Text

Exam Rept 50-267/OL-86-02 During Wk of 860915.Exam Results: Four of Six Candidates Passed Senior Operator Licensing Exams & 10 of 11 Operators Passed Requalification Program Audit Exams
	ML20210G177
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/24/1986
From:	Cooley R, Pellet J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	;
Shared Package
ML20210G097	List: ML20210G092; ML20210G177;
References
	50-267-OL-86-02, 50-267-OL-86-2, NUDOCS 8702110233
	Download: ML20210G177 (44)
	v • d • e

I , a REQUALIFICATION PROGRAM AUDIT AND OPERATOR LICENSE EXAMINATION REPORT Examination Report 50-267/01-86-02 Docket: 50-267 License No: DPR-34 License: Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 Operator License and Requalification Program Audit examinations at Fort St.

Vrain (FSV).

Examination Conducted: September 15, 1986 Chief Examiner: &u 10h3h Date Signed John L. Pellet, Examiner Approved By: i m b.b -

Fialph f.' Cooley, Sectio $hief

[ hub Date Sitned Summary:

NRC administered six Senior Reactor Operator license examinations (one Limited to Fuel Handling) at FSV during the week of September 15, 1986. Four of the six license candidates successfully completed their examinations and have been issued the appropriate license.

NRC administered 11 Requalification Pro Operator and 9 Senior Reactor Operator) gram at FSV during Auditof examinations the week September 15 (2 Reactor 1986. Ten of the eleven licensed individuals evaluated passed the NRC-

administered requalification program audit examinations. Combining these results with those from the May examinations, 74 percent of the licensed individuals evaluated passed the NRC-administered requalification program audit l

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kDb 0 PDR 67

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examinations during 1986. The excellent results of the oral examinations, ongoing facility efforts to improve the training program and facility management response to the May results, as well as results on recent license examinations, indicate substantial improvement in the operator training program. Therefore, the Fort St. Vrain Requalification Program is now evaluated as satisfactory.

As a result, the restrictions imposed on license renewal in our report OL 86-01, transmitted to you in an August 4, 1986 letter, are no longer required.

Operator license cenewals may now be granted based on facility certification of completion of the requalification program. Based on these results, NRC plans to reevaluate the Fort St. Vrain Requalification Program during the 1987 requalification cycle to assure that the ability of operators to safely operate and shutdown the facility is being satisfactorily maintained.

3 REPORT DETAILS

1. PERSONS EXAMINED License Examinations: TYPE: SRO-LFH SRO TOTAL PASS: 1-100% 3-60% 4-67%

FAIL: 0-0% 2-40% 2-33%

Requalification Examinations: TYPE: R0 SRO TOTAL PASS: 2-100% 8-89% 10-91%

FAIL: 0-0% 1-11% 1-9%

2. EXAMINERS J. Pellet,NRC(ChiefExaminer)

J. Whittemore, NRC R. Eaton, NRC

3. EXAMINATION REPORT Individual performance results are not included in this report because these reports are place in the NRC's Public Document Room.

a. EXAMINATION REVIEW COMMENT RESOLUTION In general, editorial comments or changes made during the examination, review, or subsequent grading reviews are not addressed by this resolution section. This section reflects resolution of j substantivecommentsmadeinPublicServiceCompanyofColorado(PSC)

, letter P-86564, dated September 24, 1986. The modifications discussed below are included in the master examination key which is included elsewhere in this report (see 3.e), as are all other changes

! mentioned above but not discussed herein. Note that coments from the letter referenced are paraphrased below for brevity. The full text of the comments is available in the referenced letter, which is attached (see3.f). Question numbers prefaced by "R" are from the

, requalification examinations, while questions prefaced by "L" are l from the license examinations. Coments are only resolved once.

Coments like "Same as . . . ." are not addressed or noted herein.

R1.01.b/d Accept no change if depleted is defined as complete.

! Resp.: ACCEPT. Key modified.

R1.06.b Accept enhances flow stability per HTGR Tech. course.

Resp.: ACCEPT. Key modified.

! R1.07. Question may be answered in wide variety of ways, depending I on assumptions about power history.

Resp.: ACCEPT. Key modified to account for power history.

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4 R1.09. Accept decreasing steam temperature decreases efficiency.

Resp.: ACCEPT. Key modified.

R2.02.b Accept the following additional impurities: CH4, Kr. Ar, Xe, CO.

Resp.: ACCEPT. Key modified.

R2.03. Accept system 46, loops 1 & 2 for a, 005 loop for b.

Resp.: ACCEPT. Key modified.

R2.05. Accept 152 second scram time per TS.

Resp.: ACCEPT. Key modified.

I R2.08. Physical location of equipment is appropriate for Equipment Operators not Reactor Operators.

Resp.: REJECT. Location of important equipment is considered appropriate material for licensed personnel.

R2.09.a Accept loss of the three room complex with LOFC per TS.

Resp.: ACCEPT. Key modified.

R2.09.b Accept also Fire Prot. (45) Service Water (42), He Purification (23), Liquid Nitrogen (25), Purification Cooling (47) Water,CircWaterMakeup(41),RSS(12),Rx Plant Ventilation (73), and Plant Lighting.

Resp.: ACCEPT. Key modified.

R3.01.b Accept range of answers, not exact setpoints.

Resp.: ACCEPT. Key modified.

R3.02. Accept two-loop trouble scram from 4 circulator trip.

Resp.: REJECT. Question asks for condition, not PPS signal.

R3.05. Accept concept, not verbatim.

Resp.: ACCEPT. Key modified.

R3.06.a This question should be thrown out because it is based on training material that was found to be in error too late to inform NRC.

Resp.: ACCEPT. Question removed and other parts re-weighted.

P.3. 07. Question does not ask for locations so should not be required.

Resp.: ACCEPT. Key modified. -

R3.08.b Accept also to mitigate large dryer leak.

Resp.: ACCEPT. Key modified.

R4.05.b Accept also to equalize core outlet temperatures or minimize region mismatch.

Resp.: ACCEPT. Key modified.

5 R4.09. Accept concept not verbatim.

Resp.: ACCEPT. Key modified.

R5.03. Accept reducing barrel irradiation for b and backscattering for c.

Resp.: REJECT. Key modified for backscatter. Irradiation rejected because no reference given.

R5.04. Accept concept rather than verbatim.

Resp.: ACCEPT. Key modified.

R5.05. Accept concept rather than verbatim.

Resp.: ACCEPT. Key modified.

R5.06. Accept NTC magnitude will be smaller or have less effect.

Resp.: ACCEPT. Key modified.

R5.08. Also accept higher power production, low helium flow, high heat flux, and unequal helium flow or power production as factors in hot spot evaluation.

Resp.: ACCEPT. Key modified.

, R5.09. Accept closed discharge valve allows pump pressure to increase rapidly to prevent pump damage.

Resp.: REJECT. Suggested wording does not say why this is necessary.

R7.01.b Question is invalid since it asks for a single reporting location when several are possible.

Resp.: REJECT. Alternate locations added to key. I required.

R7.01.c Accept concept rather than verbatim.

Resp.: ACCEPT. Key modified.

R7.04 Accept unexplained reactivity change operator deems unsafe.

Resp.: ACCEPT, Key modified.

i R7.08. Reference not provided in key.

! Resp.: ACCEPT. Key modified.

R8.02. Accept alternate answers provided.

Resp.: REJECT. Answers requested are same as original key.

R8.05. LSO is not required to report to the control room but HP -

tech is per APM G-5, p. 6. step 4.4.1.

l Resp.: REJECT. LSO is required per reference in key. HP tech accepted per reference provided, and key modified.

t R8.06.b Accept that individual issued key must retain until returned to Shift Supervisor.

Resp.: ACCEPT. Key modified.

6 R8.09. Accept also, assure personnel safety, notify operators equipment is not available, & show steps necessary to restore to operation.

Resp.: ACCEPT. Key modified.

L5.11.a Accept due to bi-metallic weld between EES & superheater.

Resp.: ACCEPT. Key modified.

L8.11. Question is invalid since rote memorization of Technical Specifications (TS) is required to answer.

Resp.: REJECT. Question may be answered adequately based on general knowledge of TS requirements for subject area.

SRO-LFH exam category values do not match those given in PSC TPAM.

Resp.: NRC examinations are not governed by PSC TPAM. Exam meets all NRC requirements for category weighting.

LN.03. Answer is incorrect. Total well capacity is equivalent of 70 full length elements with maximum of 56 fuel elements.

Resp.: ACCEPT. Key modified.

LN.04. Question does not apply do SRO-LFH duties.

Resp.: ACCEPT. Question dropped.

LN.09. HSF floor drains discharge through system 61 to draining station, recycle, or liquid waste sump. Any of above are acceptable answers.

Resp.: ACCEPT. Key modified.

LO.08. Checklist steps are not memorized, and order is not sensitive.

Resp.: ACCEPT. For future reference.

LP.06. Parenthetical answer on b is wrong.

Resp.: ACCEPT. Key modified.

LP.09. Accept also systems 63, 23, 11, 13, 14, 21, and 22.

Resp.: ACCEPT. Key modified.

LP.10. Additional material provided is necessary for fully correct answer.

Resp.: REJECT. Key gives concept for full credit. Additional material cited is not required and not added to key.

7

b. SEPTEMBER 18, 1986 EXIT MEETING SUM 1ARY At the conclusion of the site visit, the NRC examiners met with representatives of plant staff to discuss the site visit. The following personnel were present:

NRC PSC J. Pellet C Borst J. Whittemore S. Willford P. Michaud R. Rivera Mr. Pellet started the discussion by noting that the examiners as a group had encountered a positive, helpful attitude in everyone concerned. The following general topics were discussed.

(1) Due to the recent change in NUREG-1021, the Examiner Standards, preliminary results are no longer provided in the exit meeting.

l (2) NRC will attempt to return formal, final results within 30 days.

(3) The following areas of weakness were observed in more than one candidate and are presented for the use of the facility. Note that an area of weakness does not imply unacceptable performance but is simply an area where knowledge or skill is less completely developed than in others.

2 (a) Classifying events using the RERP appeared confusing and often resulted in erroneous classification, f

(b) Determining operability of nuclear instruments when readings did not agree was difficult and could not be referenced to plant procedures.

(c) Understanding of routing systems for procedure changes, and other mechanisms to assure currency with governing

documentation was weak.

(d) Understanding and calculation of shutdown margin was poor.

(e) Several individuals had difficulty retrieving surveillance procedures required for TS testing.

(f) Knowledge of CRD power supplies and control room documentation on them was poor. -

(g) There appeared to be some confusion about the shear number of different tags in use on the control boards.

1 l (h) Items a-c above are similar to weaknesses documented in the previous examination report. No significant improvement was observed in these areas.

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c. GENERIC COMMENTS The generic comments below were generated during grading of the i written examinations, and regional review of the oral examinations.

They are provided for the benefit of the facility and no response or corrective actions are required.

(1) The generic deficiencies identified in the May report were substantially corrected with respect to the written

, examinations.

(2) Behavior of control rods during abnormal circumstances was poorly understood, based on oral examinations as previously stated,

d. REQUALIFICATION PROGRAM EVALUATION NRCadministeredelevenRequalificationProgramAuditexaminations(2 ReactorOperatorand9SeniorReactorOperator)atFSVduringthe week of September 15, 1986. Ten of the eleven licensed individuals evaluat<td passed the NRC-administered requalification program audit examina tions. To arrive at an overall program evaluation for 1986, the results of the Piy site visit are combined with this visit.

Seventy-fourpercent(fourteenofnineteen)ofthetotalnumberof licensed individuals evaluated in both visits passed the NRC-administered requalification program audit examinations during 1986.

These results, plus ongoing facility efforts to improve the training program and facility management response to the May results, as well as results of recent license examinations, indicate substantial

improvement in the operator training program. Therefore, the Fort St. Vrain Requalification Program is now evaluated as satisfactory.

As a result, operator license renewals may now be granted based on

facility certification of completion of the requalification program.

Based on these results. NRC plans to reevaluate the Fort St. Vrain Requalification Program during the 1987 requalification cycle to assure that the ability of operators to safely operate and shutdown the facility is being satisfactorily maintained,

e. EXAMINATION MASTER COPY Master copies (questions and answers) for the SR0 and SRO-LFH license examinations and R0 and SR0 requalification examinations follow the requalification program evaluation on the next page. -

f. FACILITY EXAMINATION COMMENTS The facility examination review comments in the form of PSC letter P-86564 follow the examination master copics.

9 OVERALL REQUALIFICATION PROGRAM EVALUATION Facility: Fort St. Vrain Examiners: J. Pellet, R. Cooley, J. Whittemore, R. Eaton Dates of Evaluation: May 20-22, 1986 and September 16-18, 1986 Areas Evaluated: XX Written XX Oral Simulator Written Examination Evaluation of NRC Examination Results (if given): Marginal (14/19P)

Oral Examination i

1. Overall Evaluation: Satisfactory (19/20P)

2. Number Observed: None Number Conducted: 20 Overall Program Evaluation Satisfactory: XX Marginal: Unsatisfactory:

REASON FOR EVALUATION

- - Marginal written results (74% pass) are mitigated by: ***

1. 95% pass ratio on oral requalification examinations.

2. Facility management response to the May results.

3. Results of recent license examinations.

4. Ongoing facility efforts to improve the training program.

- - Overall program is evaluated as SATISFACTORY. ***

Submitted: Forwarded: Approved:

~^ ~

i 5 k- '

Examiner Se'cti )n Chief Branch Chief

U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY: _EIi_SIi_YB816.__________

REACTOR TYPE: _HIQB-Qa_________________

DATE ADMINISTERED:_QhlQQllh________________

EXAMINER: _EELLEli_Ji______________

CANDIDATE: _________________________

INSIBUCIl00S_IQ_GaNQ1081El Road the attached instruction page carefully. This examination replaces the current cycle facility administered requalification examination.

Rotraining requirements for failure of this examination are the same as for failure of a requalification examination prepared and administered by your training staff. Points for each question are indicated in pcrentheses after the question. The passing grade requires at least 70%

in each category and a final grade of at least 80%. Examination papers util be picked up four (4) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY

__VaLUE_ _IDI8L ___SCQBE___ _VaLUE__ ______________CaIEQQBl_____________

.25200__ _25200 ___________ ________ 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW

_25tDD__ _25100 ___________ ________ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS

_25100__ _2510D ___________ ________ 3. INSTRUMENTS AND CONTROLS

_2520D__ _25100 ___________ ________ 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 1Q010Q__ ___________ Totals Final Grade All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During 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.

2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

3. Use black ink or dark pencil 901Y to facilitate legible reproductions.

4. Print your name in the blank provided on the cover sheet of the oxamination.

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

6. Use only the paper provided for answers.

7. Print your name in the upper r ight-hand corner of the first page of REGb oection of the answer sheet.

8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a Dgg page, write 201E SD SDS Eidt 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 ibteg lines between each answer.

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

12. Use abbreviations only if they are commonly used in facility 111gtgigtg.

13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

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

15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER DLANK.

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

17. You must sign the statement on the cover sheet that indicates that the cork 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 shall:

a. Assemble your examination as follows:

(1) Exam questions on top.

(2) Exam sids - f igures, tables, etc.

(3) Answer pages including figures which are part of the answer.

b. Turn in your copy of the examination and all pages used to answer the examination questions.

c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.

d. Leave the examination area, as defined by the examiner. If after !

leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.

f.

Iz__EBINCIELE1_QE_ NUCLE 88_EQWEB_EL8MI_QEEB8IIQNi PAGE 2 IHEBBQQ1NedIGli_UE81_IB8NSEEB_8ND_ELUIQ_ELQW QUESTION 1.01 (4.00)

c. How does removing spent fuel increase core reactivity? (1.0)

b. How does removing spent fuel decrease core reactivity? (1.0)

c. How and why does removal of reflectors affect core reactivity? (1.0)

d. How does removing a depleted neutron source affect reactivity? (1.0)

QUESTION 1.02 (1.50)

How does the outermost radial fuel zone differ from the others? (1.5)

QUESTION 1.03 (3.00)

What are the two (2) maj o r reasons that orifices are used in the Fort St.

Vrain core? (3.0)

QUESTION 1.04 (3.00)

What are three (3) types of core changes that can cause a power-to-flow icbalance in a refueling region with the core at balanced overall pcwer-to-flow? (3.0)

QUESTION 1.05 (3.00)

c. Why should a centrif ugal pump be started with the discharge valve closed? (1.5)

b. What is operating a pump with too much flow and no discharge pressure called AND why should this condition be avoided? (1.5)

(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

r It__EBINGIELE1_QE_NUGLE88_EQWEB_EL8NI_DEEB8IIQNi PAGE 3 IHEBdQQ1NedIGSt_BE8I_IB8HSEEB_8ND_ELUIQ_ELQW i

l QUESTION 1.06 (3.00)

c. Why are' steam temperatures in the steam generators at Fort St. Vrain limited to 1000 deg's F7 (1.0)

< b. Why is the second superheater designed f or co-current flow, which is less efficient than counterflow as used in the EES and reheater? (1.0)

c. What is the " pinch point" of a steam generator? (1.0)

QUESTION 1.07 (3.00)

Answer the following questions comparing plant conditions after a slow (~10 hours) versus a fast (~2 hours) power reduction from 70% to 50% reactor pcwer with the same equilibrium initial conditions. Assume N0 operator cction and rod control in MANUAL following the power decrease. (3.0)

c. Which power reduction (SLOW or FAST) will require the most rod insertion during the power reduction? (1.0)

b. Which power reduction (SLOW or FAST) will have the highest final, steady state power? (1.0) l

c. Given the above conditions, how long after the fast power change will steady state conditions be achieved (power stops changing)? (1.0) l QUESTION 1.08 (2.00)

! How will an INCREASE in primary coolant flow rate affect reactivity and roactor power? Assumu flow is increased uniformly across the core. (2.0)

QUESTION 1.09 (2.50) l

o. What are two negative consequences if reheat were not used in the

! secondary system? (1.0)

b. What are two reasons that overall plant efficiency decreases at low power? (1.5) l l (***** END OF CATEGORY 01 *****)

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p 2t__fLANI_DE119N_INCLUDIN9_18EEII_eND_EMEBGENC1_111IEd1 PA'GE 4 QUESTION 2.01 (2.00)

What are two (2) functions of the Helium Circulator Compressor Inlet? (2.0)

QUESTION 2.02 (4.00)

c. What are four (4) users of pur if ied helium f rom the Helium Purification System (System 23)? Normal or Fuel Handling reisted are acceptable for full credit. (2.5)

b. What are four-impurities removed by System 237 (1.5)

QUESTION 2.03 (3.00)

.o . Name the three cooling supplies to the fuel storage wells (FSW). (1.8)

b. Nam'a the two backup cooling supplies to the FSW. (1.2)

. QUESTION 2.04 (3.50)

For the helium circulator water turbine drive system:

c. How is turbine speed controlled? (1.0)

b. How is flashing in the turbine cavity prevented? (1.0)

c. What is the normal power (water) source for the turbine? (0.5)

d. What are two (2) backup power (water) sources for the turbine? (1.0)

QUESTION 2.05 (3.00)

o. During a scram, what controle rod insertion speed? (1.5)

b. What is the maximum allowed scram insertion time? (0.5)

c. What keeps reactor pressure changes during normal operation from breaking the reserve shutdown system rupture disks? (1.0)

(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)

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2x__EL8HI_DESION_ INCLUDING _S8EEIl_6ND_EdEBGENGX_SISIEd3 PAGE 5 QUESTION 2.06 (3.00)

o. When is the redistribution mode of the PCRV Cooling Water system (System 46) used? (0.5)

b. How is redistribution of system 46 accomplished? (1.25)

c. What is accomplished by redistribution of system 467 (1.25)

QUESTION 2.07 (2.00)

c. How are fuel storage wells divided into vaults for ventilation? (1.0)

b. Compare vault flow during normal and emergency conditions. (1.0)

QUESTION 2.08 (2.00)

MATCHING. Match each of the electrical distribution system components with the appropriate location. Each location may be used more than once or not at all, as appropriate. (2.0)

COMPONENT LOCATION

___ a. 1A Battery Charger 1. Building 10 480V Room Northeast

___ b. 1A Battery Bank 2. 480V Room Northeast

___ c. 10 Osttery Charger 3. 480V Room Northwest

___ d. 10 Dettery Bank 4. Auxiliary Electric Room

___ e. 1C Dattery Charger 5. 480V Room South Wall

___ f. 1C Battery Bank 6. Building 10 480V Room Mezzanine

___ g. 10 Battery Charger 7. 480V Room Mezzanine

___ h. 125V DC Dus 1A QUESTION 2.09 (2.50)

c. For what combination of events is the Alternate Cooling Method (ACM) system 48 REQUIRE 07 (1.5)

b. What are two other system operations necessary to mitigate the consequences of an sccident requiring ACM7 (1.0)

(***** END OF CATEGORY 02 *****)

, 3 Ji__INSIBudENIS_880_CQNIBQLS PAGE 6 QUESTION '3.01 (3.00)

c. What automatic actions occur if the steam / water dump system is actuated on high primary pressure? (2.0)

b. What is the setpoint for the high pressure trip in the steam / water dump system? (1.0)

QUESTION 3.02 (2.00)

What two (2) conditions will cause the PPS to initiate a turbine trip icmediately after a reactor scram? (2.0)

QUESTION 3.03 (1.50)

TRUE or FALSE?

o. Startup range nuclear instrumentation uses the cambelling technique to eliminate gamma pulses f rom the count rate circuit. (0.75)

b. The wide range log power channels use U-235 lined fission chambers located in detector wells 3, 4, and 5. (0.75)

QUESTION 3.04 (3.00)

What are two (2) ways that the Reserve Shutdown System may be actuated from OUTSIDE the Control Room? (3.0)

(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

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-22__INSIBuuENIS_6ND_GQNIB0LS PAGE 7 s .

m 4 <

3 QUES, TION 3.05 (3.50)

A sume the plant is in a normal configuration at 50% reactor power and tufbine load and turbine load is increased to 60%. A simplif ied schematic of the steady state controls is, attached. Continue your answers until ateady state conditions <are achieved. (3.5)

c. How is turbine load'normally increased? (0.5)

b. How and WHY does feedwater flow change? (1.0)

. /,

c. How and WHY does reactor power change? (1.0)

d. How and WHY does helium flow change? (0.5)

o. How is any error in main or reheat steam temperature adj usted once at the new load condition? ,

(0.5)

QUESTION 3.06 (3.00)

TRUE or FALSE?

c. Primary coolant moisture hi alarm (MM-9306/7) is -30 deg's F or -45 deg's F. (Question deleted per facility comments -

ref. error.)(0.0)

b. A loop shutdown and steam water dump due to high moisture is inhibited

, by a circulator seal malfunction trip. (1.0)

c. A two loop trouble scram REQUIRES two high level moisture monitor trips. (1.0)

d. At an average core exit temperature of less than 725 deg's F, the basis for Technical Specification is oxidation of graphite components. (1.0)

QUESTION 3.07 (3.00)

What protective instruments are used to monitor the main turbine steam cystem radiation due to a reheater leak? (3.0)

(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

p.

' 2i__INSIBudENI1_eND_CONIBOLS PAGE 8 QUESTION 3.08 (3.00)

c. . What automatic realignment takes piece in the Instrument and Service

. Air-systems;as Instrument Air pressure decreases below 70 psig? (1.5)

'b. What potential problem is this realignment attempting to mitigate?C1.5)

QUESTION 3.09 (3.00)

,- For each of the rooms below, describe in detail how the'Halon fire protection system can be actuated.. For manual initiation, where Epplicable, explain any controls and their location. For . automatic cctuation, as applicable, explain the type of detector (s) and logic. (3.0)

a. . ' Auxiliary Electric Room. ~C1.5)

b. Control room. (1.5) 1 I

4 4

i e

(***** END OF CATEGORY 03 *****)

7:

~32_lEBQCEDUBE2_=_NDBd8Li_6BNQBdakt_EUEEGENGI_6ND; PAGE 9 88DIQLQSIC8L_CQNIBQL QUESTION 4.01 (2.50)

Explain the difference in a channel check and's channel test as defined in Technical Specifications. (2.5)

QUESTION 4.02 (3.00)

What are each person's three (3) individual responsibilities per the rcdiation protection plan as listed in SUSMAP-47 (3.0)

. QUESTION 4.03 (2.50)

.What are the five (5) immediate actions required following a reactor scram?

Specific steps to accomplish each action are NOT required. (2.5)

. QUESTION 4.04 (3.00)

Dofine, per Technical ~ Specifications:

a. Shutdown for refueling. (1.5) j .b. Irradiated fuel. (1.5) l QUESTION 4.05 (3.50)

c. What should the f ollowing switch positions be prior to withdrawing l cortrol rods for startup? (2.0) i l ~1. Reactor Mode Selector Switch.

l 2. Manual Scram Switch.

i 3. Rod Group Saguence Bypass Swicch.

I 4. Interlock Sequence Switch.

l

[ b. When increasing power from 20%, WHY should the operator perform the l

following balancing actions? (1.5) l 1. Adjust helium flow orifice valves.

2. Adj ust steam generator feedwater flow.

l

(***** CATEGORY 04 CONTINUE 0 ON NEXT PAGE *****)

w-

-dz__EBQGEQUBES_=_NQBd8Lt_8BNQBd8Lt_EMEBGENCY_8NQ PAGE 10 88019LQHIG8L_GQNIBQL QUESTION 4.06 (1.50)

What parameter (s) are used to verify that the main steam turbine is chutdown after a turbine trip? (1.5)

QUESTION 4.07 (3.00)

How does the symptom-action Matrix format of the emergency procedures identify which member of the operating crew should perform required actions cnd/or make' required decisions? (3.0)

QUESTION 4.08 (3.00)

What three (3) concepts are used concurrently to accomplish the 9oal of controlling exposure ALARA? (3.0)

QUESTION 4.09 (3.00)

Under what circumstances may personnel deviate from an approved station procedure without prior approval? (3.0)

(***** END OF CATEGORY 04 *****)

rt************* m ***************3

7

~lt__EBINGIELE1_9E_ NUCLE 88_E9 WEB _EL8HI_QEEB8IIQNt PAGE 11 IHEBdQDINedIGit_BE8I_IB8NSEEB_8ND_ELVIQ_ELQW ANSWERS -- FT..ST.-VRAIN -86/09/16-PELLET, J.

ANSWER 1.01 (4.00)

m. Increases reactivity by removing fpp (including'Xe 8.Sm) (1.0)

b. Decreases reactivity by removing f iss ionable mater ials.' (1.0)

c. Removal decreases react. by allowing increased neutron leakage. (1.0)

d. Decreases. reactivity. (1.0)

For-parts b & d, ACCEPT NONE if spent and depleted defined as complete.

REFERENCE FSV LESSON NO. 39.00, p. 3 ANSWER 1.02 (1.50)

Less uranium (0.75) & more thorium (0.75). (1.5)

REFERENCE FH 033.00, III.H.1., p. 11 ANSWER 1.03 (3.00)

1. Different refueling regions may differ in age and burnup by as much as 6 years (0.75). The newer regions produce more heat and so need more flow to maintain a constant outlet temperature (0.75).

2., Any region with a higher than average power density has a higher than average flow r es is t ance (0.75). Without orificing, the higher powered regions would receive' lower flow (0.75).

REFERENCE R0 120.00.01.02.1

r 12__EBINGIELES_9E_NUGLE88_EQWEB_EL8NI_DEEB6IIONt PAGE 12 IBEBdQDXUedIGSi_BE6I_IB6NSEEB_6ND_ELUID_ELQW ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 1.04 (3.00)

1. Core / fuel burnup.

2. Control rod movement.

3. Orifice position change. (3 answers 8 1.0 ea.)

REFERENCE R0 120.00.01.07.1 ,

ANSWER 1.05 (3.00)

c. A closed discharge valve minimizes the starting power required by reducing the initial mass flow. (CONCEPT) (1.5)

b. Runout (0.75) - overcurrent trip may result (0.75) (CONCEPT) (1.5)

REFERENCE R0 118.00.01.04 ANSWER 1.06 (3.00)

o. Metal technology at the time of design. (1.0)

b. Minimize metal temp. 8 hot end of tube OR enhance flow stability. (1.0)

c. Minimum temp. difference of working fluids (in deg's F). (1.0)

REFERENCE R0 129.00.01.05/04/06 I

It__EBINCIELES_DE_NUGLE88_EQWEB_EL8NI_DEEB8IIQNi- PAGE 13 IHEBdQDIN8dIGSt_HE8I_IB8NSEEB_8ND_ELUID_ELQW ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 1.07 '(3.00)

a. fast-Class neg. react. from Xe). (1.0)

b. slow (less insertion on downpower). (1.0)

c. Xe equilibrium in < 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months . (1.0)

For parts a & b, ACCEPT alternate answers if Xe changes are correct for power change assumptions stated.

REFERENCE LR 008.00.01.04 ANSWER 1.08 (2.00)

Increasing flow rate will increase reactor heat removal (0.5). This will decrease temperature (0.5), which inserts positive reactivity (0.5) and increases reactor power (0.5). (2.0)

REFERENCE LR 009.00.01.06 LR 009.00, p. 13, 14 ANSWER 1.09 (2.50)

a. 1. Efficiency would decrease.

2. Steam quality at last turbine stages would decrease (causing more blade erosion). (2 answers 8 0.5 ea.)

b. 1. House loads would be a larger fraction, decreasing overall eff.

. 2. Steam throttling reduces cycle efficiency. (2/3 answers e 0.75 ea.)

3. Steam temperature decrease reduces cycle eff.

REFERENCE LR 015.00.01.05/07 LR 015.00, p. 8, 10 l

l l

I

r 2r__EL'8HI_ DESIGN _INCLUDIN9_SeEEII_eND_EMEB9ENCY_SXSIEd3 PAGE 14 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 2.01 (2.00)

1. Direct helium flow (axially) into compressor (blading). (1.0)

2. Monitor flow in the primary circuit. (1.0)

REFERENCE FH 034.00, p. 7 ANSWER 2.02 (4.00)

c. 1. Buffer Helium makeup.

2. Purge helium for HTFA.

3. Purge helium for CRD's.

4. Pressurizing helium for interspace PCRV penetrations.

5. PCRV safety relief valves. (Any 4/5-G 0.625 es.)

b. 1. F iss io n-p r o duc e d isotopes.

2. tritiem.

3. dust.

4. condensed-water.

5. water vapor.

6. carbon compounds.

7. hydrogen. (Any 4/8 8 0.375 ea.)

8. noble gases.

REFERENCE FH 034.00, p .- 4-9 ANSWER 2.03 (3.00) l.

l o. 1. Helium purge.

2. RPCCW.

3. RB HVAC.

4. PCRV Aux Cooling loops 1 & 2. (Any 3/4)

b. 1. Fire Water.

2. Booster fan and dampers. (5 answers e 0.6 es.)

3. 00S PCRV Aux Cooling loop. (Any 2/3)

REFERENCE

, FH 041.00.01.05.1 i

i i

r- -

22__ELeNI_ DESIGN _ INCLUDING _S8EEIX_eND_ENEBGENGX_SYSIENS .PAGE 15 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 2.04 (3.50) -

e. Throttle-water flow. (1.0) b.- Nitrogen overpressure above Psat. (1.0)

c. emergency feedwater (boiler feed pumps). -(0.5)

d. 1. emergency condensate (condensate pumps). (0.5)

2. firewater. (0.5)

REFERENCE EO 074.00.01.01/02 EO 074.00, p. 4, 5, 11, 12, 13 ANSWER 2.05 .C3.00)

c. . dynamic' motor braking (capacitors on winch motor). ~ (1.5)

.b. 150.+/- 5 seconds.. -(0.5)

c. Pressure equalizing orifice in the CR0 purge / hopper vent. (1.0)

REFERENCE EO 062.00.01.05 EO 062.00, p. 13, 18 ANSWER 2.06 (3.00)

n. During extended loss of forced-cooling. (0.5) l b. Operator realigns remote manual valves to adj ust liner cooling. (1.25)

c. Basic goal is to increase cooling to upper side walls & top head.(1.25)

{

REFERENCE EO 084.00.01.05/06 EO 084.00, p. 12 1

J 1

, , - , e.-- - ~ , - . , - ~ - - - , - - - - - - - .,--n-- , - - - . , - , - - , , . . - . , , . - .-------,.,,,----,.n, --,,----,------;,.,--,-, ,

7 2t__ELeNI_ DESIGN _ INCLUDING _SeEEIX_eND_EbEBGENCY_SYSIEUS PAGE 16 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 2.07' (2.00)

c. The nine wells are divided into 3 vaults of 3 wells each. (1.0)

6. Normal flow is 1500 cfm and. emergency flow is 9000 cfm. (1.0)

REFERENCE EO 055.00.01.04 EO 055.00, p. 10 ANSWER 2.08 (2.00)

a. 7,.b. 3, c. 7, d. 2, e. 6, f. 1, g. 5, b. 4 (8 answers e 0.25 ea.)

REFERENCE EO 086.00, p. 19 ANSWER :2.09 (2.50)

c. Loss of normal AND emergency power OR 3-room complex (0.75) along with LOFC C0.75). (1.5)

b. 1. Primary coolant system depressurization.

2. Reserve shutdown system operation.

'3. Fire Pro. (S 45).

4. Svce water (S 42).

5. He Purge (S 23).

6. Liquid Nitrogen (S 25).

7. Purge Cooling Water (S 47).

8. Circulating Water (S 41).

9. HVAC (S 73). (Any 2 8 0.5 ea.)

REFERENCE EO 087.00.01.05 EO 087.00, p. 13

E 2t__INSIBudENIS_eND_QQNIBQLS PAGE 17 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 3.01 (3.00) c.- 1. Pre-selected loop is dumped. (1.0)

2. Other loop is depress. to just above primary press.(~850#). (1.0)

Lb. 775# 8 100% or 53 +/- 5 # > program. (1.0)

REFERENCE RO-127.00 ANSWER 3.02 (2.00) ,

1.- Reactor pressure low. (1.0)

2. All 4 circulators tripped. (1.0)

REFERENCE R0 005.01.01.04 ANSWER 3.03 (1.50)

.s. False, b. True REFERENCE-RO 003.01, p. 4, 8 ANSWER 3.04 (3.00)

1. Local relay pushbuttons on level 10. (1.5)

2. Local ACM through hook up of flexible hoses. (1.5)

REFERENCE FH 030.00, p. 11

- - - - - - - - .,:- , - - - - , -,--*-.e. - , - - - -

(-

22__INSIEUMENI2_eND_QQNIBQL1 PAGE- 18 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 3.05 (3.50)

c. Load is increased by opening the main turbine admission valves. (0.5)

b. This causes a decrease in throttle press. (0.5). The steam press.

controller causes the-setpoint for a.fw flow to be raised (0.5). (1.0)

c. The change in 1st-stage press. provides a f eed-f orward signal to the flux controller to anticipate the required increase in reactor power setpoint (0.5). The dev. between reactor power and setpoint causes the neutron flux control loop to withdraw the reg. rod (0.5). (1.0)

d. A f eed-f orward flow signal to the helium circ. speed control entici-pates the superheat outlet error and causes incr. He flow (0.5). (0.5)

e. At the new load condition, any error in main or reheat steam temperature is removed by the feedback control loops which trim circulator speed and reactor power (0.5). (0.5)

For all parts, ACCEPT CONCEPT.

REFERENCE LR 112 ANSWER 3.06 (3.00)

c. , b. T, c. F, d. F(Part a deleted per fac. comm. - ref. err.) (3 e 1.0)

REFERENCE R0 132 ANSWER 3.07 (3.00)

1. Shine monitors (look e hot reheat piping for gamma). (1.0) 2.- Process monitors (look e hot reheat piping for beta a gamma). (1.0)

3. SJAE monitor (looks e effluent to stack). (1.0)

REFERENCE EO 037.00.01.04, p. 12

7

'22__INSIBU5ENI2_8HD_GQNIBQL1 PAGE 19 ANSWERS -- FT.-ST. VRAIN -86/09/16-PELLET, J.

ANSWER 3.08 (3.00).

s. The service air backup supply (0.6) is realigned from upstream of the instrument air dryer to downstream (0.9). (1.5)

b. This attempts to mitigate dryer problems (leak, blocked, etc.) (1.5)

REFERENCE AT 001.00.01.04 AT 001.00, p. 21 ANSWER 3.09 (3.00)-

c. 1. Automatic: 1 ionization detector in each of 2 zones. (0.75)

2. Manual: Main / reserve selection / actuation outside AER door. (0.75)

b. Manual: Main / reserve selection / actuation on east wall of CR. (1.5)

REFERENCE E0.047.00.01.04 EO 047.00, p. 12, 13 I

L

SA__EBQQEDVBES_=_NQBdeLt_8HNQBd8Lt_EMEBQENQ1_eND PAGE 20 B8DIDLQQIQ8L_QQNIBQL LANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 4.01 (2.50)

A check is a qualitative (observed) verification of operability (1.25) while a test is a. functional test operability (1.25). (2.5)

REFERENCE AT 029.00.01.02 ANSWER 4.02 (3.00) *-

1. Follow procedures and practices, to maintain exposure ALARA. (1.0)

2. Identify to-supervisor, rad. work procedures & practices that need to be upgraded. (1.0)

3. Request & attend rad. prot. training. sufficient to discharge assigned responsibilities. (CONCEPT for all 3) (1.0)

REFERENCE SUSMAP-4 ANSWER 4.03 (2.50)

1. Insert a manual scram. (0.5)

2. Place ISS on Low Power Position. (0.5)

3. Ensure transfer of house power. (0.5) ,

4. Ensure turbine trip. (0.5)

5. Ensure / establish stable core cooling conditions. (0,5)

REFERENCE EP APP 8-1, p. 7-9 i

ANSWER 4.04 (3.00)

I

a. Mode switch is LOCKED in the ref ueling position (0.75) simult, with either hot or cold shutdown conditions (0.75). (1.5)

b. Has a rad. level (0.75) greater than 100 mr/hr e1 foot (0.75). (1.5)

r

$A__EBQQEQUBES_:_NQBd8kz_8BNQBd8Lt_EMEBQENC1_8NQ PAGE 21 B8DIQLQQIQ8L_QQNIBQL ANSWERS -- FT. ST. VRAIN _86/09/16-PELLET, J.

REFERENCE Technical Specifications, Section it ANSWER' 4.05 (3.50)

a. 1. Run

2. Normal

3. Normal

4. Start (4 answers e 0.5)

b. 1. To equalize reheat steam outlet temperatures. (0.75)

OR To equalize core outlet / region temperature mismatches.

2. To equalize main steam header outlet temperatures. (0.75)

REFERENCE OPOP III, p. 6, 20, 21 ANSWER- 4.06 (1.50)

Turbine speed (A SV/CV position). (1.5)

REFERENCE EP APP F-1, p. 2 ANSWER 4.07 (3.00)

The EP's use a box format keyed like below. Accept picture or description.

West Creactor) SR East (turbine) l l xx xx xx I Box is marked so that:

, West (reactor) actions are xx'ed at left. (Operator 0.5, format 0.5)

East (turbine) actions are xx'ed at right. (as above 1.0)

SS actions are xx'ed at center. (as above 1.0)

REFERENCE i EP INTRO, p. 2

F--

at__EB99EDUBES_=_N0BdeLt_8HN9BdeLt_EMEBGENGl_eNQ PAGE 22 E8DIDLQ91CeL_GDNIBQL-ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 4.08 (3.00)

1. Time (of exposure should be minimized). (3 answers e 1.0 ea.)

2. Distance (from source should be maximized).

3. Shielding (from the source should be used whenever possible), l REFERENCE FH 060.00, p. 5 ANSWER 4.09 (3.00)

Porsonnel may deviate without prior approval in emergency situations (1.0) when essential to mitigate conditions (1.0) that will adversely affect porconnel or public safety (1.0). (CONCEPT) (3.0)

REFERENCE LR 017.00.01.09 G-2, Rev. 19, Section 4.4.2.a, p. 9 3-

F 7 TEST CROSS REFERENCE PAGE 1 QUESTION VALUE REFERENCE

01. 01 ~ 4.00 JJP0001481 01.02 1.50 JJP0001482 01.03 3.00 JJP0001483 01.04 3.00 ~JJP0001484 01.05 3.00 JJP0001485 01.06 3.00 JJP0001486 01.07 3.00 JJP0001487 01.08 2.00 JJP0001515 01.09 2.50 JJP0001516 25.00 02.01 2.00 JJP0001488 02.02 4.00 .JJP0001489 02.03 3.00 JJP0001490 02.04 3.50 JJP0001491 02.05 3.00 JJP0002492 02.06 3.00 JJP0001493 02.07 2.00 'JJP0001494 02.08 2.00 JJP0001495 02.09 2.50 JJP0001496 25.00 03.01 3.00 JJP0001497 03.02 2.00 JJP0001498 03.03 1.50 JJP0001499 03.04 3.00 JJP0001500 03.05 3.50 JJP0001501 03.06 3.00 JJP0001502 03.07 3.00 JJP0001503 03.08 3.00- JJP0001504 03.09 3.00 JJP0001505 25.00 04.01 2.50 JJP0001506 04.02 3.00 JJP0001507 04.03 2.50 JJP0001508 04.04 3.00 JJP0001509 04.05 3.50 JJP0001510 04.06 1.50 JJP0001511 04.07 3.00 JJP0001512 04.08 3.00 JJP0001513 04.09 3.00 JJP0001514 25.00 100.00

l l

1

-U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _EIz_SIz_YB81N___________

REACTOR TYPE: _NIQB:Q8_________________

DATE ADMINISTERED: _QhlD2Lik________________

EXAMINER: _EELLEIz_lz______________

CANDIDATE: _________________________

INSIBUCIl0NS_IQ_GaNQlD61El Uso 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 loast 80%. Examination papers will be picked up s ix (6) hours after tho examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY

__VaLUE_ _IQIaL ___SCQBE___ _V8LUE__ ______________CaIEQQBI_____________

_252DD__ _25200 ___________ ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS

_252DD__ _25100 ___________ ________ 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUNENTATION

_2520D__ _25200 ___________ ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL

_2520D__ _25tDD ___________ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 10010D__ ___________

Totals Final Grade All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

(

7 NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the f o llow'ing rules apply:

1. Cheating on the examination means an automatic cenial of your application and could result in more severe penalties.

2. 'Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

3. Use black ink or dark pencil 201y 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 (if necessary).

6. Use only the paper provided for answers.

"7 . Print your name in the upper right-hand corner of the first page of 33gh section of the answer sheet.

8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a Dgw page, write 2DlY 2D 201 Eldt 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 ihtgg lines between each answer.

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

12. Use abbreviations only if they are commonly used in facility 111grgiurg.

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.

f 14. Show all calculations, methods, or assumptions used to obtain an answer

! to mathematical problems whether indicated in the question or not.

15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE j . QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.

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

the REAmiDet only.

1

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

1 i

1

t c

18. When you complete your examination, you shall:.

a. Assemble your examination as'follows:

(1) Exam questions on top.

(2) Exam aids - figures, tables, etc.

(3) Answer pages including figures which are part of-the answer.

b. Turn in your copy of the examination and all pages used to answer the examination questions.

c. Turn in all. scrap paper and the balance of the paper that you did

.not use for answering.the questions.

d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still, in progress, your license may be denied or revoked.

4 t

1

. .,,.__.-__-.-______,__m. _ _ . . - _ . - _ _

. _ _ _ _ _ _ _ _ . _ _ , , . _ . . _ _ . _ _ ~ , _ _ e_. ..___..

5t__INEQBl_QE_NVQLE88_EQWEB_EL8NI_QEEB8IIQNt_ELVIDSt_8NQ PAGE 2 IHEBdQQYNedICS QUESTION- 5.01 (3.00)

a. How does removing spent fuel increase core reactivity? (0.75)

b. How does removing spent fuel decrease core reactivity? (0.75)

c. How does removal of reflectors affect core reactivity? (0.75)

d. How does removing a depleted neutron source affect reactivity? (0.75)

QUESTION 5.02 (2.00)

e. Which reflector elements are replaced and when are they removed from the core? (1.0)

b. Which reflectors are permanent? (1.0) t QUESTION 5.03 (2.00)

a. How does the outermost radial fuel zone differ from the others? (1.0)

b. What effect is this difference attempting to control? (0.5)

c. What causes this effect in the outermost f uel region? (0.5)

QUESTION 5.04 (1.00)

Rank each of the materials below based on the mass of each at the beginning of cycle 3 (where 1st is the most and 3rd is the least). (1.0)

e. ' Uranium 235

b. Uranium 233

c. Thorium 232

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

-5t__IHEQBl_QE_NUQLE88_EQWEB_EL8HI_QEEB8IIQNt_ELMIDat_8ND PAGE- 3-IHEBdQQ1N8dIQ1 1 QUESTION 5.05 (2.00)

Explain why 15% of the primary coolant enters the core as " bypass flow" but only 6% leaves the core as " bypass flow." (2.0)

QUESTION 5.06 (2.00)

What are the two (2) major reasons that orifices are used in the Fort St.

Vrain core? (2.0)

QUESTION 5.07 (2.00)

What two (2) core operating characteristics change between 800 and EOC due to the buildup.of U-233 for use as fuel? (2.0)

QUESTION 5.08 (2.00)

What are three-(3) types of core changes that can cause a power-to-flow imbalance in a refueling region with the core at balanced overall power-to-flow? (2.0)

-QUESTION. 5.09 (1.00)

What are two-(2) factors accounted for in hot spot evaluation? (1.0)

QUESTION 5.10 (2.00)

c. . Why should a centrifugal pump be started with the discharge valve closed? (1.0)

b. -What is operating a pump with too much flow and no discharge pressure called AND why should this condition be avoided? (1.0)

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

15t__IHEQBl_DE_ NUCLE 8B_EQWEB_EL8HI_QEEB8I1QNt_ELU191t_8NQ PAGE- 4 IHEBdQDIN8dICS QUESTION 5.11 (3.00)

-c. Why are steam temperatures in the steam generators at Fort St. Vrain limited to 1000 deg's F? (1.0)

b. Why is the second superheater' designed for co-current flow, which is less efficient than counterflow as used in.the EES and reheater? (1.0)

Ec. What is the " pinch point" of a steam generator? (1.0)

QUESTION 5.12 (3.00)

Explain the difference in FINAL reactor power (with N0 operator action and I rod control in MANUAL) following a slow (~10 hours) power reduction versus e fast (~2 hours) power reduction from the same equilibrium initial conditions. (3.0) 4 s

i i

(***** END OF CATEGORY 05 *****)

62__EL8HI_SYSIEMS_DESIGNt_CQNIBQLt_6ND_INSIEUMENI6IIQN PAGE 5 QUESTION. 6.01 (2.00)

What are~two (2) functions of the Helium Circulator Compressor Inlet? (2.0)

QUESTION 6.02 (3.00)

o. What are four (4) users of purified helium from.the Helium Purification System (System 23)? Normal or Fuel Handling related are acceptable for full credit. (2.0)

b. What are four impurities removed by System 23? (1.0)

QUESTION 6.03 (2.00)

What are two (2) ways that the Reserve Shutdown System may be actuated from OUTSIDE the Control Room? (2.0)

QUESTION 6.04 (2.50)

e. Name the three cooling supplies to the fuel storage wells (FSW). (1.5)

b. Name the two backup cooling supplies to the FSW. (1.0)

QUESTION 6.05 (2.50)

c. What is the collection point for the fuel deck floor drains? (0.5)

b. What is the collection point for the Hot Service Facility f.loor drains? (0.5)

c. Why are there different collection points for the fuel deck and Hot Service Facility floor drains? (1.5)

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

ht__EL6NI_SISIEMS_DESIQNt_GQNIBQLt_eND_INSIBudENI8IIQN PAGE 6 QUESTION 6.06 (3.50)

Assume the plant is in a normal configuration at 50% reactor power and turbine load and turbine load is increased to 60%. A simplified schematic of the steady state controls is attached. Continue your answers until oteady state conditions are achieved. (3.5)

c. How is turbine load normally increased? (0.5)

b. How and WHY does feedwater flow change? (1.0)

c. How and WHY does reactor power change? (1.0)

d. How and WHY does helium flow change? (0.5)

o. How is any error in main or reheat steam temperature adj usted once at the new load condition? (0.5)

QUESTION 6.07 (2.00)

True or false?

o. Primary coolant moisture hi alarm (MM-9306/7) is -30 deg's F or -45 deg's F. (0.0)

(Question deleted per facility comments - reference error.)

b. A loop shutdown and steam water dump due to high moisture is inhibited by a circulator seal malfunction trip. (0.666)

c. A two loop trouble scram REQUIRES two high level moisture monitor trips. (0.666)

d. At an average core exit temperature of less than 725 deg's F, the basis for Technical Specification is oxidation of graphite components.(0.666)

QUESTION 6.08 (1.00) .

When recovering from a loop shutdown, why is a soak period required on the chutdown loop when main steam temperature is less than 400 deg's F on the operating loop? (1.0)

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

p-

.ht__EL8HI_SISIENS_DESIGNt_G9 NIB 9Lt_8NQ_INSIBudENI6IIQN PAGE 7 QUESTION 6.09 (2.00)

c. What automatic actions occur if the steam / water dump system is actuated on high primary pressure? (1.5)

b. What is the setpoint for the high pressure trip in the steam / water dump system? (0.5)

QUESTION 6.10 (1.50)

What two (2) conditions will cause the PPS to initiate a turbine trip inmediately after a reactor scram? (1.5)

QUESTION 6.11 (2.00)

Given the following I-05 pump indications, which of the hydraulic oil pumps are running and how was each running pump started? (2.0)

c. Pump 1A - Red indicator,

b. Pump 18 - Red and white indicators.

c. Pump 1C - Green indicator.

QUESTION 6.12 (1.00)

TRUE or FALSE 7

c. Startup range nuclear instrumentation uses the cambelling technique to eliminate gamma pulses from the count rate circuit. (0.5)

b. The wide range log power channels use U-235 lined fission chambers located in detector wells 3, 4, and 5. (0.5) l l (***** END OF CATEGORY 06 *****)

L

Zt__EB9CEQUBES_:_NDBdekt_6BN9Bdelt_EMEBGENCY_6ND PAGE 8 88019LQ91CeL_CQUIBQL QUESTION 7.01 (3.50)

c. Under what conditions should non-operations personnel working in the Reactor Building report to their personnel accountability station? (1.0)

b. When evacuating the Reactor Building, where is their personnel accountability station? (0.5)

c. What are two conditions that would require that they report to the Health Physics Access Control Area when leaving the Reactor Building on the way to their personnel accountability station? (1.0)

d. What should the first person to report to a personnel accountability station do? (1.0)

QUESTION 7.02 (3.00)

What are each person's three (3) individual responsibilities per the radiation protection plan as listed in SUSMAP-4? (3.0)

QUESTION 7.03 (3.00)

Classify each of the events below as either emergency or non-emergency based only on the information given. Consider each event independently.

c. The reactor has been automatically scrammed due to main steam pressure low. (0.5)

b. lA helium circulator has tripped on speed high (I-05A 1-1). (0.5)

c. PCRV Safety Valve Activity High Alarm activates (I-05A 2-2) AND reactor pressure is decreasing rapidly. (0.5)

d. Loop I moisture high alarm AND the reactor has been manually shutdown because the Technical Specification ~ limit on maximum moisture during power operations have been exceeded. (0.5)

o. Criticality alarm is reported to be activated in the Fuel Storage Building. (0.5)

f. The reactor has been automatically scrammed on high moisture AND one coolant loop has tripped and dumped. (0,5)

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

g

-Zt__EBQGEDUBES_=_NQBd8Lt_8BNQBd8Lt_EMEBQENCY_8NQ PAGE 9 88DIQLQQIG8L_CQNIBQL QUESTION 7.04 (2.00)

What are two (2) plant conditions that require inserting the Reserve Shutdown System? (2.0)

QUESTION 7.05 (2.50)

What are the five (5) immediate actions required following a reactor scram?

Specific steps to accomplish each action are NOT required. (2.5)

QUESTION 7.06 (2.00)

Oofine, per Technical Specifications:

c. Shutdown for refueling. (1.0)

b. Irradiated fuel. (1.0)

QUESTION 7.07 (2.00)

c. What should the following switch positions be prior to withdrawing control rods for startup? (1.0)

1. . Reactor Mode Selector Switch.

2. Manual Scram Switch.

3. Rod Group Sequence Bypass Switch.

4. Interlock Sequence Switch.

b. When increasing power from 20%, WHY should the operator perform the following balancing actions? (1.0) 1.- Adj ust helium flow orifice valves.

2. Adj ust steam generator feedwater flow.

QUESTION 7.08 (2.00)

List two (2) actions which should be performed by the Outy Shift Supervisor immediately upon assuming the role of Emergency Coordinator. (2.0)

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

t-Zt__EBQQEQUBES_ _NQBd8Lt_8BNDBdakt_EMEBGENQ1_8NQ. PAGE 10

~88DIQLQQ1 gel _QuNIBQL QUESTION 7.09 (1.00)

When should an immediate manus 1 reactor scram be initiated due to an cbnormal reactor power change? (1.0)

' ' . .?

9

( QUESTION '7.10 ,

(1.00)

What indication (s) are used to verify that the main steam turbine Ls

,- Ehutdown after a turbine trip? (1.0) d' QUESTION 7.11 (3.00)

,. f . .

'Kaw does the symptom-action Matrix format of the emergency procedures

' identify which member-of the operating crew should perform required' actions cnd/or make required decisions? (3.0)

.- "s

,P y

y -s

+ , 4r A'

9

,c

.i

~

s i

s v.

1

(***** END OF CATEGORY 07 *****)

/ .- - -, - . . - - . - -. .-

= '

. +

~.

+

N 4

B i__8DMINISIB 8II!/ g _ PB QQ g Q QBgit_QQNQIIIQNgt_860_LIN11811QN1 PAGE 11 QUESTION 8.01 (2.00) i

" the four reasons-that a Radiation Work Permit (RWP) may be

,f j] :]Y What . are cancelled? ,

-(2.0).

.* .> 3

' .t s ,/ -

1 'I.

J QUESTION 8.02 (2.00)

?>

What requirements must a mechanical maintenance worker meet to gain access to.a Health Physics controlled area? (2.0)

{ s QUESTION 8.03 (2.00)

What'three-(3) concepts are used concurrently to accomplish the goal of centrolling exposure ALARA? '

(2.0)

'\ ,

+

l QUESTION 8.04 '

(2.00) j

'When do Technical Specifications require that two'(2) Licensed operators be in the-Control Room? (2.0)

{

I (QUESTION 8.05 (3.00)

R;,- -.

,0n back shift, for what personnel (by job title) are assigned the Control Room-as their personnel accountability station? (3.0)

< - -0 QUESTION 8.06 (2.50)

't

a. What 2; circumstances must exis t to issue the vital access door key?(1.0) l > r b.:What-2 requirements must be met by the individual to whom the key is issued? (1.5) t

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

l --

F -

-Bi__8051N11IBeIIVE_EBQGEQUBE11_G9NDIIIONit_eND_LIMII6IIQN1 PAGE 12-

' QUESTION ' 8. 07- (2.00) -

Under what circumstances may personnel deviate from an' approved station procedure without. prior approval? .(2.0)

-QUESTION 8.08 (2.00) p What five (5) calls must be-made by the emergency-coordinator for en crergency classified as an " Unusual Event?" (2.0)

QUESTION 8.09 (2.00)

a. Why is.a " clearance".(non-operational status) assigned to equipment? (0. 5) :

b. Whonis issued the card or tag indicating a clearance? (0.5) c..-What are two (2) purposes of operation deviation system status tags? (1.0)

QUESTION -8.10 (2.00) a.- Technica1' Specifications require that the Technical Advisor be in the Control Room within what time period after an emergency call? .(0.5):

b. For how long may the Fire Brigade be at less then. minimum staff to accomodate unexpected absence of members, per Tech Specs? (0.5) c.- What are two functions of the Technica1' Advisor, per Tech Specs? (1.0)

. QUESTION 8.11 (2.00)

What are four of the five conditions required per Technical Specifications LCO 4.2.7 to pressurize the PCRV above 100 psia? (2.0)

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

T

'Bi__eQUINISIBeIIVE_EBQGEDVBESt_CQNDIIIQNS&_8HQ_LIMII8IIQN1 PAGE 13 4 QUESTION- 8.12- . (1.50)

What are .the three (3) conditions for control rod operability.for all control rod pairs not fully inserted per interim Tech Spec LCO 3.1.17 (1.5) l l

l I

I t

h

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

t g************* m ***************3

m I

-5A__IHEDBY_DE_ NUCLE 88_EQWEB_EL8MI_DEEB8II98t_EL91Q$t_8NQ PAGE 14 IHEBdQQ1NedICS ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 5.01 (3.00)

o. Increases reactivity by removing fpp_(including Xe & Sm) (0.75)

b. Decreases reactivity by removing f iss ionable mater ials. (0.75)

c. ~ Removal decreases react, by allowing increased neutron leakage. (0.75)

d. Decreases reactivity. '(0.75)

Accept NONE for b &d if spent & depleted defined as complete.

REFERENCE FSV LESSON NO. 39.00, p. 3 ANSWER 5.02 (2.00)

e. All reflectors adj acent to fuel (0.5) are replaced at the refueling of that region (0.5) (1.0)

b. All other reflectors (that aren't adj acent to f uel) are permanent.(1.0)

REFERENCE FH 033.00, III.A., p. 6 ANSWER 5.03 (2.00)

e. Less uranium (0.5) & more thorium (0.5). (1.0).

b. Power peaking (at the core-reflector interface). (0.5)

c. In-leaking / backscatter neutrons (from the reflector). (0.5)

REFERENCE FH 033.00, III.H.1., p. 11

Si__IHEQBl_DE_ NUCLE 8B_E9 WEB _EL8HI_DEEB8IIQNz_ELUIQSt_8NQ PAGE 15 IHEBdQQ1N8dICS ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 5.04 (1.00) c, a, b Cor Th-232,_U-233, U-235)(0.5 for each swap req'd to correct order)

REFERENCE FH 033.00, III.I., p.15 ANSWER 5.05 (2.00)

Since bypass flow does not pass through an orifice-(0.5), it is at a higher pressure than the coolant in the channels (0.5). Because of this higher pressure, some of the bypass flow will enter the channels in the fuel column (0.5) via the end gaps (0.5). (CONCEPT)

REFERENCE R0 120.00.01.01.2 ANSWER 5.06 (2.00)

1. Different refueling regions may differ in age and burnup by as much as 6 years (0.5). The newer regions produce more heat and so need more flow to maintain a constant outlet temperature (0.5). (CONCEPT)

2. Any region with a higher than average power density has a higher than average flow resistance (0.5). Without orificing, the higher powered regions would receive lower flow (0.5). (CONCEPT)

REFERENCE R0 120.00.01.02.1 ANSWER 5.07 (2.00)

o. Temperature coefficient (0.5) becomes less negative (0.5). (1.0)

b. Beta factor (0.5) decreases (0.5). (1.0)

REFERENCE FSV Reactor Phys ics LP on Core Changes

f Sz__IHE981_DE_NUCLEeB_EDWEB_EL6HI_DEEBoIJQNt_ELUIQSt_6HQ PAGE 16 18EB5001N65101 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 5.08. (2.00) l '. Core / fuel burnup.

2. Control rod movement.

2. Orif ice position change. (CONCEPT) (3 answers e 0.667 ea.)

REFERENCE R0 120.00.01.07.1

-ANSWER 5.09 (1.00)

1. Fuel element dimensional variance.

2. Thermal-conductivity uncertainty.

3. Coefficientaof thermal expansion uncertainty.

4. Ir radiation-induced dimensional change - data.

5. Heat-transfer correlation uncertainty.

6. Radial power peaking factor uncertainty.

7. Axial power peaking factor.

8. Fuel loading tolerance.

9. Exit coolant temperature measurement tolerance. (Any 2 e 0.5 es.

10. High power / flux at. hot spot.

11. Unequal / low helium flow.

REFERENCE R0 120.00.01.06.1 ANSWER 5.10 (2.00)

c. A closed discharge valve minimizes the starting power required by reducing the initial mass flow. (CONCEPT) (1.0)

b. Runout (0.5) - overcurrent trip may result (0.5) (CONCEPT) (1.0)

REFERENCE RO 118.00.01.07

l 152__IHEDBI_9E_NUGLE88_EQWEB_ELeNI_QEEB8IIONi_ELUIDSt_8NQ PAGE 17 IHEBdQDINedIGS

. ANSWERS -- FT. ST. VRAIN

-86/09/16-PELLET, J. ,

ANSWER 5.11 .(3.00) l 4

m. ' Metal technology at the time of des ig n (bi-metallic weld). (1.0) y

-l

b. Min. metal temp. G hot end of tube (OR enhance flow stability). (1.0)

c. Minimum temp. difference of working fluids (in deg's F). (1.0)

REFERENCE R0 129.00.01.05/04/06 ANSWER' 5.12 (3.00)

In each case, neg.' reactivity will be inserted, due to Xe buildup (1.0).

In the case of the fast downpower, there is less time over which XE can contribute and more rods must be inserted to achieve the new power (1.0).

Therefore, the final power (after XE decay) will be LOWER for the fast downpower (1.0). (3.0)

' Accept-alternate answers if assumptions about power history are stated and Xe behavior is correct for stated assumptions.-

REFERENCE LR 008.00.01.07 i

l I

i l

\ . - - - - . - , ... . . - - . - , - . , _ . - .- . _ , . - , . . _ , ,_, . _ - _ _ - - _ - - , _ - -

4 t_ _ Ek e NI_ SISI E NS _ D E SIG N t _ G Q NIB 9 L t _ eN Q _IN SIB M M E NI611Q N PAGE 18 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 6.01 (2.00)

1. Direct helium flow (axially) into~ compressor (blading). (1.0)

2. Monitor flow in the primary circuit. (1.0)

REFERENCE FH 034.00, p. 7 ANSWER 6.02 (3.00)

G. 1. Buffer Helium makeup.

2. Purge helium for HTFA.

3. Purge helium for CRO's.

4. Pressurizing helium for. interspace PCRV penetrations.

5. PCRV safety relief valves. (Any 4/5 9 0.5 es.)

b. 1. F iss ion-p roduced isotopes.

2. tritium.

3. dust.

4. condensed water.

5. water vapor.

6. carbon compounds

7. hydrogen. (Any 4/8 9 0.25 ea.)

8. noble gases.

REFERENCE FH 034.00, p. 4-9 ANSWER 6.03 (2.00)

1. Local relay pushbuttons on level 10. (1.0)

2. Local ACM through hook up of flexible hoses. (1.0)

REFERENCE FH 030.00, p. 11

. - , . .- - . -.__--_.-,v-,. - - ~ . - , - . , - . - . . , . . . , . . - - . _ . , -- . _ , - - - - - . ,

e-3 6t__ELeNI_GYSIENS_QESIGNt_GQNIBQLt_AND_INSIByNENIeI1QN PAGE 19 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 6.04 (2.50)

c. 1. ' Helium purge.

2. RPCCW.

3. RB HVAC.

4. PCRV Aux Cooling Loops 1 & 2. (Any 3/4)

b. 1. Fire Water.

2. Booster fan and dampers. (5 answers e 0.

REFERENCE FH 041.00.01.05.1 ANSWER 6.05 (2.50)

a. Reactor building sump. (0.5)

b. Liquid waste sump (via sys 61 to draining sta., recycle, or sump).(0.5)

c. RB sump is not normally contaminated and can be discharged from the plant separately (.75). The effluent from the HSF is normally contaminated C.75). (1.5)

REFERENCE FH 044.00.01.03.1

)

6t__EL8HI 3IIIEUS DE31GNt_CQNIB9Lt_6ND_INSIBudENI6IIQN PAGE 20 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 6.06 (3.50)

c. Load is increased by opening the main turbine admission valves. (0.5)

b. This causes a decrease in throttle press. (0.5). The steam press.

controller causes the setpoint for mfw flow to be raised (0.5). (1.0)

c. -The change in 1st-stage press. provides a f eed-f orward signal to the flux controller to anticipate the required increase in reactor power setpoint (0.5). The dev. between reactor power and setpoint causes the neutron flux control loop to withdraw the reg. rod (0.5). (1.0)

d. A feed-forward flow signal to the helium circ. speed control antici-pates the superheat outlet error and causes incr. He flow (0.5). (0.5)

o. At the new load condition, any error in main or reheat steam temperature is removed by the feedback control loops which trim circulator speed and reactor power (0.5). (0.5)

For ALL, accept-CONCEPT.

REFERENCE LR 112 ANSWER 6.07 (2.00)

n. , b. T, c. F, d. F (3 answers e 0.666 ea.)

(part a deleted per facility comment due to error in reference material.)

REFERENCE R0 132 ANSWER 6.08 (1.00)

To assure the gradual cooldown (0.3) of the heat transfer surfaces in the steam generator (0.4) under stagnant conditions (0.3). (CONCEPT) (1.0)

REFERENCE OPOP VIII

w ,

161__EL8HI_1IIIEUS_DESIGNt_CONIB9Lt_8NQ_INSIBUBENI8IIQN PAGE 21

. ANSWERS ---FT. ST. .VRAIN. -86/09/16-PELLET, J.

ANSWER: 6.09 (2.00)

L a. - 1. Pre-selected loop is dumped. (0.75) 2 .- Other loop is depress. to just above primary press (~850#). (0.75) b' . !775# e 100% or 53 +/-5# > program. (0.5)

-1 REFERENCE R0 127.00 ANSWER 6.10- (1.50) 1.- Reactor pressure low. (0.75)

2. All 4 circulators tripped. (0.75)

REFERENCE R0 005.01.01.04 ANSWER 6.11 (2.00)

1. Pump 1A is running (0.5) due to a manual start (0.5)

2. Pump 18 is running-(0.5) due to an automatic start (0.5).

REFERENCE R0 091 ANSWER 6.12 (1.00)

e. False, b. True REFERENCE R0 003.01, p. 4, 8

r o

Zi__EBQGEDVBEA_:_NQBd8Lt_8BNQBd8Lt_EMEBGENGl_8NQ PAGE 22 B8DIQLQQIceL_GQNIBQL ANSWERS -- FT. ST. VRAIN. -86/09/16-PELLET, J.

ANSWER 7'.01 (3.50)

a. Fire-(0.5) or Radiological (0.5) alarm. (1.0)

b. Lunchroom OR TSC OR Visitors Center. (0.5)

c. 1. Contamination (> 2x background) found at exit monitor.

2. Exit via crash bars or emergency exits (due to imminent danger).

3. Exit monitors show > 500 cpm background. (Any 2/3 0 0.5)

d. Verify ratemeter operating properly (0.5) & not alarming (0.5). (1.0)

OR " habitability.

REFERENCE G-5, p. 3, 4, 7, 11 ANSWER 7.02 (3.00)

1. Follow procedures and practices, to maintain exposure ALARA. (1.0)

2. Identify to supervisor, rad. work procedures & practices that need to be upgraded. (1.0)

3. Request & attend rad. prot. training suf f icient to discharge assigned responsibilities. (CONCEPT for all 3) (1.0)

REFERENCE SUSMAP-4

, ANSWER 7.03 (3.00)

a. Non

b. Non

c. Emer

d. Non

o. Emer

f. Non (6 answers e 0.5 ea.)

REFERENCE Emergency Procedures

m -

i l

2

'Zz__EBQGEDUBES_ _NQBd6Lt_eHNQBd8Lt_EMEBGENCY_8NQ PAGE 23 i BADIQLQQIG8L_GQNIBQL ANSWERS -- FT. ST. VRAIN. -86/09/16-PELLET, J.

ANSWER 7.'04 (2.00')

1. Loss of forced coolant flow C0.5) for required time (0.5).

2. Can't insert enough rods for req'd SOM (0.5) e hot S/D (0.5).

3. Reactor can't be maintained S/0 (0.5) after a scram or S/D C0.5).

4. Unexplained react. change unsafe to the operator. (Any 2/4 e 1.0 es.)

REFERENCE S0P 12-05, Rev. 8, p. 4 ANSWER 7.05 (2.50)

1. Insert a manual scram. (0.5)

2. Place ISS on Low Power Position. (0.5)

3. Ensure transfer of house power. (0.5)

4. Ensure turbine trip. (0.5)

5. Ensure / establish stable core cooling conditions. -(0.5)

REFERENCE EP APP B-1, p. 7-9 ANSWER 7.06 (2.00)

a. Mode switch is LOCKED in the refueling position (0.5) simultaneous with either hot or cold shutdown conditions (0.5). (1.0)

b. Has a radiation level (0.5) greater than 100 mr/hr G 1 foot (0.5).(1.0)

REFERENCE Tochnical Specifications, Section 2 l

l l

5,

- - - - . . _ _ . . , _ _ , - _ , _ - - _ , - - ~ . _ _ _ , . , - _ - . - . , , . , _ , _ _ . , _ . . _ , - _ _ , _ - _ . . _ _ , , , . , , _ , ,._.._,y , , . _ _ _ . _ , , _ . ,

e -

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Z2__EBQCEDUBES_=_NQBd8Lt_8BNDBd8Lt_EMEBQENCY_8NQ PAGE 24-88DIQLQQIG8L_CQUIBQL ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 7.07 (2.00)

e. 1. Run

2. Normal

3. Normal

4. Start (4 answers G .25)

b. 1. To equalize reheat steam outlet temperatures. (0.5)

OR to " region / core outlet temperatures.

2. To equalize main steam header outlet temperatures. (0.5)

REFERENCE OPOP III, p. 6, 20, 21 ANSWER 7.08 (2.00)

1. Initiate actions to mitigate the event.

2. Assign (preliminary) rad. assess. responsibilities.

3. Initiate protective actions for station personnel.

4. Classify the event.

5. Make management contacts.

6. Complete appropriate (RERP) checklist (s). (Any 2/6 8 1.0 ea.)

REFERENCE PT 004.01.01.02 ANSWER 7.09 (1.00)

When the reactivity change is beyond the compensating ability of the regulating rod. (1.0)

REFERENCE EP APP E, p. 52 i

ANSWER 7.10 (1.00)

Speed is decreasing (& SV/CV position), (1.0)

Z2__EBQGEDUBES_=_NQBd8Li_8BNQBU6Lt_EMEBGENCY_8NQ PAGE 25 88DIQLQ91G8L_GDNIBQL ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

REFERENCE EP APP F-1, p. 2 ANSWER 7.11 (3.00)

The EP's use-a box format keyed like below. Accept picture or description.

West-(reactor) SS East (turbine) l xx xx xx 1 Box is marked so that:

West (reactor) actions are xx'ed at left. (Operator 0.5, format 0.5)

East (turbine) actions are xx'ed at right. (as above 1.0)

SS actions are xx'ed at center. (as above 1.0)

REFERENCE IEP INTRO, p. 2

r>

.At__eQUINISIBeIIVE_EBQQEQUBESt_QQNDIIIQN2t_eND_LIMIIeIIQN2 PAGE 26

' ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 8.01 (2.00) 1.- Time expired.

2. Job completed.

3. Job cancelled.

4. Conditions change. (4 answers e 0.5 ea.)

REFERENCE LR_029.00, p. 6, 7 ANSWER 8.02 (2.00)

1. HP Tech accompanied, (0.5)

OR (0.25)

2. RWP, (0.5)

OR

3. under HP direction (operators _only) (NOT REQUIRED FOR FULL CREDIT)

AND (0.25)

4. HP authorization. (0.5)

REFERENCE FH 058.00.01.07.1 ANSWER 8.03 (2.00)

1. Time (of exposure should be minimized). (3 answers e 0.667 es.)

2. Distance (from source should be maximized).

3. Shielding (from the source should be used whenever possible).

REFERENCE FH 060.00, p. 5 ANSWER 8.04 (2.00)

1. Startup.

2. Shutdown.

3. Recovery (from reactor trip). (3 answers G 0.667 ea.)

A2__6DMINISIB6IIVE_EBCCEDVBESt GQNDIIIDNSt_8NQ_LIMIIeIIDNS PAGE 27 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

REFERENCE TS 7.1.1.2.b, p. 7.1-3 ANSWER 8.05 (3.00)

1. Shift Supervisor.

2. Reactor Operators.

3. Auxiliary Tenders.

4. Equipment Operators.

5. Duty Technical Advisor.

6. Lead Security Officer. (6 answers e 0.5 es.)

7. Off-duty Shift Supervisor - not required for full credit. ,

8. HP Tech - not required for full credit.

REFERENCE G-6, Attachment G-5A, Rev. 18, p. 11, 12 ANSWER 8.06 (2.50)

c. 1. Card reader failure (s). (0.5)

AND

2. Plant emergency exists. (0.5)

b. 1. Individual to whom the key is issued must have authorized access to all areas unlocked by the key.

2. Individual possessing the key may not exit the protected area until the key is returned to the SS.

3. Individual iss REFERENCE SO 011.00.01.06 ANSWER 8.07 (2.00)

P,ersonnel may deviate without prior approval in emergency situations (0.7) when essential to mitigate conditions (0.6) that will adversely affect personnel or public safety (0.7). (CONCEPT) (2.0)

REFERENCE LR 017.00.01.09 G-2, Rev. 19, Section 4.4.2.a, p. 9

r A2__6DMINISIB8IIVE_EB9CEDUBESt_CQNDIIIQNSt_880_LIMII6IIQNS PAGE 28 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 0.08~ (2.00)

1. Duty TA.

2. Management contact.

3. NRC.

4. State CEOC).

5. Governor's office. (5 answers e 0.4 ea.)

REFERENCE LR 019 ANSWER 8.09 (2.00)

a. requiring maintenance or modification. (0.5)

OR assure safety, notify ops inop, or recover instructions.

b. the individual intending to direct performance of the work. (0.5)

c. 1. identify & document devient operational situations.

2. authorize an operation status change.

3. control operations in respect to servicing and maintenance work on equipment.

4. restore deviant situations to normal through orderly procedures.

(For part C, any 2/4 REFERENCE LR 018.00.01.06/7/8 P-2, Rev. 13, Section 3.1, 3.2, p. 1, 2 ANSWER 8.10 (2.00)

c. I hour. (0.5) 4 b. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . (0.5)

c. 1. Maximize safety by providing tech ass ist . during events.

2. Review AOP/EP's.

3. Assist. ops in applying TS.

4. Evaluate other fac. LER's. (Any 2 0 0.5 es.)

e REFERENCE LR 023.00 TS, p. 7.1-2, 3, 4

St__8DUINISIBeIIVE_EBQQEQVBEft_QQNQIIIQN2t_6NQ_LIMIIeIIQN2 PAGE 29 ANSWERS -_ FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 8.11 (2.00)

1. PCRV SV operable (& <5# between disk & SV, w/ block vivs open).

2. All pri. & sec. penet. closures & hold-down plates operable.

3. Pri-sec interspaces > pri press w/ helium. (Any 4/5 e 0.5 ea. CONCEPT)

4. 3 except SG penet. closures can be < pri. but > cold reheat press.

5. 1 set of SV & rupture disks for SG & circ. closures operable.

REFERENCE LR 031.00.01.05, TS 4.2.7, p. 4.2-5 ANSWER 8.12 (1.50)

1. Scram time </= 152 seconds. (0,5)

2. Rod drive motor temperature </= 250 deg's F. (0.5)

3. He purge flow to es. CRD penet. when reactor press. > 100 psia. (0.5)

REFERENCE LR 032.00.01.01 Interim TS 3.1.1, p. 3/4 1-1 l

i w= r%. , - - --n.- .,----c-r-..-cr---m,--m--.w- - . - - . . , - , . . ..---..,.-,+,,-,---e--..v,-----s-

1 TEST CROSS REFERENCE PAGE. 1

' QUESTION: VALUE REFERENCE

~ 0 5 a 01 ' R3.00 JJP0001517-05.02 2.00 'JJP0001518 J05;03 2.00 JJP0001519 H05.04 ~1.00 JJP0001520 05'.05 2.00 JJP0001521 05.061 2.00 JJP0001522 05.07 2.00 .JJP0001523 05.08 2.00 JJP0001524 05.09- 1.00 JJP0001525 05.10 2.00 JJP0001526 05.11 3.00 JJP0001527 05.12 3.00 -JJP0001528 25.00

-06.01 2.00 JJP0001529 06.02- 3.00 JJP0001530 06.03 2.00 .JJP0001531 06.04 2.50 JJP0001532 06.05 2.50 JJP0001533 06.06 3.50 JJP0001534

'06.07 2.00 JJP0001535 06.08 1.00 JJP0001536 06.09 2.00 JJP0001537

+

06.10 1.50 _JJP0001538 06.11 2.00 JJP0001539 06.12 1.00 JJP0001540 25.00 07.01 3.50 JJP0001541 07.02 3.00 JJP0001542 07.03 3.00 JJP0001543 07.04 2.00 JJP0001544

07.05 2.50 JJP0001545 07.06 2.00 JJP0001546 07.07 2.00 JJP0001547 07.08 2.00 JJP0001548 07.09 1.00 JJP0001549 07.10 1.00 JJP0001550

-07.11 3.00 JJP0001551 25.00 08.01 2.00 JJP0001552 08.02 2.00 JJP0001553 08.03 2.00 JJP0001554 08.04 2.00 JJP0001555 08.05 3.00 JJP0001556 08.06 2.50 JJP0001557

C' 3 i

TEST CROSS REFERENCE PAGE 2 QUESTION VALUE REFERENCE 08.07 2.00 'JJP0001558

! 08.08 2.00 JJP0001559 08.09 2.00 JJP0001560 08.10 2.00 JJP0001561

-08.11- 2.00 JJP0001562 j 08.12 1.50 JJP0001563

l. ______

l- 25.00 l

100.00 t

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{

U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY: _EIi_5Ii_VB81N___________

REACTOR TYPE: _B198-98_________________

DATE ADMINISTERED:_thlD241h________________

a EXAMINER:

i _EELLEli_Ji______________

j CANDIDATE: _________________________

INSIBUCIl0N1_IQ_C8NQlD8IE1 Rood the attached instruction page carefully. This examination reptsces the current cycle facility administered requalification examination.

. Rotraining requirements for fatture of this examination are the same as for failure of a requalification examinetton prepared and administered by

your training staff. Points for each question are indicated in pcrentheses after the question. The passing grade requires et least 70%

in each category and a final grade of et least 80%. Examination papers cill to picked up four (4) hours after the examinetton starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY

__V8LUE_ _IQI8L ___1CQBE___ _V8LUE__ ______________C8IESQBl_____________

_25499__ _25200 ___________ ________ 5. THEORY OF NUCLEAR POWER PLANT ,

i OPERATION, FLUIDS, ANO THERMODYNAMICS i

_2540D__ _25200 ___________ ________ 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION

_254D9__ _25400 ___________ ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL t t

_25tDD__ _2520D ___________ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 199,99__ ___________ Totals Final Grade 4 All work done on this examination is my own. I have neither given nor received sid.

1

Candidate's Signature I

- - , - . , -n-- . , - , - , - - , . . . - - . - . - , , _-n_--- - , - . - _ _ . , , . , - - . - - - , - . , - . - , -

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

1. Cheating on the examination means an automatic denial of your application cnd could result in more severe penalties.

2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

3. Use black ink or dark pencil SDIY to facilitate legible reproductions.

4. Print your name in the blank provided on the cover sheet of the oxamination.

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

6. Use only the paper provided for answers.

7. Print your name in the upper right-hand corner of the first page of 339b cection of the answer sheet.

8. Consecutively number each answer sheet, write "End of Category __" as cppropriate, start each category on a agu page, write SDAY 90 90g Eidt 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 ibrag lines between each answer.

11. Separate answer sheets f rom pad and place finished answer sheets face down on your desk or table.

12. Use abbreviations only if they are commonly used in facility 1113t31gts.

' 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

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

15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.

I

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

the augm1Dat only.

17. You must sign the statement on the cover sheet that indicates that the eork 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.

I

18. When you complete your examination, you shall:

O. Assemble your examination es follows:

(1) Exam questions on top.

(2) Exam sids - figures, tables, etc.

(3) Answer pages including figures.which are part of the answer.

b. Turn in your copy of the examination and all pages used to answer I the examination questions.

i O. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.

d. Leave the examination area, as defined by the examiner. If after i

leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.

i 1

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Si__INEQBX_QE_ NUCLE 88_EQWEB_EL8NI_DEEB8IIONi_ELWIQSi_8NQ PAGE 2 IHEBdQDINedICS QUESTION 5.01 (4.00)

c. How does removing spent fuel increase core reactivity? (1.0)

b. How does removing spent fuel decrease core reactivity? (1.0)

c. How does removal of reflectors affect core reactivity? (1.0)

d. How does removing a depleted neutron source affect reactivity? (1.0)

QUESTION 5.02 (3.00)

o. Which reflector elements are replaced and when are they removed from the core? (2.0)

b. Which reflectors are permanent? (1.0)

QUESTION 5.03 (3.00)

c. How does the outermost radial fuel zone differ from the others? (1.0)

b. What effect is this dif f erence attempting to control? (1.0)

c. What causes this effect in the outermost fuel region? (1.0)

QUESTION 5.04 (3.00)

Explain why 15% of the primary coolant enters the core as " bypass flow" but only 6% leaves the core as " bypass flow." (3.0)

QUESTION 5.05 (3.00)

What are the two (2) maj o r reasons that orifices are used in the Fort St.

Vrain core? (3.0) l l

L

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

It__IHEQBY_QE_NUGLEeB_EQWEB_ELeNI_QEEB8IIQNt_ELUIDSt_eNQ PAGE 3 IHEBdQQYNedIG1 QUESTION 5.06 (3.00)

What two (2) core operating characteristics change between BOC and EOC due to the buildup of U-233 for use as fuel? (3.0)

QUESTION 5.07 (3.00)

What are three (3) types of core changes that can cause a power-to-flow icbalance in a refueling region with the core at balanced overall pcwor-to-flow? (3.0)

QUESTION 5.08 (1.00)

What are two (2) factors accounted for in hot spot evaluation? (1.0)

QUESTION 5.09 (2.00)

c. Why should a centrifugal pump be started with the discharge valve closed? (1.0)

b. What is operating a pump with too much flow and no discharge pressure called AND why sheuld this condition be avoided? (1.0) l l

(***** END OF CATEGORY 05

- - - - )

6t__ELeNI_SISIEUS_DESIGNt_G9NIBQLt_eND_INSIBWHENIeIION PAGE 4 QUESTION 6.01 (4.00)

c. What are four (4) users of purified helium from the Helium Purification System (System 23)? Normal or Fuel Handling related are acceptable for full credit. (2.0)

b. What are four impurities removed by System 23? (2.0)

QUESTION 6.02 (2.00)

What are two (2) ways that the Reserve Shutdown System may be actuated from OUTSIDE the Control Room? (2.0) 4 QUESTION 6.03 (3.00)

c. Name the three cooling supplies to the fuel storage wells (FSW). (1.8)

b. Name the two backup cooling supplies to the FSW. (1.2)

QUESTION 6.04 (3.00)

c. What is the collection point for the fuel deck floor drains? (0.5)

b. What is the collection point for the Hot Service Facility floor drains? (0.5)

c. Why are there different collection points for the fuel deck and Hot j Service Facility floor drains? (2.0) l i

I

(***** CATEGORY 06 CONTINUE 0 ON NEXT PAGE *****)

y

~

.; ~

62__EL8HI_SISIEdi_DESIGNt_C9NIBQLi_8ND_INSIBudENI8IIQN PAGE 5 n,

m'

~

QUESTION 6.05 , (4.00)

Assume the plant is in a normal configuration at 50% reactor power and turbine load and turbine load is increased to 60%. A simplified schematic

. of the steady state controls is attached. Continue your answers until eteady state conditions are achieved. (4.0)

- ~. How is turbine load normally increased? (1.0) b# How~and WHY does feedwater flow change? (1.0)

, ,% .s

,c . How and WHY does reactor power change? (1.0)

d. How and WHY does helium flow change? (0.5)

o. How is any error in main or reheat steam temperature adj usted once at the new load condition? C0.5)

QUESTION 6.06 (2.00)

True or false?

o. Primary coolant moisture hi alarm (MM-9306/7) is -30 deg's F or -45 deg's F. (Question deleted per facility comment - ref. error.) (0.0)

b. A loop shutdown and steam water dump due to high moisture is inhibited by a circulator seal malfunction trip. (0.667)

c. A two loop trouble scram REQUIRES two high level moisture monitor trips. (0.667)

d. At an average core exit temperature of less than 725 deg's F, the basis for Technical Specification is oxidation of graphite components.(0.667) s h

s QUE$ TION 6.07 (3.00)

's. What automatic actions occur if the steam / water dump system is actuated '

on high, primary pressure? (2.0) b .~ What is the setpoint for the high pressure trip in the steam / water dump system? (1.0)

-" rt***** *****9

6t__EL8HI SISIEUS_DESIGNt_GQNIBQLt_8NQ_INSIBWBENI8IION PAGE 6 QUESTION 6.08 (2.00)

What two,(2) conditions will cause the PPS to initiate a turbine trip icmediate'ly after a reactor scram? (2.0)

QUESTION 6.09 (2.00)

Given the following I-05 pump indications, which of the hydraulic oil pumps cre running end how was each running pump started? (2.0)

c. Pump 1A - Red indicator.

b. Pump 18 - Red and white indicators.

c. Pump 1C - Green indicator.

(***** END OF CATEGORY 06 *****)

Za__EBOCEDUBES_=_N9BdeLa_eRNQBdelt_EMEBGENC1_8NQ PAGE 7 88D19LQQ1G8L_GQNIBDL QUESTION 7.01 (3.50)

c. Under what conditions should non-operations personnel working in the Reactor Building report to their personnel accountability station?

(1.0)

b. When evacuating the Reactor Building, where is their personnel accountability station?

(0.5)

c. What are two conditions that would require that they report to the Health Physics Access Control Area when leaving the Reactor Building on the way to their personnel accountability station? (1.0)

d. What should the first person to report to a personnel accountability station do?

(1.0)

QUESTION 7.02 (3.00)

What are each person's three (3) individual responsibilities per the rcdiation protection plan as listed in SUSMAP-47 (3.0)

QUESTION 7.03 (3.00)

Classify each of the events below as either emergency or non-emergency bcsed only on the information given. Consider each event independently.

c. The low. reactor has been automatically scrammed due to main steam pressure "

(0.5) b.

1A helium circulator has trippea on speed high (I-OSA 1-1). (0.5)

c. !

PCRV Safety Valve Activity High Alarm activates (I-05A 2-2) AND reactor l pressure is decreasing rapidly. I (0.5) d.

Loop I moisture high alarm AND the reactor has been manually shutdown because the Technical Specification limit on maximum moisture during power operations have been exceeded.

(0.5) o.

Criticality Building. alarm is reported to be activated in the Fuel Storage I l

(0.5)

f. The reactor coolant loop has been automatically scrammed has tripped and dumped.

on high moisture AND one (0.53

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

Z4__EB0GEDUBES_=_NQBdekt_8ENQBdekt_EMEBGENCY_6ND PAGE 8 B8DIQLQQICeL_GQNIBQL QUESTION 7.04 (3.00)

What are two (2) plant conditions that require inserting the Reserve Shutdown System? (3.0)

QUESTION 7.05 (3.00)

What are the five (5) immediate actions required following a reactor scram?

Specific steps to accomplish each action are NOT required. (3.0)

QUESTION 7.06 (4.00) 00 fine, per Technical Specifications:

c. Shutdown for refueling. (2.0)

b. Irradiated fuel. (2.0)

QUESTION 7.07 (3.50)

c. What should the following switch positions be prior to withdrawing control rods for startup? (2.0)

1. Reactor Mode Selector Switch.

2. Manual Scram Switch.

3. Rod Group Sequence Bypass Switch.

4. Interlock Sequence Switch.

b. When increasing power from 20%, WHY should the operator perform the following balancing actions? (1.5)

1. Adj ust helium flow or ifice valves.

2. Adj ust steam generator feedwater flow. -

QUESTION 7.08 (2.00)

List two (2) actions which should be perforemd by the Duty Shift Supervisor immediately upon assuming the role of Emergency Coordinator. (2.0)

(***** END OF CATEGORY 07 *****)

At__6DUINISIB6IIVE_EBQGEQUEESt_GQNDIIIONSt_eND_LIMIIeIIQN3 PAGE 9 QUESTION 8.01 (3.00)

What are the four reasons that a Radiation Work Permit (RWP) may be concelled? (3.0)

QUESTION 8.02 (3.00)

What requirements must a mechanical maintenance worker meet to gain access to a Health Physics controlled area? (3.0)

QUESTION 8.03 (3.00)

What three (3) concepts are used concurrently to accomplish the goal of controlling exposure ALARA? (3.0) i QUESTION 8.04 (3.00)

(

When do Technical Specifications require that two (2) licensed operators be l in the Control Room? (3.0)

QUESTION 8.05 (3.00)

On back shift, which personnel (by job title) are assigned the Control Room as their personnel accountability station? (3.0) l l

l QUESTION 8.06 (3.00)

c. What 2 circumstances must exist to issue the vital access door key?(1.5) -

1 l b. What 2 requirements must be met by the individual to whom the key is issued? (1.5) l

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

Bi__8DMINIIIB8IIVE_EBQGEDVBEft_GQNDIIIONSz_8NQ_LIMII8IIQN1 PAGE 10 QUESTION 8.07 (2.00)

Under what circumstances may personnel deviate from an approved station procedure without prior approval? (2.0)

QUESTION 8.08 (3.00)

What five (5) calls must be made by the emergency coordinator for en energency classified as an " Unusual Event?" (3.0)

QUESTION 8.09 (2.00)

c. Why is a " clearance" (non-operational status) assigned to equipment? C0.5)

b. Who is issued the card or tag indicating a clearance? (0.5)

c. What are two (2) purposes of operation deviation system status tags? (1.0) 1

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

. _ . . . .. _ _ _ _ _ . . (*************___END OF. EXAMINATION _***************)_

l 54__IHE081_DE_NUGLE88_EQWEB_EL8HI_DEEB8IIONt_ELUIDSt_8NQ PAGE 11 l' IHEBdQDINedIGS ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

l ANSWER 5.01 (4.00)

c. Increases reactivity by removing fpp (including Xe & Sm) (1.0)

b. Decreases reactivity by removing f iss ionable mater ials. (1.0)

c. Removal decreases react. by allowing increased neutron leakage. (1.0)

d. Decreases reactivity. (1.0)

For b & d, ACCEPT NONE if defined as completely spent / depleted.

REFERENCE FSV LESSON NO. 39.00, p. 3 ANSWER 5.02 (3.00)

a. All reflectors adj acent to f uel (1.0) are replaced at the refueling of that region (1.0) (2.0)

b. All other reflectors (that aren't adj acent to f uel) are permanent.(1.0) l REFERENCE FH 033.00, III.A., p. 6 i

ANSWER 5.03 (3.00)

e. Less uranium (0.5) & more thorium (0.5). (1.0)

b. Power peaking Cat the core-reflector interface). (1.0)

c. In-leaking / backscatter neutrons (from the reflector). (1.0)

REFERENCE FH 033.00, III.H.1., p. 11 1

1

Et__INE0BY_DE_ NUCLE 8B_EDWEB_EkeNI_DEEB8IIONt_ELUIDit_eNQ PAGE 12 IHEBdQDYN8 DIGS ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

i ANSWER 5.04 (3.00)

Since bypass flow does not pass through an orifice (0.75), it is at a higher pressure than the coolant in the channels (0.75). Because of this i higher pressure, some of the bypass flow will enter the channels in the fuel column (0.75) via the end gaps (0.75). (CONCEPT)

REFERENCE R0 120.00.01.01.2 ANSWER 5.05 (3.00)

1. Different refueling regions may differ in age and burnup by as much as 6 years (0.75). The newer regions produce more heat and so need more flow to maintain a constant outlet temperature (0.75). (CONCEPT)

2. Any region with a higher than average power density has a higher than average flow resistence (0.75). Without orificing, the higher powered regions would receive lower flow C0.75). (CONCEPT)

REFERENCE R0 120.00.01.02.1 ANSWER 5.06 (3.00)

o. Temperature coefficient (0.75) becomes less negative (0.75). (1.5)

b. Beta factor (0.75) decreases (0.75). (1.5)

REFERENCE

-FSV Reactor Physics LP on Core Changes ANSWER 5.07 (3.00)

1. Core / fuel burnup.

2. Control rod movement.

2. Orifice position change. (3 answers e 1.0 ea.)

REFERENCE R0 120.00.01.07.1

54__IHE981_DE_ NUCLE 88_EQWEB_EL8NI_QEEB8IIDNt_ELUIDit_8ND PAGE 13 IHEBdQQ1N8 DIGS ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 5.08 (1.00)

1. Fuel element dimensional variance.

2. Thermal conductivity uncertainty.

3. Coefficient of thermal expansion uncertainty.

4. Irradiation-induced dimensional change data.

5. Heat-transfer correlation uncertainty.

6. Radial power peaking factor uncertainty.

7. Axial power peaking factor.

8. Fuel loading tolerance.

9. Exit coolant temperatue measurement tolerance. (Any 2 0 0.5 es.)

10. High power / flux e hot spot.

11. Unequal / low region He flow.

REFERENCE RO 120.00.01.06.1 ANSWER 5.09 (2.00)

a. A closed discharge valve minimizes the starting power required by reducing the initial mass flow. (CONCEPT) (1.0)

b. Runout (0.5) - overcurrent trip may result (0.5) (CONCEPT) (1.0)

REFERENCE R0 118.00.01.07 1

6t__EL6NI_SISIEUS_DESIGNt_CONIB9Lt_8ND_INSIBWHENI8IIQN PAGE 14 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 6.01 (4.00)

c. 1. Buffer Helium makeup.

2. Purge helium for HTFA.

3. Purge helium for CRO's.

4. Presurizing helium for interspace PCRV penetrations.

5. PCRV safety relief valves. (Any 4/5 e 0.5 es.)

b. 1. Fission-produced isotopes.

2. tritium.

3. dust.

4. condensed water.

5. water vapor.

6. carbon compounds.

7. hydrogen. (Any 4/8 8 0.5 ea.)

8. noble gases.

REFERENCE FH 034.00, p. 4-9 l

ANSWER 6.02 (2.00)

1. Local relay pushbuttons on level 10. (1.0) l

2. Local ACM through hook up of flexible hoses. (1.0)

REFERENCE FH 030.00, p. 11 ANSWER 6.03 (3.00)

a. 1. Helium purge.

I 2. RPCCW.

l 3. RB HVAC.

I 4. PCRV Aux Cooling Loops 1 & 2. (3 reg'd) 1 .

b. 1. Fire Water.

I

2. Booster fan and dampers. (5 answers e 0.6 ea.)

3. 00S PCRV Aux Cooling Loop. (2 req'd)

REFERENCE FH 041.00.01.05.1

6t__EL6HI_SISIEMS_DESIONt_QQNIBQLt_eND_INSIBWHENIeIIQN PAGE 15

-ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 6.04 (3.00)

e. Reactor building sump. (0.5)

b. Liquid waste sump (via sys 61, to sump, drain sta, or recycle). (0.5)

c. RB sump is not normally contaminated and can be discharged f rom the plant separately (1.0). The effluent from the HSF is normally contaminated (1.0). (2.0)

REFERENCE FH 044.00.01.03.1 ANSWER 6.05 (4.00)

c. Load is increased by opening the main turbine admission valves. (1.0)

b. This causes a decrease in throttle press. (0.5). The steam press.

controller causes the setpoint for afw flow to be raised (0.5). (1.0)

c. The change in 1st-stage press. provides a f eed-f orward signal to the flux controller to anticipate the required increase in reactor power setpoint (0.5). The dev. between reactor power and setpoint causes the neutron flux control loop to withdraw the reg. rod (0.5). (1.0)

d. A f eed-f orward flow signal to the helium circ. speed control antici-pates the superheat outlet error and causes incr. He flow C0.5). (0.5)

o. At the new load condition, any error in main or reheat steam temperature is removed by the feedback control loops which trim circulator speed and reactor power (0.5). (0.5)

For ALL - ACCEPT CONCEPT.

REFERENCE LR 112 ANSWER 6.06 (2.00)

e. , b. T, c. F, d. F (3 answers e 0.667 es.)

(A not graded per current design.)

I

Ei__ELeNI_SISIEMS_QESIQNi_GQNIBQLi_eNQ_INSIBudENIeIIQN PAGE 16 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

REFERENCE R0 132 ANSWER 6.07 (3.00)

e. 1. Pre-selected loop is dumped. (1.0)

2. Other loop is depress. to j ust above primary press (~8508). (1.0)

b. 775# 4 100% or 53+/-55iprogram. (1.0)

REFERENCE R0 127.00 ANSWER 6.08 (2.00)

1. Reactor pressure low. (1.0)

2. All 4 circulators tripped. (1.0)

REFERENCE R0 005.01.01.04 ANSWER 6.09 (2.00)

1. Pump 1A is running (0.5) due to a manual start (0.5)

2. Pump 1B is running (0.5) due to an automatic start (0.5).

l REFERENCE R0 091

r L. Zi__EB9CEDUBES_=_N9Bdekt_8ENQBd8Lt_EMEBGENGl_8NQ PAGE 17 88DIQLQSIG8L_GQNIBQL ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 7.01 (3.50)

e. Fire (0.5) or Radiological (0.5) alarm. (1.0)

b. Lunchroom OR TSC. (0.5)

c. 1. Contamination (> 2x background) found at exit monitor.

2. Exit via crash bars or emergency exits (due to imminent danger).

3. Exit monitors show > 500 cpm background. (Any 2/3 0 0.5)

d. Verify ratemeter operating properly (0.5) & not alarming (0.5). (1.0)

OR " habitability (1.0).

REFERENCE G-5, p. 3, 4, 7, 11 ANSWER 7.02 (3.00)

1. Follow procedures and practices, to maintain exposure ALARA. (1.0) 4

2. Identify to supervisor, rad. work procedures & practices that need to be upgraded. (1.0)

3. Request & attend rad. prot. training suf ficient to discharge assigned responsibilities. (CONCEPT for all 3) (1.0)

REFERENCE SUSMAP-4 ANSWER 7.03 (3.00)

c. Non

b. Non

c. Emer

d. Non -

o. Emer

f. Non (6 answers G 0.5 es.)

REFERENCE Emergency Procedures

Zi__EBQGEQUBES_=_NQBd8Lt_8BNQBd8Lt_EMEBGENGl_8NQ PAGE 18 88DIDLDSIG8L_GQNIBQL ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 7.04 (3.00)

1. Loss of forced coolant flow (0.75) for required time (0.75).

2. Can't insert enough rods for req'd SOM (0.75) e hot S/D (0.75).

3. Reactor can't be maintained S/D (0.75) after a scram or S/D (0.75).

4. Any unexplained react. operator feels is unsafe. (Any 2/4 e 1.5 es.)

REFERENCE SOP 12-05, Rev. 8, p. 4 ANSWER 7.05 (3.00)

1. Insert a manual scram. (0.6)

2. Place ISS on Low Power Position. (0.6)

3. Ensure transfer of house power. (0.6)

4. Ensure turbine trip. (0.6)

5. Ensure / establish stable core cooling conditions. (0.6)

REFERENCE EP APP B-1, p. 7-9 ANSWER 7.06 (4.00)

e. Mode switch is LOCKED in the refueling position (1.0) simultaneous with either hot or cold shutdown conditions (1.0). (2.0)

b. Has a radiation level (1.0) greater than 100 mr/hr G 1 foot (1.0).(2.0) l i

l REFERENCE i Technical Specifications, Section 2

r- j Zi__EBQCEQWBE1_=_NQBU8Lt_8ENQBU8Li_EMEBGENGI_8NQ PAGE 19 B6DIQLQGIG8L_GQNIBQL ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 7.07 (3.50)

a. 1. Run

2. Normal

3. Normal

4. Start (4 answers e 0.5)

b. 1. To equalize reheat steam outlet temperatures. (0.75)

OR to " core outlet / region mismatches.

2. To equalize main steam header outlet temperatures. (0.75)

REFERENCE OPOP III, p. 6, 20, 21 ANSWER 7.08 (2.00)

1. Initiate actions to mitigate the event.

2. Assign (preliminary) rad. assess. responsibilities.

3. Initiate protective actions for station personnel.

4. Classify the event.

5. Make management contacts.

6. Complete appropriate (RERP) checklist (s). (Any 2/6 e 1.0 es.)

REFERENCE PT 004.01.01.02

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

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At__8DMINISIB8IIVE_EBQQEDVEESt_QQNDIIIQNSt_8ND_LIMII8IIQNS PAGE 20 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 8.01 (3.00)

1. Time expired.

2. Job completed.

3. Job cancelled.

4. Conditions change. (4 answers e 0.75 es.)

REFERENCE LR 029.00, p. 6, 7 ANSWER 8.02 (3.00)

1. HP Tech accompanied, (0.75)

OR C0.25)

2. RWP, (0.75)

OR

3. under HP direction (operators only) (NOT REQUIRED FOR FULL CREDIT)

AND (0.25)

4. HP authorization. (1.0)

REFERENCE FH 058.00.01.07.1 ANSWER 8.03 (3.00)

1. Time (of exposure should be minimized). (3 answers e 1.0 ea.)

2. Distance (from source should be maximized).

3. Shielding (from the source should be used whenever possible).

REFERENCE FH 060.00, p. 5 ANSWER 8.04 (3.00)

1. Startup.

2. Shutdown.

3. Recovery (from reactor trip). (3 answers e 1.0 es.)

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A4__8051NISIB8IIVE_EBQGEQ9BESt_G9NDIII9NSt_8ND_LIMII8IIQNS PAGE 21 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

REFERENCE TS 7.1.1.2.b, p. 7.1-3 ANSWER 8.05 (3.00)

1. Shift Supervisor.

2. Reactor Operators.

3. Auxiliary Tenders.

4. Equipment Operators.

5. Duty Technical Advisor.

6. Lead Security Officer. (6 answers e 0.5 ea.)

7. Off-duty Shift Supervisor - not required for full credit.

8. HP Technician - not required for full credit.

REFERENCE G-6, Attachment G-5A, Rev. 18, p. 11, 12 ANSWER 8.06 (3.00)

c. 1. Card reader failure (s). (0.75)

AND

2. Plant emergency exists. (0.75)

b. 1. Individual to whom the key is issued must have authorized access to all areas unlocked by the key.

2. Individual possessing the key may not exit the protected area until the key is returned to the SS.

l 3. Individual issued the keys must keep them until he returns them l to the SS. (Any 2/3 0 0.75 es.)

REFERENCE SO 011.00.01.06 ANSWER 8.07 (2.00) -

Porsonnel may deviate without prior approval in emergency situations (0.7) when essential to mitigate conditions (0.6) that will adversely affect personnel or public safety (0.7). (CONCEPT) (2.0) l

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A4__8DMINISIB8IIVE_EBQCEDMBEft_GDNDIIIDNSt_8NQ_LIMII8IIQN3 PAGE 22 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

REFERENCE LR 017.00.01.09 G-2, Rev. 19, Section 4.4.2.a, p. 9 ANSWER 8.08 (3.00)

1. Duty TA.

2. Management contact.

3. NRC.

4. State (EOC).

5. Governor's office. (5 answers e 0.6 ea.)

REFERENCE LR 019 ANSWER 8.09 (2.00)

c. 1. equip. requiring maintenance or modification.

2. Assure personnel safety.

3. Notify operations of inoperable equip.

4. Inform ops of how to restore equip. (Any 1 0 0.5)

b. the individual intending to direct performance of the work. (0.5)

c. 1. identify & document deviant operational situations.

2. authorize an operation status change.

3. control operations in repsect to servicing and maintenance work on equipment.

4. restore deviant situations to normal through orderly procedures.

(For part C, any 2/4 answers e 0.5 es.; for all parts, CONCEPT)

REFERENCE LR 018.00.01.06/7/8 P-2, Rev. 13, Section 3.1, 3.2, p. 1, 2 e- -rw -wp-w e-w--- - - - - w

---m,-,-- - .m ~y. --

w- -- .- . ---

TEST CROSS REFERENCE PAGE 1 QUESTION VALUE REFERENCE 05.01 4.00 JJP0001123 05.02 3.00 JJP0001124 05.03 3.00 JJP0001125 05.04 3.00 JJP0001127 05.05 3.00 JJP0001128 05.06 3.00 JJP0001129 05.07 3.00 JJP0001130 05.08 1.00 JJP0001131 05.09 2.00 JJP0001132 25.00 06.01 4.00 JJP0001134 06.02 2.00 JJP0001135 06.03 3.00 JJP0001136 06.04 3.00 JJP0001137 06.05- 4.00 JJP0001138 06.06 2.00 JJP0001139 06.07 3.00 JJP0001141 06.08 2.00 JJP0001142 l 06.09 2.00 JJP0001143 25.00 07.01 3.50 JJP0001144 07.02 3.00 JJP0001145

, 07.03 3.00 JJP0001146 L 07.04 3.00 JJP0001147 07.05 3.00 JJP0001148 07.06 4.00 JJP0001149 07.07 3.50 JJP0001150 07.08 2.00 JJP0001151 25.00 08.01 3.00 JJP0001152 08.02 3.00 JJP0001153 08.03 3.00 JJP0001154 08.04 3.00 JJP0001155 08.05 3.00 JJP0001156 08.06 3.00 JJP0001157 08.07 2.00 JJP0001158 1 08.08 3.00 JJP0001159 08.09 2.00 JJP0001160 -

25.00 l

t 100.00 l

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U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION LIMITED TO FUEL HANDLING FACILITY: _EIz_SIz_YB81N___________

REACTOR TYPE: _H168:68_________________

DATE ADMINISTERED:_RklDRllh________________

EXAMINER: _EELLElt_Jz______________

CANDIDATE: _________________________

IN118UGIl0NE_ID_G8NQlD81El Uao 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 grcde requires at least 70% in each category. Examination papers will bo picked up six (6) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY

__V8LUE _IQI8L ___1GQBE___ _V8LUE__ ______________C81EGQBl_____________

_1610D__ _16222 ___________ ________ M. REACTOR AND FUEL CHARACTERISTICS

_2DADD__ _2 dad 1 ___________ ________ N. EQUIPMENT, INSTRUMENTATION AND DESIGN DESCRIPTION

_2DADD__ _2Didi ___________ ________ 0. PROCEDURES AND LIMITATIONS ~

_22 ADD __ _22xd5 ___________ ________ P. EMERGENCY SYSTMS AND SAFETY DEVICES

_201DD__ _2Didi ___________ ________ Q. HEALTH PHYSICS AND RADIATION PROTECTION

_tazGD__ ___________

Totals Final Grade All work done on this examination is my own. I have neither given ~

nor received aid.

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Candidate's Signature

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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

1. Cheating on the examination means an automatic denial of your application cnd could result in more severe penalties.

2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all con. tacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

3. Use black ink or dark pencil 901% to facilitate legible reproductions.

4. Print your name in the blank provided on the cover sheet of the oxamination.

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

6. Use only the paper provided for answers.

7. Print your name in the upper right-hand corner of the first page of aggb section of the answer sheet.

8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a Dgg page, write 2DlE ED SDR Ridt 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 ihtta lines between each answer.

11. Separate answer sheets f rom pad and place finished answer sheets face down on your desk or table.

12. Use abbreviations only if they are commonly used in facility 1113tglyrg.

13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

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

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

16. If parts of the examination are not clear as to intent, ask questions of the RERWingt only. *

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

18. When you complete your examination, you shall:

e. Assemble your examination as follows:

(1) Exam questions on top.

(2) Exam sids - figures, tables, etc.

(3) Answer pages including figures which are part of the answer.

b. Turn in your copy of the examination and all pages used to answer the examination questions.

c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.

d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.

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Mi__BE8CISB_8ND_EWEL_GH8B8CIEBISIIGS PAGE 2 QUESTION M.01 (2.00)

Explain 2 ways an adverse reaction in irradiated fuel stored in fuel otorage wells is prevented. (2.0)

QUESTION M.02 (3.50)

c. How does removing spent fuel increase core reactivity? (1.0)

b. How does removing spent fuel decrease core reactivity? (1.0)

c. How does removal of reflectors affect core reactivity? (1.0)

d. How does removing a depleted neutron source affect reactivity? (0.5)

QUESTION M.03 (2.00)

o. Which reflector elements are replaced and when are they removed from the core? (1.5)

b. Which reflectors are permanent? (0.5) i QUESTION M.04 (2.00)

Fill in the blanks in the following paragraph dealing with the Region Constraint Devices (RCD). Blinnks may represent one or more words or numbers. (2.0) l RCD's in most cases link together __(a)__ of __(b)__ regions, to

__(c)__ between regions. There are __(d)__ RCD's installed in the Core.

l QUESTION M.05 (2.00)

o. How does the outermost radial fuel zone differ from the others? (1.0)

b. What effect is this dif f erence attempting to control? (0.5)

c. What causes this effect in the outermost fuel region? (0.5)

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

Hi__BE8CIDB_8ND_EWEL_CH888GIEB11IIGA PAGE 3 QUESTION M.06 (1.00)

Rcnk each of the materials below based on the mass of each at the beginning of cycle 3 (where 1st is the most and 3rd is the least). (1.0) 4

c. Uranium 235

b. Uranium 233

c. Thorium 232 QUESTION M.07 (2.00)

What are the four types of fuel elements used at Fort St. Vrain? (2.0)

QUESTION M.08 (1.50)

What is the width and height of a normal fuel element? (1.5) i I

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(***** END OF CATEGORY M *****)

Ni__EQUIEUENIt_INSIBVUENI8IIQN_8NQ_QESION_DESQBIEIIQN PAGE 4 QUESTION N.01 (3.00)

c. Describe the seal on the top of a Reactor Isolation Valve (RIV). (0.5)

b. Describe the seal on the bottom of a RIV. [0.5)

c. Besides sealing, what are 2 functions served by the RIV? (1.0)

d. Describe three (3) RIV internal interlocks. (1.0)

QUESTION N.02 (1.00)

What is the purpose of the refueling sleeve? (1.0)

QUESTION N.03 (1.00)

How many fuel elements and reflectors can be stored in a fuel otorage well? (1.0)

QUESTION N.04 ( .00)

What are two (2) functions of the Helium Circulator Compressor Inlet? (2.0)

(Question deleted as inappropriate. 20.0 pts. in cat., 98.0 in exam.)

QUESTION N.05 (3.50)

c. What are two (2) users of purified helium from the Helium Purification System (System 23)? Normal or Fuel Handling related are acceptable for full credit. (1.0)

b. What are four impurities removed by System 23? (1.0)

c. What parameter must be controlled to prevent carbon transport? (0.5)

d. What is the net effect of carbon transport on the core? (1.0)

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

Nz__EQUIEMENIz_INSIEWMENI8IIQN_8NQ_ DESIGN _DESQBIEIIQN PAGE S QUESTION N.06 (2.00)

What are two (2) ways that the Reserve Shutdown System may be actuated from outside the Control Room? (2.0)

QUESTION N.07 (2.00)

N;me the four (4) subsystems associated with the CRD's. (2.0)

QUESTION N.08 (2.50)

e. Name the three cooling supplies to the fuel storage wells (FSW). (1.5)

b. Name the two backup cooling supplies to the FSW. (1.0)

QUESTION N.09 (3.00)

c. What is the collection point for the fuel deck floor drains? (0.5)

b. What is the collection point for the Hot Service Facility floor drains? , (0.5)

c. Why are there different collection points for the fuel de'k c and Hot Service Facility floor drains? (2.0)

QUESTION N.10 (2.00)

What two (2) differences does the FHM detect to prevent interchanging fuel olements and reflector blocks? (2.0)

(***** END OF CATEGORY N *****)

Oz__EBQGEQURE3_8NQ_LidII6110NS PAGE 6 QUESTION 0.01 (2.00)

a. What action (s) should personnel in the Reactor Building take if Reactor Building activity monitors indicate that an abnormal radioactive gas release is taking place? (1.0)

b. How would personnel working in the Reactor Building be warned that an abnormal release was taking place? (1.0)

QUESTION 0.02 (1.00)

When would the Refueling Supervisor normally inform the control room that a Shutdown Margin calculation should be performed? (1.0)

QUESTION 0.03 (1.00)

Other than control rod withdrawal, what are two refueling evolutions that can cause erratic oscillation or increase on the Start-Up Nuclear instrument channels? (1.0)

QUESTION 0.04 (2.00) l What two (2) precautions should be observed when operating the Fuel Hondling Machine handwheels? (2.0)

QUESTION 0.05 (3.00)

In what order should the electric and pneumatic lines of a Reactor Icolation Valve (RIV) be connected? (3.0)

( QUESTION 0.06 (2.50)

Where (at what 5 locations) can the ATC be secured? (2.5)

(***** CATEGORY 0 CONTINUED ON NEXT PAGE *****)

Dz__EB9CEDVBEf_8HQ_LIMII8IIQN1 PAGE 7 QUESTION 0.07 (2.50)

What are the four (4) steps required to evacuate and backfill the FHM when it is installed on a RIV? (2.5)

QUESTION 0.08 (2.50)

Put the following steps of setting and bolting a RIV in the correct coquence. (List the steps in the proper order on your answer sheet, i.e.,

e, b, c, d, ...) (2.5)

O. Lower the RIV onto the refueling penetration.

b. Install support lugs at the support points around the penetration and alignment pins.

c. Check for cleanliness of the bottom bearing surface, the upper flange surface of the lug, and the penetration seal surface.

d. Connect power lines and pneumatic hoses.

o. Lubricate threads of the lug and stud support flanges and the lug support rings.

f. Snug all lug and stud support flanges up against the bottom of the valve.

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g. Screw the support flanges all the way onto the support ring.

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h. Lower the flange and ring assembly onto the support lugs.

1. Level the valve.

J. Install lug nuts and torque to limits.

k. Remove refueling penetration cover.

(***** CATEGORY 0 CONTINUE 0 ON NEXT PAGE *****)

17, 94__EBQGEQUBES_eNQ_LIdIIeIIQNS PAGE 8

.p QUESTION 0.09 (3.50)

Fill in the blanks in the following steps from the FHM abbreviated shutdown s .. procedure. Blanks may contain one or more words or numbers. (3.5)

.y O.

If in _(1)_, go to step b.' If in _(2)_, move position controls to normal zero positions. (0.5)

b. Depresu _(1)_ switch (Master Controls) and verify _(2)_. (1.0)

c. .Close _____ and verify it indicates closed. (0.5) d. Depress _(1)_ button to _(2)_. (1.0)

o. Turn _____ off (Master Controls) and verify all power goes off. (0.5) 4 t

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(***** END OF CATEGORY 0 *****)

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Ez__E5EEGENCI_1XIIEMS_8HQ_18EEII_ DEVICES PAGE 9 l l

QUESTION P.01 (3.00)

Por Technical Specifications, what three (3) conditions must be met in order to perform any reactor vessel internal maintenance with irradiated fuel in the vessel which requires removal of both the primary and secondary closures? (3.0)

QUESTION P.02 (2.00)

Answer each part below based on Technical Specifications. (2.0)

e. When is the reactor considered shut down for refueling purposes? (1.0)

b. When is f uel considered to be irradiated fuel? (1.0)

QUESTION P.03 (2.50)

e. What process parameter is monitored, at what setpoint, to assure that irradiated fuel elements being handled with the Fuel Handling Machine are maintained less than 750 F7 (1.0)

b. What is the potential problem associated with excessive f uel element temperatures? (0.75)

c. What non-normal condition, besides temperature, must be present for this problem to occur? (0.75)

QUESTION P.04 (2.50)

e. What Plant Protective System scram is prov.deo tal use during fuel loading, including setpoints and logic? (1.5)

I b. How would such a scram affect fuel handling operations? (0.5) t

c. If you were involved in operations from the refueling floor, what would l make you aware of the scram? (0.5)

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

Et__EUEBGENGl_SXSIEUS_8NQ_S8EEIX_ DEVICES PAGE 10 QUESTION P.05 (2.50)

c. What is the purpose of the grapple interlock? (0.5)

b. What conditions and logic are measured or detected to satisfy the interlock? (1.25)

c. What condition (s) CANNOT be bypassed to satisfy the interlock? (0.75)

QUESTION P.06 (2.00)

What does each of the following alarms indicate?

o. Plate Limit. (1.0)

b. Servo Error. (1.0)

QUESTION P.07 (3.50)

c. If you are working in the Reactor Building, under what conditions should you report to your personnel accountability station? (1.0)

b. Where is your personnel accountability station? C0.5)

c. What are two conditions that would require that you report to the Health Physics Access Control Area when leaving the Reactor Building on the way to your personnel accountability station? (1.0)

d. If you sre the first person to report to your personnel accountability l station, what should you do? (1.0)

QUESTION P.08 (2.00)

List the four (4) classifications of emergencies in the order of INCREASING ~

coverity. (2.0) l t

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

Et__EdEB9ENCY_SISIEdS_8ND_S8EEII_ DEVICES PAGE 11 QUESTION P.09 (1.00)

What two (2) systems are identified in H-3 as possible sources of high cctivity in the plant? (1.0)

QUESTION P.10 (1.00)

For what purpose is the HTFA (High Temperature Filter Adsorber) used during a LOFC (Loss of Forced Cooling) accident? (1.0) l l

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(***** END OF CATEGORY P *****)

~ __ ___

92__HEeLIH_EHISIGl_8ND_B6018IIQN_EBQIECIIQN PAGE 12 QUESTION Q.01 (2.00)

Fill in the blanks below. Blanks may contain one or more words or numbers.

c. A Contaminated Area is any area in which there exists loose surface contamination in excess of _(1)_ and/or._(2)_. (1.0)

b. A Radiation Area is an accessible area where a major portion of the whole body could receive greater than _(1)_ or _(2)_. (1.0)

QUESTION Q.02 (3.00)

Answer the following questions dealing with Radiation Work Permits (RWP's).

a. What does your signature, as a worker, signify on an RWP? (1.0)

b. What action should you take if you are performing work covered by an RWP and the job is not completed at the end of your shift, but will be resumed on your shift the next day? (1.0)

c. What type of radiation instrument is used exclusively for setting dose rates for personnel at FSV? (0.5)

d. When entering a radiation area with a portable survey instrument, which range on the detector should be selected prior to entry? C0.5)

I QUESTION Q.03 (1.00)

State a formula which describes the relationship between Radiation Absorbed l Dose, Roentgen Equivalent Man, and Quality Factor. (1.0)

QUESTION Q.04 (3.00)

What are three (3) of the four checks which must be performed before you can use an RO - 2 to perform a radiation survey? (3.0) l l

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

91__BE6 LIB _EBISIGS_8ND_B6DI8IIQN_EBQIEGIIQN PAGE 13 QUESTION Q.05 (1.00)

When moving an irradiated control rod drive assembly in the ATC, where chould you, the operator, stand in relation to the ATC to maintain your oxposure ALARA? WHY? (1.0)

QUESTION Q.06 (3.00)

What are your three (3) individual responsibilities per the radiation protection plan as listed in SUSMAP-4? (3.0)

QUESTION Q.07 (2.00)

What are four reasons for termination of an RWP? (2.0)

QUESTION Q.08 (3.00)

What requirements must YOU meet to gain access to a Health Physics controlled area? (3.0)

QUESTION Q.09 (2.00)

What three (3) concepts are used concurrently to accomplish the goal of controlling exposure ALARA? (2.0)

(***** END OF CATEGORY Q *****)

(*************

END OF EXAMINATION

- - - - )

U2__BE6CI98_8ND_EMEL_GB8E8CIEB11IIG1 PAGE 14 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER M.01 (2.00)

o. The 02 content of cover gas is kept below 5% to eliminate any chance of combustion (He atmosphere is maintained). (1.0)

b. The surface temp. of spent fuel is kept below 750 F to prevent oxidation. (1.0)

REFERENCE FSV SD 14-1, P. 3 ANSWER M.02 (3.50)

! a. Increases reactivity by removing fpp (including Xe & Sm) (1.0)

b. Decreases reactivity by removing fissionable materials. (1.0) l c. Removal decreases react. by allowing increased neutron leakage. (1.0) l

! d. Decreases reactivity. (0.5)

Accept NONE for b&d if spent & depleted defined as complete.

REFERENCE FSV LESSON NO. 39.00, p. 3 ANSWER M.03 (2.00)

n. All reflectors adj acent to f uel (0.75) are replaced at the refueling of that region (0.75) (1.5) l I

b. All other reflectors (that aren' t adj acent to fuel) are permanent.(0.5)

REFERENCE FH 033.00, III.A., p. 6 l

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52__BE8GI98_eND_EMEL_GH8E8CIEBIAIIGS PAGE 15 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER M.04 (2.00)

c. 3 (adj acent) columns

b. 3 (adj acent)

c. stabilize the gaps

d. 84 (4 answers G 0.5 ea.)

REFERENCE FH 033.00, III.G., p. 10 ANSWER M.05 (2.00)

a. Less uranium (0.5) & more thorium (0.5). (1.0)

b. Power peaking (at the core-reflector interface). (0.5)

c. In-leaking / backscatter neutrons (from the reflector). (0.5)

REFERENCE FH 033.00, III.H.1., p. 11 ANSWER M.06 (1.00) i c, a, b Cor Th-232, U-233, U-235)(0.5 for each swap req'd to correct order)

REFERENCE FH 033.00, III.I., p.15 l

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U2__BE6CIDB_eND_EMEL_GH886G1EB11IIG1 PAGE 16 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER M.07 (2.00)

1. Fuel element

2. Control fuel element

3. Bottom control fuel element

4. Neutron source element (4 answers e 0.5 es.)

REFERENCE FH 033.00.01, FSV Questions, p. 3 ANSWER M.08 (1.50) 14.2" (12~16" OK) width (0.75) by 31.2" (30~33" OK) height (0.75) (1.5)

REFERENCE FH 033.00.01, FSV Questions, p. 3 e

l l

N2__E991EMENIz_INSIBydENI8IIQN_8NQ_QESIGN_QElGBIEIIQN PAGE 17 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER N.01 (3.00)

c. A rubberized metallic "0" ring. (0.5)

b. An inflatable seal. (0.5)

b. 1. Provides shielding (0.5).

2. Serve as a platform for either the FHM or the ATC (0.5). (1.0)

c. 1. Differential pressure - Gate will not open unless dp.above and below gate is < 1 psid.

2. Dif f erential atmosphere - Gate will not open unless atmospheres are identical.

3. Seals inflate on loss of power.

4. Seal must be deflated to open gate.

5. Alarm if gate is opened.

6. Alarm if seal pressure < 20 psig. (Any 3/6 8 0.333 es.)

REFERENCE FSV, FH.O.49.00.01.05.06 ANSWER N.02 (1.00)

Provide accurate guidance and alignment for proper functioning of the FHM while in the PCRV penetration. (1.0)

! REFERENCE l SD-13-1, p.7,8 ANSWER N.03 (1.00)

Esch well can store 14 f.1. ele. (28 h.1.) in each col. or 56 total. (1.0)

OR Ecch well can store the equiv. of 70 f. 1. ele., w/ no more than 56 fuel.

h REFERENCE FSV FH 041.00, p. 7 I

s

Nz__E9WIEUENIt_INSIBUUENI8IION_8NQ_ DESIGN _DESGBIEIIQN PAGE 18 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER N.04 ( .00)

1. Direct helium flow (axially) into compressor (blading). (0.0)

2. Monitor flow in the primary circuit. (0.0)

(Qeustion deleted, not graded. Per facility comment resolution.)

REFERENCE FH 034.00, p. 7 ANSWER N.05 (3.50)

c. 1. Buffer Helium makeup.

2. Purge helium for HFTA.

3. Purge helium for CRD's.

4. Pressurizing helium for interspace PCRV penetrations.

5. PCRV safety relief valves. (Any 2/5 0 0.5 es.)

b. 1. F iss ion-p r oduc e d isotopes.

2. tritium.

3. dust.

4. condensed water.

5. water vapor.

6. carbon compounds.

7. hydrogen. (Any 4/7 0 0.25 es.)

8. noble gases.

c. water or water vapor. (0.5)

d. The net result is transport of core graphite into the lower temperature portions of the core (CONCEPT). (1.0)

REFERENCE FH 034.00, p. 4-9

~

l ANSWER N.06 (2.00)

1. Local relay pushbuttons on level 10. (1.0) i

2. Local ACM through hook up of flexible hoses. (1.0)

Ni__EQUIEUENIt_INSIBVUENI8IIQN_8NQ_QESIGN_QESGBIEIIQN PAGE 19 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

REFERENCE FH 030.00, p. 11 ANSWER N.07 (2.00)

1. Control rod drive mechanism.

2. Orifice valve and drive mechanism.

3. Reserve shutdown system.

4. Control rod drive purge. (4 answers e 0.5 es.)

REFERENCE FH 031.00.01.01 ANSWER N.08 (2.50)

o. 1. Helium purge.

2. RPCCW.

3. RB HVAC.

4. PCRV Aux Cooling Loops 1 & 2. (Any 3/4)

b. 1. Fire Water.

2. Booster fan and dampers. (5 answers e 0.5 ea.)

3. 00S PCRV Aux Cooling Loop. (Any 2/3)

REFERENCE FH 041.00.01.05.1 ANSWER N.09 (3.00)

c. Reactor building sump. (0.5) i b. Liquid waste sump (via sys 61 to rcycling, drain sta., or sump). (0.5)

c. RB sump is not normally contaminated and can be discharged f rom the plant separately (1.0). The effluent from the HSF is normally contaminated (1.0). (2.0) ,

l l

REFERENCE FH 044.00.01.03.1

N2__EQUIEEENIi_INSIBWHENI8IION_6ND_DESION_DESGBIEIIQN PAGE 20 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER N.10 (2.00)

1. Elements & reflectors have different dowel pattern. (1.0)

2. Elements & reflectors are different weights. (1.0)

REFERENCE FH 051.00.02.01.1 l

I 1

02__EBQQEQUEES_8NQ_LIMII8IIQNS PAGE 21 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 0.01 (2.00)

c. Evacuate the RB. (1.0)

b. Sounding of the Radiological Alarm. (1.0)

REFERENCE FSV EP APP H-2, Rev. 51, p. 3 ANSWER 0.02 (1.00)

Normally, prior to refueling a region when two control rod pairs cre retracted. (1.0)

REFERENCE CMG-13, p. 4, 5 ANSWER 0.03 (1.00)

Moving reflector blocks (0.5) or sources. [0.5) (1.0)

REFERENCE FH 051.00.01.04.1 ANSWER 0.04 (2.00)

1. Don't move the handwheels too quickly (a servo error may result, causing the system to unclutch). (1.0)

2. Don't operate the handwheels when the machine is in the OFF mode. (1.0)

REFERENCE FH 051.00.01.12.1

Di__EBQGEDWBE1_8HD_LIMII8IIONS PAGE 22 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER 0.05 (3.00)

1. RIV power supply cable. (0.5)

2. FHM/ATC Umbilical cable or jumper plug. (0.5)

3. Seal source helium hose for pneumatic seals. (0.5)

4. Backfill hose for Helium / air. (0.5)

5. Vacuum (purge) hose. (0.5)

Order (Any with i before 3 - 0.5) (0.5)

REFERENCE FH 049.00.01.07.7 ANSWER 0.06 (2.50)

1. ATC storage location.

2. Loading port.

3. Fuel storage wells.

4. Equipment storage wells.

5. Reactor (during refueling conditions). (5 answers e 0.5 es.)

REFERENCE FH 048.00.01.07.1 ANSWER 0.07 (2.50) f 1. (With power & pneumatic hoses attached) push the " Evacuate" button (and watch gauge. (0.5)

2. When desired gauge value is reached, push " Push to stop cycle" P8.(0.5)

3. Pause to allow purge vac pumps to isolate. (0.5) i 4 Select backfill method (he/ air), turn dial to method selected, push PB until atmospheric pressure is attained. (1.0)

REFERENCE FH 049.00.01.12.2

. ANSWER 0.08 (2.50) i

k, b, e, g, c, h, a, i, f, j, d (10 swaps for correct position 0 0.25 es.)

l l

- _ - _ ._ - - - - -_ _ ~ ..-. - . - . . . - _ . _ - - - _ - _

92__EB9GEDUBEf_eWD_LIMIIeIIONS PAGE 23 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

REFERENCE FH 049.00.01.11.1 ANSWER 0.09 (3.50)

a. 1. auto 2. manual (2 answers e 0.25 es.)

b. 1. "0FF" mode selector (0.5)

2. off mode is selected. (0.5)

c. Cask Valve. (0.5)

d. 1. " Emergency Stop" (0.5)

2. turn off the Z drive pumps. (0.5)

o. Power Key Switch. (0.5)

REFERENCE FH 051.00.05.1 O

4

Ei__EMEBGENQY_SYSIEdS_8NQ_S8EEIY_DEYIGES PAGE 24 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

f ANSWER P.01 (3.00)

1. The reactor vessel is depressurized to at or below atmospheric pressure. . (1.0)

2. The reactor average helium gas inlet temperature is </= 165 F. (1.0)

3. The reactor is maintained in a shutdown or refueling condition AND the reactivity of the core is monitored continuously by at least 2 neutron flux monitors. (1.0)

REFERENCE FSV TS 4.5.2, p. 4.5-3 ANSWER P.02 (2.00)

c. The reactor is considered shut down for refueling purposes when the reactor mode switch is LOCKE0 in the " Fuel Loading" (0.5) position simultaneous with either hot shutdown or the cold shutdown reactivity conditions (0.5). (1.0)

b. Irradiated fuel has a rad. level >/= 100 mr/hr 9 1 foot from ele. (1.0)

REFERENCE FSV TS, Section 2 ANSWER P.03 (2.50)

o. FHM cooling water outlet temperature (0.5) </= 150 F (0.5).

b. Graphite oxidation. (0.75)

c. Air inleakage must also have occurred. (0.75)

REFERENCE FSV TS 4.7.2, p. 4.7-3

Ei__EDEBGENCI_111IEd2_6NQ_18EEII_ DEVICES PAGE 25 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER P.04 (2.50)

a. Startup count rate high, 1 out of 2 logic, >/= 1.0E+5 C3 answers e 0.5)

b. Cease all internal maintenance /f uel handling until saf e. (0.5)

c. Operator would advise OR Facility Hazard alarm on FHM console. (0.5)

REFERENCE FSV EP APP B-1, p. 2, 11 l

ANSWER P.05 (2.50) i G. Protects against dropping of a grappled element. (0.5)

b. All of the following conditions must be met: (0.5)

1. At least 1 dowel pin engaged. (0.25)

2. The plate is raised. (0.25)

3. Probe weight < 50 lbs. (0.25) (1.25)

c. The probe weight condition cannot be bypassed. (0.75)

REFERENCE FSV LESSON NO. FH 051.00, p. 66,67 i

ANSWER P.06 (2.00) l o. Grapple head plate above +2.5". (1.0) 1

b. Z, R, Thets servo loop position error excessive. (1.0)

REFERENCE FH 051.00.02.02.1 i

I

Et__EMEEGENC1_SYSIEMS_8NQ_18EEII_ DEVICES PAGE 26 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER P.07 (3.50)

o. Fire (0.5) or Radiological (0.5) alarm. (1.0)

b. Lunchroom. (0.5)

c. 1. Contamination (> 2x background) found at exit monitor.

2. Exit via crash bars or emergency exits (due to imminent danger).

3. Exit monitors show > 500 cpm background. (Any 2/3 0 0.5)

d. Verify ratemeter operating properly (0.5) a not alarming (0.5). (1.0)

REFERENCE

! FSV G-5, p. 3, 4, 7, 11

, ANSWER P.08 (2.00)

1. Notification of Unusual Event.

2. Alert.

3. Site Area Emergency.

4. General Eme;rgency. (4 answers e 0.5 es.)

REFERENCE SSLO Procedures Gelf-Study Guide, p. 26, for RERP, Section 4 ANSWER P.09 (1.00)

Sys. 13, Fuel Handling Purge. Sys. 13, FH Purge Sys. 63, Gas Red. Sys. 14, Fuel Stor. Bldg.

Sys. 14, Fuel Storage Building. Sys. 21, He Circ Aux.

Sys. 23, He Pur. Sys. 22, Sec. Cool. (SJAE & HRH)

Sys. 11, PCRV Aux piping. (Any 2 0 0.5 ea.)

REFERENCE '

SSLO Procedures Self-Study Guide, p. 35, for EP H-3

-n, , , - , . , . _ - _ , - _ - - - , _ - , . . . , , . ,

Et__EMEBGENC1_111IEH1_8NQ_18EEI1_ DEVICES PAGE 27 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER P.10 (1.00)

The HTFA are used to begin depressurization of the primary system by removal of primary coolant (CONCEPT). (1.0)

REFERENCE FH 035.00, p. 23 e

4

Di__HE8LIH_EHISIGS_8NQ_B8DI8IIQN_EBQIEGIIQN PAGE 28 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER Q.01 (2.00)

o. 1. 1000 dpm/100 sq cm beta-gamme. (0.5)

2. 10 dpm/100 sq cm sipha. (0.5)

b. 1. 2.5 mrom in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . (0.5)

2. 100 mrom in 5 consecutive days. (0.5)

REFERENCE FH 060.00, p. 3, 4 ANSWER Q.02 (3.00)

o. That you understand the job requirements (CONCEPT). (1.0)

b. Return white copy to SS. (1.0)

c. Ion chamber. (0.5)

d. Start on the highest range (a range down ...). (0.5)

REFERENCE FH 058.00, p. 14; FH 059.00, p. 6, 11 ANSWER Q.03 (1.00)

Rcd

QF = REM (1.0)

REFERENCE FH 058.00.01.04.1 ANSWER Q.04 (3.00) .

1. Inspect for physical damage.

2. Check for current calibration.

3. Perform battery check.

4. Verify response to a known source. (any 3/4 e 1.0 es.)

REFERENCE FH 059.00.0.03.1

92__HE8LIH_EHI11Gl_8NQ_B8018IION_EBQIEGIIQN PAGE 29 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.

ANSWER Q.05 (1.00)

Stand near the ATC - its shielding design generally produces lower dose rotes there. (1.0)

REFERENCE FH 060.00.01.01.1 ANSWER Q.06 (3.00)

1. Follow procedures and practices, to maintain exposure ALARA. (1.0)

2. Identify to supervisor, rad. work procedures & practices that need to be upgraded. (1.0)

3. Request & sttend rad. prot. training suf ficient to discharge assigned responsibilities. (CONCEPT for all 3) (1.0)

REFERENCE SSLO Procedures Self-Study Guide, p. 28, for SUSMAP-4 ANSWER Q.07 (2.00)

1. Time expired.

2. Job completed.

3. Job cancelled.

4. Conditions change. (4 answers e 0.5 es.)

REFERENCE FH 058.00, p. 15

Di__HEALIH_EUISICS_eND_BeQIeIIQN_EBQIECIIQN PAGE 30 ANSWERS -- FT. ST. VRAIN - 86/09/16-PELLET, J.

ANSWER Q.08 (3.00)

1. HP Tech accompanied, (0.75)

OR (0.25)

2. RWP, (0.75)

OR

3. under HP direction (operators only) (NOT REQUIRED FOR FULL CREDIT)

AND (0.25)

4. HP authorization. (1.0)

REFERENCE FH 058.00.01.07.1 ANSWER Q.09 (2.00)

1. Time (of exposure should be minimized). (3 answers e 0.667 es.)

2. Distance (from source should be maximized).

3. Shielding (f rom the source should be used whenever possible).

REFERENCE FH 060.00, p. 5 l

4 i

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TEST CROSS REFERENCE PAGE 1 QUESTION VALUE REFERENCE M.01 2.00 JJP0001037 M.02 3.50 JJP0001038 M.03 2.00 JJP0001058 M.04 2.00 JJP0001059 M.05 2.00 JJP0001060 M.06 1.00 JJP0001061 M.07 2.00 JJP0001062 M.08 1.50 JJP0001063 16.00 N.01 3.00 JJP0001039 N.02 1.00 JJP0001040 N.03 1.00 JJP0001041 N.04 .00 JJP0001064 N.05 3.50 JJP0001065 N.06 2.00 JJP0001066 N.07 2.00 JJP0001067 N.08 2.50 JJP0001068 N.09 3.00 JJP0001069 N.10 2.00 JJP0001070 20.00 0.01 2.00 JJP0001042 0.02 1.00 JJP0001043 0.03 1.00 JJP0001044 0.04 2.00 JJP0001045 0.05 3.00 JJP0001071 0.06 2.50 JJP0001072 0.07 2.50 JJP0001073 0.08 2.50 JJP0001074 0.09 3.50 JJP0001075 20.00 P.01 3.00 JJP0001046 P.02 2.00 JJP0001047

! P.03 2.50 JJP0001049 I P.04 2.50 JJP0001050 l

P.05 2.50 JJP0001051 P.06 2.00 JJP0001076 P.07 3.50 JJP0001077 ,

P.08 2.00 JJP0001078 P.09 1.00 JJP0001079 P.10 1.00 JJP0001080 22.00 Q.01 2.00 JJP0001053

TEST CROSS REFERENCE PAGE 2 QUESTION VALUE REFERENCE Q.02 3.00 JJP0001054

, Q.03 1.00 JJP0001055 Q.04 3.00 JJP0001056 Q.05 1.00 JJP0001057 Q.06 3.00 JJP0001081 Q.07 2.00 JJP0001082 Q.08 3.00 JJP0001083 Q.09 2.00 JJP0001084 20.00 98.00 1

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Companyof Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 September 24, 1986 Fort St. Vrain Unit No. 1 P-86564

+ M @ $ 0tf[i h Mr. Ralph Cooley, Section Chief I Operating Licensing Group 6@ 25126 U. S. Nuclear Regulatory Commission p Region IV -

611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Docket No. 50-267

SUBJECT:

NRC Administered Examinations

Dear Mr. Cooley:

The purpose of this letter is to provide comments to the NRC on the Licensed Requalification, SR0 Upgrade, and Special Senior Licensed Operator (Fuel Handler) examinations administered at Fort St. Vrain the week of September 15, 1986.

In general, the examinations were fair and applicable to the Fort St.

Vrain facility. However, we have a few concerns which are listed in Attachments 1 through 4.

Any comments or questions concerning this matter should be made to M. H. Holmes at (303) 480-6960.

Sincerely, 7LC 4et bm by etSE J. W. Gahm Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station JWG/sl Attachments

,z ..

ATTACHMENT 1 REVIEW OF REACTOR OPERATOR REQUALIFICATION EXAMINATION 1.01 A. Acceptable B. This is a_ valid question, however, should also accept the following answer with the proper assumption.

Assumption: Define spent fuel as fuel that has been completely depleted, with no fissionable material remaining. Under this assumption, removal of the spent fuel would cause no change in core reactivity, as it has no fissionable material remaining and is no longer contributing to the reactivity of the core. Could in fact consider this as an increase in core reactivity as poison is removed.

C. Acceptable D. This is a* valid question, however, should also accept the following answer with the proper assumptions.

. Assumption: Depleted is defined as the source has decayed to the point that it is producing virtually no neutrons.

Under this assumption, removal of the source would have little or no effect on core reactivity, as it is producing no neutrons.

1.02 Acceptable 1.03 Acceptable 1.04 Acceptable 1.05 Acceptable 1.06 A. Acceptable B. This is a valid question, however, should also accept enhances flow stability.

Reference:

HTGR Technology Course 1.07 Due to the numerous ways that this question may be answered utilizing the assumptions listed below, this is an invalid . ,

question. The intent of the question is valid and has in fact been utilized at Fort St. Vrain in the past. Since there are better questions to determine an individuals knowledge of Xenon, we at Fort St. Vrain no longer include this question in our training. Should also accept the following answers:

Assumption: Assume power reductions can be treated as step changes for purposes of fission product poison transient analysis.

General: Differences between the two scenarios will be primarily due to changes in Xenon-135 concentration (and therefore reactivity) with time following the downpower maneuver. Following a downpower, the Xenon concentration will vary with time as is shown on the following graph:

. N-W s e & +1*t by, SW. .

, (p*~~-

I g i I J

I P f 6 Aes j,.

The maximum Xenon concentration occurs at approximately 5-6 hours following the power transient; therefore, this is the time at which the largest negative reactivity is inserted due to the Xenon. After this time, the Xenon concentration decreases to an equilibrium value at about 40-50 hours following the transient.

Note: As long as the candidate exhibits knowledge of the above, a number of solutions are correct, depending upon the assumptions made.

CASE 1 Explanation: In the slow downpower, more time is allowed over which Xenon will be inserting negative reactivity.

Therefore less negative reactivity must be inserted via the control rods. Therefore, the rod height to achieve 50% power

, will be higher for the slow downpower. After equilibrium is i

reached, this will result in a higher final power for the slow maneuver.

Answers:

l A. Fast will require most rod insertion B. Slow will have higher final, steady state power level C. Xenon will not reach equilibrium until 40-50 hours i following this maneuver (due to the 6.6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months half-life of the Iodine and the 9.1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months half-life of the i Xenon-135). It will therefore take 40-50 hours for -

power to stabilize following the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months maneuver.

l CASE 2 Explanation: Assuming a step decrease in power, for purposes of analyzing changes in Xenon-135 concentration, and Xenon peak occurs at time =5 hours.

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For the rapid downpower, Xenon is peaking, inserting negative reactivity. At time =2 hours, Xenon reactivity (negative) will be at a higher value than at time =10 hours. The faster downpower will, therefore, require less negative reactivity due to control rods to achieve the 50% power level. As rod height will be higher in this case, final reactor power will be higher._ It will require 40-50 hours for Xenon to reach equilibrium valua for 50% power.

Answers:

A. Slow will require most rod insertion B. Fast will have higher final steady state power C. Same as (C) above.

CASE 3 Assumption: Assume the downpower is not a step change, but a ramped change (see graph below).

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r. -

4 .

i org t, v %

With a step change in power, the Xenon concentration will peak at a given value in 5-6 hours, then dccrease to a new l equilibrium in 40-50 hours.

i l With a ramp change, the Xenon transient is less easily l predicted.

With a rapid change (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ), the Xenon burnout will drop at the same rate as the flux drops (dominant means of loss), the I-135 to Xenon-135 decay will occur with a. constant 6.6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months half-life (dominant means of production). Therefore, the Xenon peak will be lower, and will occur later (time) than with a step change.

With a slow change (10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ), the Xenon burnout will again l drop at the same rate as the flux drops (slower, in this case) l and the I-135 to Xenon-135 production will occur with the constant 6.6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months half-life. The Xenon peak will be lower still, and later (time) than in cither a step change or a rapid ramp change.

l l Therefore, the slower downpower (10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ) will have the least l amount of Xenon contributing negative reactivity.

t I

Therefore, more negative reactivity must be inserted with the control rods (i.e. rod height will be lower), and therefore final reactor power will be lower. .

Answers:

A. Slow will require most rod insertion B. Fast will have higher steady state power level C. 40-50 hours 1.08 Acceptable 1.09 This is an acceptable question, however, should also accept that steam temperature decreases, lowering cycle efficiencies.

2.01 Acceptable 2.02 A. Acceptable B. This is a valid question, however, should also accept the following impurities:

CH4, Kr, Ar, Xe, CO, (LTA is designed to remove everything except Helium and Hydrogen, with Hydrogen being removed in the Hydrogen Getter.)

Reference:

E0-065.00 pp. 11, 13-17.

2.03 A. This is a valid question, however, should accept PCRV Auxiliary cooling loop 1 or loop 2 as both loops are 100%

capacity and each should be considered as a single source of cooling.

Reference:

FH 041.00.01.05.1 B. This is a valid question, however, should also accept the out of service 46 system auxiliary loop as this is considered as a backup supply.

Reference:

FH 041.00.01.05.1 2.04 Acceptable 2.05 This is a valid question, however, should also accept the

maximum scram insertion time of 152 seconds as stated in the

, Technical Specifications.

l 2.06 Acceptable 2.07 Acceptable 2.08 Although a Reactor Operator shnuld be able to answer this

l question due to his prior qualification as an Equipment

! Operator, we feel this question is invalid as it has no direct impact on his job performance in the control room and should not be used on any future license examinations.

2.09 A. This is a valid question, however, should also accept loss of the three room complex (as defined per Technical l Specifications) with a LOFC.

1

B. This is a valid question, however, the following answers should also be accepted: Fire Protection System (System 45), Service Water System (System 42), Helium Purification Syste:a (System 23), Liquid Nitrogen System (System 25),

Purification Cooling Water System (System 47), Circulating Water Makeup System (System 41), Reserve Shutdown System (Syste a 12), Reactor Plant Ventilation System (System 73),

and Selected Plant Lighting.

Reference:

EO 087.00, pg 14.

3.01 A. Acceptable B. This is a valid question, however, the question should be reworded to ask the setpoint of the high pressure scram.

The setpoint is less than or equal to 53 psi above rated, programmed with load. Upper programmed limit set to produce trip at less than or equal to 775 psia.

Reference:

Technical Specifications, Section 3.3. Due to the fact that the master setpoint list and the design setpoint list may differ (this is true for all setpoints),

training teaches the high pressure scram setpoint as 50 psi above normal. This answer should also be accepted.

The answer of 840# is incorrect and should be removed from your answer key.

3.02 This is a valid question, however, should also accept two-loop trouble scram initiated by 4 circulator trip as this is the PPS signal that initiates an immediate turbine trip.

3.03 Acceptable 3.04 Acceptable 3.05 This is a valid question, however, the point distribution should not be limited to verbatim answers as given in the answer key. Due to the complexity of the steady state control system, the answers may be longer and more in-depth than the answer key. Therefore, the answer should be valued for the overall concept versus verbatim answers.

3.06 A. This is not a valid question. Although this was taught in class, further research showed that the statement i s; false.

This information was not relayed in time to the tuinees and NRC and this question should be thrown out. All other questions on 3.06 are valid.

3.07 This is a valid question, however, the locations are not asked in the question and should not t:e required in the answer.

3.08 A. Acceptable B. This is a valid question, however, should also accept mitigation of a large air leak at the air dryer.

3.09 Acceptable 4.01 Acceptable

4.02 Acceptable 4.03 Acceptable 4.04 Acceptable 4.05 A. Acceptable B. This is a valid question, however, should also accept adjust orifice valves to maintain equal core outlet temperatures or minimize mismatches in the core regions.

Reference:

50P 12-04, Issue 12 4.06 Acceptable 4.07 Acceptable 4.08 Acceptable 4.09 This is a valid question, however, credit should be given if the individual shows understanding of the concept stated in the answer key instead of requiring verbatim wording of an Administrative Procedure.

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ATTACHMENT 2 REVIEW OF SENIOR REACTOR OPERATOR REQUALIFICATION EXAMINATION 5.01 Same comnient as 1.01 5.02 Acceptable ,

5.03 A. Acceptable B. This is a valid question, however, should also accept reducing the irradiation of the core barrel and liner.

C. This is a valid question, however, should also accept "backscattering" in lieu of "in-leakage".

5.04 This is a valid question, however, we feel that the understanding of the concepts involved with bypass flow are more important than the key words or phrases that are listed in the answer key. Therefore, credit should be given if the individual shows understanding of the concept.

5.05 This is a valid question, however, we feel that the understanding of the concepts involved are more important than the key words or phrases that are listed in the answer key.

Therefore, credit should be given if the individual shows understanding of the concept.

5.06 This is a valid question, however, should also accept that NTC will become smaller in magnitude or NTC will have a lessening effect.

5.07 Acceptable 5.08 This is an acceptable question, however, should also accept the following answers:

10. High power production at hot spot t

11. Low helium flow at hot spot

12. High heat flux

13. Unequal coolant flow distribution within a region caused by uneven power production within a region.

1

Reference:

FSAR 3.5-14 and 3.6-5

5.09 A. This is a valid question, however, should also accept a

! closed discharge valve allows pump pressure to increase to l

operating pressure rapidly to prevent damage to the pump.

Reference:

R0 118.00, pg 16 of 34 l

B. Acceptable l

l C.01 Same cor.ments as 2.02.

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6.02 Acceptable 6.03 Same comments as 2.03 6.04 Same comments as N.09 6.05 Same comments as 3.05 6.06 Same comments as 3.06 6.07 Same comments as 3.01 6.08 Same comments as 3.02 6.09 Acceptable 7.01 A. Acceptable B. This is an invalid question, as there are a multitude of places that non-operations personnel report which are delineated in Attachment G-5A pages 11 and 12 of 12. The correct answer to this question is any one of the accountability stations.

Reference:

G-5, pg 3 of 12 (4.3.1).

C. This is a valid question, however, the understanding of the concept and not memorization of the numerical values is important, therefore, the correct answer should be: 1.

When not able to card out of the reactor building (concept). 2. When contamination is found at the exit monitor (concept). 3. When high background is present at the exit monitor (concept).

D. This is a valid question, however, should also accept determine habitability.

Reference:

GE 020.00 pg. 2 and G-5 pg. 6 step 4.5.

7.02 Acceptable 7.03 Acceptable 7.04 This is a valid question, however, should also accept any unexplained reactivity change deemed unsafe by the operator.

Reference:

EP E follow-up action 3.6 7.05 Acceptable

. 7.06 Acceptable 7.07 Same comments as 4.05 7.08 This is an acceptable question, however, we would like to have the reference.

8.01 Acceptable 1

8.02 This is a valid question, however, should also accept the following two answers.

1. HP authorization or RWP. The point values should also be equal.

Reference:

APM P3, pg 5, Issue 12, step 4.5.3

2. Category III workers as described in 5.2 references are allowed to enter RWP areas. Other personnel and visitors are allowed entry only after approval of Radiation Protection Manager or his delegate. HP must be notified prior to entry into any RWP area.

Reference:

SUSMAP 5, pg2, Issue 1, steps 3.5.1-3.5.3 8.03 Acceptable 8.04 Acceptable 8.05 This is a valid question, however, the LSO is not required to report (he would report as fire brigade member), the Technical Advisor is not required to report (would report on call out),.

and the Senior HP Technician is also required to report to the control room.

Reference:

APM G-5, pg 6, step 4.4.1 8.06 A. Acceptable B. This is a valid question, however, should also accept that the person the key was issued to will retain possession of the key until he has returned the key to the Shift Supervisor.

Reference:

SMAP 12, pg 2, Issue 2, step 4.1.2 8.07 Same comments as 4.09 8.08 Acceptable 8.09 A. This is a valid quest-len, however, the following answers should also be accepted:

1. Assure the safety of personnel working on or servicing plant equipment.

2. To notify operating personnel when equipment is not available.

3. To indicate what steps are necessary to restore the system to normal.

(Concept for all parts)

Reference:

APM P-2, pg 2, Issue 13, step 3.2.1 e

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ATTACHMENT 3 REVIEW 0F SENIOR REACTOR OPERATOR UPGRADE EXAMINATION 5.01 Same comments as 1.01 5.02 Acceptable 5.03 Same comments as SR0 Requal 5.03 5.04 Acceptable 5.05 Same comments as SR0 Requal 5.04 5.06 Same comments as SRO Requal 5.05 5.07 Same comments as SR0 Requal 5.06 5.08 Acceptable 5.09 Same comments as SR0 Requal 5.08 5.10 Same comments as SR0 Requal 5.09 5.11 A. This is a valid question, however, should also accept that due to the bi-metallic weld between EES and Superheat II is sensitive to thermal shock.

Reference:

R0 129.00, pg 17 Parts B and C are acceptable.

5.12 The discussion presented in 1.07 also applies to this question.

The answers associated with each assumption stated in part B of 1.07 are the correct answers for this question.

6.01 Acceptable 6.02 Same comments as 2.02 6.03 Acceptable 6.04 Same comments as 2.03 6.05 Same comments as N.09 6.06 Same comments as 3.05 6.07 Same comments as 3.06 6.08 Same comments as SRO Requal 5.05 6.09 Same comments as 3.01 6.10 Same comments as 3.02

6.11 Acceptable 6.12 Acceptable 7.01 Same comments as SR0 Requal 7.01 7.02 Acceptable 7.03 Acceptable 7.04 Same comments as SR0 Requal 7.04 7.05 Acceptable 7.06 Acceptable 7.07 Same comments as 4.05 7.08 Acceptable 7.09 Acceptable 7.10 Acceptable 7.11 Acceptable 8.01 Acceptable .

8.0? Same comments as SR0 Requal 8.02 8.03 Acceptable 3.04 Acceptable 8.05 Same comments as SRO Requal 8.05 8.06 Same comments as SRO Requal 8.06 8.07 Same comments as 4.09 8.08 Acceptable 8.09 Same comments as SR0 Requal 8.09 8.10 Acceptable 8.11 This is an invalid question as rote memorization of the Technical Specifications is not a requirement of the Senior .

Reactor Operator. However, the recognition and interpretation of Technical Specifications is a requirement of the Senior Reactor Operator. Therefore, future questions regarding Technical Specifications should be on recognition and j interpretation and the Technical Specification should be available for reference.

8.12 Same comments as 8.11.

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r ATTACHMENT 4 REVIEW OF SPECIAL SENIOR LICENSED OPERATOR (FUEL HANDLER) EXAMINATION Evidently there is a discrepancy in the category values between what is stated in the PSC TPAM and the values on this examination.

Our values are:

Category M - 20% i 5%

Category N - 20% 15%

Category 0 - 30% i 5%

Category P - 15% i 5%

Category Q - 15% 15%

REVIEW OF QUESTIONS AND ANSWERS Category M M.01 Acceptable M.02 Acceptable, however, reference probably should be FH 039.00, pages 2-4 (same comments as 1.01, R0 Requalification).

M.03 Same comments as 5.02, SR0 Requalification M.04 Acceptable M.05 Same comments as SRO 5.05)

M.06 Acceptable, however, answer contains a typographical error which should read: c,a,b,[ orth-232,U-235, U-233] (Note:

U-235 was listed twice)

M.07 Acceptable M.08 Acceptable Category N N.01 Acceptable - Reference probably should be FH 049.00, pages 11-13 instead of past examination question FH 049.00.01.05.5.

This would allow using both objective FH 049.00.01.05 and FH 049.00.01.06 as references for answers. This question utilizes both objectives.

N.02 Acceptable

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N.03 Question and answer as stated are incorrect. However, the intent is valid. Question wording asks for information which is partially variable. Question should ask for:

1) Maximum capacity in fuel elements (4 outer columns X 14

_ fuel elements per column = 56 fuel elements maximum).

Fuel may only be stored in outer columns. Fuel is only full length.

2) Maximum equivalent capacity in reflector elements (all 5 columns X equivalent of 14 full length. elements = 70 equivalent full length reflector elements, assuming FSW only held reflector and no fuel). Reflector may be stored in all 5 columns (4 outer plus center), and reflector could be full, half, or three-fourths length elements.

ANSWER as stated is incorrect. Total well capacity is the equivalent of 70 full length elements, with a maximum of 56 fuel elements. Fuel is only full length elements. Reflector length can be full, half, or three-fourths length.

A better reference is FH 041.00, page 7.

N.04 Question does not apply to fuel handler duties. An extra sheet (attachment 2) was enclosed with letter P-86318, which stated

" Fit 034.00 is given as information only, as helium circulator internals do not pertain to licensed fuel handlers. No test i was given for this lesson plan." This lesson plan was presented at the option of the fuel handler candidates purely out of their interest in knowledge of the overall reactor t system at Fort St. Vrain and will not be included in fuel handler training in the future.

N.05 Acceptable -

same comments as 6.01. Also reference stated is incorrect. Reference should be FH 035.00, pages 4-9. Answer a.4. should be "...for PCRV penetration interspaces."

l N.06 Acceptable l

[ N.07 Acceptable N.08 Same comments as 6.03, SR0 Requalification N.09 Acceptable. Reference should be FH 044.00.01.03.1 and FH I 044.00.01.04.1. In addition, FH 043.00.01.03.1 shows that the l HSF floor drains discharge through System 61 (decontamination system), and by valve alignment can be drained to a draining station, routed for recycle of system 61, or discharged to the .

liquid waste sump. Therefore, any of these answers is acceptable.

I N.10 Acceptable I

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Category 0 0.01 Acceptable 0.02 Acceptable 0.03 Acceptable 0.04 Acceptable 0.05 Question as stated is incorrect. However, the intent is valid.

The question should read "... Reactor isolation valve..."

Answer as referenced in FH 049.00, pages 10 and 11 was placed in the referenced sequence to aid clarity. The only two critical sequential steps are: RIV power supply cable must be connected before seal source helium hose for pneumatic seals.

The other steps were listed only to identify the actions and need not be sequential.

0.06 Acceptable 0.07 Question as stated is incorrect. Should be "What are the four (4) steps required..."

0.08 Acceptable. It is important to note that these steps are presented in detail in the Fuel Handling Procedure checklists and are in actuality not necessary to memorize since they are checked off sequentially as performed when setting an RIV as per the FHP. For example: c and e could be performed at the same time, and g could be performed after h.

i j 0.09 Acceptable Category P P.01 Same comments as SR0 8.11 P.02 Acceptable P.03 Acceptable P.04 Question acceptable. Answer c. should be "... advise or facility hazard..."

P.05 Acceptable l

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- , - . . ,-,_._ ._m. - _ _ , , __m_____ _ _ . . _ _ _ _ , . - , _ . . . . , _ . . . _ . _ , _ _ _ . . _ _ . - _ _ _ _ _ _ _ _ _ _ _ - , _

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P.06 Question acceptable. However, answer b. must be clarified for Servo error. A Servo error indicates that the difference is too great between commanded and actual machine position, or words to that effect. The circuit utilizes only analog signals and not digital in this instance. Therefore, the answer referenced by question FH 051.00.02.02.1 is correct axcept

"(analog and digital positions do not agree)" and in the future will be corrected for that question. The information in the lesson is correct and should be used for the reference.

Reference is FH 050.00, page 50.

P.07 Acceptable P.08 Acceptable P.09 Question as stated is incorrect. However, the intent is applicable. The question should read, "What two fuel handling related systems ..." in order to get the referenced answer. As written, the possible answers to this question could be any two of the following per Emergency Procedure H-3, Section 2.1.

a) System 63, Radioactive Gas Waste b) System 23, Helium Purification c) System 11, PCRV Auxiliary Piping d) System 13, Fuel Handling Purge e) System 14, Fuel Storage Building f) System 21, Helium Circulator Auxiliaries g) System 22, Secondary Coolant (SJAE and HRH)

P.10 Question acceptable. Answer as stated is incomplete. Answer per FH 035, Pages 23 and 24 is that HTFA is utilized to cool helium flowing through HTFA (during depressurization) by insertion of pipe spools to utilize System 46 PCRV cooling water to cool the helium. This in turn protects other helium purification system components from the high temperatures at a LOFC during depressurization. Normal helium purification and depressurization helium flowpath is through HTFA.

Category Q Q.01 Acceptable Q.02 Acceptable Q.03 Acceptable Q.04 Acceptable Q.05 Acceptable Q.06 Acceptable Q.07 Question acceptable. Answer 3. as stated is incorrect, and should be job cancelled. Job completed, which is redundant to

2. Reference should be FH 058.00, Page 15.

Q.08 Acceptable Q.09 Acceptable l

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