _2Dz99 ___________ ________ PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION

_2Dz99-_ 2DAQ9 ___________ ________ PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL iS . o o CONTROL 1H.$o eMves  !

_Ekt@9__ _EDI1l!g ___________ ________ ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS

%.5o lisass__ ___________ ________% Totals -

Final Grade t

i All work done on this examination is my ow I have neither given l nor received ai ,

___________________________________

Candidate's Signature

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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS

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During the administration of this examination the following rules apply

, Cheating on the examination means an automatic denial of your application and could result in more severe penaltie . Restroom trips are to be limited and only one candidate at a time may leav You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

Use black ink or dark pencil 9D1y to facilitate legible reproduction !

! Print your name in the blank provided on the cover sheet of the

examinatio i Fill in the date on the cover sheet of the examination (if necessary).

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i Use only the paper provided f or answer . Print your name in the upper right-hand corner of the first page of gggh section of the answer shee ,

, Consecutively number each answer sheet, write "End of Category __" as l appropriate, start each category on a Ogw page, write gely 90 gag Sldg i j of the paper, and write "Last Page" on the last answer sheet.

i Number each answer as to category ano number, for example, 1.4, 6.3.

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i 1 Skip at least th tgg lines between each answe f

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or tabl i

, 12. Use abbreviations only if they are commonly used in facility LLtgtetytg.

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l 13. The point value for each question is indicated in parentheses after the  !

question and can be used as a guide for the depth of answer required.

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14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

! 15. Partial credit may be give Therefore, ANSWER ALL PARTS OF THE l QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

I I 16. If parts of the examination are not clear as to intent, 'ask questions of the gxamtagt only.

17. You must sign the staterent on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.

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18. When you complete your examination, you sha11:

r Assemble your examination as follows:

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(1) Exam questions on top.

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(2) Exam aids - figures, tables, et (

(3) Answer pages including figures which are part of the answe !

l Turn in your copy of the examination and all pages used to answer  !

the examination question Turn in all scrap paper and the balance of the paper that you did i

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not use for answering the questions.

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' Lee.ve the examination area, as defined by the examiner. If after 1 leaving, you are found in this area while the examination is still

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in progress, your license may be denied or revoke I

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. .Ds__IMEDBY_DE_ NUCLE 88 EQBEB_EL8BI_DEEBBIIDui ELUIDS t_8ND PAGE 2 THEBDQDyB6 Mig 5

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i OUESTION 5.01 (2.50)

a. When the speed of a centrifugal pump triples, what happens to its capacity? (0.50)

b. When the speed of a centrifugal pump is slowed to one-half its original speed, what happens to pump head? (0.50)

c. If there is a 75% increase in pump speed, by what factor must the power to the pump increase? (0.50)

d. Water enters a condensate pump at 90 deg. F and a 27 in-Hg vacuum. Does the pump cavitate? Provide data to support your answe (1.00)

OUESTION 5.02 ( .75)

Which one of the following conditions would result in the smallest subcooled margin? Assume identical RCS pressures and briefly explain your answe a. A controlled natural circulation cooldown immediately following a reactor trip from a complete loss of flo b. Continued operation at 5% power c. All RCP's are operated at normal no-load temperature after extended shutdow QUESTION 5.03 (2.00)

An ECP is calculated for a startup 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after a reactor trip from 100%

steady state powe Indicate whether the actual critical position will be HIGHER THAN, LOWER THAN or the SAME as the ECP for the following condition The steam dump pressure setpoint is increased by 45 psi All steam generator levels are increased by 5% one minute before the calculated ECP is to be reache Condenser vacuum is reduced 3 " Hg due to a small air lea Reactor startup is delayed for 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

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QUESTION 5.04 (2.50)

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Indicate how the f ollowing parameters will change f rom initial values,once new steady state conditions are established,1f the #1 RCP trips while the unit is operating at 40% power. Assumo no operator actions, that no reactor trip, turbine trip, or SI occurs and that all controls are in automatic and

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operating initially from the 4-loop mod Answer should states INCREASES, DECREASES, or ESSENTIALLY THE SAME.

- Indicated DP in loop 3.

i Turbine Loa .

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J Delta-T in loop ; Core differential pressur ,

• Steam pressure from the steam generator for loop 4.

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l OUESTION 5.05 (3.00)

Give three parameters on the primary side, affecting DNBR, that i can be observed or controlled by the reactor operator, noting whether an increase in each parameter will RAISE or LOWER the I

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, DUESTION 5.06 (2.00)  ;

) The plant has operated at 100% power for the last ten days. If the plant were to trip from this power level, state the effect that

, Xenon would have on the shutdown margin at each of the following times. Consider each separately and assume all other factors

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remain the sam hours after the trip i

i l hours after the trip j hours after the trip hours after the trip

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QUESTION 5.07 (2.25)

Use Figures 5-3a, 5-3b and 5-3c to answer the following questio,ns. ._ , ,_ g l&$ see; ^- - -

• kyr What portion, if any, of the moderator deficit.of b66 pcm from HZP to HFP can be attributed to a pr,wer increase from 0 to 60% power?

Explain your answe (0.75) The CY plant is being operated at 100% power at 4 EFPD with Bank B [

at 320 step If boron concentration does not change, calculate l the equilibrium rod height if power is lowered to 50% . Show all ,

work and state all assumption (1.50) '

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b OUESTION 5.08 (1.75) What is the subcooling margin (SCM) of the plant if the following [

conditions exist? Show all calculation (1.00) l Th =550 F Ppzr=1985 psig Tave=535 F Psg #700 psig Tc =520 F If plant power is raised from 50 to 100%, will SCM change INCREASE, DECREASE,or STAY THE SAME7 Explain wh (0.75)

OUESTION 5.09 (2.00)

Explain the two methods by which an operator may confirm the continued effectivenens of natural circulatio ,

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QUESTION 5.10 (1.75)

The following data is obtained curing an initial approach to criticality following a refueling outage:

RCS BORON CONCENTRATION (ppm) SOURCE RANGE DETECTOR COUNTS (cps)

j _____________________________ _________________________________

i 1900 32 1850 39 1600 50 1750 70 Using figure 5-1 as an answer sheet, construct an inverse multiplication plot (1/M plot) and predict the boron concentration at which criticality l

will occur. Show all equations used and calculations made. Next to each j point on the 1/M plot LIST the coordinates for that point.

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QUESTION 5.11 (1.5T Describe HOW, (mcre or less negative), and explain WHY the l Moderator Temperature Coefficient varies due to the following j

changes Buildup of fission product possons.

! Core age increases, c. Control rode are inserted into the cor DUESTION 5.12 (3.00) What are the major factors which contribute to the Axial Flux Redistribution Reactivity for an equilibrium core at BOC7 l Explain HOW and WHY the magnitude of the Axial Flux Redistribution Power Coefficient changes as the core ages?

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QUESTION 6.01 (2.00)

Indicate whether the following statements are TRUE or FALSE:

a. Loss of any vital 120 VAC bus during normal operation at 100% power will cause a turbine runback below 70% powe > Loss of any single vital 120 VAC bus can result in a reactor trip due to loss of power to instrumentation which provides input to the reactor protection syste c. Loss of semi-vital bus number 2 will affect semi-vital bus nur,3ber MCC-5 normal supply to the semi-vital bus is lost and subsequently restored. The ABT will automatically transfer back to MCC-5 caucing a momentary interruption in power to the semi-vital bu QUESTION 6.02 (3.00)

Indicate whether the following are TRUE or FALSE. If your answer tu FALSE, explain why the statement is FALS a. Following an SI/HCP actuation, concurrent with a loss of offsite power, the charging pumpt will auto start at T=20 sec Prior to rearming the 51/HCP, (following reset), the operator aust ensure all twelve of the HCP MCB operated valves are shu c. Following an SI/HCP actuation, the HPSI cold leg injection valves, (SI-MOV-861 A-D), may be throttled if the safety injection actuation signal is not presen d. HPSI pump "A" breaker controls can be separated from the control room portion of the pump control circuits for local operations concurrent with an " appendix R" class fir (***** CATEGORY u6 CONTINUED ON NEXT PAGE *****)

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OUESTION 6.03 (3.00)

While operating at rated power, a feed water regulating valve fails open due to a control system failure. State whether the the following will INCREASE or DECREASE and briefly explain wh INITIAL steam generator water leve Feed pump suction pressure, c. Steam line delta pressur QUESTION 6.04 (1.50)

a. What potential problem can result from operating greater than 3 reactor coolant pumps with an RCS temperature less than 465 degrees F7 What potential problem does the anti reverse rotation device associated with the reactor coolant pumps prevent 7 When reactor coolant pumps 3 or 4 are shutdown, why must

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their corresponding loop spray valve be closed?

QUESTION 6.05 (1.50)

Give three methods by which an operator can recognize voiding in the reactor coolant syste DUESTION 6.06 (2.25)

Listed below are several valves contained in the Chemical and Volume Control System (CVCS) that will be affected by either a low pressurizer level, high letdown temperature or HCP signal. For each valve listed, state ONLY the signal (s) that affect them and the position the valves will go to automatically. (Assume that all systems are in AUTOMATIC and that NORMAL system lineups are in effect. ) LD-MOV-2OO (Letdown Stop Valve) LD-FCV-202 (Letdown Orifice Isolation Valve)

c. LD-FCV-113A (Demineralizer Dypass Valve) LD-TCV-113D (Letdown Radiation Monitor Trip Valve)

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e OUESTION 6.07 (1.50)

A. Why is at necessary for the backup heater banks A and E to trip on an 517 (0.501 b. What two interlocks must be satisfied prior to placing the low pressure overpressure protection system in service? (1.00)

DUESTION 6.08 (2.00)

a. What is the purpose of TE-1000 temperature indication in the AFW main header and what specific problem does monitoring this temperature help prevent? (1.00)

b. What specific conditions will EXTINGUISH the white lights labeled

" AUX FDWTF Auto Start Actuation Train A/D" on MCB panel G-27 (0.50)

c. Why does the AFW auto initiation circuit contain a 30 second time delay on low SG 1evel? (0.50)

DUESTION 6.09 (2.50)

a. For normal operation of the Containment Spray System (CSS), what are the two sources of water, and what two systems provide the motive force for the wate (1.00)

b. What is the emergency bac6:up water supply for the CSS? (0.50)

c. What other system is utilized inside containment to reduce containment pressure following a LOCA7 (0.50)

d. With 40 psig in the containment, how would the CSS be initiated? (0.50)

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DUESTION 6.10 (2.00)

The plant in in hot chutdow NI-12 reado 600 cps and NI-14 reads 800 cps, a. An instrument technician reports to the shift supervisor that he thinks NI-14 discriminator voltage is too hig What is meant by the term " discriminator voltage"?

b. If the technician reduced the magnitude of NI-14's discriminator voltage, what would you expect to see happen to the NI-14 reading?

OUCSTION 6.11 (1.25)

List the five potential EcurCes of radioactiND Contamination which, if introduced into the Service Water System, would be indicated on R-18. (Service Water Effluent monitor).

QUESTION 6.12 (2.50)

a. Driefly describe any AJTOMATIC actions, besides alarnt, associated with each of the following Radiation Monitoring System monitors: (1.50)

1. River Effluent Monitor (R-10)

2. Component Cooling System Monitor (R-17)

3. Main Stack Effluent Manitor (R-14A)

b. List the process radiation monitors on at least twc different systems that con be used to detect primary to secondary tube leakag (1.00)

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OUESTION 7.01 (2.00)

Indicate whether the following statements regarding AOP-3.2-22,'

" REACTOR COOLANT SYSTEM / VENTING OF NONCONDESABLE GASES" are TRUE or FALS An indication of non-condensable gases in the pressurizer can be ascertained indirectly by pressurizer pressure being higher than saturation pressure for a given pressurizer temperatur While venting the RCS from the vessel head vent, pressurizer level increases. This indicates that gaseous voids exist within the pressurize c. While venting the RCS from the vessel head vent, pressurizer level remains approximately the same. This indicates that no significant gaseous voids exists in the RC Increased charging flow with condensable gases in the RCS may result in a decreasing pressurizer leve QUESTION 7.02 (2.50)

a. What are t he two criteria used in E-2 to identify a faulted SG7 (0.50) What are the four critoria contained in E-3 used to identify a ruptured SG (2.00)

OUESTION 7.03 (1.50) Who, by title, may outhorize higher emergency radiation exposure limits for volunteers during search and rescue efforts 7 What whole body exposure levels can be authorized for a volunteer entering an area:

1) To remove an injured perso ) To control a fir (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

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OUESTION 7.04 (3.00) I

The following questions concern the precautions and prerequisites of ;

.' procedure NOP 2.4-2, Reactor Coolant Pump (RCP) Operation , Why must the seal water return valves be closed when primary [

pressure is less than 100 PSIG7 (0.50) !

, List two conditions that allow a RCP to be operated without f seal wate (1.00) ' What action must be taken if Component Cooling Water (CCW) is i

lost to the RCP motors? (1.00)

I What would be the results of exceeding the motor starting i limits?

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QUESTION 7.05 (3.00)

. Procedure AOP-3.2-12, LOSS OF RESIDUAL HEAT REMOVAL SYSTEM, describes I

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alternate flowpaths or methods to be used for decay heat removal dependent on plant status. ORIEFLY describe the flowpath (

j used for decay heat removal given a loss of RHR during '

the following conditionc. Assume RHR piping and components are l 4{ intac l l

j a. Refueling cavity ful :

l b. Reactor vessel head secure c. Reactor vessel head partially remove ~

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OUESTION 7.06 (2.00)

a. Procedure AGP 3.2-23, MALFUNCTION OF ROD CONTROL SYSTEM, instructo

the operator to immediately reduce power to less than i J

70 % by boration if a control rod is misaligned by greater than [

. 24 steps for less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Explain the basis for this ,

power reduction.

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b. How would the operator actions differ if the rod were {

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misaligned for GREATER than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 7 t i i

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QUESTION 7.07 (1.50)

According to procedure ACP 1.04, RWP COMPLETION AND FLOW CONTROL, three alternatives are available for providing radiation doso protection when entering a HIGH RADIATION AREA. What are these three alternative QUESTION 7.00 (2.25)

Answer the following questions concerning EOP 3.1-48, Cavity Seal Failure, a. List the TWO immediate operator actions for a Cavity Seal (1.00)

Failure, If irradiated fuel assemblies are in the following locationc (1.25) ,

when a Cavity Seal Failure occurs, describe what shoulo be done with the fuel assemblie . In the core envelope and attached to the manipulation crano In the fuel transfer car

, In the RCC change itxture l

OUESTION 7.09 (1.50)

l ODI W109 deals with the utarting of reactor coolant pumps while the RCS is in a nolid condition. Daned or, the instruction portion of this ODI, answer the following

,

a. State the two locations for ncacuring S/G secondary sido temperaturo

! AND the method used for adjusting secondary sido temperatur What are the secondary side temperature limits which must be met prior to starting a reactor coolant pump?

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(**sst LATEGORY 07 CONTINUED ON NEXT PAGE 88844)

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QUESTION 7.10 (2.00)

During an emergency condition the STA reports the following:

1. Core Cooling -

Orange Path 2. Subcriticality - Yellow Path 3. Integrity -

Orange Path 4. Heat Sink -

Red Path In what order should the above conditions be addressed? (1.00) Ten minutes later the STA reports that the above conditions still l exist except that Core Cooling is on a Red Pat What actions should be taken and why? (0.50)

After a Reactor Trip, what two circumstances initiate monitoring the l Status Trees? (0.50)

OUCSTION 7.11 (1.75)

l a. What three indications must be present for " adverse containment" conditions to be in effect? (0.75)

l b. Explain how adverse containment conditions can result in instrument

'

loop inaccuracie (1.00)

DUESTION 7.12 (2.00)

l According to procedure FR-H-1, " Response to Loss of Secondary Heat l Sink," what two methods are availabic for an operator to provide core cooling when in a loss of heat sink condition, and, how does the operator verify the effectiveness of these two methods?

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(***** CND OF CATEGORY 07 *****)

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. Bi__8DDINISIBBIIVE_EB9CEDUBESi_CONDIIIONS2_8ND_LIMIIBI1ONS PAGE 14

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QUESTION 8.01 (2.00)

Indicate whether the following statements regarding refueling operations are TRUE or FALSE: Crane lifts (excluding manipulator crane) can be made over -

the cavity and transfer canal when the cavity is flooded and transfer tube ope If communications are lost, fuel movements in progress may be completed using the backup communications syste c. For purposes of limiting locations of fuel assemblies, fuel in tl.o core is counted as "in the cavity," as soon as it is latched with a manipulato At least two neutron monitors must be operable when movement of irradiated fuel is in progres QUESTION O.02 ( .50)

Per Tech Specs, select the one set of crew manning that best represents the minimum requirement for a reactor startup. An STA is on-shift in each cas A. 2 SOPS, 1 ROA, 1 AOP B. 1 SOPS, 2 ROPs, 2 AOPs C. 2 SOP, 2 ROPs, 2 AOPs SOP, 1 ROP, 1 AOP QUESTION 8.03 (1.00)

Answer the following questions concerning CY facility staffing. Assume plant power is 100% unless otherwise specifie What is the minimum number of fire brigade members 7 (0.25) What is the minimum number of operators necessary for safe shutdown? (0.25) !s it permissible to use an individual required for safe shutdown as a member of the fire brigade? (0.50)

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

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QUESTION 8.04 (2.00)

Indicate whether the following would require a one hour notification of the NRC: Initiation of a plant shutdown required by Technical Specification b. Any airborne release that exceeds 2 times applicable concentrations of the limits specified in 10CFR20, when averaged over a one hour time perio Any event, related to health and safety of the public, for which notification to other government agencies has been, or will be made.- An error during a calibration procedure occurs which should have caused a safety injection. Safety injection did not occu QUESTION 8.05 (2.00)

Classify the following events using the attached copy of table 4-1 from EPIP 1.5-1. State which EAL from table 4-1 you used to determine the classification. EXAMPLE ANSWER: Alert , Equipment Failure Explosion in the emergency diesel room and subsequent fire which is extinguished within ten minute Diesel generator is severely damaged; plant in mode Due to improper maintenance practices, all onsite batteries banks musts 5e declared inoperable (DC voltage still exists). Service water effluent process rad monitor R-18, in alarm condition for 25 minutes due to an uncontrolled releas Maximum reading on monitor was three times alarm setpoin Tornado sighted within five miles of site boundar (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

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QUESTION- 8.06 (3.00)

a. What are the TWO responsibilities of the Shift Supervisor as outlined in ACF 1.0-4, Radiation Work Permit Completion and Flow Control? (1.00)

b. Under what condition would a blanket RWP be issued? (1.00) How long is a blanket RWP in effect? (0.50) Who can terminate a blanket RWP? (0.50)

QUESTION 8.07 (1.50)

Techncal Specification 3.15 addresses reactivity anomalie Define a reactivity anomal Explain the significance of a reactivity anomal Describe the method used to determine if a reactivity anomaly exist QUESTION 8.08 (2.00) From whom must permission be obtained for MANUALLY opening the pres-surizer PORV's during NORMAL plant operation? (2 approvals) (1.00) Who must be notified in the event of spurious opening of the PORV's? (0.50) Why are the restrictions from part (a) in place? (0.50)

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. QUESTION 8.09 (3.00)

'

a. ADMINISTRATIVE VERIFICATION may be used to determine operability of. equipment. Define ADMINISTRATIVE VERIFICATIO b. State whether the following equipment should be verified operable by an ADMINISTRATIVE VERIFICATION or TEST RUN prior to removing the redundant counterpart for maintenanc . LPSI pum . RHR pum . Auxiliary Steam Generator Feed pum . Emergency Diesel Generator, How is an ADMINISTRATIVE VERIFICATION documented?

!

OUESTION 8.10 (1.50)

According to procedure ADM 1-1-60, " Access to the Control Room During Emergencies," the Shift Supervisor may be relieved if it is apparent that he has become ineffective in carrying out his duties to mitigate cicumstances of the emergency. What

administrative requirements e>

ist f or this type of relief?

OUESTION B.11 (1.50)

Prior to ordering a station evacuation, the shift supervisor must evaluate certain criteria in order to determine the appropriate

' evacuation mode. State what this criteria is and the basis for its evaluation.

s DUESTION 8.12 (2.00)

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While operating in mode 1, an electrical malfunction occurs which renders diesel generator EG-2A inoperable.HPSI pump P-15-1A has been inoperable for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Using the attached technical specifications, determine what actions, if any, should be taken. Be sure to i

reference all portions of technical specifications used to develop your answer.

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

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QUESTION 8.13 (3.00)

As part of a turnover. you are told that valve LD-ADV-203 (Letdown Orifice Isolation) appears to be " mechanically bound" and will-NOT close. The reactor is currently in mode 3, and it is expected that your shift will commence a reactor startup. The off-going supervisor explains that no actions are necessary for the malfunctioning valve other than to notify maintenance in the morning. Reference the applicable paragraphs

. from the attached technical specifications to answer the following question Do you agree with the determination of the offgoing i supervisor? Justify your answe May you commence a reactor sta-tup? Justify your answer, j

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(***** END OF CATEGORY 08 *****)

(************* END OF EXAMINATION ***************)

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,-,n,..--,,n---,---, - . , , , - - - , , - . - , , - - an,. ,.n.,.,n,-- , , , , , , , - - - . - , . , - . - - - - . , - - , . - . - - , , , - - , . . , - . ~ . ,

_ _ = _ __ . _ .

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' PAGE 19

1. 2__IBEDBY_DE_NUDLE88_EDWEB_EleNI_DEEBBIIONz_ELUIDSi _8ND

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j lIBEBdDDYNedIDS-87/03/17-CRESCENZO, .

,

. ANSWERS -- HADDAM NECK pg.e---

n .. > . _. .

ANSWER 5.01 - ( 2: . 50 ) Capacity triples. (0.5)

b. Pump head decreases to one-fourth the original head. (0.5)

c. Power must be increased by a factor of (1.75)**3 = 5.36 (0.5)

- Psat = .698 psia (0.25)

Psuct-= 1.44 psia (0.25)

.Psuct > Psat; pump will not cavitate. (0.5)

REFERENCE CY-OP-LO-HTFF-L65013, pgn. 9-11, E.O. 5, 3.

'

193003 K1.25 3.3/ K1.05 2.3/ K1.06 3.2/ K1.01 2.5/ '

i 1 ANSWER 5.02 ( .75)

a (0.25)

Core delta T during natural circulation ccoldown will approach full load That is greater than in the other 2 case (0.5)

delta REFERENCE CY-OP-RO-HTFF-L65011, pg 12-14 19003 K1.25 3.3/3.4 i

ANSWER 5.03 (2.00)

1) Higher (Tavg increases, adds negative reactivity)

2) Lower (Tavg decreases due to cold feedwater addition)

3) No effect 4) Higher (Xenon concentration increases adding negative reactivity)

'

REFERENCE CY-LO-RXTH L35011 pg. 27 EO 11, 12

,

001/000 K5.29 3.7/3.9

! 001/000 K5.38 3.5/4.1

, 192006 K1.08 3.3/3.4

,

i

. , _,.,_,,.,_.-,.,m- . ,,, ,, ,_., __, _ - ,- - -,- _ .-.-_, _ _.- -

. - . . . _ - . . . . - _ - - . . - - - - - - - - - - - - . _ _ - . _ _ _ _ .

, .. .

-

It__IBEQBY_QE_UUCLE68_EQWEE_EL6MI_QEEBBI1QUm_ELUlQEt_6NQ PAGE 20 f ISEBdQQYNedlGE

ANSWERS - 'HADDAt1 NECK -87/03/17-CRESCENZO, .

ANSWER 5.04 (2.50) Increases Decreases c. Decreases Decreases Decreases [ 5 9 0.50 each 3 REFERENCE CY-OP-LO-EOP-L30, page 10 CY-OP-RO-HTFF-L65015, page 20 through 23 003/000 K3.01 3.7/ .4-1 000/015 EK1.04 2.9/ ANSWER 5.05 (3.00)

RCS coolant flowrate (0.5) increase will raise DNBR (0.5)

Coolant inlet temperature (0.5) increase will lower DNBR (0.5)

Pressurizer p(essure (0.5) increase will raise DNBR (0.5) g Pau.. r le ve l (e4)m c. r eg s t msR l o w e r- D v 0 02. (o. 5 ) 3 rept< 4 REFERENCE CY-OP-RO-HTFF-L65011 pgs 13 thru 15, /000 K5.01 3.3/ K1.05 3.4/ v ANSWER 5.06 (2.00)

a. Increase

. Increase TT.; C rr D s creas e d. Decrease EO.5 each3 REFERENCE PIB module B chapter 5 pg. 16 001/000 K5.33 3.2/ /000 K5.38 3.5/ . ,

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/ IMEBdQQYNedlCE

. ANSWERS -- HADDAM NECK -87/03/17-CRESCENZO, /000 K5.26 3.5/ ANSWER 5.07 (2.25)

a. None (0.25) RCS Tave is constant (at 535 F) up to 657. power. (0.5)

b. The negative reactivity of the rods must overcome the positive reactivity f rom power deficit and Xeno .

Xenon reactivity = 2293-1696= 597 pcm (0.5) M*I Power deficit = 1290- 520= + 770 pcm (0.5) eqbd' n[<4

= 1367 pcm y Using Figure 5-3c, rods must be inserted to 215 steps on Bank A (0.5)

REFERENCE CY, Cycle 14 Physics Data 000/001 EK1.23 2.6/ ANSWER 5.08 (1.75)

a. From the C-E Stm Tables, Tsat for 2000 psia = 635.8 F (0.5)

SCM= Tsat-Th= 635.8-550= B5.8 F (0.5)

b. decrease (0.25)

Th increases as unit delta T increases with power and Tave (0.5)

.

REFERENCE CY-OP-RO-HTFF-L65011, pg 12-14 EO 11 002/000 K5.09 3.7/ ..

Qu__IBEQBY_QE_NUCLEeB_EQWEB_EL6MI_QEE86IlQUt_ELQ1QEt_6dQ PAGE 22 e ISEBMQQYN6 MIGS

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ANSWERS -- HADDAM NEC /03/17-CRESCENZO, t *

A . .

ANSWER 5.09 (2.00) M'C 4 (' t P

• * ' **' O 5 O' I on Pu- nqit 4N ab Ndd 1. Steam release is occurring from the steam generators (0.5)

and is ef f ective in maintaining essentially constant steam pressure. (0.5)

2. The averaged (0.25) reading of core exit thermocouples (0.25)

maintained at a'value less than saturation temperature for pressurizer pressure (0.5)

a REFERENCE g...u-.........i..-....

CY-LO-HTFF L65015 pg. 14, 15, , 8, , , , ,,,,, ,,,,,..,,,,, ,,,,,

. . - .n .eucmi .

002/000 A4.02 4.3/ .* " ' " " ' ' ' " ' " " " " " * ' " " ' * ' " -

193008 K1.22 4.2/ i.' ""e w n"u"n*u*."*' "*a

. ". .'"'e'n"w~ son fuwiennes ses es ANSWER 5.10 (1.75)

R atta.mm wi apia iur waLo gi wiLi. For using correct equation for 1/M: 1/M=CRo/CR1 [O.253 For each correct data point: (1900,1.OO);(1850,0.82);(1800,0.64);

(1750,0.46) C 4 G O.25 each 3 For correct boron concentration for criticality;1620 ppm "- 10r,., e k EO.503 o v- vee en p% se REFERENCE CY, Reactivity and Reactor Control, Ch. 2. pages 17 & 1 /010 K5.16 2.9/ .1-7 192008 K1.06 2.9/ _

, Et__ldEQ8Y_QF_Nyg(g8B_EQWEB_ELONI_QEEB811QNt_ELylD$t_8NQ PAGE 23 J4- IMEEdQQYNed1GE ANSWERS -- HADDAM NECK -87/03/17-CRESCENZO, F.-

ANSWER 5.11' (1.50)

a. More negative (0.25)., more neutrons are lost due to absorption by the poisons.(0.25)

b..More negative (0.25). As boric. acid concentration decreases, core tends to the undermoderated state or buildup of fission product poisons as neutron absorbers (0.25).

c. More negative (0.25). More neutrons are lost due to absorption in the control rods (.25).

REFERENCE CY-OP-LO-L35006 pgs. 17-21, E.O. 8,9,1 K1.06 3.1/ K1.03 2.9/ ANSWER 5.12 (3.00) At BOC, AFR'is a combination of the flux shift to'less reactive fuel, (bottom half of the core) (0.5) , and variation of the MTC with respect to moderator temperature (0.5).

b. As the core ages, K-excess in the top half of the core decreases (0.5)

and the bottom half of the core is better moderated due to low boric acid concentrations (0.5) These two effects csuse the power

~

to shift downward into an area of even less K-excess effectively adding -dk/k (0.5) thus the AFRPC will become MORE negative.(0.5)

REFERENCE CY PIB, Module D, rev. 2, chapter 3, pgs. 84, 85 CY-OP-LO-RXTH-L35007, E.O. 1 001/000 K5.49 3.4/ /000 K5.30 2.9/ K1.06 3.1/ ,

_ _ _ _ _ _ - _ ._ __- .. . .,

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ht__ELGUI_HYSIEdH_DESIGut_GQUIBQLt_000 195IBudEUI611QU PAGE. 24

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• ANSWERS -- HADDAM NECK -87/03/17-CRESCENZO, .

ANSWER 6.01 (2.00) True M pr A g g g (L mp gy a,jg , Q ., c, g[g ,,,g ,t [p h False

, True (0.5 each)

REFERENCE CY-OP-LO 6700 rev. O, pgs. 27 thru 29, E.O. 10 000/057 EA2.19 4.0/ /000 K4.10 3.1/ CV-OP-LO 6800 rev. O, 10, 13 E.O. 2, 3, 4

. 062/000 A2.10 3.0/ /000 A2.04 3.1/3.4 i

ANSWER 6.02 (3.00) FALSE (0.5), Charging pumps will not auto start with loss of offsite power. (0.5) FALSE (0.5), one valve must be * open prior to rearming.(0.5)

c. M (9.8) FALSE g9 i L45 ss 44 r* * *'t" (. 2 5) TRUE.(0.5) l, REFERENCE CY-OP-LO-PRISYS-LOO 500, p /000 K4.09 3.0/ """""""""""""""""""""" p /000 K4.05 4.3/ """""""""""""""""""""" p /050 K4.01 3.9/ """""""""""""""""""""" p /068 EA1.06 4.1/ E.D. 6,9 ANSWER 6.03 (3.00)

4 Decrease (0.5) due to shrink of level due to increased subcooling (0.5)

b. Decrease (0.5) due to increased flow and resistance. (0.5)

c. Decrease (0.5) due to increased carryover causing an increase i (0.5)

{ in pressure ( c(ec at W4> the outer t: Mtappin s ithe Steam v et'. in [line 5. vuelbowItk)

n REFERENCE i CY-OP-LO-AOP-LI902 pg. 15 of 20' , O /000 A.2.12 3.1/3.4

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,n -,,,---,.-~-~----,---,----_,,,n.v.-m-w,,,,~n-----,-, _ - - - - ,,,.- n.--m-w , . _ , . . , , ,

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6t__ELONI_SYSIEDE_QE@l@Ut_GQU18QLt_eNQ_LNEISUUEN1611QU PAGE 25

o ANSWERS -- HADDAM NECK -87/03/17-CRESCENZO, F.

.

ANSWER 6.04 (1.50) ,

" gg ki9 Possibility of pressure shifting of core internals. (0.5) Excessive starting currents. (0.5) To prevent "short circuiting" spray flow. (0.5)

REFERENCE LO-PRISYS-LOO 220 pgs. 28, 13, 33 EO 31, 9a, 9b 003/000 SG 4 s

ANSWER 6.05 (1.50)

1. Increase in pzr level while depressurizing Difficulty in reducing system pressure while soli ~. Temperature indications at saturation conditions 4. Net zero reading of SCM monitor (3 required at 0.5 each)

REFERENCE AOP 3.2-30 000/074 sg 11 4.5/ ANSWER 6.06 (2.25) HCP CO.25] SHUT CO.253 (, e c (o ul on f\M) HCP [0.253 Low PZR Level CO.25] SHUT CO.25] High LD temp. [0.25] Bypass to VCT [0.253 High LD temp. [0.253 SHUT [0.25]

REFERENCE CY-OP-LO-PRISYS-LOO 400, pages 9-1 /020 A1.05 3.7/ p. 3.1-27 004/020 K4.03 3.0/ p. 3.1-24

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. bz__ELONI_SYSIEUS_DESISUA_CQUIB b _6ND_INSIBQdgNI6119N PAGE 26

. ANSWERS -- HADDAM NECK -07/03/17-CRESCENZO, '.

. ' * f- p s. a n ANSWER 6.07 (1.50) 'M k m c the diesels % W g e,c%g ((0.5)q@<h  %.h To prevent overload of RCS temp ^9 d:;-F (0.5) 340 'P ST (ou RCS pressure <^^9 ;;i;_ (0.5) 3 8o fsL 6 REFERENCk:

PRISYSLOO250 EO 3.d, 9, 5-010/000 K4.03 3.8/ /000 K6.03 3.2/ ANSWER 6.00 (2.00)

a. To alert the operator of FW backflow through the check valves (0.5)

thetrm414-6 shock or water hammer ( 0.. "Y) A Aw Do W ee v%por Wia whichcancausk'.w3 -

4 i: w p sq / L S s AFW auto init. circuit defeated, (0.25) or initiated (0.25)

c. MFW should restore SG 1evel within 10 seconds. 30 seconds allows time for MFW to restore level. (0.5)

REFERENCE CY LO 2100 EO 5 pg. 22,32,34 061/000 A2.06 2.7/ ANSWER 6.09 (2.50)

g H in RWST or containment sump (0.5) Yore: o,,d a no 4 n .f n l{'I. S

,

LPSI or RHR pumps (0.5) g,3 p y hi ., n

- The firemain system (0.5)

c. The Containment Air Recirculation (CAR) fans (0.5) Manually (0.5)

REFERENCE CY, PIB, Primary Systems, Sect A, p0 40,4 /000 K1.01 4.2/ /000 K3.01 3.9/ /000 K4.01 4.2/4.3

. - - _ _ _ _ _ - - _ _ _ _ - - _ _ _ _ _ - - _ - _ _ - _ _ _ _ _ - _ _ _ _ _ _ - _ _ - - - _ _ _ _ _ _ _ _ - _ _ _ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _

___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _

.

fat __ELONI_GYSIEd5_QESIQut_GQUIBOLt_GUE 1NSIBudENI611QU PAGE 27

$ ANSWERS -- HADDAM NECK -87/03/17-CRESCENZO, .

ANSWER 6.10 (2.00) The discriminator voltage is a bias voltage placed on the output from the detectors to eliminate gamma signa (1.0) NI-14 reading should increas (1.6)

REFERENCE CY, PID, Nuclear Instrumentation, pg 13,19 015/000 K5.02 2.7/ ANSWER 6.11 (1.25)

h hf hnk 1. Radwaste releases (planned or unplanned). yt c(e b5 54 " Boron waste evaporator . S/G blowdown tan . RHR HX' . Spent fuel HX' (0.25 each)

REFERENCE CY-OP-PRISYS-LO43OO E.O. 2,5 073/000 K1.01 3.6/ /000 K1.17 3.6/2.7

. . . . . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

a

.

.

,.

6t__ELONI_gySIEdQ_QEQ1QUt_QQU18QLt_80Q_lNE18QdgN1811QU PAGE 26 6 ANSWERS -- HADDAM NECK -87/03/17-CRESCENZO, F.

'.

ANSWER 6.12 (2.50) At alarm point it terminates any liquid discharge in progres (0.5) '

(trips FRCV-1003)

2- At alarm point causes vent isolation valve on CCW surge tank to shut (CC-TV-605) isolating the surge tank from the environment. (0.5)

3- Alarm trips the waste gas decay tank release valv (0.5)

b. Steam Generator Blowdown Monitor (R16A and B) (0.5)

Air Ejector Gas Monitor (R-15) (0.5)

REFERENCE CY-OP-RO-FUNHP-L25010, pg 2-4,7,8

!

EO 4 073/000 K4.01 4.0/ K1.01 3.6/ .

~

. Zt__BBOGE99BES_:_U9BdGLt_8EURBd86t_EdEBEEUGY_GUQ PAGE 29

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B001QLQQ1GOL_GQUlBOL o

ANSWERS -- HADDAM NECK ~B7/03/17-CRESCENZO, *

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ANSWER 7.01 (2.00)

A. F^' nr q gvE B. FALSE C. TRUE D. TRUE (0.5 each)

REFERENCE ADP 3.2-22 rev. 6 pg. 3 of 10 000/074 SG7 3.4/ /074 SG10 4.2/ ANSWER 7.02 (2.50) any SG depressuri:ing in an uncontrolled manner (0.50)

- Any SG completely depressurized (0.50) unexpected increase in any SG wide range level (0.50)

- High activity from any SG blowdown line sample (0.50)

-

high radiation from any SG steamline (0.50)

- high radiation from any SG blowdown line (0.50)

REFERENCE EDP-L10102 EO 1 EOP-L10100 EO 1 000/030 EPEG #10 4.5/ ANSWER 7.03 (1.50) Director of Site Emergency Operations CO.503 ) 75 rems CO.501 2) 25 rems CO.503 REFERENCE RAP 6.2-0, pages 10,11 and 5 through EO: CY-OP-RO-FUNHP-L25005, # 3 and PWG K1.03 2.8/ PWG A1.16 3.1/4.4

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B001QLQQ1G66_CQUIBQL o

ANSWERS -- HADDAM NECK -87/03/17-CRESCENZO, F.

.

ANSWER 7.04 (3.00) To prevent contamination due to backflow through the seal. (0.5) (1) Reactor Coolant System Temperature is less than 150 DEGF. (0.5)

(2) RCP seal leak rate is 5 GPM or less and 20 GPM is flowing through the the Thermal Barrier Cooling Coil. (0.5) The RCP must be stopped within two minutes (0.5) or before either the upper or lower bearing temperatures exceed 200 DEGF. (0.5) Winding damage (due to the heat from excessive starting current). (0.5)

REFERENCE CY, NDP 2.4-2, pgs 1-4 003/000 K1.03 3.3/ /000 K6.02 2.7/ /015 SWG11 4.4/ ANSWER 7.05 (3.00) Gravity drain cavity (.25) through RHR HX's to RWST(.25).

Use LPSI pumps to return RW3T water to cavity. (0.5) RCP (0.5) and steam generator. (0.5) Align purification pump (.25) to draw through RHR HX's (.25) and return through HPSI injection valves. (0.5)

REFERENCE AOP 3.2-12 p , 3 of 4 000/025 EK3.01 3.1/ /000 K4.02 3.2/ r

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.D ANSWERS -- HADDAM NECK -87/03/17-CRESCENZO, '

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l ANSWER 7.06 (2.00)

a. Power must be reduced rapidly because potential for fuel damage is high (.5) and shutdown margin must be restored. (0.5)

b. Continue power decrease to 10% (0.6) using boration (0.4)

i REFERENCE CY-OP-LO-ADP-L13 PG. 35 E.O. G l

001/000 A2.03 3.5/ /024 EK3.01 4.1/ K1.14 3.0/ ANSWER 7.07 (1.50)

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1. Use a doserate meter (which you are trained to use).

2. Health physics toch provides positive control of activities in the are . Individual has an integrating radiation monitoring device set to alarm when a preset dose is receive (0.50 each)

REFERENCE CY-OP-ADMIN-LD5000, pg. 16 of 22, E.D. 7, 10CFR20.203 PWO K1.03 2.0/3.4

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ANSWER 7.08 (2.25)

a. Sound the cntmt evac alarm Close the SF Bldo sluico gato Move irradiated fuel assemblies to shielded locations [Any 2 G O.5 ea3 b. 1. Put it back in the core Unlatch the assembly Move the crano away from the core [3 items 0.25 ma2

! 2. Return it to the entmt but leave it lying down (0.25)

3. Leave it there (0.25)

REFERENCE CY EOP 3.1-40, pg 1,2 00/036 EK3.03 3.7/4.1 l

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ANSWERS -- HADDAM NECK -87/03/17-CRESCENZO, ,

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ANSWER 7.09 (1.50)

( .5 o )

a. - Secondary side temperature taken on hand-hole covers 50.25: '

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- _. SOT" ! d :: 2 .' m,- 5, 6 0.252

- adjusted by feed and blood CO.503 b. - No hotter than primary side temperature Co.253 l

<

- No more than 20F colder than primary side temperature CO.253 i REFERENCE ODI # 109 I

010/000 A1.04 3.6/ .3-2

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l ANSWER 7.10 (2.00)

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i- ,1,3,2 (1.0) i The Core Cooling Red Path should be immediately addressed (.25) l because it is of higher priority than the Heat Sink Red Path (.25).

1 When directed to in E-O or when transforring out of E-0 (0.5)

l 3 REFERENCE

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WOG ERG, Executive Volumo , < CY E-0 i 194001 A1.02 4.1/3.9 i

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4 ANSWER 7.11 (1.75)

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a. High containment pressure (5 psig)  ;

i High containment done rate (100,000 R/hr) l j High integrated doso (1 X 10ee6 Rad) (0.25 each)  ;

1 .

j b. Pressure detectors are calibrated at ambient pressures l

increased pressure will cause detectors to i dicate i

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, less than actua (1.00) ggg gg to q-kyt REFERENCE NWN M d Y bO ,

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j MITCOR-L75004 pg. 27, 10 E0 la,5 194001 A1.02 4.1/ L 7.5 00 y  ;

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em.hh. n,,acA

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, 2t__EBQCEDUEEH_:_UQBUBLt_GEUREUBLt_EdEEEEUCY_GUE PAGE 37 86010LQQ1GOL_GQUIBQL

.o ANSWERS -- HADDAM NECK -87/03/17-CRESCENZO, F.

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l ANSWER 7.12 (2.00) e I4 ((d,c,at438" 3 Restoration of feed flow (0.5); core exit TCs apprce:hin; 575 and r"E p ;;;;r pp u.u a ng e tv psiv6..s, un -,s i c :1 != -1 " OCs-2 . . - w Loan 2^sk #^

_EE}- Bleed and Feed (O.5); "TE pr ; ; e m. - ; - e ti. .-, ;-a^0 ,, e t , ' O . 5 9

REFERENCE con , p 7 c, , , [,

ECP-L10002 EO 4 '

000/074 SG 7 4.4/ de cwws s .

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. at__6Dt1915156I1YE_E60CEQU5EEt GQNQ11100Et_suR_t1d1IeIlQg5 Pact 34

• • ANSWERS -- HADDAM NECK -87/03/17-CRESCENZO, F.

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ANSWER O.01 (2.00)

a. FALSE b. TRUE c. TRUE d. f^LJE (0.50 each)

TRue -

( g 41 a 4,1(

REFERENCE ACP 1.0-10 ANSWER O.02 ( .50)

C (0.5)

REFERENCE CY, Tech Specs Sec PWG23 2.0/ ANSWER O.03 (1.00)

a. 5- fire brigade (0.25) safe shutdown (0.25) No, operators required for saf e shutdown must be e>tcluded from the firo brigade (0.5)

REFERENCE CY, Tech Specs Sec PWG23 2.0/ ANSWER O.04 (2.00)

a. You b. Ne yc5 y oku t 7 b-Ch MT WNM ,

c . Ner 145 d. You (0.5 nach)

REFERENCE ACP 1.0-16 10CFR50.72 194001 M1.02 2.0/ o .

-, .Qu__6Dd181SIBBI1YE_EBQGGQUBESt_C99D1I1QUEt_eNQ_LidlIBIlQUQ PAGE 3r

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ANSWERS -- HADDAM NECK -07/05/17-CRESCENZO, ANSWER O.05 (2.00)

e. Site area, Other Hazards A. (0.5) .c F i *s b. U.E., Equipment Failure B. (0.5)

c. U.E., Radiation Hazards A. (0.5)

d. U.E., Natural Phenomena A. (0.5)

REFERENCE CY EPIP 1.5-1 PWG A1.16 3.1/ ANSWER 8.06 (3.00)

a. 1. The plant will not bo jnopardized by tho work indicated on the RWP 2. No plant evolutions are planned which could change the radiological conditions in the work area. C2 itomo 0.5 ea3 b. Used to record incidental exposure for routine station activities or where small amounts of exposure will be received. (1.0)

r- < - -e r % 5 t- hgT ch4 y

{roctc C., q ,

d. HP (0.5)

REFERENCE CY, ACP 1.0-4, pg 2-4, 12 PWG 1.00 2.0/ ANSWER D.07 (1.50)

a. A deviation from the calculated reactivity orburnup of the core (0.5).

b. Represents a possible error in calculations of core behavior (.25)

can affect assumptions mado concerning core design conditions (.25 c. Measured baron concentration in compared with predicted values (0.5)

REFERENCE CY T.S. 3.15 SG 6 2.7/ o o ,

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2t__0Dul01SIEGILYE_EGQCEDUEC5t_COUD1Il095t_000_ Lid 110110SR FAGE 06 a

ANSWERS -- HADDAM NECI' -07/03/17-CRESCENZO, ANSWER O.00 (2.00s Operations Supervisor (or designated alternate) [0.503 AND the Duty Officer. [0.503 Reported to the Duty Officer. [0.503 To reducu the chancos of a PORV becoming inadvertently stuck open[0.503 REFERENCE ODI #121 010/SG1 0.5/ /GG2 3.9/ ANSWER O.09 (3.00) Review appropriate logu or similar documents to verify operability of the attornato or backup equipmen (1.0) . Test run Test run Administrativo verification 4. Tout run [0.250a3 (1.0) In the Control Room lag cr SG log (1.0)

REFERENCE CY ODI-39 PWG1 3.5/ ANSWER O.10 (1.50)

He may be relieved by tho Opnrating Gupervisor (0.5) and one other GRO (0.5) or by Unit Supt. (.25) or Gtation Supt.(.25)

REFERENCE ADM 1-1-60 section A.16 5.3/ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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ANSWER 0.11 (1.50) re o ( ,,n d v %vwJ enve , , , n n. l . g y Radiolo01 cal release and meteorological data. (0.75) To provent ovacuating personnel through the plumo (0.7b).

REFERENCE CY-OP-LO-ADMIN-LO3000, pg. 22 of 39, PWG A1.16 3.1/ ANSWER O.12 (2.00)

Spec. 3.12.A (2) cannot be mot (0.5) because other HPSI pump is inoperable (0.5).

Spec 3.6 A-I la and 4 apply (which roquire action of 3.6.A.I.4) (0.5)

Decauco both are incpurable at the same time and are on separato safety buson then plant shutdown required CAF (0,5).

REFERENCE CY Toch Spuco 006 SG .5/ ANSWER 0.13 (3.00)

a. No [O.53. The valvo is required for containment integrity por TS 3-11. Muut take action of T.S. 3.11.G.a-d [1.03 b. No [0.51. T.S. 3.11.D.(3) disallown +dk/L addition without containment integrity. Until action of above a-c can be mot, this will appl [1.01 REFERENCE CY Toch Spocs 3.11 013/000 #0 3.6/4.4