Text

NRC Operator Licensing Exam Repts 50-313/98-302 & 50-368/98-302 for Tests Administered on 980914-18.Overall, Operator License Applicants Demonstrated Good Performance & Use of Good Communication Practices,As Well as Peer Checks
	ML20154H058
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/08/1998
From:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	;
Shared Package
ML20154H043	List: ML20154H040; ML20154H058;
References
	50-313-98-302, 50-368-98-302, NUDOCS 9810140065
	Download: ML20154H058 (150)
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ENCLOSURE

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U.S. NUCLEAR REGULATORY COMMISSION

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REGION IV

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Docket Nos.:

50-313;50-368

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License Nos.:

DPR-51; NPF-6

Report No.:

50-313/98-302;50-368/98-302

Licensee:

Entergy Operations, Inc.

- Facility:

Arkansas Nuclear One, Units 1

Location:

Junction of Hwy. 64W and Hwy. 333 South

Russelville, Arkansas

Dates:

September 14-18,1998

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Inspector (s):

T.O. McKernon, Chief Examiner, Operations Branch

S. L. McCrory, Senior Examiner, Operations Branch

M. E. Murphy, Senior Examiner, Operations Branch

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R. E. Lantz, Examiner, Operations Branch

Approved By:

John L. Pellet, Chief, Operations Branch,

Division of Reactor Safety

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ATTACHMENTS:

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Attachment 1:

Supplemental Information

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Attachment 2:

Facility initial License Written Examination Comments and Analysis

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Attachment 3:

Final Written Examinations, Answer Keys, and Proctor's Comments

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EXECUTIVE SUMMARY

Arkansas Nuclear One, Units 1 and 2

NRC Inspection Report 50-313/98-302; 50-368/98-302

NRC examiners evaluated the competency of 6 reactor operator and 6 senior operator

applicants for issuance of operating licenses at the Arkansas Nuclear One, Unit 1 facility. The

licensee developed the initial license examinations using NUREG-1021, " Operator Licensing

Examination Standards for Power Reactors," Interim Revision 8. NRC examiners reviewed,

approved, and administered the examinations. The initial written examinations were

administered to all 12 applicants on September 11,1998, by facility proctors in accordance with

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instructions provided by the chief examiner. The NRC examiners administered the operating

tests on September 14-17,1998.

Operations

Five of six applicants for reactor operator licenses and all six applicants for senior

operator licenses displayed the requisite knowledge and skills to satisfy the

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requirements of 10 CFR Part 55 and were issued the appropriate licenses

(Sections 04.1,04.2).

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Overall, the operator license applicants demonstrated good performance and use of

good communication pract;ces, as well as, peer checks (Section 04.2).

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The licensee initially failed to submit an acceptable examination for administration to

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operator license applicants for the operating test portion of the examinations. Several

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revisions by the licensee were required to produce a product which satisfied

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examination standards (Section 05.1.2).

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Report Details

Summary of Plant Status

Both units operated at essentially 100 percent power for the duration of this inspection.

1. Operations

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04

Operator Knowledge and Performance

04.1

initial Written Examination

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a.

Insoection Scope

On September 11,1998, the licensee proctored the administration of the written

examination approved by the NRC to six individuals who had applied for initial reactor

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operator licenses and six individuals who had applied for senior operator licenses. The

licensee graded the written examinations and its staff reviewed the results. The

licensee also performed a post-examination question analysis, which was reviewed by

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the examiners.

b.

Observations and Findinos

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The minimum passing score was 80 percent. All except one applicant for a reactor -

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operator license passed the written examination. Scores for the reactor operator

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applicants ranged from 74.7 percent to 90.9 percent. All applicants for senior operator

licenses passed with scores ranging from 81.6 to 91.8 percent. The average score for

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reactor operator applicants was 83.7 percent and the average score for senior operator

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applicants was 85.7 percent.

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The above grades reflected the results after examination changes recommended by the

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licensee as a result of post-examination question analysis were incorporated. The

examiners reviewed and accepted these recommendations based on the technical

merits of each recommendation. As a result of this analysis, two choices were accepted

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for one question (RO 91, SRO 87) because the wording in choice "b" was also a true

statement for the conditions given in the question stem. Also, Questions RO 90,

S30 85, and SRO 71 were deleted because no correct choice esisted. The answer for

SRO question 50 was changed to choice "b" to correct a typographical error on the

answer key. Additionally, the SRO Question 64 correct choice was changed to "c"

because of the conditions stated in the question stem.

c.

Conclusions

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All except one reactor operator applicant passed the written examinations

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04.2 Initial Operatina Test

a.

Inspection Scope

The examiners administered the various portions of the operating test to the

12 applicants on September 14-17,1998. Each applicant participated in 1 or 2 dynamic

simulator scenarios. Each applicant also received a walkthrough test, which consisted

of either 10 or 5 system tasks, depending on application type, with 2 followup questions

for each task. The applicants also received an operating test administrative portion

consisting of tasks or questions related to 5 subjects in 4 administrative areas.

b.

Observations and Findinas

All applicants passed all sections of the operating test. The applicants generally

performed well and used good communication practices and peer checks. The

applicants exhibited good plant knowledge and ability to find components when asked.

The examiners observed good plant awareness, ownership, and application of principles

for self verification by the applicants throughout the examination.

c.

Conclusions

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All applicants passed all sections of the operating test. Overall, the license applicants

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demonstrated good performance and use of good communication practices, as well as,

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peer checks.

05

Operator Training and Qualification

05.1

Initial Licensina Examination Develooment

The licensee developed the initial licensing exami.."on in accordance with guidance

provided in NUREG-1021.

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05.1.1 Examination Outline

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Inspection Scoce

The licensee submitted the initial examination outline on May 15,1998. The examiners

reviewed the submittal against the requirements of NUREG-1021.

b.

Observations

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The chief examiner provided enhancement suggestions related to examination integrity

and responsiveness to NUREG-1021 requirements, which were incorporated by the

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licensee into the written examination outline. The chief examiner noted that the written

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examination distribution differed from that of Examiner Standard ES-401. The licensee

stated that the differences were due to site specific characteristics and attributes. The

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submitted scenario outlines contained malfunctions associated with immediate or

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submitted scenario outlines contained malfunctions associated with immediate or

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automatic reactivity actions, which were responses to abnormal conditions such as a

dropped control rod. The chief examiner explained to the licensee that operator actions,

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such as recovery of the dropped rod, would be required for credit as a required reactivity

manipulation. The licensee stated that the scenarios would be reviewed and power

maneuvers would be added where appropriate. The administrative test portion of the

examination outlines contained a mix of job performance measures and questions,

which did not meet the predominant "open reference" criteria of NUREG-1021. The

licensee agreed to incorporate enhancement suggestions into the examination outlines

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and submit the revised outlines along with the proposed examinations on July 16,1998.

The chief examiner noted that the revised outlines for the operating test portion of the

examination did not satisfy the requirements of NUREG-1021. For example, the

licensee took credit for reactivity manipulations by the reactor operator on a manual

reactor trip, which was not a controlled evolution and, therefore, did not satisfy Examiner

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Standard ES-301-5, " Transient and Event Checklist." The chief examiner provided

further revisions to the draft examinations prior to use, as described below.

c.

Conclusions

The licensee submitted final revised examination outlines on July 16,1998. The revised

outlines for the operating test portion of the examination did not fully satisfy the

requirements of NUREG-1021 and the resulting examinations were modified prior to

use.

05.1.2 Examination Packaae

a.

'nspection Scoce

The licensee submitted the initial examination package on July 20,1998. Because of

extensive NRC .umments on the initial operating test submittal, the licensee submitted a

revised operating test package by September 10,1998, following an onsite review by

the examiners during the week of August 17,1998. The chief examiner reviewed the

submittal against the requirements of NUREG-1021.

b.

Observations and Findinas

The licensee submitted 130 draf t written examination questions, of which 57 were

designated to be common to both the reactor operator and senior operator

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examinations. The chief examiner provided comments or questions on 12 of the

130 questions. Additionally, the licensee performed internal audits, which identified

enhancements to another 23 questions. The majority of changes made to the questions

were changes to question stems and choices, which helped to clarify areas. Although

failure to make the above changes would not have invalidated the written examinations,

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it would have degraded their discriminatory value. The written examinations were

adequate for administration.

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The licensee submitted five dynamic scenarios, including one backup scenario, which

was not used during the examination. The submitted scenarios were not adequate for

administration. In some of the scenarios, emergency actions were credited as reactivity

manipulations, such as the reactor trip push-button failure to trip the reactor. In other

scenarios, component malfunctions were credited as instrument malfunctions and vice

versa. Other instrument malfunctions required no active operator responses, only

recognition and monitoring redundant instruments providing little or no discrimination.

These and other comments on the scenarios were discussed with the licensee during

the examination onsite review.

The licensee submitted four sets of the administrative portion of the test. Two sets were

intended for the reactor operator applicants and two sets for the senior operator

applicants. While most of the job performance measure tasks in the administrative test

were adequate, prescripted questions were predominantly testing at a low cognitive

level and required revision or replacement. The licensee revised the administrative

portion of the examinations and incorporated several chief examiner enhancement

suggestions.

Similarly, the system portion of the examination was inadequate for administration. The

majority of the job performance measure followup questions were at a low cognitive

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level and did not meet the requirements for open reference questions. Additionally,

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some job performance tasks referenced inaccurate reference material. Further, some

followup questions required multiple answers, but did not indicate the criteria which

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constituted an acceptable response. Finally, other job performance measures

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overlapped with tasks performed during the dynamic scenarios.

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As a result of the above comments, the licensee resubmitted the operating portion of the

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examination by September 10,1993. The revised examination materials satisfied

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NUREG-1021 requirements and were of good quality.

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c.

Conclusions

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The licensee initially failed to submit an acceptable examination for administration to the

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operator license applicants for the operating portion of the examination. The final as-

given examination met the requirements of NUREG-1021 and was considered good

quality.

05.1.3 Licensina Conditions

a.

Inspection Scope

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The chief examiner reviewed the final applications as submitted by the facility for the

license applicants against the requirements of NUREG-1021, Interim Revision 8.

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The chief examiner verified that the facility licensee properly identified the required five

significant reactivity manipulations on the applications. The chief examiner also verified

that the facility had properly documented these manipulations and that they were

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significant in accordance with NRC Information Notice 97-67,

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Conclusions

The facility's program was adequate to ensure that initial license applicants satisfied the

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requirements for performance of significant reactivity manipulations.

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05.2 Simulation Facility Performance

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a.

Insoection Scope

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The examiners observed simulator performance with regard to fidelity during the

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examination validation and administration.

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Observations and Findinas

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The simulation facility supported examination administration well, No modeling

deficiencies were observed during performance of dynamic job performance measure

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tasks or dynamic scenarios.

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c.

Conclusions

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The simulation facility supported examination administration well.

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05.3 - Examination Security

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a.

Scope

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The examiners reviewed examination security both during onsite preparation week and

examination administration week for compliance with NUREG-1021 requirements.

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b.

Observations and Findinas

During onsite preparation the week of August 10,1998, the examiners observed that

examination security was generally good. However, one individual involved in the

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preparation of some of the operating examination had left the facility prior to the onsite

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preparation week. The licensee's compensatory measures were appropriate. Further,

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the chief examiner did not consider this a significant concern since the proposed

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operating examination required significant revision after the individual's departure.

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c.

Conclusions

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The licensee adequately controlled examination material to preserve examination

integrity.

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V. Management Meetings

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Exit Meeting Summary

' The chief examiner presented the inspection results to members of the licensee

management at the conclusion of the inspection on September 17,1998. The licensee

acknowledged the findings presented.

The licensee did not identify as proprietary any information or materials examined during

the inspection.

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ATTACHMENT 1

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PARTIAL LIST OF PERSONS CONTACTED

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Licensee

G. Giles, Operations Training Supervisor

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M. Goad, Operations Training .

R. Fuller, Unit 1, Operations Manager

R. Byford, Operations Training

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L. McLerran, Simulator Training Supervisor

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S. Cotton, Director Training / Emergency Preparedness

C. Zimmerman, Unit 1, Plant Manager

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ATTACHMENT 2

FACILITY INITIAL LICENSE EXAMINATION

COMMENTS AND ANALYSIS

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1998 ANO- linit i NRC RO License Exam Analysis

RO Examination Analysis Summary

The exammation was admimstered to six RO candidates. The following chan summarizes the candidates

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responses to questions on the examination:

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6of6

5 of 6

4 of 6

3 of 6

2 of 6

l of 6

Oof6

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CORRECT

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13

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An analysis was performed on the 13 questions incorrectly answered by 2 50% of the candidates. Analysis

results are summarized below.

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No.

Analysis Results:

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Question and answer are correct as written. (4 of 6 incorrect)

0046

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A condition will be added to stem prior to reuse, but the correct caswer can be

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determined as written. (3 of 6 incorrect)

0053

44

Question and answer are correct as written. (3 of 6 incorrect)

0063

51

Question and answer are correct as written. (3 of 6 incorrect)

0065

53

Question and answer are correct as written. (4 of 6 incorrect)

0068

54

The question will be revised prior to reuse, but the correct answer can be

determined as written. High difficulty level. (6 of 6 incorrect)

0088

70

Question and answer are correct as written. High difficulty level.

(4 of 6 incorrect)

0090

72

Question and answer are correct as written. (3 of 6 incorrect)

0094

76

Question will be revised prior to reuse, but the correct answer can be determined as

written. (3 of 6 incorrect)

0112

90

Question deleted. See attached response. (5 of 6 incorrect)

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91

Answer "B" accepted as correct in addition to answer "D" See attached response.

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(5 of 6 incorrect)

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92

Question and answer are correct as written. Training Evaluation Action Request

written to ensure the information is included in the License Class Training

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Program. (5 of 6 incorrect)

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96

Initial condition clarified during examination administration. Master exam pen

and ink changed. Question and answer correct as modified. (3 of 6 incorrect)

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Qll) Hil 2 \\ \\ \\l.) 515

R() Esam Questi<m 40 5R()tl i Esam Question 85

Question:

During a FW transient. the CBOT manually controls FW to stabilize the plant.

RN pow er is 1015% for approximately 10 mmutes while the plant is brought under control.

Is this acceptable or unacceptable?

This is acceptable to mitigate transients for short periods of time per Conduct of Operations.

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b Dis is unacceptable due to limitations on our fuel as specified by Babcock & Wilcox.

This is acceptable for short periods of time as specified by NRC correspondence with Licensing.

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d This is unacceptable due to exceeding the maximum thermal output in our operating license.

Answer:

d Tius is unacceptable due to exceeding the maximum thermal output in our operating license.

Exam Analysis Results:

Delete question due to no correct response as written.

Justification:

The original intent of the question was to reinforce management expectations concerning "brief" excursions

abos e 100% power.

I102.004. Power Operations. Section 5 0. Limits and Precautions, Step 5.1, states:

the average shitiJidl steady state pon er level over any 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months permd shall not exceed the hcensed power

level (25M MWt) It as never permissible to mtentionally operate at greater than 100% heat balance power.

It is not a vwlatwn ofthis requarement of100% heat balance power is briefly exceeded, but. m no case

shmdd 102% he exceeded. There are no limits on the number oftimes these excursions may occur; or the

nme mierval that must separate such excurswns, except the averagefidi steady heat balance pon er level

over any eight hour period shall not exceed the hcensed power level of 2568 MW1.

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The stem of the question describes a transient condition. The licensed power level limitation of 2568 MWt is

applicable for steady state conditions. Power limitations during transient conditions are bounded by the

safety at 11vsis. In addition, the candidate could calculate the average power over an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period of time

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based on power at 101.5% for ten minutes and power remaining at 100% for the remainder of the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

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period and not exceed average power limits per Reactor Power History, Tilt and Imbalance Log.

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Therefore. thoe it no correct response to the question as written.

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INITIAL RO/SRO EXAM CANK QUESTION DATA

ARKANSAS NUCLEAR ONE - UNIT 1

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QlD: 0112

Rev: 0

Rev Date: 6/29/98

Source: New

Originator: JCork

TUOl: ANO-1-LP RO NOP

Objective: 7.4

Point Value: 1

Section: 2.0

Type: Genenc K/As

System Number: 2.1

System Title: Conduct of Operations

Description: Knowledge of conditions and limitations in the facility license.

K/A Number: 2.1.10

CFR Reference: CFR: 43.1/ 45.13

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Tier:

3

RO Imp:

2.7

RO Select:

Yes

Difficulty: 4

Group: G

SRO Imp: 3.9

SRO Select: Yes

Taxonomy: Ap

Question:

During a FW transient, the CBOT manually controls FW to stabilize the plant.

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Rx power is 101.5% for approximately 10 minutes while the plant is brought under control.

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is this acceptable or unacceptable 7

a. This is acceptable to mitigate transients for short penods of time per Conduct of Operations.

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b. This is unacceptable due to limitations on our fuel as specified by Babcock & Wilcox.

c. This is acceptable for short periods of time as specified by NRC correspondence with Ucensing.

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d. This is unacceptable due to exceeding the maximum thermal output in our operating license.

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Answer:

d. This is unacceptable due to exceeding the maximum thermal output in our operating license.

Notes:

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Answer (d) is the only correct response.10 minutes far exceeds a "brief" moment during transient conditions.

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The other answers are wrong due to being non-conservative.

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References:

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1102.004 (Rev 38), Power Operations. Limits and Precautions, page 6.

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History:

Developed for 1998 RO/SRO exam,

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8RCC.tt'ORK PLAN NO.

PRCCEDUREWOR;t PLNe TITLE:

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38

POWER OPERATION

1103.004

CHANGE:

4.3

NFC COMMITMENTS

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5.0

.IMITS AND PRECAUTIONS

5.1

The average shift full steacy power level over any eight hour period

shall not exceed the 11censeo power level (2568 MWel.

It is never

permissible to intentionally operate at greater than 100% heat balance

power.

It is not a violation of this requirement if 100% heat balance

in no case should 102% be exceeceo.

power is.briefly exceecec, cut,

There are no limits on the numoer of times these excursions may occur;

or the time interval that must separate such excursions, except the

average full steady heat calance power level over any eight hour

period shall not exceed the licensed power level of 2568 MWt.

5.2

Maintain power imbalance at or near zero unless otherwise specified by

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Reactor Engineering staff.

Power imbalance outside the envelopes

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defined in Attacnment M shall be limited to less than four hours.

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Tech Spec 3.5.2.6.

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5.3

To minimize power tilts, maintain red positions within a group at

same level.

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5.4

The reheat temperature should not be allowed to step change >250*F/hr.

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5.5

observe limits and precautions of referenced operating procedures.

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annunciates, observe the computer

5.6

M POWER DISTRIBUTICN ALARM (K08-D4)

alarm CRT message to determine the affected parameter.

5.6.1

y a limit is exceeded, either bring affected parameter

within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per Tech Specs 3.5.2.4 thru

3.5.2.6 og take action specified by applicable Tech Spec.

5.6.2

If necessary, ::ntact Peacter Engineering fer assistance,

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The Teen Spec h:r.it en quacrant : lt measureo cy One incere monitoring

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system plant ::=puter, ;s variacle as follcws:

EFFD

Til: *imit

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0 to 250 : 10

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250 2 10 to ECC

4.00

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These values incluce inaccuracles in the inects monitoring system

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(Tech Spec 3. 5.2. 4 ) .

The incere monitoring system, using the plant

computer, is the most accurate method of monitoring quadrant t;lt.

ey monitoring both incere and execre tilt.

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Tech Spec compliance is met

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PROC NecRC1 PLAN NO

PROCEDUREN,GRK PLAN TITLE.

PAGE.

16 of 69

109 5.003 A

UNJT 1 OPERATIONS LOGS

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Rea: Or Bu11cing Pressure Instrumentation

NOTE

The ECCS safety analysis assumes a pre-accident Reactor Building pressure no

lewer than -1 psig (13.7 psia).

However, the Jower limit specified in Tech

Spec is lower than this,

-2.7 psig (12 psla).

A Tech Spec change is in

progress to correct this inadequacy.

Tnere are 3 sets of instruments monitoring RB pressure; each set has

d;fferent instrument error characteristics.

To protect the assumptions of

the safety analysis, we average the set with the least error: RPS instruments

?!-2400 nru PI-2403) and take instrument error into account.

The average

value is used in order to reduce the band required for instrument error.

Cn the logsheets, the RB pressure limits are shown with no error calculated

for ESAS and wide range instruments, because the addition of instrument error

would make the lower limit higher than the normal RB pressure.

A.

If the average of the operable RB Pressure indicators

(PI-2400, 2401, 2402, 2403) is <-0.64 psig, or

>2.64 psig, enter LCO 3.6.4 and write a Condition

Report.

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9.2

Instructions for Reactor Power History, Tilt, and Imbalance Log

(OPS-AB)

9.2.1

The everage power level for any eight hour period should

not exceed the licensed power level (2568 Mwt).

It is

never permissible to intentionally operate at greater than

100.0% heat balance power.

It is not a violation to

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briefly exceed 100.0% heat balance power, and there are

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neither limits on the number of, nor the time intervals

separating such excursions.

However, in no case should

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102% be exceeded.

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9.2.2

Use Function NASP, N3, 6; Imbalance, Tilt, and Red !ndex

for imbalance and quadrant tilt readings.

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9.2.3

If the Plant Computer is inoperable, take logs in the

following alternate manner:

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A.

Commence taking Alternate RX Power History, Tilt and

Imbalance Log (OPS-A21) and make a comment stating

such on log OPS-AB.

B.

Heat Balance Power shal'. Se determined at least once

per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months by performing a manual heat balance

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calculation per 1103.016.

Enter results in the

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comments section of OPS-A21.

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C.

Calculate Average NI Power and Shift Average NI Power

from Nuclear Instruments on C03.

D.

Determine Tilt and Imbalance as follows:

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Log out-of-core imbalance using Nuclear

Instruments en C03.

QlD 0ll4

RO Esam Question 91/ SROttl Esam Question 87

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. Question:

Which of the following actions involving a hold carded MCC breaker is allowable per 1000.027, Hold and

Caution Card Control?

a.

Remoung "a" and "b" contact terminations.

b.

Rackmg a breaker in and out but not closing it.

c.

Leaving the door open as long as breaker is removed.

d.

Performing a PM to lubricate contacts.

Answer:

d.

Performing a PM to lubricate contacts.

Exam Analysis Results:

Accept answers (b) and (d) as correct responses.

Justification:

,

The (b) distracter uses wording that is unclear. At ANO,480V MCC breakers are hold carded as " Breaker

Open/ Removed" For 480V MCC breakers, the term " racking"is synonymous with " removing". A 480V

)

MCC breaker is removed from its cubicle by the act of racking it out. It is a permissible to remove a hold

carded MCC breaker from its cubicle in accordance with 1000.027, Hold and Caution Card Control, Step 7.5,

which states:

Ifa Carded AfCC breaker must be removedfrom its cubicle, then the Craft shall coordinate with Operations

to perform thefollowing:

Obtam CRSpermission to remove the breaker and move CARD as necessary.

e

Remove breaker ""~nts cubicle ensuring the breaker remains open at all times.

Re-attach the CARD to the exterior breaker door as required to ensure the CARD remains at the

AfCC door.

A Carded cubicle breaker may not be remstalled unless the craftsperson installing the breaker is the

,

e

only one left on the tagout or the tag has been cleared.

Therefore, (b) is a correct response in addition to (d).

i

_=~

.

-=.= =.= = - -

INITIAL RO/SRO EXAM DANK CUESTION DATA

ARKANSAS NUCLEAR ONE - UNIT 1

biDI'0114

Rev: 0

Rev Data: 7/13/98

Source: New

Originator: JCork

TUOI: AA30001005

Objective: 3

Point Value: 1

-

Section: 2.0

Type: Generic K/As

System Number: 2.2

System Title: Equipment Control

Description: Knowiedge of tagging and clearance procedures.

K/A Number: 2.2.13

CFR Reference: CFR: 41.10 / 45.13

Tier:

3

RO Imp:

3.6

RO Select:

Yes

Difficulty: 4

Group: G

SRO Imp: 3.8

SRO Select: Yes

Taxonomy: Ap

Question:

Which of the following actions involving a hold carded MCC breaker is allowable per 1000.027, Hold and

Caution Card Control?

a. Removing "a* and "b" contact terminations.

b. Racking a breaker in and out but not closing it.

c. Leaving the door open as long as breakeris removed.

d. Performing a PM to lubricate contacts.

Answer:

d. Performing a PM to lubricate contacts.

Notes:

"D" is permissible since it is routine maintenance which doesnt require breaker oper -' ion.

"C" is not alkmed even though the breaker is removed, connections intemal to cubicle would be exposed.

"A" is incorrect, maintenance is not permitted on a hc!d carded breaker.

B" is wrong since breaker operation is not allowed, even just racking it up or down.

References:

1000 027. Hold and Caution Card Control Rev. 24, pages 12 & 13

History:

Developed for 1998 SRO/RO exam

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rpoc /wca t w No.

Facczoenz/wcRx r w ; m.E:

PAst:

11 of 56

REY:

24

1000.027

HOLD AND CAUTION CARD CONTROL

GDWGE :

-

~AFDS ON ELECTFICA* EQU:FMENT

7.1

All grounding devices shall,be Carded with the tag conspicuously hung on

the grounding device and shall specify GROUNDING DEVICE INSTALLED.

i

l

7.2

CARDS for load center breakers should specify BREAKER RACKED OUT and

l

should be hung on the cubicle door.

The breaker may be removed or

reinstalled as long as the breaker does NOT get racked i~.

j

i

7.3

CAPDS for MCC breakers should specify BREAKER OPEN/ REMOVED and should bc

)

l

hung on the exterior breaker door.

{

\\

for breakers with lights on the breaker door, the operator shall

i

e

check the light indication before and after hanging the CARD to

ensure the breaker mechanism has actually opened the breaker.

For breakers without light indication, then alternate methods should

be utilized such as checking remote light indication or opening the

MCC breaker door and verifying breaker position.

7.4

Switchgear Breakers

r

e

CARDS for 2A9 Switchgear should specify BREAKER RACKED OUT and should

'

be hung on the cubicle door.

The breaker may be removed or installed

as long as the breaker does NOT get racked in.

For ESF switchgear breakers (A3, A4, 2A3 and 2A4), BREAKER RACKED

.

e

DOWN means the breaker has been racked down to the floor then racked

f

{3.3.7)

up -1"

off the floor.

This will ensure the seismic analysis of the

i

ESF switchgear is maintained,

i

e

CARDS for switchgear breakers other than 2A9 should specify BREAKER

RACKED DOWN, and should be hung near the elevator engagement lever.

The breaker may be removed from or be reinstalled in its cubicle as

long as the breaker does NOT get racked up.

~.5

If a Carded MCC breaker must be removed from its cubicle, then the Craft

snall cc rdinate witn Operations to perform the following:

,

.5.1.

Obta:n CPS permission to remove the breaker and move CARD as

necessary.

7.5.2.

Remove breaker from cubicle ensuring the breaker remains open

at all times.

7.5.3.

Re-attach the CARD to the exterior breaker door as required

to ensure the CARD remains at the MCC door.

7.5.4.

A Carded cubicle breaker may not be reinstalled unless the

craftsperson installing the breaker is the only one left on

the tagout or the tag has been cleared.

".6

If a bus is deenergized for breaker PMs, the CARDS may be removed using

Electrical Bus Hold Card Authori:ation Addendum (1000.027N).

l

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~ _ _

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

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pwc /wcom e.AN wo.

i rRoctrt Rz,wCRK r".AN T!rl.E.

PAGE:

12 Of N

REV:

24

1000.027

HOLD AND CAUTION CARD CONTROL

dpSGE:

1

f

7.7

A Carded MCC breaker may have its cubicle door opened to perform

!

ins p e c t.i ons , limited cubicle maintenance, or insulation resistance

testing provided the following conditions are met:

,,

!

7.7.1.

Activities involving actual terminations to a melded case

breaker in an MCC cubicle shall be performed with the breaker

disconnected from the bus (in its test position with locking

tabs in place) or removed from the MCC.

l

7.7.2.

INSPECTION ACTIVITIES

The person wants the door opened for inspection purposes

l

!

only.

This activity will not cause accidental closure of the

breaker

(i.e.,

look only).

!

7.7.3.

LIMITED MAINTENANCE ACTIVITIES

l'

l.

The person wants the door opened for activities agreed to

l

by the CRS as minor in nature.

!

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2.

When work is complete, the individual verifies the

breaker is still in the position specified on the CARD

!

and the door is reclosed.

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7.7.4.

INSULATION RESISTANCE TESTING

i

1.

The Craftsperson performing the insulation resistance

test must notify his/her supervisor for concurrence.

'

2.

The cognizant supervisor shall review all CARDS attached

to the Cubicle to determine if any associated work or

workers might be at risk due to accidental energization,

and take actions necessary to prevent injury.

l

3.

If any associated work is identified (CARDS hung)

{

allowing unrelated work on power cables, penetrations,

terminal boxes or other items that may be energized by

the insulation resistance test, then a.e cognizant

supervisor must determine appropriate action to ensure

worker safety. This might include posting a safety man

at the affected area, contacting the other work crew,

,

obtaining a temp clear or performing the insulation

resistance test later.

4.

Station a safety person at *.ho load powered by the

circuit breaker if it is in an accessible area.

5.

The circuit breaker remains open at all times.

t

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6.

When work is complete, the individual verifies the

breaker is still in the position specified on the CARD

and the door is reclosed,

i

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6

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mocEctimwcR:t 31M TITLE

PAGE;

13 of 56

RE*C

24

1000,027

HOLD AND CAUTION CARD CONTROL

auscE:

~.s

When a switchgear test / ground creaker is being racked up or down, then

inat brea<er location shal. NCT te used as an isolation boundary.

Any

HOLD CAPD on that breaker location shall be released.

7.9

CARDS for switchgear test / grounding breakers should specify BUS GROUNDED

or LINE GROUNDED as applicable, and should be hung on the operating

handle on the breaker face.

7.10

CARDS should be hung so that normal, safe maintenance of breakers and

cubicles, that does NOT tamper with the isolation condition, may be

performed.

'.11

Conductive materials, such as wire, shall not be used for attaching

CARDS on or near electrical devices.

7.12

When fuses are to be pulled for CARD installation, Electrical

Maintenance should be contacted to remove any fuse if the circuit

voltage is greater than 150 VAC or 150 VDC.

!

7.13

During special conditions or testing when there is essentially no risk

to personnel, equipment, or plant operations, control switches may be

carded to prevent operation.

l

~.14

4160V and 6900V breaker control switches may be used to provide

equipment protection only.

This is intended for short term usage.

For

J

long term equipment protection, consideration should be given to racking

down breaker.

7.15

CARDS on control switches shall NOT provide the only barrier for

personnel and equipment protection unless no other plausible isolation

methods are available.

Consider using other methods to provide physical

l

restraint or isolation in addition to the control switch.

control switch provide the only barrier for

If it is necessary that a

personnel or equipment protection, then the CBS shall approve its use

and inform the Lead Craftsman.

.

- 16

For Unit 2 4160 and 6900 V breakers, place their handswitch in PTL prior

to racking down the breaker.

It is not necessary to CARD the handswitch

in PTL, however, a plasti: information label hung on the handswit:h is

desired.

This provides the Control Poom Operators with the reason the

component is out of service and minimizes potential for auto start while

the breaker is being operated,

t

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_

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PR:r-

WPE P*AN NC

T E oCErt."P2 , W:P2 P:AN T * T*.E

Pact

14 of SG

1000.027

HOLD AND CAUTION CARD CONTROL

' RIV '

34

jCHANGE~ k;

i

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~.1~

Caros for Breaker / Sus PMs

'.1T.1.

Wnen seenerg1:ing an electri:al bus for breaker / bus PMs, all

CARDS hung on any associated breaker shall be documented on

Electrical Bus Hold Card Authorization Addendum (1000.027N).

The Hold Card Authorization Form shall be annotated to

reference Form 1000.027N, and the form attached to the Hold

Card Authori:ation Form.

Any CARDS removed shall be retained

with Fo rm 1000.027N.

".17.2.

CARDS required to be hung on the bus during the breaker / bus

PMs shall be added to Form 1000.027N.

l

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7.17.3.

If desired to remove CARDS providing boundary isolation for

the breaker / bus PMs, then perform either of the following:

i

Hang and verify all CARDS removed by Form 1000.027N.

Verify all craftsman protected by the CARDS on 1000.027N

=

have provided release authorization on Partial / Temporary

Release Authorization Sheet (1000.027C).

1

7.17.4.

Prior to permanent removal of the breaker / bus FM CARDS and

bus restoration, verify each breaker on Form 1000.027N is in

the required position with CARD installed.

Independent

verification shall be performed prior to bus restoration.

'

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8

CARDS ON MECFJWICAL EQUIPMENT.

8.1

Vents and drains opened for system depressurization and draining for

!

personnel protection shall be hold carded.

For those that will be

removed or worked on during the maintenance, tagging is NOT required.

8.2

Hard piped vents and drains that share a common header with other

components may require isolation to ensure adequate protection.

,

l

S.3

If a system er component cannot be drained completely due to lack or

location of vents and drains, use diverse methods to ensure adequate

isolation as follows:

If cn a steam system, perform the isolation and later check that it

has cooled to near ambient temperature.

Annotate inf erraation about the incomplete draindown on the tagout.

When systems are opened that are not completely vented and drained,

component boundaries shall be disassembled slowly and carefully.

8.4

Double valve isolation shall be considered .or high energy systems

(>200"F or >275 psig) with an open intermediary drain where possible.

B.5

If double valve' isolation from a high energy system is not practical due

,

l

to system limitations, . hen the operator determining hold card

l

Installation boundaries should specify a means ci completing a leak

l

check at or near normal system operating pressure for each necessary

single valve isolation boundary.

'

.6

Wnen practical, use manual valves as boundary isolations.

i

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. - - . -

_ - . - - - . . - - -

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!:

1998 ANO- L' nit 1 NRC SRO(l') License Exam Analysis

SRO(L) Examination Analysis Summary

The examination was administered to six SRO(U) candidates. The following chart summarizes the

i

candidates responses to questions on the examination:-

i

j

6of6

S of 6

4of6

3of6

2of6

l of 6

Oof6

l

-CORRECT

CORRECT

50

23

13

8

2

1

3

j

L

An analysis was performed on the 14 questions incorrectly answered by 2 50% of the candidates. Analysis

'

results are summarized below.

QlD

No.

Analysis Results:

0054-

40

Answer keyed wrong. Changed answer key to correct response "B"

(6 of 6 incorrect)

l

0061

44

Question and answer are correct as written. (3 of 6 incorrect)

'

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0067

48

Question and answer are correct as written. (5 of 6 incorrect)

i

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0068

49

The question will be revised prior to reuse, but the correct answer can be

determined as written. High difficulty level. (3 of 6 incorrect)

0069

50

Question and answer are correct as written. (3 of 6 incorrect)

l

0087

64

Changed answer to "C"

See atached response. (6 of 6 incorrect)

l

0088

65

Question and answer are correct as written. High difficulty level.

(4 of 6 incorrect)

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0090

67

Question and answer are correct as written. (3 of 6 incorrect)

!

0095

71

Deleted question. No correct answer. See attached response. (6 of 6 incorrect)

0108

81

Question and answer are correct as written. (3 of 6 incorrect)

0112

85

Question deleted. See attached response from RO Exam Analysis.

(3 of 6 incorrect)

,

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0114

87

Answer "B" accepted as correct in addition to answer "D"

See attached response

l

from RO Exam Analysis. (3 of 6 incorrect)

0126

96

Question and answer are correct as written. (3 of 6 incorrect)

l

0128

48

Question and answer are correct as written. (4 of 6 incorrect)

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--<_____,_ _ ______ _ _

INITIAL RO/CRO EXAM CANK QUESTION DATA

ARKANSAS NUCLEAR ONE - UNIT 1

' hv7 0

Rev Date: 7/11/98

Source: New

Originator: GGiles

QlD: 0054

R

TUOI: ANO-1-LP-RO-ICS

Objective: 30

Point Value: 1

Section: 3.4

Type: Heat Removal From Reactor Core

System Number: 003

System Title: Reactor Coolant Pump System (RCPS)

Description: Knowledge of the effect that a loss or malfunction of the RCPS will have on the following: ICS.

K/A Number: K3.05

CFR Reference: CFR: 41.7 / 45.6

Tier:

2

RO Imp:

3.6

RO Select:

No

Difficulty: 4

Group: 1

SRO Imp: 3.7

SRO Select: Yes

Taxonomy: An

Question:

Given the following plant conditions:

- Power at 27%

- ICS in full automatic

- D Reactor Coolant Pump trips

Which of the following best describes ICS response to the change in RCS flow?

a. Delta Tc will remain at zero (0) due to the response of the total flow controller.

b. A Delta Tc error will develop with Loop A Tc < Loop B Tc due to the response of the total flow controller.

c. A Delta Tc error will develop with Loop B Tc < Loop A Tc due to the response of the total flow controller,

d. Delta-Tc will not be effected due to the total flow controller signal being blocked.

Answer:

b. A Delta-Tc error will develop with Loop A Tc < Loop B Tc due to the response of the total flow controller.

Notes:

D RCP trip affects Loop A RCS flow. The RCP trip will cause ICG w re-ratio feedwater flow demands.

Feedwater Loop A demand will g) down and Feedwater Loop B demand will go up. At the given power level,

A loop feedwater demand will go down until the A OTSG reaches low level limits. The total flow controller will

then be relea;ed and Delta-Tc will be sacrificed to maintain total feedwater demand. Therefore, (b) is the

only correct response.

-

References:

STM-1 34 (Rev 5), Integrated Control System, pages 41 and 42.

History:

Developed for the 1998 SRO Exam.

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QID 0087

SRO Question 64

I

1

Question:

During a Blackout condition, it may become necessary to perform an EDG start without DC control power.

In this condition, how is the generator output voltage adjusted (no battery chargers are loaded)?

.

a.

Adjusting engine speed via speed setting knob on governor,

b. The automatic voltage adjuster will still function.

c.

Using the manual voltage adjuster on Exciter Control Panel.

d.

Using voltage adjuster handswitch on C10.

Answer:

b. The automatic voltage adjuster will still function.

Exam Analysis Results:

Change correct response to (c).

. Justification:

In accordance with 1104.036, Emergency Diesel Generator Operation, a loss of DC power to the field

' flashing circuit will cause a loss of automatic voltage regulator setpoint adjustment due to a loss of power to

the motor-operated rheostat. Ahhough the setpoint of the automatic voltage regulator cannot be adjusted, the

automatic voltage regulator will still function to maintain voltage. However, the stem of the question asks

for how the generator output voltage will be adjusted versus maintained. This implies an action. The correct

action to take if voltage adjustment is required is described in 1104.036, Emergency Diesel Generator

Operation, Step 11.10.I, which states:

Ifvoltagefalls outside 3800-.1500 volts, place Excitation control selector switch (on E11for DG1, E21for

~ DG2) in MANUAL and af e the manual voltage adjust dial as necessary.

Therefore, the correct response as the question is written should be (c).

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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INITIAL R2/SRO EXAM CANK QUESTION DATA

ARKANSAS NUCLEAR ONE - UNIT 1

QlD: 0087

Rev: 0

Rev Date: 7/11/98

Source: New

Originator: JCork

TUOl: ANO-1 LP RO-EDG

Objective: 22

Point Value: 1

Section: 3.6

Type: Electrical

System Number: 063

System Title:

D.C. Electrical Distribution

Knowledge of the effect that a loss or malfunction of the de electrical system will have on the

Description:

following: ED/G

K/A Number: K3.01

CFR Reference: CFR: 41.7 / 45.6

Tier:

2

RO imp:

3.7

RO Select:

No

Difficulty: 3

Group: 2

SRO imp: 4.1

SRO Select: Yes

Taxonomy: C

Question:

During a Blackout condition, it may become necessary to perform an EDG start wdhout DC control power.

In this condition, how is the generator output voltage adjusted (no battery chargers are loaded)?

a. Adjusting engine speed via speed setting knob on govemor,

b. The automatic voltage adjuster will still function.

c. Using the manual voltage adjuster on Exciter Control Panel.

d. Using voltage adjuster handswitch on C10.

Answer.

b. The automatic voltage adjuster will still function.

Notes:

Without DC control power the automatic voltage SETPOINT will not be present, but since the majority of the

EDG generator controls are powered directly from its output, the auto voltage adjuster will still functiori.

Therefore "B" is the correct answer as long as battery chargers are not loaded, restoring DC power and

probably skewing voltage with the restoration of the automatic setpoint.

This would then require the use of the manual adjuster as i., nswer "c".

Answer *D" is incorrect, no DC power is available.

Answer "a" is incorrect, this will adjust frequency, not voltage.

References:

1104.036, Emergency Diesel Generator Operation , Rev. 37, page 21

History:

Developed for 1998 SRO exam

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PROCJWORX PLAN NO. I PROCEDUREAYORX PLAN TTTLE:

l PAGE:

31 of 160

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37

1104.036

EMERGENCY DIESEL GENERATOR OPERATION

CHANGE:

,

CJVUTION

IWithlossofcontrolpower,

the only functional DG protection is the

mechanical overspeed device.

11.8

Start diesel generator by overriding one of the starter solenoid

valves with the override plunger.

Release solenoid when engine

starts.

11.8.1

If DG does not start after -5 seconds, repeat step 11.6.

11.8.2

If it becomes necessary to shut down the diesel:

A.

Pull the EMERGENCY FUEL CUTOFF (FO-66A for DG1, FO-668

for DG2) valve handle,

CI

B.

Release the governor solenoid by lifting the knurled

knob, thus releasing the locking pin, and push the

knurled knob down and ensure fuel rack lever returns

to the shutdown position (black pointer moves to <1 on

governor).

11.9

Verify governor maintains engine speed at -900 RPM speed and -60 Hz.

If necessary, adjust engine speed by turning speed setting knob on

governor.

NOTE

Loss of DC power to field flashing circuit will cause loss of automatic

voltage regulator setpoint adjustment (loss of power to motor-operated

rheostat). Automatic voltage regulation should still function.

11.10

Verify diesel generator output voltage is normal.

11.10.1

If voltage falls outside 3800-4500 volts, place Excitation

control selector switch (on Ell for DG1, E21 for DG2) in

MANUAL and adjust the manual voltage adjust dial as

necessary.

CJMUTION

The next step will cause automatic loading of the diesel if 125V DC is

restored through a batte.ry charger.

Be prepared to manually adjust the

diesel voltage and frequency each time a load is startec'.

11.11

Manually close output breaker for diesel that was started (A-308 for

DG1, A-408 for DG2).

I

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QID 0095

SRO Esam Question 'l

j

'

i

Question:

f

ESAS has actuated due to a LOCA.

.

RCS pressure has dropped to approximately 1200 psig within five minutes of actuation.

Which of the following best describ's the effects on the ICW system or the components it cools?

l

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All RCPs must be secured due to loss of seal cooling.

l

a

'

b. CRD cooling pumps must be secured due to isolation of discharge path.

t

ICW booster pumps are protected by opening of bypass valve.

i

c.

'

d.

ICW pumps must be secured due to isolation of SW to ICW coolers.

l

Answer:

l

!

b. CRD cooling pumps must be secured due to isolation of discharge path.

t

Exam Analysis Results.

t

Delete question due to no correct response as written.

!

Justification:

1104.028. ICW System Operation, Section 5.0, Limits and Precautions, Step 5.1 states:

r

Runmng CRD Pumps (P-79A or B) at a shut-ofhead willlead to pump damage A shut-offhead could be

encountered after ESactuanon or upon closure ofthefollowmg:

Non-Nuclear ICWfor RCP Air & Lube Oil Coolers and CRD 's Outlet (CV-2220 or CV-2221)

a

b.

Non-Nuclear ICWfor RCP Air & Lube Oil Coolers and CRD 's Inlet (CV-2235).

However, the stem of the question directs the candidate's attention to the ESAS procedure from the given

l

plant conditions. The stem of the question does not state the status of RCPs. No specific actions concerning

CRD cooling pumps are stated in 1202.010, ESAS emergency operating procedure. He actions taken

following ES actuation include performance of Repetitive Task 10 (RT-10) to verify proper actuation of ES

components. The only action concerning CRD cooling pumps in accordance with 1202.012, Repetitive

Tasks. Step 10 D.4.c is to verify a CRD cooling pump mnnmg if any RCP is running.

De given correct answer is based on a limit and precaution from a normal oper ting procedure, while the

stem of the question directs the candidates attention to an emergency condition, ne operations! priorities

following a LOCA with ES actuation do not include the actions of the limit precaution. The EOP and the

normal operating procedure do not state that the CRD cooling pumps MUST be secured. Therefore, the

question will be deleted due to no cerrect response as written.

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c

n.= =_, _ , -

- - - _

INITIAL RO/SRO EXAM BANK QUESTION DATA

ARKANSAS NUCLEAR ONE - UNIT 1

. _ _ _ , _ _ _ . . _ _ . . . _ _

QlD: 0095

Rev: 0

Rev Date: 7/12/98

Source: New

Originator: JCorK

TUOl: ANO-1 LP-RO-EOP10

Objective: 6

Point Value: 1

Section: 3.8

Type: Plant Service Systems

System Number: 008

System Titte: Component Cooling Water System (CCWS)

Description: Ability to monitor automatic operation of the CCWS, including: Automatic actions associated

with the CCWS that occur as a result of a safety injection signal.

K/A Number: A3.08

CFR Reference: CFR: 41.7 / 45.5

Tier:

2

RO Imp:

3.6

RO Select:

No

Difficulty: 3

Group: 3

SRO Imp: 3.7

SRO Select: Yes

Taxonomy: C

Question:

ESAS has actuated due to a LOCA.

RCS pressure has dropped to approximately 1200 psig within five minutes of actuation.

Which of the following best desenbes the effects on the ICW system or the components it cools?

J

a. All RCP's must be secured due to foss of seal cooling.

!

b. CRD cooling pumps must be secured due to isolation of discharge path.

,

c. ICW Booster pumps are protected by opening of bypass valve.

d. ICW pumps must be secured due to isolation of SW to ICW coolers.

1

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Answer:

b. CRD cooling pumps must be secured due to isolation of discharge path.

1

Notes:

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"B"is correct per limits and precautions in 1104.028. damage may occur due to running at shutoff head.

"A" is incorrect, RCP's are secured due to loss of subcooling margin in this situation.

"C" is incorrect.1CW Booster pumps should be secured dt/s to isolation of suction and discharge, and RCP's

,

are not needed.

"D" is incorrect SW will be isolated to coolers but this doesn't require securing ICW pumps.

,

!

{SROs review EOPs under TUO! AAG1004-001 using RO tesson plans.)

References:

!

1104.028. ICW System Operating Procedure. Rev. 20 PC-4, page 4

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History:

l

Developed for 1998 SRO exam

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scoc/ WORK PLAN

PROCEDURE / WORK FLAN TTTLE:

PaGE:

4 Cf 63

REV:

20

(CW SYSTEM OPERATING PROCEDURE

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1104.028

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4."

REFERENCES USED IN CONJUNCTION WITH THIS PROCEOURE

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4.2.1

Plant Startup (OP 1102.002)

4.2.2

Plant Shutcown and Cooldown (OP 1102.010)

'

4.3

NRC COMMITMENTS

l

d

4.3.1

P 13736,

Verify that the correct chemicals are being added

O

to the appropriate systems.

Contained in Nuclear ICW Loop

L

Chemical Addition and Non-Nuclear ICW Loop Chemleal

Addition sections.

5.0

LIMITS & PRECAUTIONS

l

5.1

Avoid frequent starts of any ICW pump.

5.2

Running CRD Pumps (P-79A or B) at a shut-off head will lead to pump

damage. A shut-off head could be encountered after ES actuation or

upon closure of any of the following:

A.

Non-Nuclear ICW For RCP Air & Lube Oil Coolers and CRD's

Outlet (CV-2220 or CV-2221)

8.

Non-Nuclear ICW For RCP Air & Lube Oil Coolers and CRD's

Inlet (CV-2235)

5.3

Before starting any pump af ter prolonged system shutdown or following

maintenance on the pump, ensure pump casings are filled & vented.

5.4

If ICW to RCP seal cooling is interrupted due to closure of RCP Seal

Clr and Ltdn Clra NUC ICW Supp Isol (CV-2233) or RCP Seal Clr and Ltdn

Clrs NUC ICW Rtn Isol (CV-2214) or both, stop the RCP Seal Cooling

Pump (s) (P-ll4A, P-ll48) and open the RCP Seal Cooling Pumps Bypass

i

(CV-2287) until ficw can be restored.

5.i

Minimize temperature transients wnen adjusting ICW temperature.

L6

"I CRD cooling is 1:st cue to pump failure, filter clogging, or loss

Of suction, prompt Operator action is requirec to prevent CRDM's from

reacning maximum allcwed temperature.

5.7

Due to service water normally being cross-connected at the inlet to

the ICW coolers, any adjustment on either ICW Coolers Loop I SW Bypass

(SW-4026A) or ICW Coolers Loop II SW Bypass (SW-4026B) will affect

both nuclear & non-nuclear temperatures.

5.9

Prior to energiting the CRDM's or at RCS temperatures >200*F, CRD

cooling water shall be provided, except for stator replacement.

5.9

Maximum allowable temperature of CRD cooling water entering the CRDM

is 120*F.

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1202.012

REPETITIVE TASKS

REV 3

PAGE 13 cf 27 [

Page 1 of 4

NOTE

Obtain Shift Superintendent /CRS permission prior to overriding ES.

RB H2 sampling must be established within 13 minutes of ESAS actuation.

10. Verify proper ESAS actuation:

A. Verify BWST Outlets open (CV 1407 and 1408L

1) E CV-1407 or 1408 f ails to open,

THEN stop associated HPI, LPI, and RB Spray pumps until failed valve is opened.

B. Verify SERV WTR to DG1 and DG2 CLRs open (CV-3806 and 3807).

C. E RCP Seal INJ Block (CV-1206) closed on low flow,

THEN restore Seal injection as follows:

1) Place RC Pump Seals Total INJ Flow (CV-1207) in HAND AND close.

2) Place CV 1206 in OVRD AND open.

3) E RCP Seal Bleedoff temps are 5180*F,

T. HEN slowly open CV-1207 until 30 to 40 gpm total flow is reached AND place in

'

AUTO.

4) E RCP Seal Bleedoff temps are > 180'F,

THEN slowly open CV 1207 until 8 to 12 gpm total flow is reached.

a) Record current time

,

b) Maintain 8 to 12 gpm total flow for at least 30 minutes.

L

c) After 30 minutes, slowly open CV-1207 until 30 to 40 gpm total flow is reached

AND place in AUTO.

)

D. IF_ any RCP is running, THEN perform the following:

Obtain Shif t Superintendent /CRS permission to override ES for RCP services restoration.

1)

!

2) Dispatch an operator to perform the following:

l

a) Verify the following valves closed;

i

l

ICW Cooler Loop 1 SW Bypass (SW-4026A)

ICW Cooler Loop 11 SW Bypass (SW-4026B)

f

.

idle ICW Cooler (E28) SW Outlet (SW-8A, B or C)

e

b) Throttle in-service ICW Cooler (E28) SW Outlets ~ 5 turns open from closed seat

(SW F A, B, C).

(10. CONTINUED ON NEXT PAGE)

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1202.012

REPETITIVE TASKS.

REV 3

PAGE 14 ef 27

Page 2 of 4

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10. (Continued).

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3) Verify instrument Air System operation by depressing CH1 and CH2 ES Electrical

t

Alignment MAN PBs on C16 and 18.

4) g ESAS Channel 5 or 6 has actuated,

THEN perform the following

.

a) E > 2 RCPs are running,

THEN reduce number of running RCPs to one per loop.

b) Dispatch an operator to monitor ICW Surge Tanks (T-37A and B) for loss of level as

,

ICW is aligned to RB, indicating'possible piping failure in RB, while continuing with

this procedure.

c) Verify the following pumps running:

{

Two ICW pumps (P33A, B, C)

One RCP Seal Cooling pump (P114A or B)

.

.

One CRD Cooling pump (P79A or B) running,

I

d) Override AND open Nuclear and Non-nuclear ICW Outlets

]

(CV-2215, 2214, 2221, and 2220).

e) Override AND open Nuclear and Non-nuclear ICW Inlets

' (CV-2233, 2234, and 2235).

f) IF piping f ailure is evident,

THEN close Nuclear and Non-nuclear ICW Inlets and Outlets.

)

CAUTION

SW pump runout can occur with flow as low as 8000 gpm.

5) WHEN ICW Cooler SW Outlets and 8ypasses are aligned,

THEN override AND open one Service Water to ICW Coolers Supply

(CV-3811 or 3820).

a) IF any ES equipment shows signs of overheating

_0_R

SW pump approaches runout,

THEN throttle ICW Coolers SW Outlets.

,

E, Verify proper ESAS Channels tripped:

Condition

Channels Actuated

k

_RCS press 51550 psig

1,2,3,4

RB press 218.7 psia

1,2,3,4,5,6

_

R8 press 244.7 psia

7,8,9,10

'(10. CONTINUED ON NEXT PAGE)

PC-5

1202.012

REPETITIVE TASKS

REV 3

PAGE 15 cf 27

10. (Continued).

Page 3 of 4

F.

On C19 verify:

1) LPI(Decay Heat) Room Cooler running in each Decay Heat Room:

VUC1 A or B

l

AND

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VUC1C or D

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2) IF RB Spray has actuated,

!

THEN verify Service Water to RB Spray P35A and B Lube Oil CLRs open

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(CV 3804 and 3805).

i

G. Verify each component properly actuated on C16,18, and 26, except those overridden in

previous steps.

1) Verify proper ES system flow rates.

2) l_F only one train of HPIis available

AND

y,

RCS press is > 600 psig,

THEN throttle the HPI Block valve witn the highest flow to within 20 gpm of the next

highest flow.

H. On C10 verify:

1) Both DGs operating,

2) A3 to A4 Crossties open (A-310 and 410),

3) B5 to 86 Crossties open (B-513 and 613),

I

4) Unit AUX feeds to A1 and A2 open (A-112 and 212),

5) Both A3 feeds to B5 closed (A-301 and B-512),

6) Both A4 feeds to B6 closed (A-401 and B 612).

j

l.

On C09 verify:

1) AUX Cooling Water header depressurized.

2) Proper EFW actuation and control:

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!l

a) Verify EFW actuation indicated on Bus 1 and 2 of both trains A and 8 on C09.

t

b) Verify at least one EFW pump (P7A or B) running with flow to SG(s).

c) IF SCM is less than adequate, THEN select Reflux Boiling setpoint.

!

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(10. CONTINUED ON NEXT PAGE)

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PC-1, 5

1202.012

REPETITIVE TASKS

REV 3

PAGE 16 ef 27

10. (Continued).

Page 4 of 4

i

d) Verify EFW CNTRL valves modulate such that SG levels are controlling at or

approaching the applicable level at 2 Required Minimum Fill Rate, unless throttling is

required to prevent overcooling:

SG A

SG B

CV-2645

P7A

CV-2647

CV-2646

P78

CV-2648

oc.s

l

Condition

Level Band

Required Minimum Fill Rate

Any RCP running

20 to 40"

N/A

2 to 8"/ min in AUTO

E

All RCPs off

300 to 340"

280 gpm/SG in HAND

2 SGs available

1 SG available

All RCPs off

2 to 8"/ min in AUTO

AND

370 to 410"

OR

430 gpm in HAND

Reflux Boiling Selected

280 gpm/SG in HAND

e) IF all RCPs are off,

THEN check primary to secondary heat transfer in progress indicated by all of the

following:

,

T-cold tracking associated SG T-sat (Fig. 2)

.

T-hot tracking CET temps

.

T-hot /T-cold AT stable or dropping

.

Initiate RB H sampling within 13 minutes of ESAS actuation using Containment Hydrogen

J.

2

Control (1104.031), Exhibit A.

K. IF AUX Lube Oil pump for running HPl pump f ails to stop after 20 second time delay,

THEN within one hour of ESAS actuation dispatch an operator to stop AUX Lube Oil pump

locally at breaker.

ac.i

P 64A

P-648

P-64C

B5721

85722/B6515

B6514

L.

Monitor ESAS alarms on K-11.

.

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

. . _ . . _

_.

1998 ANO- Unit i NRC Operating License Written Examination Final Results

RO Candidates:

l

Byran August Dochring:

81.8 %

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Michael Eugene Harris:

87.9 %

Karl Raymond Jones:

82.8% .

John Porter Morgan:

83.8 %

. Anthony Lee Morris:

74.7 %

.. Steve John Wolfe:

90.9 %

!

Average Score:

83.7 %

l

SRO(U) Candidates:

StevenWendell Avery:

81.6 %

Brian Thomas Dungan:

86.7 %

John Cli%rd Hanson:

81.6 %

Elizabeth Ann Owen:

82.7 %

Robert David Pace:

91.8 %

Daniel Wesley Reed:

89.8 %

Average Score:

85.7 %

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ATTACHMENT 1

PARTIAL LIST OF PERSONS CONTACTED

Licensee

G. Giles, Operations Training Supervisor

M. Goad, Operations Training

R. Fuller, Unit 1, Operations Manager

R. Byford, Operations Training

L. McLerran, Simulator Training Supervisor

,

S. Cotton, Director Training / Emergency Preparedness

. ~

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_

C. Zimmerman, Unit 1, P,lant Manager

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ATTACHMENT 2

FACILITY INITIAL LICENSE EXAMINATION

COMMENTS AND ANALYSIS

. . , .

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1998 \\NO -I nit I %RC RO License Esam Analysis

4

i

RO_ Eununation Analysis Summary

fhe eununation was admmistered to six RO candidates The following chart summarizes the candidates

)

responses to questions on the examination:

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6of6

5 of 6

4 of 6

3 of 6

2 of 6

lof6

O of 6

CORRECT

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44

30

13

6

3

1

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An analy sis was performed on the 13 questions incorrectly answered by 2 50% of the candidates. Analysis

results are summarized below.

QlD

No.

Analysis Results:

l

0042

37

Question and answer are corroet as wnessa. (4 of 6 imoonect)

l

0046

39

' A condition will be added to stem prior to reuse, but the coned answer can be

I

determined as wntten (3 of 6 incorrect)

0053

44

Question and answer are correct as written. (3 of 6 incorrect)

'

0063

51

Question and answer are correct as written. (3 of 6 incorrect)

0065

53

Question and answer are correct as written. (4 of 6 incorrect)

j

0068

54

The question will be revised prior to reuse, but the correct answer can be

detennined as wntten High difViculty level. (6 of 6 incorrect)

,

.

0088

70

Question and answer are correct as wntten High difficulty level.

(4 of 6 incorrect)

0090

72

Question and answer are correct as written. (3 of 6 incorrect)

0094

76

Question will be revised prior to reuse, but the correct answer can be determined as

written. (3 of 6 incorrect)

0112

90

Question deleted. See attached response. (5 of 6 incorrect)

0114

91

Answer "B" accepted as correct in addition to answer "D"

See attached response.

(5 of 6 incorrect)

0115

92

Question and answer are correct as written. Training Evaluation Action Request

written to ensure the information is included in the License Class Training

Program. (5 of 6 incorrect)

i

0121

96

Initial condition clarified during examination administration. Master exam pen

and ink changed Question and answer correct as modified. (3 of 6 incorrect)

l

.

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> lim . . \\ N si i sis

>

Rt i I s im i.hn si m m sRtbl i s em Question %f

tjorsto.n

,

'

l)onng a IM transient. the CBOI manually controls FW to stabihze the plant

Rs power is 1015. for approximately 10 minutes while the plant is brought under control.

Is this acceptable or unacceptable'

'

i

a This is acceptable to mitigate transients for short periods of time per Conduct of 0perations.

'

h.

This is unacceptable due to hmitations on our fuel as specified by Babcock & Wilcot

e

This is acceptable for short periods of time as specified by NRC correspondence with Licensing.

d This is unacceptable due to esceeding the maximum thermal output in our operating license.

Answer:

d ' His is unacceptable due to exceeding the maximum thermal output in our operating license.

1

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Exam Analysis Results:

1

Delete question due to no correct response as written.

Justification:

i

The original intent of the question was to reinforce management expectations concerning "brief" excursions

abose 100% power.

,

i102 004. Power Operations. Section 5.0. Limits and Precautions. Step 5.1, states:

'

Ihe acerage shut tidl steady state pas er level over any 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period shall not exceed the licensed power

level C!M SIWtt ' It is never permissible to antennonally operate at greater than 100% heat balance power.

It as not a violanon ofthis rec;iarement if100% heat balance power os briefly exceeded, but, in no case

rhordd in:% he exceeded There are no hmits on the number ofnmes these excursions may occur; or the

nme mterval that must separate such excursions. except the averagefidi steady heat balance power level

user any eight hour period shall not exceed the hcensed power level of 2368 MWI,

The stem of the question describes a transient condition. The licensed power level limitation of 2568 MWt is

applicable for steady state conditions. Power limitations during transient condition.s are bounded by the

safety 0 6 sis. In addition. the candidate could calculate the average power over an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period of time

based on power at 101.5% for ten minutes and power remaining at 100% Jor tl e remainder of the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

period and not exceed average power limits per Reactor Power History. Tilt md imbalance Log.

Therefore.' there is no ccrrect response to the question as written.

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I

INITIAL RO,SRO EXAM QANK QUESTION DATA

ARKANSAS NUCLEAR ONE UNIT 1

. m _ ..,_ m - ~

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QlD: 3112

Rev: 0

Rev Date: 5,29,98

Source: New

Originator: JCork

l

TUOI: ANO-1.LP.RO-NOP

Objective: 7.4

Point Value: 1

Section: 2.0

Type: Genenc K/As

'

f

System Number: 2.1

System Title: Conduct of Operations

I

Description: Knowledge of conditions and limitations in the facility license.

FUA Number: 2.1.10

CFR Reference: CFR: 43.1/45.13

Tier:

3

RO Imp:

2.7

RO Select:

Yes

Difficulty: 4

Group: G

SRO imp: 3.9

SRO Select: Yes

Taxonomy: Ap

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Question:

l

During a FW transent, the C80T manually controis FW to stabilize the plant.

Rx power is 101.5% for appnndmately 10 minutes while the plant is trought under contml.

l

is this acceptable or upWaMa?

a. This is acceptable to mitigate transients for short pedods of time per Conduct of Operations.

b. This is unacceptable due to limitations on our fuel as specified by Babcock & Wilcox.

c. This is acceptable for short periods of time as specified by NRC correspondence with Licensing.

d. This is unacceptable due to exceeding the maximum thermal output in ou operatiry license.

Answer:

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d. This is unacceptable due to exceeding the maximum thermal output ln our operating license.

Notes:

Answer (d) is the only correct response.10 minutes far exceeds a *brief" moment during transient conditions.

l

The other answers are wrong due to being non-conservative.

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References:

1102.004 (Rev 38). Power Operations. Limits and Precautions, page 6.

History:

Deveioped for 1998 RO/SRO exam.

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38

D C'.*iE R C P E U T C N

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~KANGE.

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N FC COMM:"?'E.NTS

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.one

5.0

.IMITS AND PRECAUTIONS

1

f

5 . '.

The average shift full steacy power level over any eight hour period

'

shall not exceed the 11censeo power level (2568 MWt).

It is never

permissible to intentionally operate at greater than 100% heat balance

'

power.

It is not a violation of this requirement if 100% heat balance

l

power as criefly exceecea, cut, in no case should 102% be exceeceo.

There are no limits on the numoer of times these excursions may occur;

or the time interval that must separate such excursions, except the

average full steady heat balance power level over any eight hour

l

the licensed power level of 2568 Mwt.

period shall not exceed

i

Maintain power imbalance at or near zero unless otherwise specified by

'

5.2

Reactor Engineering staff.

Power imbalance outside the envelopes

See

defined in Attacament M shall be limited to less than four hours.

Tech Spec 3.5.2.6.

the

.

To minimize power tilts, maintain rod positions within a group at

5.3

same level.

5.4

The reheat temperature should not be allowed to step change >250*F/hr.

Observe limits and precautions of referenced operating procedures.

5.5

annunciates, observe the computer

,I_f Potter DISTRIBUTION AIARM (K08-D4)

f

5.6

alarm CRT message to determine the affected parameter.

is exceeded, either bring affected parameter

M a limit

5.6.1

within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per Tech Specs 3.5.2.4 thru

3.5.2.6 oj take action specified by applicable Tech Spec.

5.6.2

If necessary, ::ntact Peacto: Engineering fer assistance.

i.~

The Tecn Spec _imit :n cuaorant t:10 measureo cy tne incere monitoring

system plant ::mpute:. .s variacle as f 11cws:

>

ETPD

Tilt ~_ imi t

4)

!

O to 250 : 10

4.17

4.00

}

250 z 10 to EOC

..

These values include inaccuracles in the incore monitoring system

(Tech Spec 3.5.2.4)

The incore monitoring system, using the plant

accurate method of monitoring quadrant tilt.

computer, is the most

ey monitoring both incore and execre tilt.

Tecn Spec compliance is met

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PAGE

16 of 69

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a 3. ..;.;;...

as ;.:E x mE v. tax a ; a. * m E

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REV:

43

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UNIT 1 OPERATIONS LOGS

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1015 003A

CHANGE:

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4

Fea:::: Sul.

n; ?:essu:e *nstrumentation

NOTE

The ECCS safety analysis assumes a pre-accident Reactor Building pressure no

lewer than -1 psig (13.7 psia).

However, the lower limit specified in Tech

Spec is lower than this,

-2.7 psig (12 psia).

A Tech Spec change is in

progress to correct this inadequacy.

!

!nere are 3 sets of :nstruments monitoring RB pressure; each set has

'

diffe:ent instrument error characteristics.

To protect the assumptions of

ne safety analysis, we average the set with the least error: RPS instruments

P -2400 tnru PI-2403) and take instrument error into account.

The average

l

value is used in order to reduce the band required for instrument error.

!

On the logsheets, the RB pressure limits are shown with no error calculated

for ESAS and wide range instruments, because the addition of instrument error

would make the lower limit higher than the normal R8 pressure.

.

s _ .m .

2

A.

If the average of the operable RB Pressure indicators

(PI-2400, 2401, 2402, 2403) is <-0.64 psig, or

i

>2.64 psig, enter LCO 3.6.4 and write a condition

i

Report.

1

9.2

Instructions for Reactor Power History, Tilt, and Imbalance Log

1

(OPS-A8)

9.2.1

The everage power level for any eight hour period should

not exceed the licensed power level (2568 Mwt).

It is

never permissible to intentionally operate at greater than

100.0% heat balance power.

It is not a violation to

briefly exceed 100.0% heat balance power, and there are

neither limits on the number of, nor the time intervals

separating such excursions.

However, in no case should

102% be exceeded.

s.2.2

Use Function NASP, N3, 6; Imbalance, Tilt, and Rod Index

for imbalance and quadrant tilt readings.

9.2.3

If the Plant Computer is inocerable, take logs in the

following alternate manner:

A.

Commence taking Alternate P'. Power History, Tilt and

Imbalance Log (OPS-A21' and make a comment stating

such on log OPS-A8.

B.

Heat Balance Power shal' be determined at least once

per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months by performitig a manual heat balance

calculation per 1103.016.

Enter results in the

comments section of OPS-A21.

C.

Calculate Average NI Power and Shift Average NI Power

from Nuclear Instruments on C03.

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0.

Determine Tilt and Imbalance as follows:

Lc; out-of-core imoalance using Nuclear

..

Instruments en C03.

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

_ _ _ . . _ . . .

r-

Q11) 0116

j

Rt i f um (Juestmn "I

sH()(t i Eum Question 8"

l

Question;

Which of the followmg actions ms oh mg a hold carded MCC breaker is allowable per 1000.027, Hold and

Caution Card Control'

.

a.

Remoung "a" and "b" contact termmations

b Rackmg a breaker in and out but not closing it.

e

Leaung the door open as long as breaker is removed.

d Performmg a PM to lubricate contacts.

Answer:

,,

,

d. W g a N h m

"d'

"?$$SD/N N3YIb -

.

.s

,

".3,*..*~.

-. ~ ^ ' .'

'"

~'

Exam Analysis Results:

Accept answers (b) and (d) as correct responses.

Justification:

The (b) distracter uses wording that is unclear. At ANO,480V MCC breakers are hold carded as " Breaker

Open/ Removed" For 480V MCC breakers, the term " racking"is synonymous with " removing". A 480V

MCC breaker is removed from its cubicle by the act of racking it out. It is a permusible to remove a hold

carded MCC breaker from its cubicle in accordance with 1000.027, Hold and ('=dian Card Centrol, Step 7.5,

which states:

,

ifa Carded MCC breaker must be removedfrom its cubicle, then the Crap shall cocrdinate with Operations

to perform thefollowmg:

Obram CRSpermission to remove the breaker and move CARD as necessary.

Remove break., ' m its cubicle ensuring the breaker remains open at all times.

Resttach the CARD to the exterior breaker door as required to ensure the CARD remains at the

MCC door.

A Carded cubicle breaker may not be remstalled unless the craftsperson installing the breaker is the

=

only one left on the tagout or the tag has been cleared.

Therefore. (b) is a correct response in addition to (d).

l

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

. _ _ _ _ _ . . _ _

. . _ . _ _

_ _ _ _ _ _

_

-- _

INITI AL RO/SRO EXAM OANK QUESTION DATA

i

ARKANSAS NUCLEAR ONE - UNIT 1

Q10: 0154

Rev: 0

Rev Date: i/13/1IH5

$io~urce: New

Originator: JCork

~

TUOI: AA30001-005

Objective: 3

Point Value: 1

,

l

Section: 2.0

Type: Generic K/As

System Number: 2.2

System Title: Equipment Control

'

Description: Knowledge of tagging and dearance procedures.

K/A Number: 2.2.13

CFR Reference: CFR: 41.10 / 45.13

Tier:

3

RO imp:

3.8

RO Select:

Yes

Difficulty: 4

Group: G

SROImp: 3.8

SRO Select: Yes

Taxonomy: Ap

Question:

'

Noid and

Wluch of the following actions involvin0 a hold canied MCC tweaker is alloweble por 1000.027,

Caution Cani Control?

a. Removin0 *a" and "b" conted terminations.

b. Racking a breaker in and out but not closmg it.

c. Leaving the door open as long as breaker is removed.

d. Performing a PM to lubricate contacts.

Answer:

d. Pe,%. n;7.ii a PM to lutwicate contacts

Notes:

"D* is pe.r: 'W since it is routine maintenance which doesnt require tweaker operation.

'C' is not allowed even though the breaker is removed, connections intomal to cubicie would be e

"A" is incorred, maintenance is not permitted on a hold carded breaker.

B' is wrong since breaker operation is not allowed, even just racking it up or down.

References:

1000.027, Hold and Caution Card Control Rev. 24, pages 12 & 13

History:

Developed for 1998 SRO/RO exam

11 e f 56

vez

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rsac e m wesy a w -:-

REY

24

1000.027

HOLD AND CAUTION CARD CCNTROL

ausoz;

~

IAF;3 :N E'ECT.~CA*

ElU FMENT

shall,be Carded with the tag conspicuously hung on

All grounding devices

'

grounding device ano shall specify GROUNDING DEVICE INSTALLED.

.

the

for load center breaPers should specify BREAKER RACKED OUT and

7.2

CARDS

should be hung on the cubicle door.

The breaker may be removed or

reinstalled as long as the areaker does NOT get racked in.

for MCC breakers should specify BREAKER OPEN/ REMOVED and should be

".3

CAPDS

hung on the exterior breaker door.

For breakers with lights on the breaker door, the operator shall

check the light indication before and after hanging the CARD to

ensure the breaker mechanism has actually opened the breaker.

, .

.r,

.,

For breakers without light indication, then alternate methods should

,

I

be utilized such as checking remote lighp indication or opening the

"" O " '

MCC breaker door and verifying'tir' aker poYitilbn'.*l

'

e

7.4

Switchgear Breakers

CARDS for 2A9 Switchgear should specify BREAKER RACKED OUT and should

be hung on the cubicle door. The breaker may be removed or installed

long as the breaker does NOT get racked in.

!

as

For EST switchgear breakers (A3, A4, 2A3 and 2A4), BREAKER RACKED

l

'

DOWN means the breaker has been racked down to the floor then racked

(3.3.H

!

up -1" off the floor.

This will ensure the seismic analysis of the

ESF switchgear is maintained.

CARDS for switchgear breakers other than ZA9 should specify BREAKER

and should be hung near the elevator engagement lever.

RACKED DOWN,

The breaker may be removed from or be reinstalled in its cubicle as

long as the breaker does NOT get racked up.

,5

If a Carded MCC oreaker must be removed from its cubicle, then the Craft

snall :ocrdinate with Operations to perform the following:

l

,

'.5.1.

Obtain CRS permissiva to remove the bres

r and move CARD as

necessary.

Remove breaker from cubicle ensuring the breaker remains open

i

7.5.2.

l

at all times.

i

l

7.5.3.

Re-attach the CARD to the exterior breaker door as required

f

to ensure the CARD remains at the MCC door.

l

A Carded cubicle breaker ray not be reinstalled unless the

l

7.5.4.

craftsperson installing tne breaker is the only one left on

the tagout or the tag hr.s been cleared.

~.6

If a bus is deenergized for breaker FMs, the CARDS may be removed using

Electrical Bus Hold Card Authorization Addendum (1000.027N).

a

__ _ . . _ _ _ _ _

_ _

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

. ______--_

.

. . .

~

12 of $6

PKr* v;PY T.M WC

7pccr.DURz,w0py 3 M ;;;;,g

j

pagg;

Rev

24

1000 027

HOLD AND CAUTION CARD CONTROL

[

muscr:

.

A Carced MCC Dreaxer may nave its cuolcle door opened to perform

~ ~

l

nspections, limited cubicle maintenance, or insulation resistance

testing provided the following conditions are met:

,,

,

'

7.7.1.

Activities involving actual terminations to a molded case

j

breaker in an MCC cubicle shall be performed with the breaker

disconnected from the bus (in its test position with locking

i

tabs in place) or removed from the MCC.

.

l

7.7.2.

INSPECTION ACTIVITIES

The person wants the door opened for inspection purposes

i:

only.

This activity will not cause accidental closure of the

!

-

breaker

(i.e.,

look only).

7.7.3.

LIMITED MAINTENANCE ACTIVITIES, emws3 u wn ,

1.

The person wants the?doorfopeneditorjectivities agreed to

l

by the<CAS,as-minor in,natura g p q p y,g ,y.g ,

m m AsA;m , ,s.2.m . f

.

2.

When work is complete, the individual verifies the

j

breaker is still in the position specified on the CARD

and the door is Leclosed.

7.7.4.

INSULATION RESISTANCE TESTING

1

1.

The craftsperson performing the insulation resistance

L

test must notify his/her supervisor for concurrence.

I.

I

.2.

The cognizant supervisor shall review all CARDS attached

to the cubicle to determine if any associated work or

1

workers might be at-risk due to_ accidental energization,

and take actions necessary to prevent' injury.

3.

If any associated work is identified (CARDS hung)

allowing unrelated work on power cables, penetrations,

terminal boxes or other items that may be energized by

!

the insulation resistance test, then ene cognizant

superv'isor must determine appropriate action to ensure

worker safety.

This might include posting a safety man

(

'

at the affected area, contacting the other work crew,

obtaining a temp clear or performing the insulation

resistance test later.

L

4.

Station a safety person at +ho load powered by the

circuit breaker if it in in an accessible area.

5.

The circuit breaker remains open at all times.

i

6.

When work is complete, the individual verifies the

l

j

breaker is still in the position specified on the CARD

j

and the door is reclosed.

L

s

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I

swr yv

y

-mr

y

w-

_

_ _ _

_.

. _ _ _ _

_

_ _

_

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_ . _ _ _ . _ _ _

_

_ . .

m en r.M e

rs:ct.:'eus wepy r Ax c: : z

i pa.2e

13 of 56

l

E'

24

1300 02'

HOLD AND AUTION CARD CONTROL

MMSGE:

.-

Wnen a swit:ngear test.;r:ana crea<er is ceing rac<ec up or cown, tnen

l

nat crea<er ;otat;cn snal. N;; ce used as an isclation boundary..

Any

HOLD CAPD on that breaker location shall be released.

!

CARDS for switchgear test / grounding breakers should specify SUS GROUNDED

7.9

l

or LINE GROUNDED as applicable, and should be hung on the operating

i

handle on the breaker face.

7.10

CARDS should be hung so that normal, safe maintenance of breakers and

l

cubicles, that does NOT tamper with the isolation condition, may be

performed.

' 11

Conductive materials, such as wire, shall not be used for attaching

j

.

CARDS on or near electrical devices.

,

7.12

When fuses are to be pulled for CARD installation, Electrical

Maintenance should be contacted to remove any fuse if the circuit

!

voltage is greater than 150 VAC or 150 VDC.a 1<#

.

~

l

7.13

During special conditions or testing when there is essentially no risk

to personnel, equipment, or p! ant operations, control switches may be

carded to prevent operation.

' ;4

4160V and 6900V breaker control switches may be used .to provide

equipment protection only.

This is intended for short term usage.

For

l

.

consideration should be given to racking

i

long term equipment protection,

down breaker.

.

1.15

CARDS on control switches shall NOT provide the only barrier for

l

personnel and equipment protection unless no other plausiule isolation

methods are available.

Considec using other methods to provide physical

j

restraant or isolation in addition to the control switch.

,

i

control switch provide the only barrier for

If it is necessary that a

personnel or equipment protection, then the CRS shall approve its use

i

and inform the Lead Craftsman,

i

l

~ ;{

Tor Uni

4160 and 6900 V breakers, place their handswitch in PTL prior

'

l

>

to racking down the breaker.

It is not necessary to CARD the handswitch

plastic information label hung on the handswitch is

i

n PTL, however, a

desired.

This prov; des the Control Poom Operators with the reason the

component is out of service and minimizes potential for auto start while

the breaker is being operated.

i

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.- ,

-

_~ -

75 ..- vsy tw v

rs :n: 52 v:sy ;;.g n I

FAar

14 of 56

~, 0 0 02'

HOLD AND CAUTION CARD CONTROL

ReV

34

, cuect

f( ;

~

"a:35 i: Brear,e:! Bus ?Ms

.

".;~...

Wnen seenergi:ing an electri:al bus for breaker / bus PMs, all

CARDS hung on any associated breaker shall be documented on

Electrical Bus Hold Card Authorization Addendum (1000.027N).

The Hold Card Authorization Form shall be annotated to

i

reference Form 1000.027N, and the form attached to the Hold

Card Authorization Form.

Any CARDS removed shall be retained

with Form 1000.027N.

'.17.2.

CARDS required to be hung on the bus during the breaker / bus

PMs shall be added to Form 1000.027N.

7.17.3.

If desired to remove CARDS providing boundary isolation for

the breaker / bus PMs, then perform either_of the following:

. .

J

Hang and verify all' CARDS removedWbyeroemy1000.027N.

,

Verify all' Craftsman] protected M

' ap'MW'rs,ial/Temporary

(

Un Pa

have provided release'authbrizati~

Release Authorization Sheet (1000"927C),J,9%,

--

+ An.g ,-

,

l

7.17.4.

Prior to permanent removal of the breaker / bus PM CARDS and

j

bus restoration, verify each breaker on Form 1000.027N is in

1

'

the required position with CARD installed.

Independent

'

l

Verification shall be performed prior to bus restoration.

[

l

8

CARDS ON MECHANICAL. EQUIPMENT.

!

8.1

Vents and drains opened for system depressurization and draining for

l

personnel protection shall be hold carded.

For those that will be

removed or worked on during the maintenance, tagging is NOT required.

8.2

Hard piped vents and drains that share a common header with other

components may require isolation to ensure adequate protection.

l

3.3

If a system or component cannot be drained completely due to lack or

j

location of vents and drains, use diverse methods to ensure adequate

i

isolation as follows:

l

If en a steam system, perform the isolation and later check that it

l

e

!

has cooled to near ambient temperature.

Annotate information about the incomplete draindown on the tagout.

When systems are opened that are not completely vented and drained,

!

component boundaries shall be disassembled slowly and carefully.

!

(

34

Double valve inolation shall be considere3 .or high energy systems

l

(>200'F or >2~ 5 psig) with an open intermediary drain where possible.

!

9.5

!! double valve' Isolation from a high energy system is not practical due

,

to system limitations, then the operator determining hold card

installat;on boundaries should specify a means of completing a leak

check at or near normal system operating pressure for each necessary

s;ngle valve isolation boundary.

.

.u. e n ;:a::::al, use ranua; valves as bouncary :solations

- -

4

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_

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_ ____.

_

.

_ _.

_ _ _

_

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1998 \\NO- I nit I %RC SRO(t i License Esam Analysis

1

l

NROil ) Esammation Analysis Summary

I

The eumination uas admmistered to six SRO(U) candidates. The following chart summarizes the

candidates responses to questions on the e.samination:

i

6of6

5 of 6

4 of 6

3 of 6

2 of 6

lof6

00f6

I CORRECT

CORRECT

I

50

23

13

8

2

1

3

j

An analysis was performed on the 14 questions incorrectly answered by 2 50% of the candidates. Analysis

results are summanzed below.

,

_

QlD

No.

Analysis Results:

.

-

\\

- u.a,w

0054

40

Answer keyed wrong Changed answer key to cornx* respdMeiDWF%

(6 of 6 incorrect)

0061

44

Question and answer are correct as wntten. (3 of 6 incorred)

0067

48

Question and answer are correct as written. (5 of 6 incorrect)

0068

49

The question will be revised prior to reuse, but the correct answer can be

,

determined as written. High difficulty level. (3 of 6 incorrect)

,

0069

50

Question and answer are correct as wnteen (3 of 6 incorrect)

0087

64

Changed answ:r to "C" See attached response (6 of 6 incorrect)

J

0088

65

Question and answer are correct as written. High difficulty level.

(4 of 6 incorrect)

,

'

1

0090

67

Question and answer are correct as written. (3 of 6 incorrect)

'

0095

71

Deleted question. No correct answer. See attached response. (6 of 6 incorrect)

0108

81

Question and answer are correct as written. (3 of 6 incorrect)

0112

85

Question deleted. See attached response from RO Exam Analysis.

(3 of 6 incorrect)

l

0114

87

Answer "B" accepted as correct in addition to answer "D". See attached response

from RO Exam Analysis. (3 of 6 incorrect)

!

0126

96

Question and answer are correct as written. (3 of 6 incorrect)

0128

98

Question and answer 1re correct as written. (4 of 6 incorrect)

i

,

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1

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t

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_ _ -. . _ _ _ _ -

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

_ _ . . _ .

l

_-

.

INITI AL RO/SRO EXAM CANK GUESTION DATA

ARKANSAS NUCLEAR ONE - UNIT 1

QlD: C34

Rev: 0

Rev Date: 7/11/98'

Source: New

~ diiginator: GGiles

TUOl: 4 NO-1-LP RO-ICS

Objective: 30

Point Value: 1

1

.

l

Section: 3 4

Type: Heat Removal From Reactor Core

System Number: 003

System Title: Reactor Coolant Pump System (RCPS)

j

Description: Knowledge of the effect that a loss or malfunction of the RCPS will have on the following: ICS.

l

K/A Number: K3.05

CFR Reference: CFR: 41.7 / 45.6

,

Tier:

2

RO Imp:

3.6

RO Select:

No

Difficulty: 4

Group: 1

SRO Imp: 3.7

SRO Select: Yes

Taxonomy: An

l

Questiori$

Given the followmg plant conditions:

,

)

- Power at 27%

- ICS in full automate

- D Reactor Coolant Pump trips

Which of the following best describes ICS response to the change in RCS flow?

a. Delta Tc will remain at zero (0) due to the response of the total flow controller.

b. A Delta-Tc error will develop with Loop A Tc < Loop B Tc due to the msponse of the total flow controller.

,

j

c. A Delta-Tc error will develop with Lcop B Tc < Loop A Tc due to the response of the total flow controller.

d. Delta-Tc will not be effected due to the total flow controller signal being blocked.

Answer:

l

b. A Delta-Tc error will develop with Loop A Tc < Loop B Tc due to the response of the total flow controller.

Notes:

D RCP trip affects Loop A RCS flow. The RCP trip will cause IC , .s re-ratio feedwater flow demands.

Feedwater Loop A demand will go down and Feedwater Loop B demand will go up. At the given power level,

A loop feedwater demand will go down until the A OTSG reaches low level limits. The total flow controller will

then be released and Delta Tc will be sacrificed to maintain total feedwater demand. Therefore, (b) is the

only correct response.

!

-

References:

STM * A (Rev 5), Integrated Control System, pages 41 and 42.

History:

Developed for the 1998 SRO Exam.

,

4

i

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.

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._.

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. - -- ~.- - .

~ -.-

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. . - . -

.

. . ... .

.

_

Ql0008"

SRO Question 64

Question:

Durmg a Blackout condition. it may become necessary to perform an EDG start without DC control power.

In this condition, how is the generator output voltage adjusted (no battery chargers are loaded)?

a.

Adjusting engine speed via speed setting knob on governor.

b. The automatic voltage adjuster will still function.

c.

Using the manual voltage adjuster on Exciter Control Panel.

d.

Using voltage adjuster handswitch on C10.

Answer:

,g.g ,gg ..

,

.

, . ,

,

b. De autonudic,vokage a4sster.will st31 function.94 TFTPiP8, MMIt,$@bNMkNNfWN *

.

-

,~ v

,

,.n .

~

'

Exam Analysis Results:

Change correct response to (c).

Justification:

In accordance with 1104.036, Emergency Diesel Generator Operation, a loss of DC power to the field

flashing circuit will cause a loss of automat 4c voltage regulator setpoint a4ue=aat due to a loss ofpower to

the motor operated rhoostat Although the seapoint of the automatic voltage reguistor cannot be a4usted, the

automatic voltage regulator will still function to n==*== voltage. However, abo seem of the question asks

for how the generator output voltage will be adjusted versus mamtmined. His implies an action De correct

action to take if voltage adjustment is required is described in' 1104.036, EmergencyDiesel Generator

Operation, Step 11.10.1, which states

if voltagefalls outside 3800-4500 volts, place Excitation control selector switch (on Elifor DGI, E21for

'X12) in MANUAL and c'" -* the manual voltage adjust dial as necessary.

Herefore, the correct response as the question is written should be (c).

.

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m._

_ _ - - -

_,

.

a-

.-

. .

- - . -

INITIAL RO/SRO EXAM CANK QUESTION DATA

ARKANSAS NUCLEAR ONE UNIT 1

-

. - . . . .

_-

QlD: 0087

Rev: 0

Rev Date: 7/11/98

Source: New

Originator: JCorK

-.

._

TUOl: ANO-1 LP-RO EDG

Objective: 22

Point Value: 1

Section: 3.6

Type: Electrical

System Number: 063

System Title:

D.C. Electrical Distribution

Knowledge of the effect that a loss or malfunction of the de electrical system will have o

Description:

followin0: ED/G

K/A Number: K3.01

CFR Reference: CFR: 41.7 / 45.6

Tier:

2

RO Imp:

3.7

RO Select:

No

Difficulty: 3

Group: 2

SRO Imp: 4.1

3RO Select: Yes

Taxonomy: C

Question:

Durtne a Blackout condhion, it may become necessary to perform an 500 start nthout DC c

In this condition, how le the generator output voltage acqueted (no bettery chargers are loaded)?

a. Adjustin0 en0ine speed via speed setting knob on governor,

b. The automatic voltage adjuster will still function.

c. Using the manuel voltage adjuster on Excster Control Panel.

d. Usin0 volta 0e adjuster handswitch on C10.

Answer:

b. The automatic voltage asqueter will still function.

Notes:

Without DC control power the automatic voltage SETPOINT will not be present, but since th

EDG generator controls are powered directly from its output, the auto voltage adjuster will s

Therefore "B" is the correct answer as long as battery chargers are not loaded restosing DC p

probably skewing voltage with the restoration of the automatic setpoint.

This would then requite the use of the manual adjuster as s.

..swer "c".

Answer *D" is incorrect, no DC power is available.

Answer "a" is incorrect, this will adjust frequency, not voltage.

- n

References:

1104.036, Emesgency Diesel Generator Operation Rev. 37, page 21

History:

Developed for 1998 SRO exam

l

- - - - - - - _ _ _ _ _ _ _ _ _

! PROC.WORX Pt.AN W

P90CEDUREMORM Pt.AN Tm.E:

} PAGE:

31 of 160

3I

1104.036

EMERGENCY O!ESEL GENERATOR OPERATIOfd

RM

l cKANGE:

-

CAUTION

IWithlossofcontrolpower,

the only functional DG protection is the

nachanical overs;;:d device.

11.8

Start diesel generator by overriding one of the starter solenoid

valves with the override plunger.

Release solenoid when engine

starts.

11.8.1

M DG does not start after -5 seconds, repeat step 11.6.

11.8.2

I,,f,it becosnes necessary to shut down the diesel:

A.

Pull the EMFJtGENCY FUF.L CUTorr (FO-66A for DG1, FO-665

^

for DG2) valve handle,

.

.x. ,, w ,4,4p.g,;w

,.w.

>

-~c

-

tK '

%gfql,9

%

yy,wf{tf Q W Hsy. ~

'

.

B.

Release the governor solenoid by,. lifting.the knucled

knob, thus releasing the locking pin,' and push the

knurled knob d m and ensure fuel rack lever returns

to the shutdorni position (black pointer snovos to <1 on

governor).

11.9

Verify governor maintains engine speed at -900 RPM speed and -60 Hz.

If necessary, adjust engine speed by turning speed setting knob on

governor.

NOTE

loss of DC power to field flashing circuit will cause loss of autonnatic

voltage regulator setpoint adjustment (loss of power to motor-operated

rhoostat). Automatic voltage regulation should stil1Vfunction..

11.10

Verify diesel generator output voltage is normal.

11.10.1

g voltage falls outside 3800-4500 volts, place Excitation

control selector switch ron E11 for DG1, E21 for DG2) in

MANUAL and adjust the manual voltage adjust clal as

necessary.

CAUTIO84

l

The next step will cause automatic loading of the diesel if 125V DC is

restored through a battery charger.

Be prepared to manually adjust the

diesel voltage and frequency each time a load is started.

11.11

Manually close output breaker for diesel that was started (A-308 for

DG1, A-408 for DG2).

.

..

.. ..

..

_ _ .

_.

_ _ _ _ _ _ - _ _ _ _ _ _ - _ - - -

_ _ - - _ _ _

()ll) 00 6

R4 ) 1.s.un (Jur imn ~l

(juntmn:

ES AS ha< actuated due to a LOC A

RCS pressure has dropped to approsimately 1200 psig uithm five minutes of actuation.

Which of the following best describes the etTects on the ICW system or the components it cools?

a All RCPs must be secured due to loss of seal coolmg

b CRD cooling pumps must be secured due to isolation of discharge path.

ICW booster pumps are protected by opening of b pass valve.

c

3

d.

ICW pumps must be secured due to isolation of SW to ICW coolers.

Answer:

b CRD cooling pumps must be secured due to isolation of discharge path.

Exam Analysis Results:

I

Delete question due to no correct response as written

/

Justification:

1104 028. ICW System Operation, Section 5.0. Limits and Precautions, Step 5.1 states:

Runmng CRD Pumps (P-79A or B) at a shut-ofhead will lead to pump damage. A shut-offhead could be

encountered after ESactuation or upon closure ofthefollowing:

Non-Nuclear ICWfor RCP Air & Lube Od Coolers and CRD 's Outlet (CV-2220 or CV-2221)

a

h Non-Nuclear ICW thr RCP Air & Lube Od Coolers and CRD 's Inlet (CV-2235).

Howeser. the stem of the question directs the candidate's attention to the ES A S procedure from the given

plant conditions The stem of the question does not state the status of RCPs. No specific actions concerning

CRD cooling pumps are stated in 1202.010, ESAS emergency operating procedure. The actions taken

following ES actuation include performance of Repetitive Task 10 (RT-10) to verify proper actuation of ES

components. The only action concerning CRD cooling pumps in accordance with 1202.012, Repetitive

Tasks. Step 10 D 4.c. is to verify a CRD cooling pump running if any RCP is running.

De given correct answer is based on a limit and precaution from a normal oper ting procedure, while the

stem of the question directs the candidates attention to an emergency condition. He operational priorities

fellowing 2 LOCA with ES actuation do not include the actions of the limit precaution. The EOP and the

r,ormal operating procedure do not state that the CRD cooling pumps MUST be secured. Herefore, the

question uill be deleted due to no correct response as written.

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INITIAL RO SRO EXAM BANK QUESTION DATA

' ARKANSAS NUCLEAR ONE UNIT 1

.

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TUOl: ANO 1 LP RO-EOP10

Objective: 6

Point Value: 1

Section: 3.8

Type: Plant Service Systems

System Number: 008

System Title: Component Cooling Water System (CCWS)

Description: Abiltty to monitor automatic operation of the CCWS, including: Automatic actions associated

with the CCWS that occur as a result of a safety injection signal.

i

K/A Number: A3.08

CFR Reference: CFR: 41.7 / 45.5

Tier:

2

RO Imp:

3.6

RO Select:

No

Difficulty: 3

Group: 3

SRO imp: 3.7

SRO Select: Yes

Taxonomy: C

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Question:

i

ESAS has actuated due to a LOCA.

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RCS pressure has dropped to approximately 1200 psig within five minutes of actuation

Which of the fcitowing best desenbes the effects on the ICW system or the components it cools?

a. All RCP's must be secured due to loss of seal cooling.

b. CRD cooling pumps must be secured due to isolation of discharge path.

c. ICW Booster pumps are protected by opening of bypass valve,

d. ICW pumps must be secured due to isolation of SW to ICW coolers

Answer;

b. CRD cooling pumps must be secured due to isolation of discharge path.

!

Notes:

B* is corTect per limrts and precautions in 1104 028. damage may occur due to running at shutoff head.

"A" is incorrect, RCP's are secured due to loss of subcooling margin in ths situation.

,

!-

'C' is incorrect. ICW Bocster pumps should be secured due to isolation of suction and discharge and RCP's

i

are not needed.

D" is incorrect, SW will be isolated to cooters but this doesn't require secunng ICW pumps.

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(SRos review EOPs under TUCI AA61004 001 using RO lesson plans.)

References:

}

1104 028. ICW System Operating Procedure. Rev. 20 PC-4. page 4

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History:

Developed for 1998 SRO exam

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oc.woRx Fus

ntocEDURE, WORK PLAN TTTLE:

PaGE:

4cf63

e

20

ICW SYSTEM OPERATING PROCEDURE

'

1104.028

l CHANGE: PC-2,

f

4.~

REFERENCES USED IN CCNJL*NCTION WITH THIS PROCEDURE

4

4.2.1

Plant Startup (CP 1102.002)

<

4.2.2

Plant Shutdown and Cooldown (OP 1102.010)

.

!

4.3

NRC Cole (ITMENTS

f4

4.3.1

P 13736, verify that the correct chemicals are being.added

'

0

to the appropriate systests.

Contained in Nuclear ICW Loop

h-

Chemical Addition and Nort-Nuclear ICW Loop Chemical

,

Addition sections.

5.0

LIMITS & PRECAUTIONS

5.1

Avoid frequent starts of any ICW puey.

,

gg

, , ,

dannage. A shut-off head.could be encountered afto'jpild.fMSW

Runnimig CRD Pumps (P-7A Eor S fdt N imat-off bead

5.2

r!ESLaotuation or

upon closure of any of the followings

c @, ;

3,

A.

Non-Nuclear ICW For RCP Air & Lube Oil Cool'ers and CRD's

Outlet (CV-2220 or CV-2221)

8.

Non-Nuclear ICW For RCP Air & Lube 011 Coolers and CRD's

Inlet (CV-2235)

,

5.3

Before starting any pump after prolonged system shutdown or following

maintenance on the pump, ensure pump casings are filled & vented.

5.4

If ICK to DCP seal cooling is interrupted due to closure of RCP seal

Clr and Ltdn Cirs NUC ICW Supp Isol (CV-2233) or RCP. seal Cir and Ltdn

Cirs NUC ICW Rtn Isol (CV-2214) or both, stop the RCP, Seal Cooling

Pumpts) (P-114A, P-1148) and open the RCP Seal Cooling Pumps Bypass

!

ICV-2287) until flow can be restored.

5.1

Minimize temperature transients when adjusting ICW temperature.

.s

CRD cool:.ng is lost cue ta pump failure, filter clogging, or loss

Of suction, prompt operator action is required te prevent CRDM's from

reacning maximum allowed temperature.

5.7

Due to serv >ce water normally being cross-connected at the inlet to

the ICW coolers, any adjustment on either ICW Coolers Loop I SW Bypass

(SW-4026A) or ICW Coolers Loop II SW Bypass (SW-40268) will affect

both nuclear & non-nuclear temperatures.

5.8

Prior to energizing the CRDM's or at RCS temperatures >200*F, CRD

cooling water shall be provided, except for stator replacement.

5.9

Maximum allowable temperature of CRD cooling water entering the CRDM

s 120*F.

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9202 092

REPETITIVE TASKS

REV 3

Page 1 of 4

NOTE

Obtain Shif t Superintendent /CRS permission prior to overriding ES.

RB H2 sampling must be established within 13 minutes of ESAS actuation.

10. Verify proper ESAS actuation:

A. Venfy BWST Outlets open (CV 1407 and 1408).

1) LF CV 1407 or 1408 fails to open,

THEN stop associated HPl, LPI, and RB Spray pumps until failed valve is opened.

j

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B. Verify SERV WTR to DG1 and DG2 Cl.Rs open (CV-3806 and 3807).

J

C. IF RCP Seal INJ Block (CV-1206) closed on low flow,

j

THEN restore Seal Injection as follows:

1

1) Place RC Pump Seals Total INJ Flow (CV-1207) in HAND AND close.

2) Place CV-1206 in OVRD AND open.

1

E RCP Seal Bleedoff temps are 5180*F,

3)

THEN slowly open CV-1207 until 30 to 40 gpm total flow is reached AND place in

j

AUTO.

4) LF RCP Seal Bleedoff temps are > 180*F,

THEN slowly open CV-1207 until 8 to 12 gpm total flow is reached.

,

al Record current time

b) Maintain 8 to 12 gpm total flow for at least 30 minutes,

Af ter 30 minutes. slowly open CV-1207 until 30 to 40 gpm total flow is reached

i

c)

AND place in AUTO.

D. E any RCP is running, THEN perform the following:

Obtain Shift Superintendent /CRS permission to overrid., ES for RCP services restoration.

1)

2) Dispatch an operator to perform the following:

'

a) Verify the following valves closed:

l

ICW Cooter Loop i SW Bypass (SW-4026A)

..

.

ICW Cooter Loop 11 SW Bypass (SW 40268)

.

c

g ICW Cooler (E28) SW Outlet (SW-8 A, B or C)

.

b) Throttle in-service ICW Cooler (E28) SW Outlets ~ 5 turns open from closed seat

.

(SW F A, B, C).

f

(10. CONTINUED ON NEXT PAGE)

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1202.012

REPETITIVE TASKS

REV 3

PAGE 14 cf 27

Page 2 of 4

10 (Continued).

I

3) Verify Instrument Air System operation by depressing CH1 and CH2 ES Electrical

t

Alignment MAN PBs on C16 and IS.

4) IF ESAS Channel 5 or 6 has actuated,

THEN perform the following:

a) JF > 2 RCPs are running,

THEN reduce number of running RCPs to one per loop.

b) Dispatch an operator to monitor ICW Surge Tanks (T 37A and B) for loss of level as

ICW is aligned to RB, indicating possible piping failure in RB, while continuing with

this procedure.

c) Verify the following pumps running:

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Two ICW pumps (P33A, B, C)

U

One RCP Seal Cooling pump (P114A or 8)

One CRD Cooling pump (P79A or B) running.

d) Override AND open Nuclear and Non-nuclear ICW Outlets

(CV-2215, 2214, 2221, and 2220).

e) Override AND open Nuclear and Non-nuclear ICW Inlets

(CV-2233, 2234, and 2235).

f) IF piping f ailure is evident,

THEN close Nuclear and Non-nuclear ICW Inlets and Outlets.

,

CAUTQN

SW pump runout can occur with' flow as low as 8000 gpm.

5) WHEN ICW Cooler SW Outlets and Bypasses are aligned,

THEN override AND open one Service Water to ICW Coolers Supply

(CV-3811 or 3820).

a) IF any ES equipment shows signs of overheati .g

j

OR

SW pump approaches runout,

THEN throttle ICW Coolers SW Outlets.

E. Verify proper ESAS Channels tripped:

I

Condition

l Channels Actuated

ih

_RCS press s1550 psig '

1,2,3,4

RB press 218.7 psia

!

1.2.3.4,5.6

RB press 244.7 psia l

7.8.9.10

(10. CONTINUED ON NEXT PAGE)

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PC 5

1202.012

REPETITIVE TASKS

REV 3

PAGE 15 of 2$

Page 3 of 4

1;

ntinueos.

F.

On C19 verify:

8

1) LPI (Decay Heat) Room Cooler running in each Decay Heat Room:

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VUC1 A or B

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AND

.

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VUCIC or D

1

2) E RB Spray has actuated,

THEN verify Service Water to RB Spray P35A and B Lube Oil CLRs open

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(CV-3804 and 3805).

G. Verify sech component property actuate'd on C16,18

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3. , , -,

. . ,m m

those: overridden in

,

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presms steps.

s

1) Vdrify proper ES system flow rates &Mnc@9 * r esvEpNW$Nedew

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2) E only one train of HPl is available

.

I

AND

,,

RCS press is > 600 psig,

TtgN throttle the HFI Block valve with the highest flow to within 20 gpm of the next

hq$wst flow.

H. On C10 verify:

.

1) Both DGs operating,

.

2) A3 to A4 Crossties open (A-310 and 410),

3) B5 to 86 t rossties open (B-513 and 61??

.

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4) Unit AUX feeds to A1 and A2 open (A 112 and 212),

5) Both A3 feeds to 85 closed (A-301 and B-512),

6) Both A4 feeds to B6 closed (A-401 and B-612).

l.

On C09 verify:

I

i

1) AUX Cooling Water header depressurized.

I

2) Proper EFW actuation and control:

Verify F.FW actuation indicated on Bus 1 and 2 of both trains A and B on C09.

I

a)

Verify at least one EFW pump (P7 A or B) running with flow to SG(s).

b)

c) IF SCM is less than adequate, THEN select Reflux Boiling setpoint.

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f10. CONTINUED ON NEXT PAGE)

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PC-1. 5

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1202.012

REPETITIVE TASKS

REV 3

PAGE 16 of 21

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1C (Continued).

Page 4 of 4 l

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di Verify EFW CNTRL vaives modulate such that SG levels are controlling at or

approaching the applicable level at 2 Required Minimum Fill Rate, unless throttling is

required to prevent overcooling:

i

SG A

SG B

I

CV-2645

P7A

CV-2647

i

CV-2646

P7B

CV-2648

M5

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Condtion

Level Sand

Required Minimum Fill Rate

.

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my#.~ ,w.. w , , .

Any RCP runnino

20 to' 40'.A

"' N O?EU M N M -i

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s.

na r . .

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yhsj,2Ao,8"dminin AUTO

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s

5+

..

,

All RCPs off

300 to 340"

280 gpm/SG in HAND -

_

2 SGs swallalde

1 SG available

All RCPs off

2 to 8"/ min in AUTO

AND

370 to 410"

QB

430 gpm in HAND

Reflux Boiling Selected

280 gpm/SG in HAND

,

e) E all RCPs are off,

.

THEN check primary to secondary heat transfer in progress indicated by all of the

following:

T-cold tracking associated SG T sat (Fig. 2)

T-hot tracking CET temps

4

T hot /T-cold AT stable or dropping

.

J. Initiate RB Ha sampling within 13 minutes of ESAS actuation using Containment Hydrogen l

Control (1104.031), Exhibit A.

I

K. E AUX Lube Oil pump for running HPI pump f ails to stop after 20 second time delay,

THEN within one hour of ESAS actuation dispatch an operator to stop AUX Lube Oil pump

'

locally at breaker.

I

mi

P-64A

P-648

P-64C

1,

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B5721

B5722/B6515

B6514

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L. Monitor ESAS alarms on K-11.

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This page is intentionally left blank

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3

ATTACHMENT 3

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FINAL WRITTEN EXAMINATIONS, ANSWER KEYS, ~

' !

AND PROCTOR'S COMMENTS

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Arkansas Nuclear One-l' nit I

'

Initial 1.icensing Esamination Written Esamination Comments

wi t s8

'

QlD

' QUESTION NO.

QUESTION

RESPONSE

0076

SRO(U): 56

Are all rates " power rates"?

All rates are " rates of change of

Power?

RO: 61

0085

SRO(U): 63

Can you clarify " normal source"?

Word non tal in stem of question is

in refereri c to the inverter only.

0124

SRO(U): 95

Does the term " natural circulation

Natural circulation cooling is

c Idown established" mean

established.

RO: 98

" natural circulation cooldon

established or cooldown in

Pmgress?"

.

0095

SRO(U) 71

What assumptions are we to make

ESAS functions normally for given

for given initial conditions?

initial conditions.

0105

SRO(U) 78

What is meant by " implementing?"

The person responsible for

7

'

" assembling."

0120-

SRO(U) 91

Are the team members volunteers?

The team members are NOT

I""I'**

RO 95 '

0121

SRO(U) 92

Are the initial conditions correct?

Candidates asked to change 1.8 to -

13 Rent in the W condMons.

RO %

Pen andink change made to exam

originals.

0124.

SRO(U) 95

Does Blackout still exist at these

Yes, Blackout still exists.

""

* " " "

"5

RO 98

0108'

SRO(U) 81

is the question asking for the

What will the valve do with the

Position of the valve due to a loss

given plant conditons..

RO 86

ofinsuument air?

0058

RO 47

What does " commencing" imply?

" Commencing" implies " starting."

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ES-401

Site-Specific Wntien Examination

Fonn ES-4017

i

Cover Sheet

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U.S. Nuclear Regulatory Commission

Arkansas Nuclear One

Written Examination

.

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App 5cantInfonnation

Name:

Region: IV

Date:

FacityAJnit ANO-UnitOne

Ucense Level: RO

ReactorType: BW

StartTime:

Finish Tune:

Instructions

Use the answer sheets provided to document your answers. Staple this cover sheet on top of the

answer sheets. The passing grade requires a inal grade of at least 80.00 percent Exammation papers

will be collected four hours aber the examina6on starts.

Applicant Certification

M work done on this examination is my own. I have nedher given nor recewed aid.

App 6 cants Signature

Results

99 m

Points

Examination Value

. o y p. ,, . , , ,, - ,, , .

Points

Applicants Score

Percent

Applicants Grade

NUREG-1021

39 of 39

Interim Rev. 8, January 1997

APPENDIX E

POLICIES AND GUIDEUNES FOR TAKING NRC EXAMINATIONS

,

Each examinee shall be briefed on the policies and guidelines applicable to the examination ca

(wntten and/or opersong test) being administered. The applicants may be briefed individually or as a

group. Facdity licensees are encouraged to distnbute a copy of this appendix to every examinee before

the examinations begm. Allitems apply to both initial and requalification examinations, except as noted

PART A - GENERAL GUIDEUNES

1.

. fRead Verbadsf Cheanng on any part of the examinabon will result in a donal of your app 6caho

and/oraccon againstyourlicense.

2.

If you have any questons concoming the admmistraeon of any part of the exammabon, do not

hesitate asking them before starting that part of the test

j

4

SRO applicants will be tested at the level of responsibility of the senior licensed shift position (i.e.,

shift supervisor, senior shift supervisor, or whatever the title of the position may be).

5.

- You must pass every part of the examination to receive a license or to continue performing hcense

duties. Applicants for an SRO-upgrade license may require remedal trammg in order to congnue

their RO duties if the examination reveals deliciences in the reqused knowledge and abdidos.

6.

The NRC exammer is not allowed to reveal the results of any part of the examinahon until they

have been rewewed and approved by NRC management Grades prowded by the facihty licensee

are preliminary until approved by the NRC, You will be informed of the official examination results

about 30 days after all the examinations are complete.

PART B - WRITTEN EXAMINATION GUIDELINES

.

1.

fRead Verbadmf After you complete the examination, sign the statement on the cover sheet

indicadng that the work is your own and you have not received or given assistance in cig@ng

the examination.

2.

To pass the examination, you must achieve a grade of 80.00 percent or greater. Every queston is

worth one point

3.

For an initial examination, the time limit for completing the examination is four hours.

4.

You may bnng pens. pencils and calculators (non-programmable)into the examination room. Use

only black ink to ensure legible copies on the exam cover sheet #2 Lead Pencil, which will be

provided, shall be used on the answer sheet

5.

Print your name in the blank provided on the examinanon cover sheet and the answer sheet You

may be asked to provide the examiner with some form of positive identification.

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Annonniv F

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Mark your answers on tne answer sheet provided and do not leave any question bla

the paper provided ana co not wnte on the back side of the pages. If you decide to chan

onginal answer, erase the incorrect answer completely and then enter the desired answer.

7

(f the intent of a queston is unclear, ask questons of the NRC examiner or the design

l

instructor only.

l

8.

Restroom tnps are permitted, but only one applicant at a dme will be allowed to leave. Avoid a

,

!

contact wrth anyone outside the examination room to eliminate even the appearance or po

i

ofcheating.

!

9.

When you complete the examination, assemble a package including the examination questi

examination aids, answer sneets, and scrap paper and give it to the NRC examiner or proctor.

Remember to sign the statement on the examination cover sheet indicanng that the wor

own and that you have neither given nor received assistance in completing the examination. The

!

l

scrao paper will be disposed of immediately after the examination.

10.

After you have turned in your examination, leave the examination area as defined by the p

!

NRC examiner. If you are found in this area while the examination is stillin progress, your lice

may be denied or revoked.

11.

Do you have any questons?

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NUREG-1021

2 of 5

Intenm Rev. 8, January 1997

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ANO Unit 1 - 1998 Reactor Operator License Exarn

?

Quesdes No.1

QID: 0001

Potat Value: 1

The followmg plaat conditions exist:

A manual plaat rumbar* to 40% of 902 MWe has been -W-

Group 7 Rod 3, sensor temperature is 193 'F and rising.

All other Control Rod stator temperatures are normal.

A stator temperstme HI alarm en the plant computer slum screes is in alarm.

How will the Group 7, Rod 3 seasor temperature be reduced?

a. Mammany trip the menor due to Groep 7, Rod 3 sentor maperature exoosding 190 *F.

b. Transfer Osasy 7 Red 3 to the Amt Bus and pull psegrammercommel Asses der the Asur Power Supply,

c. Drop Group 7, Rod 3 by resonag the six sensor Asses for ,the rod la the CRD trander cabeast.

d. Trander Group 7, Rod 3 to the DC Hold Bus to reduce stator current.

Question No. J

QID: 0002

Point Value: 1

Power escalation as 60% power is la presmas. Current reactor power is 40%. There are 3 ROs la service.

"A" RO is out of service due to an eleckuni fault la breaker H 11 (Reactor Coolant Pemy P-32A).

Which of the fouentag h weedd warrant a anamuel reactor trip?

a. Annunciator "RCP MOTOR WDG TEMP HI" (K08-B3) is in almin with "C" RCP winding temperature

at 280 *F and rimag

b. Breaker B-7146 (ICW Booster Pusep P 114 A) trips opes and P-P 'B fails to auto start causing a loss

of RCP Seal Coohng.

c. A =====*ar "RCP TRIP" (K08 A6) is clear, RCS flow is lowertag and "B" RCP aanperage indicates

0 amps on SPDS.

d. Breaker H-21 (Reactor Coolant Pump P-32D) trips opea due to an own curmet raanistian causing a

lw of the "D" RCP.

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ANO Unit 1 - 1998 Reactor Operator License Exam

Question No. J

QlD: 0004

Point Value: 1

i

The plant is in a degraded power situabon with natural circulation cooldown in progress. The ERV isolation

valve CV-1000 has been closed due to leakage past the ERV. Which of the following best describes the

appropnate action concerning operation of CV-1000 during the cooldown?

'

a. CV-1000 should remain closed dunng the cooldown unul repairs to the ERV are completed.

b CV-1000 should be cycled open and closed during cooldown to prevent thermal binding of the valve.

l

c. CV-1000 should be opened to allow the pressuruer to go solid and transition to a HPI Cooldown.

d. CV-1000 should be deenergtzed and hold carded to prevent operation of the valve during cooldown

Questice No. 4

QID: 0005

Point Value: 1

'

4

The reactor has tripped and 3 control rods failed to fully insert. The CRS has instructed you to perform

Emergency Boration in accordance with RT-12. Which of the following best describes the initial setting on

the batch controller?

"

a. Set the batch controller to the beach size determinad by the plant computer boron program to compensate

for the reactivity worth of the stuck rods.

b. Set the batch controller to the manmum batch size setting of 999999 gallons and commence adding

boric acid to the make up tank.

4

c. Set the batch controller to the batch size required to obtain the boron concentration as determined by a

reactivity balance calculation.

d. Set the batch controller to the batch size required to maintain make up tank level between 55 and 86

inches while maintaining pressunzer level >100 inches.

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ANO Unit 1 - 1998 Reactor Operator License Exam

Question Na, .f

QID: 0007

Point Value: 1

The plant is operating at 100% power and "A" RCP expenences a simultaneous loss of seal cooling and seal

injection flow. Anempts to restore seal cooling and/or seal infaw flow to the pump are unamanful. How

soon should action be taken to avoid damage to the pump seal due to overheating?

a. Within 1 minute

b. Within 2 minutes

c. Within 3 manutes

d. Withia 4 aminutes

Question No. 6

QID: 0008

Point Value: 1

Given:

- Pmcess Radiation Monitor RI-2236, Nuclear ICW, is in alana.

- Nuclear ICW flow rate is >3100 gym

- Local reports of Nuclear ICW Surge Tank overflomag

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A leak in which of the follomag v*s would be capable of caumag these conddaoes?

a. RCP Seal Retura Coolers

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b. Spent Fuel Coolers

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c. Letdown Coolers

d. Pressuruer Sample Cooler

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.\\NO Unit 1 - 1998 Reactor Operator License Exam

Question No. 7

QID: 0009

. Point Value: 1

!

Given the following plant conditions, choose the correct operator response:

A loss of both Main Feedwater Pumps has caused an automatic reactor tnp.

- Annunciator K02-B6, A3 LO. RELAY TRIP, is in alarm

- Steam Dnven EFW Pump P 7A, is tagged out and disassembled for corrective maintenance.

l

- OTSG levels are at 15 inches and slowly dropping.

a. Take manual control of the E:ectric EFW Pump, P 7B, flow control valves and control OTSG levels

at 20 to 40 inches.

b. Start Auxiliary Feedwater Pump, P 75, and contml OTSG levels at 20 to 40 inches using the Startup

!

Control Valves.

c. Close the MFW ! solation Valves to prevent feeding with a Condensate Pump and allow the OTSGs

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to boil dry.

d. Lower OTSG pressure to feed the OTSGs using a Condensate Pump to establish primary to secondary

heat transfer.

Question No. 8

QID: 0010

Point Value: 1

,

Given the following plant conditions, choose the appropriate operator acuons

- Plant is operating at 40% power

- E II A North Waterbox is OOS for maintenance

Condenser vacuum is degrading rapidly

5

a. Trip the reactor and turbine if vacuum falls below 26.5 inches Hg.

i

b. Trip the reactor and turbine if vacuum falls below 24.5 inches Hg.

c. Trip the turbine if vacuum falls below 26.5 inches Hg.

d. Tr'o the turbine if vacuum falls below 24.5 inches Hg.

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ANO Unit 1 - 1998 Reactor Operator License Exam

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Question No. 9

QED: 001/

Point Value: 1

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Due to severt weather the plant is in a station blutr='t condition. The steam driven emergency feedwater

pump (P-7A) is feedtag both steam generators. Under what conditions would an "EE.r.igy RCS Cooldown"

be performed?

a. I.oss of subcooling margin, no HPI available, and reactor vessel head voids are indicated.

b. Reactor vessel head voids are inntward and Core Exit Ther=www=T e temperature > 610 T.

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c. Loss of = Mar margia and steams generator tube to shall delta-T >100 Y (tubes colder).

d. Core Exit Ther=vww=T e temperature > 610 T and steen generator tube to shall delta T >100 T

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(tdes colder).

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Question No.10

QtD: 00/2

Point Valse: 1

Given the following plant conditions:

- Reactor is tnyped

- NNI X Iantnument Power Supply Status lights on Cl3 are OFF

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- NNI Y Instnanent Power Supply Status lights on Cl3 are ON

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What is the W_ pamha= cf CV-1235, the pressunzer level control valve?

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a. Failed 100% open.

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b. Failed 50% open.

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c. Failed 0%open.

d. Functioning normal

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ANO Unit 1 - 1998 Reactor Operator License Exam

Queseion No.11

QID: 00/3

Point Value: 1

Dunng the wtate- =aanha wluch of the followmg would u.dacate a tube leak in Nuclear ICW Cooler, E28C7

a. Increase in SW sysica activity

b. lacrease in ICW Surge Tank level

c. Increase in SW header pressure

d. Decrease is Nuclear ICW header flow

Quesdes Me.12

Qtp: 0014

Point Value: I

' A are watch reported a ihe in the Imer South Elemrual Eqmpansat Roca and the fire brigade has been

ag- r:d How can the control room staff quickly deternune parensi=Ily afrM compoacets?

a. Conduct control board walk <lowns and refer to the plant labchas to assist la descr=namelan

b. Refer to psocedme 1107.001, Elecencal Systesa Operatices, besaker alismusset manneh=ames

c. Deestmine a5scled v Acan the Fire Zone drawings mainealaad in the control room.

d. Refer to the ANO Pro Fire Plan for the asemed the zoos for a listang of a5scoed na-pananas

Quesdos No.13

QID: 0015

Point Value: 1

A fire in the control room forced an i===Amte evacuation. An alternate shutdown is in progress and the crew

is attempting to ardulaw the plant at hot shutdown natural cur =Intian conditions. It is desued to raise reactor

malaat syst;m pressure How is this -9h?

a. Energue all pressuruer heaters front their respective power supply breaker enivelar

b. Raise steasung rate at the Atma =pheric Dump Valves to raise RCS temperature and pressure-

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c. Manually initiate High Pressure Igection to compress the pressuruer steam bubble.

d. Maanally throttle open on the pressunzer makeup block valve to raise pressuruer level.

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Question No.14

QID: 0017

Point Value: 1

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A large break LOCA and several equipnunt failures have placed the plant into an inadequate core cooling

condiuon. Which of the following provids the best indication that core damage has occurred?

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a. Core Exit Thermocouple temperatures en the ICCMDS manue display are flashing and rising.

b. Self Powered Neutron Detector (SPND) cutputs demonstrate progressive high and low swings.

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c. Source Range Monitors indicate higher than normal readings by more than a factor of ten.

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d. The Reactor Vessel Level Monitoring System indscates voids present in the reactor vessel head.

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Question No.15

QID: 0018

Point Value: 1

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Following a reactor trip the plant experiences a loss of eMag margin. Why is it desirable to secure all

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reactor coolant pumps within 2 minutes following a loss of subcooling margin?

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a. To allow the void coefficient of reactivity to add negauve reacuvity to the core.

b. To protect the mechamcal seals on the reactor coolant pumps.

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c. To prevent --- "- a 70% void fraction and possible core uncovery.

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d. To reduce operator burden by securing the RCP's prior to overheaung of motors.

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Question No.16

QID: 0019

Point Value: /

l

Fuel pin leakage has caused higher than normal activity in the reactor coolant system. Which of the following

l

indicauons on the Failed Fuel Monitor (RI-1237) would be indicative of failed fuel and require power

i

reduction?

a. A marked riac by 20% in the IODINE / GROSS ratio.

!

b. A marked rise by 40% in the GROSS / IODINE ratio.

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c. A marked drop by 20% in the IODINE / GROSS ratio.

d. A marked drop by 40% in the GROSS / IODINE ratio.

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ANO Unit 1 - 1998 Reactor Operator License Exam

Quesdem No.17

QID: 0020

Point Value:-1

Given the following indacauons/ alarms

.

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- SASS Ms== mach alana (faa flasu)

- SG B1U Liant alana(slow flash)

f

- SG *B* FW Temp signal select switch selected to SASS Enable with

J

the white indenting light out and the blue "Y" light on.

What operseer asmos is g *

"y requued?

a. Place the SG "B' PW Temp signal seien switch to the "Y" position.

b. Depsess the Ameo y=h int SG "B" FW Temy on the SASS panel la C47-2.

c. No acaca ascessary, SASS has - ~

^'=Hy transfoned to "Y" NNL

d. Place both FW loop demands in manual

Quesdem No.18

QID: 0021

Point Value: 1

1

ne plant is operating at 100% power. A fallast of as ICS modale c'owastseem of the SASS M comms

i

the Nudser Inser======sia= input to the Raamor Demand saadas to Adi low seemidag is a large angssim

asutros error. Assmaung no operator action, how will this fhilure aSect control rods and sanim isedwater flows?

a. Cosmol sods will insert and mais feedwater flows will increase.

b. Control rods will withdraw and main foodwater flows will increase

c. Control rods will insert and main feedwater flows will decrease.

a2 Control rods will withdraw and main foodwater flows will decrease.

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ANO Unit 1 - 1998 Reactor Operator License Exam

Question No.19

QID: 0022

Point Yahme: 1

Which of the following dropped or misaligned control rod arvannos would require a reactor shutdown instead

of a control rod recovery anempt?

a. A fully dropped rod at 38% power

b. A dropped rod at <2% power.

I

c. A portaally dropped rod at 10% power

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d. A rod anisaligand for >24 hours.

<

Question No. 20

QID: 002J

Point Value: 1

The following conditions exist i==artely a8er a reassor trip:

- Group 2, Red 4 failed to fully insert into the awe.

- RCS pressure is at 1750 psig and trending down

- Pressuriser level is at 50 inches and tree <har down

- A OTSO psessess is at 880 paia and trending down

- B OTSG psessues is at 950 psig and trendung down

- Subcooling margia is at 70 Y and trending up slowly

Choose the appropnses operator response.

a. Manually actuate "A" MSLI and EFW.

b. Ca==earw emergency t. ... tion per RT-12.

c. Trip all Reactor Coolant Pumps,

d. Initiate High Pressure Injecuon per RT-2.

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Question No. 21

' QID: 0024

Point Value: /

The plant is operating at 100% power when a single rod drops and fully inserts into the core. ICS is in full

automauc and commences a plant runback Which of the following will determine how fast plant power can

change?

>

a. The operator set rate of change.

b. De pre-set ICS runback rate of change.

c. The speed of the control rods and core age.

d. De rate of change in main feedwater Sow.

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Questica No. 22

QID: 0025

Point Value: 1

The following plant conditions exassed just prior to an automatic reactor trip:

- Reactor power at 45%

- IAss of Bus H 1 due to an electncal fault

"B" Main Feedwater Pump tripped

-

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ch vacumn at 23.5 inches Hg

!

- RCS pressus at 1950 peig '

)

!

Which of the following was the most likely cause of the automatac reactor trip?

a. Main Turbine Anticipatory trip.

b. Power to Pumps tnp.

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c. Variable law Pressure trip.

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d. Main Feedwater Anticipatory trip.

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ANO Unit 1 - 1998 Reactor Operator License Exam

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Quesdes No. 23

QID: 0027

Pelat Value: 1

The following plant conditions exist:

}

Pressuruer temperature is 645 T

Pressmuer level is 225 inches and nmng

i

RCS Pressure is 2150 psig and stable

Quench Tank pressure is 10 peig and nang

,

The ERV acmusuc monitor indicates flow anse

j

What would be the expecaed tempscomme as indicated on the ERV PSV-1000 Oudet Tamp on the

Safety Parameter Display System (SPDS)?

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a. .*;,

",193 T

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b. A

-

^",212 Y

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c. Approximately 239 Y

d. Appenemaanly 645 Y

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Questies No. 24

QID: 0028

Point Yahme: 1

A small betek IACA cooldown is in peogress with mecochng marpa less than adequate.

.

Which of the folloinng cooldown liants apply?

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a. 100 T/hr wben >300 Y

b. 50 T/hr when 300 - 170 Y

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c. 25 T/hr when < 170 7

d. No cocidownlimits apply

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Quesnes No. 25

QID: 0029

Pelat Value: /

l

Given the following plant conditions:

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- Reactor trip from full power

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- Full ES actuence

- ICCMDS Display Sthling Margin indicates 0 'F

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- ICCMDS CET '- ;- - :- -s are alternaung between superheated and saturated conditions.

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Which of the follomag best desenbes the made d RCS cochng for these amadisiana?

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a. RcGuxBodsag

b. Forced Convection

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c. Neaural Circulation

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d. Natural Conduction

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Questies No. 26

QID: 0030

Palat Value: 1

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Dunas a maall brealc thCA cooldown, wiuch of the follomag criteria must be mot before High Pressure

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Igection may be secund?

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a. Ressoration of adequase subanoling margML

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b. Total low pressure injection flow >2800 gym.

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c. Restosauon of forced flow coohng.

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d. At least one OTSG is avadable as a heat sinic.

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Question No. 27

QID: 0031

Point Value: 1

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The unit is operating at 100% power. SU-l transfonner is INOPERABLE. The Startup Transformer Prefermi

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Transfer Switches on C 10 for Al/H1 and A2/H2 are selected to SU-2 transformer. SU-2 feeder breakers to

'

Al, A2, H1 and H2 are out of the pull-to-lock position. Which of the following best describes the electncal

system response to a reactor /turtune trip?

a. With SU-l inoperable, the load shed protects circuitry will require a manual transfer of electncal

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buses to SU-2 due to the limited capacity of SU-2.

b. The resceosAuthse trip will actuses the gemacoast lockout relay and usuk is a " slow transfer" of

Al, A2, H1 and H2 elecencal buses to SU-2 transionner.

!

c. The tie breakare between the vital and non vital buses will open, the meergsacy diesel genorneoss

I

will start and supply the vital buses and SU-2 will power A1, A2, H1 and H2.

d. The generator lockout relay trip will cause a ' fast transfer" to SU-2 transfonner and appliable Iceds

will be shed to limit the loading on SU-2 transformer

Question No. 28

QID: 0032

Point Value: 1

Given:

l

- Plant operasang at 100% pomw

- PZRleveltrendsag down slowly

-IAndown flow 45 span

- Makeup flow 0 spm

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- MUrlevel trending down

-Total sealinjecuon flow 70 spm

Which of the following would cause the above indacations?

a. Makeup pump has tripped

b. PZR level transmitter failed high

c.14ss ofInstrument Air in LNPR

d. Makeup line break upstream of CV-1235

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ANO Unit 1 - 1998 Reactor Operator License Exam

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- Question No. 39

QID: 0033

Point Value: 1

J

Which of the following is an immediate Action performed only for loss of DH Removal due to vortexing?

)

a Close at least one DH suction valve from the RCS.

b Start the other DH pump to makeup to RCS from BWST.

'

c. Irutsate containment closure per Att. G of 1203.028.

d. Stabdue flow by throtthng one of the discharge flowpath valves.

Question No. 30

Q1D: 0034

Point Value: /

Which of the following best describes how the DROPS AMS AC signal trips the main turbine?

a. Relays in the turbine trip circuitry energize the Auto-Stop Oil trip and Backup Trip Solenoids.

b. Relays in the OPC circuitry energize the OPC Solenoids and close the Governor and Intercept Valves.

' c. Relays in tbc EHC circuitry actuate the EHC Solenoid Trip Valve to trip the main turbine.

i

d. Relays in the RPS cabanets actuate the Anucipatory Trip of the main turbine.

)

Question No. 31

Q1D: 0036

Polet Value: 1

Given the following plant conditions:

- Beactor Startup to progress

- Proper overlap between source and interinediate range detectors has been observed

Stabilizing reactor power to obtain critical data

- NI 501 fails low

Choose the correct operator response;

a. Trip the reactor due to the loss of NI 501.

b. Place plant in Hot Shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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c. Continue reactor startup per 1102.008, Approach to Criticality.

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d. htuntain present power level until N1501 repaired.

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ANO Unit 1 - 1998 Reactor Operator License Exam

Quesden Na, 32

QID: 0037

Point Vaine: 1

1202.006, Tine Rupture, emergency operseng procedme pnmdes guadance to " Operate Pressurizer Hansers

AND Pressuruer Spray valve (CV-1008) to amnemn RCS presswe low within limits of Figure 3" while

coohag down the RCS.

What is the PRIMARY reason for maintaining RCS pressure low?

a. To prevent liAiag main steam safeties.

b. To maananias thanaal stresses on the steams pasmessa,

c. To asiaianas the RCS leak mes into the sames ymmenar.

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d. To peuvent cychag of the ERV(CV-1000).

Quesdem No. JJ

QID: 0038

Point F&c .

The plant is shusdown and a cooldown is in progress due to i 2w spa tube leak in the A OTSG

- RCS temperammeis 520 Tandlonenag

- BWSTlevet is at 35 R andlowering

- A OTSGlevelis 290 inehas and shing

- Does rutas at site bonaday are normal

Which of the followng RCS cooldown hauts apply?

a. IAss than or equal to 50 T/ hour.

b. I.ees than or equal to 100 T/ hour,

c. IAss than or equal to 240 T/ hour,

d. IAas than or equal to 520 T/bour.

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ANO Unit 1 - 1998 Reactor Operator License Exam

Question No. 34

QID: 0039

Palat Yahme: /

ICS is in full automauc and the CBOR is unfying proper plant response to a main feedwater pump trip from

100% power

Which of the following should the CBOR expect to occur?

a. The operating main feedwater pump demand will have a bias of 30% added.

b. The pressuriser spray vain will come open whom RCS pressus reaches 2205 p4

c. The coatsoi sods will start insesting inusedssesly dus to a csossiimit fross imedwater,

d. 1he mais desdweser bkdvalves will dass is inst speed osos power goes below 80%

Q=*=ria= No. JJ

QID: 0040

Point Value: 1

Given-

. A degraded power <=iana exists

- Natural circulataca cooldown in progress

- RCS presses at 1700 psig and slowly beseg reduced

-CETs at 5507

- Rancest vessel hand *==r====es at 6147

- Pressunaar level = 150 inches, them makes saep change to 180 inches

What operator action is reqmsed for the above i-6=*h?

a. Comunue the cooldown at an increased rate.

b. Pressmue slightly and reduce cooldown rane.

c. M===*=3= RCS pressme as low as allowed by At*=rs=*=t A.

d. Open all RCS high point vent valves.

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Question No. 36

QID: 0041

Point Value: 1

,

A reactor inp has occurred from 100% power following a loss of D01. Attempts to transfer 125V DC panel

D11 to its emergency supply are unsuccessful. Both OTSGs pressures are ~890 psig. Which of the following

is the appropriate action?

a. Crosstic D 11 and D-21 from panel C-10 in the control room to proside power to Dil.

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b. Manually actuate MSLI and EFW for both OTSGs and verify proper actuation and control.

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c. Select main turbine control to RJRBDE MANUAL and cloes the governor valves in fast speed.

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d. Dispatch as operator to manually trip the main turbine from the main tubane front standard.

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Question No. 37

QID: 0042

Point Value: 1

The plant is operating at 100% power. A radioactive liquid release from a Treated Waste Monitoring Tank (T-

16A) was commenced by the previous shiA. AAer reviewing the release permit paperwork, you discover that

the setpoint on the Liquid Radwaste Process Monitor (RI-4642) is set HIGIER than the setpoint called for on

the release permit.

Which of the following best describes the appropriate actions in accordance with Technical Specifications?

a. Adjust the setpoint to the correct value and continue the release

b. Continue the release since the incorrect setpoint is more conservative.

c. Stop the release and adjust the setpoint to the correct value.

d. Stop the release and sample the tank to obtain a new setpoint.

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Questies No. 38

QID: 004J

Palat Value: 1

,

.

A radioactsve gas release of WGDT T 18B has been terminatad by naaaana Radweste Monitor, RE-4830, in

high alarm Franunnema of the =xorder paper shows RE-4830 had been trending steadaly at ~2000 cpsn when

i

it jumped to 30,000 cpm and then dropped back to ~2000 cpan.

l

What actaon should be taken?

a. Subaut Coadstaca Report and check symem alignment.

l

b. Needy Nuclear Chessisky to podem sette does pndemiens via RDACS.

,

c. Isoises T-ISS and then so st.besit sampling and seisess perudt.

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d. Reset RE4830 and rem

iT-18B gaseous release.

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Questies No. 39

QID: 0046

Point Value: 1

Gives:

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- Degaded Power

- Both EDGs operanas

- ESAS has NOT actuated

- P4C failed to start

Which dthe Adlowing aaions should be WiaW7

a. Close SW Loop IIIsolation Valve (SW 10C).

b. Open SW Imop i & II Cm==*a (SW-5 and SW 6),

c. Close ACWLoopIsotahon(CV-3643).

d. Cross.4ae SW Imops at Makeup Punp (SW-14 thru SW-17).

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ANO Unit 1 - 1998 Reactor Operator License Exam

Quession No. 40

QID: 0047

Pelat Value: 1

In accordamm with the EOP, when do the Pressurtzed Thermal Shock limits NO LONGER apply?

l

a. When the RCS pressure / temperature is to the right of the NDTT limit line on Figure 3.

b. Following restoration of RCP services and starting of Reactor raalant Pumps.

c. Upon ter====aan of High Pressure Tarr+== to the Reactor Coolant System.

d. Following an evalustnes widch will allow morumal RCS pressuss costal to susumes.

._

Questies No. 41

QtD: 0048

Point Value: 1

)

A Blackout has occurred.

1 EDG has been placed in service on a "No DC* start using 1104.036, EwgfDiesel C--or

Operatiost

What DG prosecuca is operable to protect the only operable AC source?

a. positive crankcase pressure trip

b. Iow lubs oilpsessere trip

c. =achanic=1 overspeed trip

d. highJacket water temperature tnp

Question No. 42

QID: 0050

Point Value: 1

A rapid plant shutdown at 4 % per minide is in progress due to a RCS leak inside the reactor MilAia: The

CBOT reports that the RE Oump has risen 7% over the past 5 nunutes.

Which of ;he following best describes the correct response?

a. Continue the rapid plant shutdown at 4 % per minide

b. Raise the shutdown rate to 8 % per minute

c. Initiate HPI to maintain pressurtzer level >200 inches

d. Trip the reactor and turbine and perform immediate actions.

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kkO Unit 1 - 1998 Reactor Operator License Exam

Question No. 43

QID: 0052

Point Value: 1

. The plant had been operating at 100% power for 200 days. Following a plant trip, preparations for startup are

in progress. The CBOR is perfornung a calculation for Estimated Critical Position (ECP). At a given boron

concentration. which of the following times would result in the higbest rod index due to the effects of Xenon?

a. 4 to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

b. 8 to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

c. 40 to 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months

'

d. 70 to 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months

Questice No. 44

QID: 0055

Point Value: /

\\

Without operator action, which of the following incidents would have the most detrimental effect on RCP

operation?

a. Loss of nuclear ICW to RCP

b. Main steam line rupture inside RB

c. Loss of RCP sealinjection

d. RCP Blendas Normal Return, CV 1274, fails closed

Question No. 45

QID: 0055

Polat Value: 1

l'

Batch Controller Flow Control Valve (CV-1249) should normally be open no more than 20% when fe eding

l

boric acid. Why?

j

a. To prevent pump runout on the boric acid pumps

!

'

b. To prw it exceedag design flow through the batch controller.

c. To prevent overheating of the boric acid pumps.

I

d. To prevent inaccurate readings on the batch totaluer.

.

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ANO L~ nit 1 - 1998 Reactor Operator License Exam

Question No. 46

QID: 0057

Point Value: 1

-

Which of the following would result in all ten (10) ESAS Digital Channels receiving an Analog Channel Trip

signal?

,

!

a. Removal of the low RCS Pressure Bistable from Analog Channel 1.

i

b Removal of the RB Pressure Buffer Amphfier from Analog Channel 1.

c. Removal of the 30 psig RB Pressure Bistable from Analog Channel 2.

j

d. Removal of the RCS Pressure Buffer Amplifier from Analog Channel 2.

.

Question No. 47

QID: 0058

Point Value: 1

,

.

l

A startup is in progress. The reactor is critical and the CBOR is commencing power escalation to <2% reactor

l

power. The following indications are obsened:

!

NI-3 1 x 10-8 amps

M-4 8 x 10 7 amps

l

NI 5 0.8%

!

. NI 6 1.1%

i

NI-7 1.3%

i

NI-4 1.2%

What conclusion should you deduce from the above indications?

i

j.

a. Power Range channel 5 requires calibration.

b. He Intermediate Range channels are overcompensated

c. The POAH has not yet been reached.

!

d. Tbc Intermediate Range channels are usc- p = mad-

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ANO Unit 1 - 1998 Reactor Operator License Eram

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Quesnes No. 4

QID: 0059

Pelet Value: 1

Dunas a brge break LOCA the value on the ICCMDS CET Subcochng Margin Display is negative and

1

n="--

What does this indicate?

a. An ICCMDS -=h error,

b. CET rendangs are invahd.

c. Core damage has occurred.

d. CET readagsindicate superheat.

,

Quesdes No, 49

QID: 0060

Point Value: I

Which of the folkmng load centers supply power to the five (5) Ranctor Buikhng Ventilation Fans?

a. B5, B6 and B7

b. B3, B4 and B2

c. B3, B4 and B7

d. B5, B6 and B2

l

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ANO Unit 1 - 1998 Reactor Operator License Exam

Question No. 50

QID: 0062

Polat Value: 1

Given the following plant conditions:

100% power

- Condensate Pump P 2.A OOS

K06-E7 *COND PUMP MTR WDG TEMP HI* is in alarm

- AO reports fire in P-2C motor

J

The CRS instructs the CBOT to trip P-2C, which of the following best describes the correct response?

a. Trip P 2C, perform immaham acuons per 1203.027, Imss of Steam

Generator Feed.

b. Trip P-2C, monitor ICS runhw+ to 40% power and dispatch the fire brigade

per 1203.034, Smoke, Fire or Explosion.

c. Trip P 2C and reduce p'wer per 1203.045, Rapid Plant Shutdown, to maintain

adequate main feed pump suction pressure

d. Trip P-2C then trip the turbine and reactor and carry out imd* actions

per 1202.001, Reactor Trip.

l

Question No. 51

QID: 0063

Point Value: 1

Given:

- 100% power

- ICS in full automatir.

l

The CBOR places the ICS Delta T-Cold Hand Auto Station meter selection switch in "POS" (position). The

meter reads 54%. What does this mean in terms ofICS control of main feed water?

l

a. 'Ihe average of feedwater loop A and feedwater loop B demand is 54%.

I

b. Fredwater loop B demand is greater than feedwater loop A demand.

c. The feedwater loop B demand is being boosted by a 4 'F Delta T-Cold error.

d. Feedwater loop A demand is greater than feedwater loop B demand.

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ANO Unit 1 - 1998 Reactor Operator License Exam

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Quesden No. 52

QID: 0064

Point Value: /

4

1"

Given:

i

'

- SmallBreak LOCA in progress

!

- RCS Pressure at 1500 psig and stabdinag

ES channels I,2 and 4 actuated

<

- ES chmanel 3 failed to actuale

'

Assunung no operator action, which of the following best describes the response dthe EPIC /EFW system?

s. EPIC train A will acessee, EFW pump P 7B is running.

,

i

b. EFIC train A will accuses, EFW pump P-7A is rumming.

,

i

j

c. EPIC train B will actuate, EFW pump P-7A is rummag.

j

d. EFIC train B will actusse, EFW pump P-7B is runaang.

i

j

Questies No. 53

QID: 0065

Point Value: 1

i

A radioactive liquid reicase is in progrees. RI-4642, Lkpud Radweste Process Monster, loses power due to na

a

sisarical duelt. -

j

What e5ect will this have on the release?

f

a. A loss of power will cause a process moster trouble alarm to alert the control

room staff to stantially terrmante the telease

}

b. A loss of power to RI-.d42 will cause a high radiation alarm sgnal which will

{

automatically termmate the release.

s

!

c. A loss of power to RI 4642 will align instrument air to the radwaste flow control

valve, CV-4642, and -

^r=1'y ternunste the release

.

j

d. A loss of power will cause the radweste flow control valve, CV-4642, to fail open

j'

and respuse manual termanaham of the release-

.

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ANO Unit 1 - 1998 Reactor Operator License Exam

Questies No. 54

QID: 0068

Peine Value: 1

Control Venhlatian is in a normal alignment when the Unit 1 Control Roosa IrJet Air Radiation Monitor

(2RITS4001 A) cosses into alarm. VSF4A/B gees OFF and VSF-9 comes ON. Which of the following

desenbes additional expected control room ventilation system response?

a. All fealaham dampers CLOSED,2VSF4A/B ON, and 2VSF-9 OFF.

b. Unit i faal=*iam dampers CLOSED,2VSF4A/B OFF, and 2VSF-9 ON.

c. AllIsolairdampersn en,2VSF4A/B OFF, and 2VSF 9 ON.

<

d. Unit 1isoission dasspersrv rusrn, 2VSF4A/B OFF, and 2VSF-9 OFF.

!

1

I

Questies No. 55

QID: 0069

Point Valas: 1

Given:

- Mammat nacscr trip has taken place, and innandate acucas are @e

-OrSG v levet is incnastag sieve 390-

- orSo 7

is dessessias benew soo pois aphey

- Presseruar pumane and level are decreamag

- Senasa line high aangs nadiation * RI-2682 is la alana

Which of the ibliowing events is la progress?

a. OrSG tube rupture and stuck open MSSV

,

b. OTSG tube rupture and excessne EFW flow

c. Small break LOCA and excessive EFW flow

d. Smallbreak LOCA and stuck open ERV

l.

.

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ANO Unit 1 - 1998 Reactor Operator License Exam

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Question No. 56

QID: 0070

Polet Value: 1

l

Given:

l

- LOCA in progress with Degraded Power conditions

'

EDG 42 did NOT start

- RCS pressure stabilized at 1750 psig

- RCS leakage calculated to be 210 gpm

With these accident conditions, which of the following would pose the greatest challenge to core cooling?

a. RCS leakage increases to 1000 spe

b. Both CPT presswes at $60 psig

c. Lockout relay trips on 41(,0v A3 bus

'

d. initial BWSTlevel at 37 A.

4

i

Questaos No. 57

QID: 0071

Point Value: 1

Gives:

- P36B out of service

- LOCA in progress

- RCS pressee 1250 psig

-.4160v bus A3 doenergized

HPI flows: A = 90 gpm

B = 100 gpm

C = 250 gpm

D = 75 gpm

Which of the following actions is required?

l

a. nrottic *C' flow to within 20 gpm of"B"

b. Throttle "C" flow to within 20 gpm of"D"

c. nrottle all to within 20 gpm of each other

d. nroule *C flow to within 20 gpm of"A"

1

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ANO Unit 1 - 1998 Reactor Operator License Exam

Questies No. 58

QID: 0072

Point Value: 1

Given:

I

l

- RCS pressure 1950 psig and decrusing

(

- RELIEF VALVE OPEN", K09-A1, in alarm

"

l

- ERV inacanne closed

!

- Acousuc monitor indacates ERV is lealang

i

You i==aA% close ERV Isolshoa valve, CV-1000. RCS pressee matt ==as to decrease.

What should your mest actionbe?

a. Begin rJant runiack

b. Cycle tLe ERV

c. Inmaan AallHPI

d. Trip the reassor

Quesdem No, 59

QID: 0073

Pelet Value: 1

A reactor trip occurs fman 100% power.

'IBV acepmat bias does N(yI' nancnos.

You observe all of the PZR beaters turning off.

l

Why did this occur?

a. 4160v bus transfer imm Unit Aux to S/U #1

b. RCS pressure is greater than besser seapoint

c. PZR level decreased due to cooldown

d. PZR swelled, squeezing the steam bubble

{

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Question No. 60

QID: 0075

Polat Value: 1

1

Given:

C" RPS is placed in Channel Bypass for I&C troubleshooting

"

- Plant is at 40% power and stable

- A* MFW pump is in service, "B" h0'W Pump is tripped

Which of the following would cause an automatic reactor trip with the given conditions?

l

a. Contact monitor module pulled in "C" RPS and "A" RPS taken to Shutdown Bypass

b. Tuntune trip contact buffer module pulled in "C" RPS and NI 6 power range test module

taken to " test operate" in Channel "B".

c. Shutdown Bypass 5% power module taken to " test operate" in channel "C" and

"D" channel plamd in Shutdown Bypass.

d. 'l&C deenergizes "C" RPS cabinet and "A" MFW pump contact buffer trip test switch

operated in "A" cabinet.

Qu sta= No. 61

QID: 0076

Point Value: 1

At 100% power, a CRD in Group 6 with a lustory of faulty API has been determined by Incore detectors to be

~50 inches inserted. It has been in this position for at least 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

How would you re-align the rod with the rest of Group 67

j

i

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a. Recuce power to 90% then withdraw rod, while keeping power rate <5%/br.

b. Hold pown and withdraw rod while keeping power <100%.

c. Reduce swer to 60% of MWt for RCP combination then withdraw rod, keeping rate <3%/hr.

d. Reduce power to 40% of 902 MWe then withdraw rod, keeping rates to < 30 %/hr.

_

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ANO Unit 1 - 1998 Reactor Operator License Exam

Questies No. 62

QID: 0077

Point Value: 1

Ginn:

- Loop A RCS flow 68,000,000 lbm/hr

- Loop B RCS flow 63,000,000 lbm/br

-Imop A Taw 578'F

- Loop B Taw 580*F

- Unit Tave 579'F

Which Taw will be selected by the SASS Auto / mammal transfer swieck and why?

a. Unit Teve due toImop B thm

b.14cp ATaw due to Loop B Sow

c. Loop B Tave due toImop B flow

d. Unit Tave, flows are within tolerances

Questies Me 63

QID: 0078

Point Value: 1

If an ESAS occurs =i==le=M with a less of Offuite Power, the start

of RB Spray pumps is delayed by 35 sec. Why?

a. To allow the EDGs to come up to speed.

b. To allow SW pumps to start for spray pump coohng

c. To prevent overtoed of the EDGs.

d. To prevent water hammer of the spray headers.

)

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ANO Unit 1 - 1998 Reactor Operator License Exam

Question No. 64

QID: 0079

Point Value: 1

2

i

Given:

'

Unit operaung at 100%

Reactor Building pressure is 15.9 psia and stable

j

No other abnonnal conditions exist

What action should be taken to lower RB pressure?

,

I

a. Open RB purge inlots first, then open outlets

l

b. Vent RB vis H2 sample lines.

~

c. Use vent flowpath via RB leek detector,

d. Open RB purge oudets firm, then open inlets.

Question No. 65

QID: 0080

Point Value: 1

Which of the following design features allows for the safe storage of new fuel in the spent Anel pool?

a. Sper. ke coohng systent is designed to = min *=in pool temperature <150 *F.

b. Spent fuel boron concentration is ==inenM >1600 ppm boron.

c. A syphon break is incorporated into system piping to prevent inadvertent draining.

d. Fuel racks designed with boraGex plates and adequate spectag

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ANO Unit 1 - 1998 Reactor Operator License Exam

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Qaa*=ria= No. 66

QED: 0081

Point Value: I

Wluch of the following are perfonned by Rapid Feedwater Reducuon (RFR)?

L

l

1) Cicees MFW block valves in fast speed

2) laserts a aero desmand signal into both FW loop eemands

3) Inserts a negative error into the S/U and 14w Load valve controllers

4) Throttles S/U valve to 40% open

,

!

5) Shdts MFW pump control to high FW loop DP

l

6) Closes the lowload block valve

l

7) Holds S/U and Iow Imad vahes shut if MSU is also present

!

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a. 2,3, and 7

b. 1, 2,' and 6

l

c. 1, 3, and 7

l

d. 2,5, and 6

i

Questies No 67

QID: 0083

Point Value: 1

A ressaar startup is is progress with the reassor CRT11 CAL at 1 E-8 amps power. Aa =*==a=ld=ric dump vahe

fhils OPEN Which one of the following descsibes the initial prunary plant response?

l

a. Reactor power will INCREASE, t ,..u-s will DECREASE, and pressure will DECREASE.

L

b. Reactor power will D" CREASE, teenperature will INCREASE, arvi c'essur; will DECREASE.

c. Reactor power will INCREASE, temperatwo will INCREASE, and pressee will INCREASE.

d. Reactor power will INCREASE, temperature will DECREASE, and pressee will INCREASE

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ANO Unit 1 - 1998 Reactor Operator License Exam

Quescoe No. 68

QID: 0084

Point Value: 1

A loss of 125v DC bus D02 has occurred. W reactor subsequently trips.

Which of the following conditions will be present?

a. EDG 2 running with A4 bus deenergized

b. EDG 2 runmng with A4 bus energized

c. EDG 2 stopped with A4 bus energized

d. EDG 2 stopped with A4 bus deenergized

Question No. 69

QID: 0086

Point Value: 1

The plant is at 70% power. Which of the following DC buses / panels, if deenergized, would cause a reactor

trip?

a. Panet D41

4

b. Panet RAI

c. MCC D15

d. Panel D21

-

Question No 70

QID: 0088

Point Value: I

h CRS direcfJ you to perform Supplement 1 of 1104.036, #1 EDG Monthly Test. You depress the start

pushbutton or, C10, nothing har=. then the "EDG 1 OVERCRANK" nannawar K01-B2 alarms. The

CRS ducets the inade AO to check the EDG out and then depress the local RESET p ==Wittan.

_

Which of the following would occur after the AO depresses the RESET pushbutton?

a. EDG would be ready for another manual start.

b. EDG will not manually or automatically start.

c. EDG output breaker will be locked out.

<

d. EDG will immediately start cranking.

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ANO Unit 1 - 1998 Reactor Operator License Exam

Questica No. 71

QID: 0069

Point Value: 1

Given:

Treated Waste Monitor Tank, T16A release in progress

- PROC MONITOR RADIATION HIGH", K10-B2, in alarm

"

- Liquid Radw3ste Process Monitor, RI-4642, in alarm

What should your Imnwhase Action be?

a. Venfy no Dow on Discharge to Flume, FI-4642

b. Trip the rusuung Radwaste Transfer pussp, P-53A/B

c. Close Liquid Waste to Flume valve, CV-4642

d. Reset RI 4642 to venfy alarm is valid

Questica No. 72

QID: 0090

Point Value: /

De yellow trouble LED is ON on #1 EDG flame detector module on C463 and has been acknowledged on

C463. Subsequently, a #1 EDG smoke detector alarms.

Wluch of the following p====ciasars would you expect to alarm?

a. " FIRE WATER FLOW", K12-A2

b. " FIRE PROTECT SYSTEM TROUBLE", K12 - D1

c. " FIRE *, K12 Al

d. " FIRE PUMP AITTO START', K12-B2

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ANO Unit 1 - 1998 Reactor Operator License Exam

Question No. 73

QED: 0091

Point Value: 1

Given:

- Plant cooldown in progress

- A' DH Removal pump in service

'

A" and "C" RCPs runmng

"

What is the maximum allowable cooldown rate in this condition?

a. 5'Fh

b. 25Th

c. 50*F h

d. 100*F h

Question No. 74

QID: 0092

Point Value: 1

The white light above the handswitch for CV-1410, DH Sucoca from RCS, is ON.

What does this indicate?

a. The interlock will allow valve opening.

b. DC Control Power is avadable

c. "B' CFT Outlet valve is open.

d. The MOVs breaker has tripped.

Questice No. 75

QID: 0093

Polat Value: 1

Which of the following parameters would todicate a leaking PZR code safety?

a. Quench Tanklevel 7500 gallons

b. Quench Tank pressure 5 psig

l.

c. Code safety tailpipe temperature 215 'F

d.' Quench Tank temperature 155 "F

,

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Question No. 76

QtD: 0094

Point Value: 1

(CW Booster pump P 114 A is in senice and trips due to breaker overcunent with a low suction pressure

liow is seal cooling to RCPs maintained?

a. ICW pump P-33B will start due to low discharge pressure

i

b. Bypass Contsol valve CV-2287 wdl open to maintain flow to seal coolers.

'

c. ICW Booster pump P-1148 wdl start due to low discharge pressure.

d. ICW Booster pump P-Il4B will start due to low succon pecesure

]

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Question No. 77

QED: 0096

Polet Value: 1

Which of the following Reactor Building systems are required to be operable whenever RB Integrity is

required?

j

a. Both trains of RB Coolers

b. Hydrogen Pawnhiners

c. Both RB Spray Pumps

d. RB Purge

Question Na, 78

QID: 0097

Point Value: 1

What is the purpose of the overload setpoint of 2700 pounds on the Spent Fuel hoist?

,

a. Prevents a fuel assembly from being dropped while grapple is ang= gad

b. Prev < .t: damage to a fuel assembly ifit is stuck in place.

c. Keeps the bridge from moving in fast speed while transportmg an assembly,

d. Stops downward motion of hoist to allow the grapple to be engaged.

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ANO Unit 1 - 1998 Reactor Operator License Exam

Question No. 79

QID: 0099

Polat Value: 1

Which one of the follomag indications implies proper transfer of EHC from Speed Control to Load Control?

i

a. Operator Auto indicating light turns ON.

b. GV control indicating light turns ON.

c. TV-GV Transfer indicating light turns OFF.

d. Rdesence commeer indacanes GV demand voltage.

i

1

Quesdom No. 80

QID: 0100

Point Value: I

'Ilie plant is operatang at 90% power whom a -Inauman of the Main Turtune EH control systems causes a

spunous OPC mumma

Whach of the following would ocair dunng the tranment?

a. RCP sealinfartma flow would dag.

b. PZR spray flow would drop.

c. PZR makeup flow would drop.

d. FW flow to both OTSGs would rise.

l

Quesdom No. 81

QID: 0101

Point Value: 1

Which of the follomng would be an appropnate action to take with only ONE SW pump running and the plant

at 100% power?

a.f---

"

'y trip the reactor and turbane to reduce heat loads

l

b. Align SW pump suction to the emergency coohng pond.

l

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c. Isolate idle or non-essential ca==& cooled by ACW.

d. Open ICW Coolers Loop I & II bypass valves

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ANO l' nit 1 - 1998 Reactor Operator License Exam

Question No. 82

QID: 0102

Point Value: 1

'

Instrument Air pressure has fallen to 70 psig, which of the following will be in use to restore or consene

Instrument Air pressure?

a. Instrument Air to Service Air X-over valve, SV-5400

b. Use of HPI Block valve vs. Makeup valve, CV 1235

c. Breathing Air to Instrument Air X-connection, HS-5503

d. IfICW avadable, isolate Seal %Ma by clomag CV-1206

I

Questics No. 83

QID: 0/04

Point Value: /

i-

.

-

!

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Following an ESAS actuation the CBOT is duected to perform RT-10 to verify proper actuauon Step G

l

states: " Verify each component properly actuated on C16, C18, and C26, except those overridden in previous

steps."

How is this accomplished for containment isolation valves?

l

a. Verify all marnin=ene isolabon valve " closed" indsation lights are illuminanart

b. Compare mat =nament iaalariaa valve positions to positions listed on chart in RT-10.

l

c. All containment isolation valves have the same color coding for case of verification.

l

. d. Venfy containment isolation valves are in position marked with black tape background.

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_

r

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!

ANO Unit 1 - 1998 Reactor Operator License Exam

Question No. 84

QID: 0106

Point Value: 1

,

Given:

Unit at 100% power

l

- A" OTSG pressure initiate bistable trips in "A" EFIC cabinet

"

- B" OTSG pressure initiate bistable tnps in "C" EFIC cabinet

l

What will the EFIC response be?

a. Half trip on both EFW trains

b. Train "A" EFW actuanos

c. Train "B" EFW actuation

d. Both trains will actuate EFW

Question No. 85

QID: 0107

Point Val 6e: 1

The plant is operaung at 60% power with Delta Tc H/A stanon in Hand. All other ICS stauons are in Auto.

If one RCP has to be tripped due to high windmg w.i w how will the IC5 respond?

Assume no operator acuan other than tripping the RCP.

a. The ICS will runhacer the plant to 45% load at 50%/ min.

b. The Delta Tc Integral is blocked so no re-ratio of FW occurs

c. Demand is less than the RCP runheck limit, no changes occur to FW.

d. The RC flow difference will re-ratio the FW Dow demand

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ANO Unit 1 - 1998 Reactor Operator License Exam

Qwia= No. 86

QID: 0108

Point Vahse: 1

Given:

Plant operstang at 100% pour

The instrunnent air line to Turtune Bypass Valve (CV 6688) valve operator is severed, causing the instrwnent

air am-dmar for CV 6888 to depsessurue

What affect will this have ce CV 6688 opensos?

a. CV4688hilsOPEN.

b. CV 6688 fails AS-IS.

c. CV 6688 hils CLOSED.

d. CV4688 will function nonnally.

Quesdem No. 87

QID: 0109

Pohst Value: 1

Gwen.

- Plant operating at 95% power

- Group 6 pr,

"s 'A' 24v power supply has faded.

What would happen ifI&C tests DROPS channel 27

a. Nottung, DROPS outputs are defeated during testing.

b. An AMSAC test would result in tripping the turtune.

c. A D,tS test would cause Group 6 rods to drop.

d. A 9SS test would cause a turtune trip.

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1

___

ANO Unit 1 - 1998 Reactor Operator License Exam

Quesnon No. 88

QtD: 0110

Point Value: 1

ne ONLY acuon staternent in Tech Specs reganhag Hydrogen concentration instruments operability (3.14.4)

states:

"With one oDwo hydrogen concentration instruments inoperable restore the inoperable analyzer to

OPERABLE stams within 30 days or be in at least hot shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ."

Which of the following actions would be applicable if BOTH hydrogen concentration instruments were

tnoperable7

a. Place the plant in Hot Shutdown wittua one hour.

l

b. Follow the guidance pnmded by Technical (par =Krarian 3.0.3.

l

c. Restore at least one anazyzer to operable status in 15 days or be in Hot Stanchy within 6 hrs.

l

d. Conunue operation and submit report to NRC within 7 days.

Quesnos No. 89

QID: 0111

Point Value: 1

A SmallBreak LOCA has occurred.

. RCS pressee 1890 peig and falhas slowly

,

1

- RB pressure is 1.5 peig and rising slowly

Wluch of the following operator acuons is appropnate for these conditions?

a. Immarlistely actuate ESAS then verify proper actuation per RT-10.

b. Obtain concurrena from CRS, then manually actuate ESAS and make announcement.

c. Announce parameter and immment ESAS actuation. then vertfy proper automatic actuation.

d. Obtain concurrence from CRS and then bypass ESAS prior to automauc eintian

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ANO Unit 1 - 1998 Reactor Operator License Exam

i

gQ

Question No. 90

QID: 01/2

Point Value: 1

During a FW transent, the CBOT manually controls FW to stabilize the plant.

Af,y

Rx power is 101.5% for approximately 10 minutes while the plant is brought

trol.

p es t r ko m

Is this W4M or na=v*r*=hla?

aaly05

a. This is ==*9 to nutigste trannents for

of time per ('a= Art of Opersuons.

b. This is naanrwptahl* due to

on our fuel as WW by Rahrnr+ & WilooX.

c. Thisis

short penods of time as spec Sed by NRC -. , - '-- = with i laanmar

d.

is ===aa=y==h8 due to exceeding the maximum thermal output la our operating license.

Question No. 91

QID: 0114

Point Value: 1

Which of the following acuoes involvsag a hold carded MCC breaker is allowable per 1000.027, Hold and

Caution Card Control?

a. Resumag "a" and "b" contact termunnemna

b. Racknas a brealasr is and out but not classag it.

c.14sving the door open as long as breaker is removed.

d. Performmg a PM to lubricate contacts.

._.

Questies No. 92

QID: 0115

Pelat Vabe: 1

Wluch of the following acoces is required per Teh==l R---

=d=_=_ if you dismver that a safety limit had

,

been exceeded?

l

a. Plax the unit in Hot Shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. Maineman stabic plant conatman until ====g- and engineertng deternune a correct course of action.

c. h==~ii=8y begin a slow, conservative shutdown at <0%/ min.

d. Place the unit in Hot Shutdown within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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ANO Unit 1 - 1998 Reactor Operator License Exam

l

Questies No. 93

QID:0/16

Pelat Value: 1

Dunng an INITIAL approach to criticality, if criticality a NOT actueved within

of the ECP,

j

insert

a.d

.

l

a. plus or nuous 1.0% delta k/k

l

control rods to achieve 1.5% SD margin

l

catabhsh hot shutdown a=8itiana

b. plus or saiams 1.0% delta k/k

seguisting spoups

motify Reactor Engineering

l

c. plus or minas 0.5% della k/k

control rods to achieve 1.5% SD margin

venfy e=8a=8=*'a=

l

d. plus or nunus 0.5% delta k/k

'

ri =

'-*ia

groups

venfy cale==Intiaa

!

Quessism No. 94

QID: 0118

Point Value: 1

l

Which of the following describes a Channel Check as Maad by Tech Epocs?

a. A test oflogic elesaents in a protecnon channel to venfy their naaariatad trip merwi

.

l

b. Adjusunent of a chmanel such that it responds accurately to known values.

c. Verine=tian of acceptable channel p-fu,-- - + by observation of other avadable indications.

l

'

d. fatarvaan of a einintnead signal into the ekannel to venfy proper response.

l

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Page 42

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_. . _ _ _

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ANO Unit 1 - 1998 Reactor Operator License Exam

Question No. 95

QED: 0120

Point Value: 1

Given:

A Site Area Emergency has been declared on Unit 1.

- An Emergency Medical Team must enter a 50 REM /hr area to rescue a critically injured employee.

The team members have NO previous exposure for the year.

Which of the following is the MAXIMUM time the team can stay in this ares?

a.15 munutes

b. 30 annutes

,

c. 45 minutes

d. 60 minutes

Question No. 96

QID: 0121

Point Value: I

Unit One refuelingis in progress

A Unit Two WCO resourm shared fuel handler is assigned to the Main Fuel Bridge from 0700 so 1200 on

Friday, Sepsember 11.

"Ihe local ares dose rate is 25 mR/hr.

He has an accumulated yearly dose of

Rem.

Whose permission must the WCO have to work on the Main Fuel Bridge?

a. EMS the AdminiWrative Dose Control level can NOT be authorized.

b. Manager, Radiation Protection and Chenusuy AND General Manager, Plant Operations

c. Manager, Radsauon Protection and Niary AND General Manager, Plant Operauons AND Vice

Presulent, Operations

d. M: ager, Radanuon Protection and Chenustry

Page 43

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ANO Unit 1 - 1998 Reactor Operator License Exam

.

Quesdes No. 97

QID: 0122

Point Vahee: 1

A WCO is assigned to align "A* Decay Heat Rernoval during a shutdown.

It is emi==nad thejob will take 40 mamdem

High RCS activity has creased a whole body dose rate of 2.5 R/hr in this area.

The WCO has an ami-alasad exposure of 0.225 Rem for the year.

The WCO makes the statement that he can complete the job without exceeding exposure lindts.

Do yms agree or disagree with the WCO's amenwed?

a. Agree, the WCO will NCyr recerve a dose suscaent to exceed the Adminstrative Dose Control Level.

b. Disagree, the WCO will exceed the Adminstratrve Dose Control Level aAer 38 minutes.

c. Agree, the WCO is allowed to exceed the Adminnarative De Controllevel by a maximum of 500 mR.

d. Disagree, the WCO will exceed tbc Adminierative Doec Control Level aner 12 minutes.

Question No. 98

QID: 0124

Felat Value: 1

The rencear was at 90% power,100% flow, and a core deks T of 487 when a Blackout occurred.

Natural circulation was ===Mi=had with Tave at 545T and a core delta T of 40T.

With assural circulation cooldown an=Nishad you would expect to see:

a. core exit temperstme r==ein=ng to decrease.

b. core delta T matinuing to increase

c. demand for EFW decrease to zero,

d. TBVs opening periodically to maintain pressure

Page 44

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ANO Unit 1 - 1998 Reactor Operator License Exam

i

j

Quesden No, PP

QID: 0125

Point Value: 1

i

j

Dunas an Alternate Shundown requanag an immadmane control room evacuation, which of following is

j

perfonned by a control board operaser (ROWl or #2)?

a. Start and load EDGs to power vital P ea

j

b. Start and stop HPI pump to mannaman PZR level

{

c. Throele EFW to OTSGs to maha heat siak -

I

d. Strip 6900v R1 and H2 buses

i

l

Quesden Na,100

QID: 0127

Peist Value: 1

1

Given:

~

-Large BreakIDCAla progress

!

- Case exit temperatures nadacate an ICC condition la Region II of Figure 4

{

(Figure 4 is enfallowing page)

-EPWis avanlable

,

% the above candleiens, whid of the inliowing semessies would be used in 1202.005, Inadegames

,

Case Coohns, so lower cose exit temperatens tous Region 2 to Region I of Figuse 47

j

a. Raise pnmary to secondary Delta-T to 90 to 110*F.

i

b. Start and run one RCPin each loop.

4'

j

c. Open loop, Rx vessel, and PZR high point vents.

i

j

d. Open ERV until RCS to SG DP is less thaa or equal to 100 psig.

4

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Page 45

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4

l

1202.013

E0P FIGUF25

i

REV 2

PAGE 4 of 6

FIGURE 4

Core Exit Thermocouple Temperature for

i

Inadequate Core Cooling

2600

RC

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Core Exit Thermocouple Temperature (20*F Increments)

t

,

!

.

..

_-_

-. .- -

- .

. . _ .

1998 ANO Unit 1 Initial RO Exam Key

'

Question No.1

QID: 0001

Point Value: 1

Answen

b. Transfer Group 7 Rod 3 to the Aux Bus and pull progrs=mer control fuses for the Aux Power Supply.

!

Question No. 2

QID: 0002

Point Value: 1

Answen

I

c. Annunctator "RCP TRIP" (K08-A6) is clear, RCS Dow is lowering and "B" RCP amperage indicaten

0 amps on SPDS.

_

Qusatism No. J

QID: 0004

Palet Value: 1

Answen

,

b. CV-1000 should be cycled open and closed during cooldown to prevent thennal binding of the valve.

1

-

Questics No. 4

QID: 0005

Point Value: 1

Answen

i

b. Set the besch controller to the mammiim beach size ar*4*of 999999 gallons and rammeane adding

boric acid to the make up tank.

QuestiesNo.5

QID: 0007

Point Vaine: 1

Answer:

b. Within 2 minutes

Question No. 6

QID: 0008

Point Value: 1

Answen

c. Letdown Coolers

Question No. 7

QID: 0009

Point Value: 1

Answen

b. Start Auntaary Feedweser Pump, P-75, and connot OTSG levels at 20 to 40 inches using the Startup

Control Valves.

l

Question No. 8

QID: 0010

Point Value: 1

Answen

d. Trip the turbine if vacuum falls below 24.5 inches.

l

1998 ANO Unit 1 Initial RO Exam Key

.-

Question No. 9

QID: 0011

Point Vahne: 1

Answer:

a. IAss of awar margin, no HPI avadable, and reactor vessel head voids are indicated.

Question No.10

QID: 0012

Point Value: 1

i

.

Answen

b. Failed 50% opea.

]

Quesdes Me,11

QID: 0013

Pelet Value: 1

Answen

b. IncreaseinICW Surge Tank level

1

I

Quesdom No.12

QID: 0014

Palat Value: 1

Answen

d. Refer to the ANO Pse-Fire Plan for the a5ected are zone for a hating of afrarnart en-pan ne.

Questies No.13

QID: 0015

Point Value: 1

Answer:

c. Manually inmase High Pressus Ispemios to ceanpress the pressarazer steams bubble..

Questica No.14

QID: 0017

Point Value: 1

Answen

b. Self Powered Neutron Detector (SPND) outputs demonstrate progressive high and low swings.

Question No.15

QID: 0018

Point Value: 1

Answen

c. To prevent eWia a 70% void fraction and possible core uncovery.

Questies No.16

QID: 0019

Point Value: 1

Answen

d. A marked drop by 40% in the GROSS / IODINE ratio.

_. .

. - . . -

-.

-._

..

-

. . _ -

-

1998 ANO Unit 1 Initial RO Exam Key

Question No.17

QID: 0020

Point Value: 1

Answen

a. Place the SG 'B' FW Temp signal select switch to the (Y) position.

Questies No.18

QID: 0021

Point Value: 1

Answen

d. Control rods will withdraw and main feedwater flows will decrease

Qeesdom No.19

QID: 0022

Point Vadme: 1

Answen

b. A dropped red at <2% power

Questies No. 20

QID: 0023

Point Value: 1

Answen

a. Manually actuate "A" MSLI and EFW.

Questies No. 21

QID: 0024

Point Value: 1

Answer:

c. 'Inc speed of the control rods and core age.

'

)

Questies No. 22

QID: 0025

Point Value: 1

Answen

a. MainTurbiac Anucipatorytrip.

Questice No. 23

QID: 0027

Point Value: 1

Arawen

c. Appron% 239 'F

-

Q A No.24

QID: 0028

Point Value: 1

Answen

d. No cooldown limits apply

.

_ . _ _ . . _

_

.

. _ _ . _ _ _ _

.

_ . _ _ . _ . . _

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

_.

1998 ANO Unit 1 Initial RO Exam Key

,

Question No. 25

QtD: 0029

Point Value: 1

.

a. Reflux Boiling

Questics No. 26

QID: 0030

Point Value: 1

Answer:

a. Restoratson of adequate subcoohng margin.

Questica No. 27

QID: 0031

Point Value: 1

Answer:

d.11 e esmoment lockout seley trip will cause a '1hst tramsAw" to'8U-2 tramatumer asul applicable loisde -

will be shed to limit the loadsag on SU-2 transfonner.

Question No. 28

QID: 0032

Point Value: 1

Answer:

c. Imes ofInstrunnent Airin LNPR

Questies No. 29

QID: 0033

Palat Value: 1

l

Answer:

i

d. Stabdue flow by throttling one of the discharge flowpsth valves.

l

Question No. 30

QID: 0034

Polat Value: I

!

Answer:

a. Relays in the turtune trip circuitry energme the Auto-Stop Oil trip and Racirup Trip Solenoids.

l

t

Question No. 31

QID: 0036

Point Value: 1

Answer:

c. Coritinue reactor startup per 1102.008, Approach to Criticality.

Question No. 32

QID: 0037

Point Value: 1

i

l

Answer:

.

c. To minimtze the RCS leak rate into the steam generator.

3

L

1998 ANO Unit 1 Initial RO Exam Key

Question No. 33

QID: 0038

Point Value: 1

Answer:

b. Less than or equal to 100 'F/ hour.

.

.'

Question No. 34

QID: 0039

Polat Value: 1

i

Answen

d. The main feedwater block valves will close in slow speed once power goes below 80%.

Questies No. JJ

QID: 0040

Point Vahme: 1

Answer:

b. Presortae shghtly and redum cooldown rate.

Q W No.36

QID: 0041

Point Value: 1

Answen

b. Manually actuate MSLI and EFW for both CTTSGs and verVy proper scenatum and control.

Question No. 37

QID: 0042

Point Valar: 1

Answen

c. Stop the release and a4ust the seapoint to the correct valz.

Qa=atia= No. 38

QID: 0043

Point Yahne: 1

Answen

d. Reset RE-4830 and re-establish T-18B gaseous release

Question No. 39

QID: 0046

Point Value: 1

Answer:

c. Close ACW Loop isolation (CV-3643).

!

_=

Question No. 40

QID: 0047

Point Value: 1

Answer:

d. Following an evaluation which will allow normal RCS pressure control to resume

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1998 ANO Unit 1 Initial RO Exam Key

Q=mia= No. 41

QlD: 0048

Point Value: 1

Answen

c. rnechanical overspeed trip

Question No. 42

QID: 0050

Polat Value: 1

Answen

a. Continue the rapid plant shutdown at 4 % per minwe

Queslies No. 4J

QID: 0052

Palet Value: 1

Answen

b. 8 to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Questies No. 44

QID: 0053

Point Value: 1

Answen

b. Mais steam line rupture inade RB

Questies No. 45

QID: 0055

Point Value: 1

A*****

d. To prevent inaccurate rendangs on the beach tasallw.

Q=*1a= No. 46

QID: 0057

Polat Vahee: 1

Answen

b. Removal of the RB Pressure Buffer Amplifier freen Analo Channel 1.

s

Questies No. 47

QID: 0058

Polet Value: 1

Answer:

b. 'Ihe Intermediate Range channels are owF- =- ==M

,

Questlos No. 48

QID: 0059

Polat Yahne: 1

Answen

d. CET readings indicate superheat.

l.

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.

1998 ANO Unit 1 Initial RO Exam Key

Quesdom No. 49

QID: 0060

Point Value: 1

Answen

a. B5. B6 and B7

-.

..

Questica No. JO

QID: 0062

Point Value: I

)

Answen

.

b. Trip P 2C, monitor ICS runbeck to 40% power and d= patch the fire brigade

i

per 1203.034, Smoke Fire or Explomon.

,

Qasedes No. 51

QID: 0063

Point Value: 1

'

Answer:

d. Feedwater loop A demand is greater than feedwater loop B dammarf

4

Quesdos Na JJ

QID: 0064

Point Value: 1

l

Answen

c. EFIC train B will utmer EFW pump P-7A is runasag

l

Quesdes No. JJ

QID: 0065

Point Value: 1

Answer:

b. A loss of power to RI-4642 will cause a high radiation alarm signal which will

arsondacally ternuasse the release

Question No. J4

QID: 0068

Polat Value: 1

Answer:

a. All Isolation dampers CLOSED, VSF-8A/B OFF,2VSF-8A/B ON, VSF-9 ON and 2VSF-9 OFF.

Q A No.55

QID: 0069

Palat Value: 1

Answer.

a. 'OTSG tube rupture and stuck open MSSV

Quesdon No. 56

QID: 0070

Polat Value: 1

Answen

c. W relay trips on 4160v A3 bus

.

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.

1998 ANO Unit 1 Initial RO Exam Key

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I

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Question No. 57

QID: 0071

Point Value: 1

!

l

Answer:

a. Throule "C" flow to within 20 gpm of"B"

!

l

Qala= No. 58

QID: 0072

Point Value: 1

Answer:

d. Trip the reactor

l

.

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Qassdes No. 59

QID: 0073

Point Value: 1

1

Answer:

c. PZR level docsussed due to cooldown

l

Question No. 60

QID: 0075

Point Value:' 1

Answer:

d. I&C decaergizes "C" RPS cabinet and "A* MFW pump contact buffer trip test switch

operated la "A" enne

l

,

l

Quesnes No. 61

QID: 0076

Point Valmet 1

Answer:

c. Raduce power to 60% of MWt for RCP de then withdraw rod, keeping rate <3%/hr.

Question No. 62

QID: 0077

Point Value: 1

Aemer:

b. Loop A Tave due to Loop B Gow

Q===elam No. 63

QID: 0078

Point Value: 1

Answer:

c. To rrevent overload of the EDGs..

Question No. 64

QID: 0079

Polat Value: 1

Answer:

c. Use vent flowpath via RB leak detector

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1998 ANO Unit 1 Initial RO Exam Key

Questica No. 65

QID: 0080

Point Value: 1

Answer:

d. Fuel racks designed with boraflex plates and adequate spacing

Question No. 66

QID: 0081

Point Value: 1

Answen

a. 2,3, and 7

Questies No. 67

QID: 0083

Point Value: 1

Answen

a. Reactor power will INCREASE, temperstme will DECREASE, and pressee will DECREASE.

Question No. 68

QID: 0084

Point Value: 1

Answen

d. EDG 2 stopped with A4 bus neenergized

Question No. 69

QID: 0086

Point Value: I

b. Panet RAI

Question No. 70

QID: 0088

Point Value: 1

Answen

d. EDG will immediately start craninng.

!

Question No. 71

QID: 0089

Point Value: 1

Answen

a. Verify no Cow on Discharge to Flume, FI-4642

i

Question No. 72

QID: 0090

Point Value: 1

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Answer:

c. " FIRE *, K12.Al

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1998 ANO Unit 1 Initial RO Erm Key

j.

Question Na, 73

QID: 0091

Toint Value: 1

Answen

c. 507/hr

!

Questies No. 74

QID: 0092

Point Value: 1

Answen

a. The interlock will allow valve opening.

Questies No. 75

QID: 0093

Point Vahme: 1

Amewen

c. Code sadsay sailpipe temperemme 215 Y

i

I

Questies No. 76

QID: 0094

Peine Vehme: 1

,

Answen

b. Bypass Coetrol valve CV-2287 will open to manat=in flow to seal coolen

Questies No. 77

QID: 0096

Point Vaine: 1

Answer:

b. Hydrogen amnihim

n

Question No. 78

QtD: 0097

Point Value: 1

'

Answen

b. Prevents damar to a fuel assembly ifit is stuck in place.

i

!

Questies No. 79

QID: 0099

Point Value: 1

Answen

d. Rderence counter todacetes GV demand voltage.

,

l

Questies No. 80

QID: 0100

Point Value: 1

i

l

Answen

j.

c. PZR makeup flow would drop.

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. -

.

.-

-

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-

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.

--

.

l

1998 ANO Unit 1 Initial RO Exam Key

l

Qaa**la= No. 81

QID: 0101

Point Value: 1

,

'

Answer:

f

c. Isolate idle or non-*==*arial ca=ra=*=** cooled by ACW.

!

?

l

Questies No. 82

QID: 0102

Point Value: 1

'

Answer:

c. Breathing Air to Inst. Air X<;onnection, HS-5503

i

Questian No. 85

QID: 0104

Peist Yahis: 1

Answers

d. Verify M-=* isolation valves are in position smarked with black tape background.

l

Question No. 84

QID: 0106

Pelat Value: 1

Answer:

b. Traia "A" EFW an=*iaa

l

Questies No. 85

QID: 0107

Pelet Vahne: 1

Answer:

.

d. De RC thm difference will ro<atio the FW floww

Questies No. 86

QID: 0108

Point Value: 1

Answer:

a. CV 6688 fails OPEN.

l

Question No. 87

QID: 0109

Point Value: 1

Answer:

c. A DSS test would cause Group 6 rods to drop.

-

Question No. 88

QID: 0110

Point Value: 1

Answer:

b. I==wdiately invoke Technical Specification 3.0.3.

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1998 ANO Unit 1 Initial RO Exam Key

Question No. 89

QID: 0111

Point Value: 1

Answen

i

b. Obtain permassion from CRS. then manually meenate ESAS and make annannamnent

-

d fOk#Y

Questies No. 90

QID: 0112

Point Vaine: 1

'

Answer:

d' * 'M /"

- 1. '

" " b

d. ThiAs--

.--- due to eWa- the merunum thermal output la our operating hcense

'

Questies No. 91

QID: 0114

Peist Value: 1

[' .y ,,

% * of ')'

a ec

4e cl, fu l-o* ~ "~'r

^*****

e

d. Perfonning a FM to lulwicote contacts.

'

Questies No. 92

QID: 0115

Point Value: I

Answen

d. Place the unit in Hot Shutdown within I hour.

l

Questies No. 9J

QID: 0116

Point Vahe: 1

!

Answer:

c. plus or manus 0.5% deka ivk

control rods to achieve 1.5% SD margin

venfy enlantatsan

Question No. 94

QID: 0118

Point Value: 1

Answer:

c. Verifientian of =---,244 channeJ performanca by observation of other avadable indacations.

Question No. 95

QID: 0120

Point Value: 1

Answen

b. 30 adauses

-

r

I

!

Question No. 96

QID: 0121

Polat Value: 1

l

Answen

d. Manager, Radsation Protection and Chemistry

a

s

4

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1998 ANO Unit 1 Initial RO Exam Key

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l

Question No. 97

QID: 0122

Point Value: 1

'

Answen

a. Agree, the WCO will NOT receive a doec suf5cient to exceed the Administrative Doec Control Level.

Question No. 98

QID: 0124

Point Value: 1

Answen

a. core exit temperature continuing to decrease

,

Questies No. 99

QID: 0125

Peint Vaine: 1

)

c. Throttle EFW to SGs to maintana heat siak

Questies No.100

QID: 0127

Pelat Value: I

Answen

i

a. Rais primary to earandary Delta-T to 90 to 110*F.

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ES-401

Site-Specific Written Examination

Form ES401-7

Cover Sheet

U.S. Nuclear Regulatory Commission

Arkansas Nuclear One

Written Examination

Appscantinfonasson

.

~

Name-

Region IV

Date:

FacBty/ Unit ANO-UnitOne

License Level: SRO

ReacerType: BW

StartTwne:

Finish Trne:

Instructions

Use he answer sheets provided e document your answers. Staple this cover sheet on tp of the

answer sheets. The passing grade requires a tinal grade of atleast 80.00 percent Examinadon papers

,

wil be colected four hours aner the exammation starts.

,

~

Applicant Certifir-%n

.

AN work done on this examination is my own. i have nedher given nor received aid.

'.

Applicants Signature

Results

98 +#-

Points

l

ExaminationValue

,,n,. ,,... ...- _ .m

>

Points

Applicants Score

l

Applicants Grade

Percent

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NUREG-1021

39nf39

InterimRev.8 January 1997

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APPENDIX E

i

POUCIES AND GUIDEUNES FOR TAKING NRC EXAMINATIONS

. Each examinee shall be briefed on the policies and guidelines applicable to the examination category

l

(wntten and/or operating test) being administered. The applicants may be briefed individually or as a

group. Facility licensees are encouraged to distribute a copy of this appendix to every examinee before

!

the examinations begin. Allitems apply to both initial and requahfication examinadons, except as noted.

l

PART A - GENERAL GUIDELINES

1.

fRead Verbadsf Cheating on any part of the examination will result in a denial of your appbcabon

and/or acton agamst yourlicense.

2.

If you have any questons concoming the administ'abon of any part of the exammaton, do not '

hesitate asking them before starting that part of the test

"

4.

SRO applicants will be tested at the level of responsibility of the senior licensed shift position (i.e.,

shift supervisor, senior shift supervisor, or whatever the title of the position may be).

5.

You must pass every part of the examination to receive a license or to continue performing bcense

duties. Applicants for an SRO-upgrade license may require remedial training in order to congnue

i

their RO duties if the examinaton reveals deficiencies in the required knowledge and abihees.

6.

The NRC examiner is not allowed to reveal the results of any part of the examinabon until they

have been reviewed and approved by NRC management Grades provided by the facibty licensee

are preliminary until approved by the NRC. You will be informed of the official examination results

,

about 30 days after all the examinations are complete.

PART B - WRITTEN cdllNATION GUIDELINES

1.

[ Read Verbatief After you complete the examination, sign the statement on the cover sheet

indicating that the work is your own and you have not received or given assistance in completing

the examination.

2

To pass the examination, you must achieve a grade of 80.00 percer t or greater. Every question is

worth one point

3.

For an initial examination, the time limit for completing the examination is four hourt.

l

4.

You may bring pens, pencils anti calculators (non-programmable)into the examination room. Use

'

only black ink to ensure legible copies on the exam cover sheet #2 Lead Pencil, which will be

provided, shall be used on the answer sheet

!

5.

Print your name in the blank provided on the examination cover sheet and *M. ocwer sheet You

.

may be asked to provide the examiner with some form of positive identificat)on.

i

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Annonmr F

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6

Mark your answers on the answer sheet provided and do not leave any question blank. Use only

l

the paper provided and do not wnte on the Dack side of the pages. If you decide to change your

cnginal answer, erase the incorrect answer completely and then enter the desired answer,

7-

If the mient of a queston is unclear, ask questons of the NRC examiner or the designated facility

instructor only.

8.

Restroom trips are permtted, but only one applicant at a time will be allowed to leave. Avoid all

l

contact with anyone outside the examination room to eliminate even the appearance or possibility

l

ofcheating.

l

9.

When you complete the examination, assemble a package including the examination questions,

examinadon aids, answer sheets, and scrap paper and give it to the NRC examiner or proctor.

Remember to sign the statement on the examination cover sheet indicating that the work is your

own and that you have neither given nor received assistance in completing the examination. The

l

scrap paper will be disposed ofimmediately after the examination.

l

10.

After you have turned in your examination, leave the examination area as defined by the proctor or

l

NRC examiner. If you are found in this area while the examination is stillin progress, your license

'

may be denied or revoked.

11.

Do you have any questions?

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NUREG-1021

2 of 5

interim Rev. 8. January 1997

l

ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Quesdos No.1

QID: 0001

Point Value: 1

The following plant conditions exist:

1

A manual plant runback to 40% of 902 MWe has been completed.

Group 7, Rod 3 stator temperature is 193 7 and rising.

All other Control Rod stator temperatures are normal-

A stator temperature HI alarm on the plant computer alarm screen is in alarm.

How will the Group 7, Red 3 stator tesaperatwo be redmoed?

1

a. Manually trip the reactor due to Group 7, Red 3 stator temposatus moosedag 190 7.

b. Transfer Group 7, Rod 3 to the Aux Bus and pull programmer control fbees for the Aux Power Supply.

c. Drop Group 7. Rod 3 by ramoving the six stator ihses for the rod in the CRD transfer emhiant

d. Transfer Group 7. Rod 3 to the DC Hold Bus to reduce stator current.

Quesdem No. 2

QID: 0003

Pelet Value: 1

The following plaat Mh exist:

Reasseris tnyped

All 4 RCPs are OFF

RCS pressus is 1950 psig and rising

RCS That is $60 Y

RCS Tcoldis 545 Y

"A" and "B" OTSG pressues are ~980 peig

'Ihe CBOR repons that RT-5 (Venficanon of EFW Armatian and Control)is completed. Which of the

following desentes the expected EFIC system response?

a. OTSG levels will be rising at a rate of 4 inches per minute to 370 to 410 inches.

b. OTSG levels will be rising at a rate of 4 inches per minute to 300 to 340 inches.

c. OTSG levels will be rising at a rate of 4 inches per minute to 370 to 410 inches

d. OTSG levels will be rising at a rate of- 4 inches per minute to 300 to 340 inches.

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Question No. 3

QtD: 0004

Point Value: 1

1

j

The plant is in a degraded power situation with natural circulation cooldown in progress. The ERV isolation

valve CV 1000 has been closed due to leakage past the ERV. Which of the following best describes the

appropnate action concerning operation of CV-1000 during the cooldown?

l

a. CV-1000 should remain closed during the cooldown until repairs to the ERV are completed.

l

b. CV-1000 should be cycled open and closed dunng cooldown to prevent thermal binding of the valve.

c. CV-1000 should be opened to allow the pressuruar to go solid and tr===naa to a HPI Cooldown.

t

d. CV 10M should be Ly,md and hold cm to prevent operation dthe valve during cooldown

Question No. 4

QID: 0006

Point Value: 1

Following a reactor trip, which of the following plant conditions would require " Emergency Boration"?

a. All rods are fully inserted into the core and reactor power is dropptag.

b. Use of the CRD Power Supply Breaker Trip Pushbuttons is requimd to trip the reactor

c. One safety group control rod fails to fully insert and reactor power is dropping.

d. Failure of more than one rod to fully insert into the core and reactor power dropping

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

.-

Question No. .i

QID: 0009

Point Value: 1

l

'

Given the following plant conditions. choose the correct operator response:

- A loss of both Main Feedwater Pumps has caused an automatic reactor trip.

- Annunctator K02-B6, A3 LO. RELAY HIP, is in alarm.

l

Steam Dnven EFW Pump, P 1 A, is tagged our and disassembled for corrective maintenance.

OTSG levels are at 15 inches and slowly dropping.

a. Take manual control of the Electric EFW Pump, P 7B, flow control valves and control OTSG levels

at 20 to 40 inches

b. Start Aimimry Feedwater Pump, P-75, and control OTSG levels at 20 to 40 inches using the Startup

Control Valves.

c. Close the MFW Isolation Valves to prevent feodang with a Condensate Pump and allow the OTSGs

to boil dry.

d. Lower OTSG pressure to feed the OTSGs using a Condensate Pump to establish primary to secondary

heat transfer.

Question No. 6

QID: 0010

Point Value: 1

Given the following plant conditions, choose the appropriate operator actions:

- Plant is operating at 40% power

- E 11 A North Waterbox is 005 for maintensner

- Condenser vacuum is degrading rapidly

a. Trip the reactor and turbine if vacuum falls below 26.5 incnes Hg.

b. Trip the reactor and turbine if vacuum falls below 24.5 inches Hg.

c. Trip the turbine if vacuum falls below 26.5 inches Hg.

d. T 'p the turbine if vacuum falls below 24.5 inchen Hg.

Page 3

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

l

Queedes No. 7

QID: 0011

Point Vaine: 1

Due to severe weather the plant is in a station blackout mndition. 'Ibe steam driven emergency feedwater

i

'

pump (P-7A) is feeding both eenm generators. Under what conditions would an " Emergency RCS Cooldown"

be performed?

a. Loss of phling margin, no HPI available, and reactor vessel head voids are indicated.

b. luector vessel head voids are indnsad and Core Exit hgde 'w.a . > 610 T.

c. Imes d subcooling margia and steena gamerator tube to shall delta-T >100 Y (tubes colder).

!

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d. Cost Exit WW W > 610 7 and steamt gamerator tube to abou delta T >100 7.

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(tubes colder).

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Question No. 8

QID: 0012

Point Value: 1

Given the fouowing plant condnuons

-Ramssoris inpped

- NNI X Instnanent Power Supply Status lights on C13 are OFF

- NNI Y Instrument Power Supply Status lights on C13 are ON

What is the W position of CV-1235, the pressurizer level control valve?

,

a. Failed 100% open.

b. Failed 50% open.

c. Failed 0%open.

l

d. Functioning normal

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Question No. 9

QtD: 00/3

Point Value: 1

During the winter months, which of the following would indscate a tube leak in Nuclear ICW Cooler, E28C7

a. Increase in SW system activity

b. Increase in ICW Surge Tank level

c. Increase in SW header pnseure

d. Decrease in Nuclear ICW header flow

Q=*me== No.10

QID: 00/4

Point Vaine: 1

A fire watch reported a fire in the lower South Electncal Eqmpment Roca and the fire bngade has been

<taparew How can the control room staff qmcidy detenmac potentially affected Pe=?

a. Conduct control board walk-downs and refer to the plant labehag to assist in detennanation.

b. Reder to pacedure 1107.001, Electncal Systeen Operations, breaker align ===e =m=ch=*=e=

c. Desenname a5ected P from the Fire Zone drawings samstrha in the coetml room.

i

d. Reder to the ANO Pre-Fire Plan for the affaceed fire some for a heting of aSecond P

Qsession No.11

QID: 0016

Point Value: 1

To coordinate plant activities during a remote shutdown, wa is the primary means of co-unications?

a. Dial 111 on the plant telephane system to access the party line,

b. Portabic rahos avadable in the ahernate shutdown cabmet.

c. The plant gastronics phones located thmughout the plant.

d. Cellular phones avadable in the contml room extension.

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ANO bnit 1 - 1998 Senior Reactor Operator License Exam

'

Question No.12

QID: 00/7

Point Value: 1

A large break LOCA and several eqmpment failures have placed the plant into an inadequate core cooling

condibon Which of the following prendes the best indication that core damage has occurred?

a. Core Exit Thermocouple temperatures on the ICCMDS mimic display are flashing and rising.

b. Self Powered Neutron Detector (SPND) outputs demonstrate progressive high and low swings.

c. Source Range Monitors indicate higher than normal readangs by more than a factor of ten.

d. De Reactor Vessel Lael Monitoring System indniem voids present in the reactor vessel head.

Question No.13

QID: 0018

Point Value: 1

Following a reactor trip the plant experiences a loss of subcooling margin. Why is it desirable to secure all

j

reactor coolant pumps within 2 minutes following a loss of subcooling margin?

a. To allow the void coefficient of reactivity to add negative reactivity to the core,

b. To protect the mechanical seals on the reactor coolant pumps.

l

c. To prevent Wiag a 70% void fraction and possele core uncovery

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d. To reduce operator burden by securing the RCP's prior to overheating of motors,

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Question No.14

QID: 00/9

. Point Val'.

I

Fuel pin leakage has caused higher than normal activity in the reactor coolant system. Which of the following

indicadons on the Failed Fuel Monitor (RI-1237) would be indicative of failed fuel and require power

reduction?

a. A marked rise by 20% in the IODINFJGROSS ratio.

b. A marked rise by 40% in the GROSS / LODINE ratio.

c. A marked drop by 20% in the IODINE / GROSS ratio.

d. A marked drop by 40% in the GROSS / LODINE ratio.

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

!

Q.esden No 15

QID: 0020

Pelat Vahm: /

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!

Given the followmg indications / alarms

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- SASS Mamatch alarm (fast flash)

'

SG BTU Limit alarm (slow Gash)

l

SG "B" FW Temp signal select switch selected to SASS Enable with

j

the white i=Heannt light out and the blue "Y" light on.

]

What operator amaos is p--

- yrequired?

" "

-

I

a. Plans the SG "B" FW Tony signal asion: sinsch to the 'Y" positana.

j

,

b. Depress the Auto pushbutten ter SG "B" PW Tamp on the SASS paani la C47-2.

a

c. No action necessary, SASS has - -

^'- '8y translernd to "Y" NNL

j

d. Plam both FWloop demands in manual

1

i

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Question No.16

QID: 0021

Peist Vaine: 1

l

The plant is operatnag at 100% power. A fadute of an ICS anodule downstman of the SASS circuatry causes

,

the Nudser Instnuassessoa input to the Rancear Demand station to inil low sesulting is a largs negative

i

4

asussen error. Assuadag no operator accos, how win this thiluss aSus control seds and main feedwater flows?

,

!

a. Control rods will insert and main feedwater flows will increase

4

j

b. Control rods will withdraw and main feedwater flows will increase.

?

I-

c. Coctf0110ds will insert and main feedwater Dows will decrease,

d. Coatml mis will withdraw and main feedwater flows will decrease.

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a

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

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Question No.17

Q1D: 0022

Point Value: 1

Which of the following dropped or misaligned control rod scenanos would requut a reactor shutdown astead

.

of a control rod recovery attempt.?

l

a. A fully dropped rod at 38% power.

i

b. A dropped rod at <2% power.

'

c. A partially dropped rod at 10% power.

d. A rod udenligned for >24 hours.

,

.

4

Question No.18

QID: 0023

Point Value: 1

1

!

ne follomag conditions exist immath*Iy aAer a reactor trip:

j

- Group 2, Rod 4 failed to fully insert into the core.

- RCS pressure is at 1750 psig and tremhng down

- Pressanser level is at 50 iaches and treadmg down

.

- A OTSG pressus is at 830 peig and trending down

l

- B OTSG presume is at 950 peig and treadans down

i

- Subcoening :narsia is at 70 ar and trending up slowly

i

Choose the e p p.

!

a. Manually actuate "A" MSLI and EFW.

l

j

b. Co=- emergency borsuon per RT-12.

C. Trip all Reactor Coolant Pumps

j

d. Initiate High Pressure Injecuon per RT-2.

1

4

d

.

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ANO l! nit 1 - 1998 Senior Reactor Operator License Exam

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Question No.19

QID: 0024

Point Value: /

The plant is operaung at 100% power w hen a single red drops and fully inserts into the core. ICS is in full

automaue and commences a plant runback. Which of the following will determine how fast plant power can

change?

a The operator set rate of change.

b. The pre-set ICS runback rate of change.

c. The speed of the control rods and care age.

d. Tbc rate of change in main foodwater flow.

Question No. 20

QID: 0026

Point Value: 1

Which of the following best desenbes the purpose of adding the Anticipatory Trips to the Reactor Protection

System onginal design?

a. To limit plant cooldwvn following a loss of heat sink.

b. To limit reactor power to prevent **% hnear heat rate limits.

c. To limit reactor power to prevent exceeding DNBR limits.

d To limit plant heatup follomng a loss of heat sink.

Question No. 21

QID: 0028

Point Value: 1

A small break LOCA cooldown is in progress with subcooling margin less than adequate.

Which of the following cooldown linuts apply?

a. 100 *F/hr when >300 *F

'a.

0 'F/hr when 300 - 170 'F

c. 25 'F/hr wben < 170 *F

d. No cooldown limits apply

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Question No. 22

QID: 0029

Point Value: 1

Given the folkming plant conditions:

Reactor trip fium full power

. Full ES we==

ICCMDS Display Subcooling Margin indicates 0 'F

ICCMDS CET 4auies are alternaung between superheated and saturated conditions.

Which of the following best describes the mode of RCS coohng for theos conditions?

l

a. RaGusBothag

l

b. Fosted Cosmectica

l

c. NaturalCirculation

i

d. NaturalConduction

!

,

Questies No. 23

QID: 0030

Pelat Value: 1

i

Dunng a small bseek IDCA cooldows, which of the following cnsena must be met before High Pressure

'

Isischen maybe secured?

a. Restoranon of adequate submohng margm.

b. Total low pressure injection flow >2800 gym.

c. Restoranon of forced flow coohng.

l

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d. At least one OTSG is avadsbie as a heat sink.

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Questaos No. 24

QID: 0031

Point Value: 1

!

The unit is operatang at 100% power SU-l transfosmer is INOPERABLE. De Startup Transformer Prefened

Transfer Switches on C 10 for Al/H1 and A2/H2 are -lawl to SU-2 transformer. SU-2 feeder breakers to

A1. A2, H1 and H2 are out of the pull-to-lodt position. Which of the following best describes the electncal

)

.

system response to a reactor /turbane trip?

l

!

a. With SU-1 inoperable, the load shed protective circuitry will require a manual transfer of electrical

buses to SU-2 due to the limited capacity of SU-2.

t

l

b. De reactor /turtmas trip will ammate the geacrator lockout relay and result in a " slow transfer" of

'

A1, A2, H1 and H2 electncal buses to SU-2 transfonner.

c. The tie beeskers between the vital and non-vital bases will open, the emerEsszy diesel generatoes

will start and supply the vital buses and SU-2 will power A1, A2, H1 and H2.

d. De generator lockout relay trip will cause a " fast transfer" to SU-2 transfonner and @ loads

,

l

will be shed to limit the loading on SU-2 transfonner

Qusaties No. 25

QID: 0032

Point Vaine: 1

Given:

- Plaat operatag at 100% power

-PZRlevel treading down slowly

-leadown flow 45 spm

- Makeup flow 0 gym

,

MUTlevel trending down

-Total sealinjection flow 70 gym

Which of the followmg would cause the above indications?

a. Makeup pump has tripped

b. PZRlevel transmitter failed high

c. Imes ofInstnuneet AirinLNPR

d. Makeup line break upstream of CV-1235

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

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Question No. 26

QID: 0033

Point Value: 1

i

. Which of the following is an Imd='a Action performed only for loss of DH Removal due to vonexing?

a. Close at least one DH suction valve from the RCS.

b Stan the other DH pump to makeup to RCS from BWST.

c. Initiate containment closure per Att. G of 1203.028.

d Stabili.ze flow by throttling one of the discharge flowpath valves.

Question No. ' 27

Q F. 0035

Point Value: /

The plant is at 100% power when 'B' MFW pump trips.

FW pumps discharge cross-tie valve, CV-2827, fails to open due to rnochanical binding.

The CBOR depresses the manual reactor trip pushbutton.

All rods remain out.

1

Which one of the following actions should be the number one priority?

l

a. Manually tnp the turtune and verify GVarTVs closed.

b. Open BWST outlet valve to runnmg Makeup pump.

c. Open CRD power supply breakers on C03,

,

d. Manually insen rods and send operator to locally trip CRD breakers.

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Question No. 28

QID: 0037

Pelat Value: 1

1202.006. Tube Rupture, emergency operatang FM; provules rMa=~ to " Operate Pressuruer Heaters

AND Preenaruer Spray valve (C%l008) to =minamin RCS pressure low within limits of Figure 3" while

coohng down the RCS.

What is the PRIMARY reason for ==intaining RCS pressure low?

a. To prevent hAing main steam anha

b. To mini =i= thermal stresses on the steams pamermann

~

c. To miniadas the RCS leak ass ines the stuum seassumer.

d. To prevent cychag of the ERV(C%1000).

Questies No. 29

QID: 0038

Point Valae: 1

The plant is shuseown and a cooldown is in progrees due to a 200 spa tube leak in the A OTSG

- RCS tesapersese is $20 T and lowering

- BWSTlevelis at 35 A andlowenag

,

- A OTSGlevelis 290 inches and rising

j

- Dose reses at sine bonadery are monaal

Which of the following RCS h limits apply?

a. Less than or equal to 50 T/ hour.

b. Less than or equal to 100 T/ hour,

c. IAss than or equal to 240 T/bour.

d. IJss than or equal to 520 T/bour.

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

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Question No. 30

QID: 0040

Point Value: 1

.

,

Given:

- A degraded power condition exins

]_

- Natural circulation cooldown in progress

i

- RCS pressme at 1700 psig and slowly being reduced

- CETs at 550*F

Ranctor vessel head temperatures at 614*F

. Pressmuer level = 150 inches, them makes map change to 180 inches

-

,

What operator action is required for the above Mh?

i

a. Comenue the cooldown at am iscuessed raes.

3

t

'

b. Pressuize slightly and reduce cooldown raec.

c. Maintaan RCS pressee as low as allowed by Amaramwar A.

i

3-

d. Open all RCS high point vent valves.

Question No. 31

QED: 0041

Peine Value: 1

A reactor trip has occurred Aces 100% power fouowing a loss of D01. Attauspes to transfer 125V DC pensi

D11 to its esmergency supply are na===dd Both OTSGs pressures are -490 peig. Which of the following

is the appropnaec scanos?

a. Crossue D-11 and D-21 from panel C-10 in the control room to petmde power to D11.

l

b. Manually actuate MSLI and EFW for both OTSGs and venfy proper actuauon and control.

c. Select main tutune conuoi to TURBINE MANUAL and close the governor valves in fast speed.

d. Dispatch an operator to manuauy trip the main tubine from the main turbine front standard.

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

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Question No. 32

QID: 0044

Point Valse: 1

l

Events are in progress which have resulted in an unpl===M gaseous radMve release to the environment

which is av to be limited to a small fraction of the EPA Protective Action Guadeline exposure levels.

a

'

What emergency cinamArmama would you recommend to the shiA supertarendear7

a. Noti 5 canon of Unusual Event

b. Alert

l

c. Site Area Emergency

i

1

d. GeneralEmergency

l

!

Question No. JJ

QID: 0045

Point Valse: 1

Refuchag is in progress.

B" Decay Heat Removal system is in semcc.

!

ne following eade=*=== are reponed.

-Transfer canallevel decreasing

- Reamer Buddaag sump level incressmg

- waner manias dows primary shield wall

Whach pmcodest aheund be entered?

a. 1203.028, less of Decay Heat Removal

1

b.1203.042, Refueling Abnonnal Operaucar

c.1203.039, Excess RCS Laakage

4

d. 1502.004, Control of Unit 1 Pd=lia=

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ANO Unit 1 - 1998 Senior Reacter Operator License Exam

Questice No. 34

QID: 0046

Polet Value: 1

Given:

- Degraded Power

- Both EDGs operaung

- ESAS has NOT actuated

P4C failed to start

Wluch of the following accoes should be excenphshed?

a. Close SWImop II fanismiam Valve (SW.?OC).

b. Open SW Imop I & II Cmaar*= (SW 5 and SW4).

c. Close ACWImop I=alahan (CV-3643).

d. Cross-ce SW loops at Makeup Pump (SW-14 thru SW-17).

Question No, 35

QID: 0047

Point Value: 1

In accordance with tLe EOP, when do the Pnesurized Thermal Shodt limits NO LONGER apply?

a. When the RCS pressure /+ hue is to the right of the NDTT limit line on Figure 3.

b. Following restoration of RCP services and starung of Reactor Coolant Pumps

c. Upon ternunation of High Pressure Injection to the Reactor Coolant System.

d. Following an evaluation which will allow normal RCS pressure control to resume

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Q=*= eta = No. 36

QID: 0048

Pelat Value: 1

A Blackout has occurred.

1 EDG has been placed in service on a "No DC' start using 1104.036, Emergency Diesel Generator

Operation.

What DG protection is operable to protect the only operable AC source?

a. positive crankcase pressure trip

b. Iow lube oil pressue trip

c. modunicalomspeedtrip

d. highjacket water temperature trip

Question No. 37

QED: 0049

Point Value: 1

Lake Dardanelle level is rising due to severe weather and heavy rains. Which of the following is the mimmum

level at which comederannon womid be given to r===-ng a plant shutdows la accordm with 1203.025,

NaturalEmergsacaes?

a. Lake level >330 A. and foncasted leks level at sies >340 A.

b. Lake level >340 A. and forecassed lake level at site >350 ft.

c. Lake level >350 ft. and forecasted lake level at site >360 A.

d. Lake level >360 ft. and forecasted lake level at site >370 ft.

$

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Questies No. 38

QID: 0051

Pelat Value: 1

An carthquake has caused structural damage to the plant. The shiA superintendant has man <=moed a plant

evamar= Wluch of the following accons should be performed?

a. All crew me=hans should log into the neanut security card reader using the special

.m.ine=hikty code '0000'.

b. All crew smesabers, with the ==pria= of the control room staff, should report to the

Operanons Support Center.

c. All off shit operations persommel should nport to the Technical Support Cemeer.

d. All operations persommel, wkh the anosytion of the operatir.; csew should evacuses the plant.

,

Question No 39

QID: 0052

Point Value: 1

4

The plant had been operanag at 100% power for 200 days. Following a plant trip, preparanons for startup are

in progress. The CBOR is perfonmaag a e=I=l=**a= for Fmismaanni Critical Posinos (ECP) At a given baron

,

naanansvation, which of the following times would result in the highest rod index due to the effects of Xenon?

j

'

a. 4 to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

b. S to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

c. 40 to 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months

.

d. 70 to 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months

<

d

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d

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Questaos No. 40

Q1D: 0054

Point Value: 1

,

Given the following plant conditions:

- Power at 27%

ICS in full automatic

D Reactor Coolant Pump tnps

Which of the fouowing best desenbes ICS response to the change in RCS flow?

a. Delta Tc will remaan at zero (0) due to the response of the total flow contreuer.

b. A Deha-Tc error will develop with Imop A Tc < Imop B Tc due to the response of the total flow contreuer.

c. A Delta-Tc error will develop with Loop B Tc < 14cp A Tc due to the rw of the total flow contreuer

d. Delta-Tc will not be effected due to the total flow controuer signal being blocked.

Question No. 41

QID: 0056

Point Value: 1

Preparaticas for reactor startup are in progress. Wluck of the fouowing best describes the p'-. --- - = and

review requiressents for the catailanaa of Fisimated Critical Rod Pameiaa (ECP) per 1102.008, Approach to

Criticality?

1

a. The entaita*iaa shall be performed by a licensed operator and reviewed

by a seruor licensed operator

b. The calculation shall be performed by a licensed operator and senior licensed

operator and reviewed by the startup reactor engineer,

c. The calailatian shall be performed and reviewed by the licensed operator and

senior licensed operator perforang the startup

d. The catailatian shall be performed by the startup reactor engineer and licensed

reactor operator and reviewed by the semor licensed operator.

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

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Quentlea No. 42

QID: 0057

Point Value: I

Which of the folkmng would result in all ten (10) ESAS Digital Channels receiving an Analog Channel Trip

signal? -

a. Resuwal of the low RCS Pressure Bistable from Analog Channel 1.

l

b.. Removal of the RB Pressure Buffer Ampli6er from: Analog Channel 1.

i

c. Removal of the 30 peig RB Pressure Bistable from Analog Chaanci 2.

d. Removal of she RCS Pressus BuSr AnspliSer 6am Analog Cheesel 2.

e

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Quesdes No. 43

QID: 0059

Point Value: 1

Dunng a large break IX)CA the value on the ICCMDS CET Subcooling Margin Display is negatrve and

nashing Whatdoesthisindicate?

l

a. An ICCMDS e error,

b. CETreedsagsareinvalid.

C. Case W has occwed.

i

'

d. CET readings imbcess superheet.

t

I

seeden No. 44

ND: 0061

Pelet Value: 1

a

l

Which of the folkmng Reactor Building parameters are trended on the Safety Parar :tu Display System

!

(SPDS) prunary grapluc display for Reactor Building Conditions (RB)?

a. RB pressure, RCS pressure, RB flood level

b. RB temperature, RB pressure, RB hydrogen %s

c. RB rh levels, RB pressure, RB humadity

l

d. RB Sood level, RCS hot leg level, hydrogen concentrauon

'-

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Question No. 45

Q1D: 0063

Point Value: 1

Given:

- 100% power

- ICS in full automatic

T'he CBOR places the ICS Delta T. Cold Hand Auto Station meter selection switch in "POS" (position). The

meter reads $4% What does this mean in terms ofICS contml of main feed water?

a. The average of feedwater loop A and 'eedwater loop B desund is 54%

b. Feedwater loop B desiand is gresser than feedwater loop A demand.

c. The feedwater loop B demand is being boosted by a 4 'F Delta T Cold error.

d. Feedwater loop A dennaad is greater than feedwater loop B denund

Question No. 46

QID: 0064

Point Value: /

Given:

- Small Bnak LOCA in progress

- RCS Pressure at 1500 peig and sed =Imar

- ES channels 1,2 and 4 actussed

- ES channel 3 failed to actusse

Assunung no operator action, which of the following best describes the response of the EFIC/EFW system?

a. EFIC train A will actuate, EFW pump P-7B is pinning

b. EFIC train A will actuate, EFW pump P-7A is omning.

c. EFIC train B will actuate., EFW pump P-7A is runmng.

' d. EFIC train B will actuate, EFW pump P-7B is runmng.

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Question No. 47

QID: 0066

Point Value: 1

It is desired to release the consente of Treated Waste Monitoring Tank T-16A.

FI-4642, Discharge Flow to Flume, is OOS.

To comply with Technical Specificanons, what must be done in order to 9=i'-r the release?

a. Repaus must be made and FI-4642 must be operabic to moduct releases via that pathway.

b. Take i%* ==plas and maduct W analyses and valve haeups prior to the release

i

c. Estimens release now rate using pump curves at least every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during the release.

d. Verify RI-4642, liquid radweste process momeer, is operable and proceed with the release.

Question No. 48

QID: 0067

Point Value: 1

Given:

- C-119A H2/02 Analyzw is 005 with repaars on parts hold

- C-119 H2/02 Analyzer is aligned to T-17

- T-18C Wasic Gas Decay Tank is in semce

Chesustry has .-;

' Opennons to vent the makeup tank to raise hydrogen purity. Wluch of the following

best denenbes the proper H2/02 Analyzer system operation during the makeup tank venting operations?

a. Makeup tank venting is not allowed unless both H2/02 Analyzers are operable

in accordance with Tehaw al Raei6=*ia==

b. Keep C119 aligned to T-17 and m==eane makeup tank wating operations,

align C119 to T-18C if high H2K)2 rannearranons occur.

c. Align C119 to T-18C and -- makeup tank venting operations while

monitortag for high H2/02 er=wwatranons.

d. Kaco C119 shgned to T-17 and have hy sampic T-18C every 15 mins

when venting the makeup tank.

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

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Questies Me, 49

QID: 0068

Palat Valene: 1

- Control V=tahaa is in a nonnat alismaent when the Unit 1 Control Roose talet Air Radianon Momsor

(2RITS4001 A) comes into alana. VSF4A/B goes OFF and VSF-9 comes ON. Which of the following

desenbes additional expected control room ventilation rjstem response?

j

a. All Isolanon dampers CLOSED,2VSF4A/B ON, and 2VSF-9 OFF.

b Unit 1 faalahan dampers CLOSED,2VSF4A/B OFF, and 2VSF-9 ON.

. c. AM Isolanos dampersn nom,2VSF-SA/B OFF, and 2VSF-9 ON.

d. Unit 1 isolados dampses QDSED,2VSF4NB 0FF, and 2VSF-9 0FF.

j

Questies No, 50

QID: 0069

Feist Value: 1

Given:

- Manual reassor trip has taken place, and immedasse accons are P

-(TTSG T level is incseassag above 390*

- OTSG T pnesuse is dsciensing below 900 peig rapidly

- Pressunaer passee and level are decreenag

- Sessa lies high reage radation =nnient RI 2682 is la alana

Whach of the fouowing events is la progress?

a. OTSG tube rupture and stuck open MSSV

b. OTSG tube nspture and excessive EFW Sow

i

c. Sman bank LOCA and excessive EFW flow

d. SmallbetekIDCA and stuck open ERV

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ANO khnit 1 - 1998 Senior Reactor Operator License Exam

Question No J/

QlP: 0070

Point Value: I

i

!

Given:

t

- LOCA in progress with Degraded Power conditions

- EDG #2 did NOT start

- RCS presaire stainlized at 1750 psig

- RCS leakage calculated to be 210 gpm

j

With these accident conditions, which of the following would pose the greatest challenge to core cooling?

l

a. RCS leakageincreases to 1000 gym

i

l

b. Both CFT pnseures et $60 peg

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c. I ekma relay trips on 4160v A3 bus

d. Initial BWST level at 37 ft.

Question No. 52

QID: 0071

Point Value: I

l

'

Given:

- P36B out of semce

-LOCAin progress

- RCS pressure 1250 psig

- 4160v bus A3 deenergized

- HPI flows: A = 90 gpm

'

B = 100 gpm

C = 250 gpm

D = 75 spm

l

i

Which of the following acuens is required?

a. nrottle 'C' flow to within 20 gpm of"B"

b. Thrt ttle "C" flow to within 20 gpm of "D"

c. nroule all to within 20 gym of each other

!

d. Throttle "C flow to within 20 gpm of "A"

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- ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Question No. 53

QID: 0072

Point Value: 1

Given:

- RCS pressure 1950 psig and decreasing

- RELIEF VALVE OPEN", K09-Al, in alarm

- ERV.indscates closed

- Acousuc monitor indacates ERV is lealdag

You'

"-

'y close ERV Imaantiam valve, CV 1000. RCS pecesse ==== to decease.

i

l

What should your next accan be?

)

a. Begin plaat mnbeck

'

b. Cycle the ERV

c. Initiate full HPI

d. Trip the reactor

Questies No. 54

QID: 0074

Pelet Value: 1

J

Plant steady at 90% power with:

- Pressurtzer spray isolauon valve closed

- Makeup tank level 35 inches

- Preemanzer levelind- on C04 are sm

g

What operator actaan should be taken?

a. Take maanal control of makeup valve CV-1235 and open.

b. Take ====m1 control of spray valve CV 1000 and close.

c. Seleu alternese makeup tank level instraneet on C04.

d. Determine valid level indmar and select it for motml

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Question Na. J5

QID: 0075

Point '/alue: /

Given-

i

- C* RPS is placed in Channel Bypass for !&C troubleshooting

"

Plant is at 40% power and stable

- A" MFW pump is in service, "B" MFW Pump is tripped

"

Which of the following would cause an automatic reactor trip with the given conditions?

a. Contact monitor module pulled in "C* RPS and "A" RPS taken to Shutdown Bypass.

b. Turtune trip contact buffer module pulled in "C" RPS and NI-6 power range test module

taken to * test operate" in Channel "B",

i

c. Shutdown Bypass 5% power ==winte taken to " test operate" in channel *C" and

"D" channel placed in Shutdown Bypass.

d. IAC deenergizes "C" RPS cabinet and "A" MFW pump contact buffer trip test switch

operated in "A" cabinet.

_

Question No. 56

QID: 0076

Point Value: 1

At 100% power, a CRD in Group 6 with a history of faulty API has been determined by Incore detectors to be

~50 irches inserted. It has been in this position for at least 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

How would you re-align the rod with the rest of Group 6?

a. Reduce power to 90% then withdraw rod, while keeping power rate <5'/Jhr.

b. Hold power and withdraw rod while keeping power <100%.

c. Reduce power to 60% of MWt for RCP combination then withdraw rod, keeping rate <3%/hr.

d. Reduce power to 40% of 902 MWe then withdraw rod, keeping rates to < 30 %/hr.

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

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Questies No. 57

Qtp: 0077

Point Value: 1

Given:

- Loop A RCS Dow 68,000,000 lbm/br

- 14cp B RCS Dow 63,000,000 lbm/hr

- Loop A Tave 578'F

- Loop B Tave 580*F

- Unit Tave $79'F

Which Tave will be selected by the SASS Auto /maanni trander sueck and why?

a. Unit Tsve due to locy B Sow.

b. Imop A Tave due toImop B flow

c. Loop B Tave due toImop B flow

d. Unit Tave, flows are within tolerances

._

Quesden No. 58

QID: 0078

Peist Value: 1

If an ESAS occurs -W with a Imss of Odhite Power, the start

n

cf RB Spray pumps is deisyed by 35 sec. Why?

a. To allow the EDGs to come up to speed.

b. To allow SW pumps to start for spray pump coohng

c. To prevent overload of the EDGs.

d. To prevent water hauuner of the spray twmders.

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

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Quemiam No. 59

QID: 0079

Polet Value: 1

Given:

4

Unit operating at 100%

Reactor Building pressure is 15.9 psia and stable

No other abnonnal conditions exist

4

i

What acuon should be taken to lower RB pressure?

I

a. Open RB pury inless Srst, then open outlets.

b. Vest RB via H2 snaiple lissa.

%

,

..

+

'

,

c. Use vest flowpath via RB leak detector

d. Open RB pury outlets Srst, then open inlets.

Q=**ia= No. 60

QtD: 0080

Point Value: I

Which of the follomag denga features allows for the safe storage of new fuel in the spent fuel pool?

a. Spent fuel cochas systein is demaned to ==naamia pool temperature <150 *F.

b. Spent fbel boros concentration is ==na*=iw >1600 ppaa boroa.

c. A syphon break is incorporated into system piping to prevent inadvertent draining.

d. Fuel racks designed with bornflex plates and adequate spacing

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

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Question No. 6/

QID: 0062

Polet Value: 1

l

Given the following conditions:

Startup from Cold Shutdown in progress.

- A steam bubble has been formed in the pressuruer,

i

l

- Nitrogen is being vented from the pressuruer.

i

Which of the following indications demonstrates that nitrogen has been vented from the pressuruer?

t Pressuruer pressure stops decreamag.

b. Qusack taak pressure stops increasing.

c. Pressuruer spray causes a signia e RCS pressme decrease

1

d. Proporuonal pressuruer heaters can maintain a steady RCS pressure increase

,

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<

Q=**4a= No. 62

QID: 006J

Point Value: 1

A reactor startup is in progress with the reactor CRITICAL at 1 E-8 amps power. An armaapharic dump valve

fails OPEN. Whack one of the following describes the instaal prunary plaat response?

i

a. Reactor power will INCREASE, temperstme will DECREASE, and pressure will DECREASE.

i

b. Reactor power will DECREASE, temperature will INCREASE, and pressure will DECREASE.

c. Reactor power will INCREASE, temperature will INCREASE, and pressure will INCREASE.

i

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d. Reacu power will INCREASE, temperature will DECREeE, and pressure will INCRE,wE.

l

Question No 63

QID: 0085

Point Value: 1

,

!

l

Which of the following power supplies is the normal source for RPS channel D7

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a. Inverter Y22 from B61

b. Inverter Y22 from D01

c. Inverter Y24 from B61

d. Inverter Y24 from D01

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Questaca No. 64

QID: 0087

Point Value: 1

Dunng a Blackout condition, it may become necessary to perform an EDG start without DC control power.

In tius condiuon. how is the generator output voltage adjusted (no battery chargers are loaded)?

a. Adjusung engine speed via speed setting knob on governor.

b The automaue voltage adjuster will still funcuon.

c. .Using the manual voltage adjuster on Exciter Control Panel.

d. Using voltage adjuster handswitch on C10.

Question No. 65

QID: 0088

Point Value: 1

The CRS directs you to perform Supplement 1 of 1104.036, #1 EDG Monthly Test. You depress the start

pushbutton on C10. nothing happens, then the 'EDG 1 OVERCRANK' annunciator K01-B2 alarms The

CRS directs the inside AO to check the EDG out and then depress the local RESET pushbutton.

Which of the following would occur aAer the AO depresses the RESET pushbutton?

a. EDG would be ready for another manual start.

b. EDG will not manually or automatically start.

c. EDG output breaker will be locked out.

d. EDG will immediately stan cranking.

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ANO Unit 1

1998 Senior Reactor Operator License Exam

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Question No. 66

QID: 0069

Point Value: 1

Given:

1

Treated Waste Monitor Tank, T16A. release in progress

- PROC MONITOR RADIATION HIGH", K10-B2, in alarm

"

Liquid Radwaste Process Monitor, RI-4642, in alarm

l

What should your Imma$mne Action be?

i

.

a. Verify no flow on Discharge to Flume, FI-4642

b. Trip the runsaag Radweste Transfer pump, P-53 A/B

c. Close Liquid Waste to Flume valve, CV-4642

d. Reset RI-4642 to verify alarm is valid

Question No. 67 -

QID: 0090

Point Value: 1

llic yellow trouble IED is ON on #1 EDG flame detector module on C463 and has been acknowledged on

C463. Sa%==*iy, a #1 EDG smoke detector alanna

Which of the following ====M=nars would you expect to alarm?

a, " FIRE WAER FLOW", K12 A2

b. " FIRE PROECT SYSTEM TROUBLE", K12 - D1

c. " FIRE *, K12 Al

d. " FIRE PUMP AITTO START *, K12-B2

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

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Question No. 68

QID: 0091

Point Value: 1

i

Given:

- Plant cooldown in progns:

J

A* DH Removal pump in service

"A" and "C" RCPs running

)

What is the maximum allowable cosidown rate in this condition?

a. 5 7/hr

b. 25T/br

c. 50 T/hr

d. 100 T/hr

Question No. 69

QID: 0092

Point Value: /

The white light above the handswitch for CV-1410, DH Sucten front RCS, is ON.

What does this indzate?

a. The interlock will allow vahe opening.

b. DC Control Power is avadable

c. *B" CFT Outlet valve is open.

d. The MOVs breaker has tripped.

Question No. 70

QID: 0093

Point Value: I

Which of the following parameters would inchcate a leaking PZR code safety?

a. Quench Tank level 7500 gallons

b. Quench Tank pressure 5 psig

c. Code safety tailpipe temperature 215 7

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[

d. Quench Tank temperature 155 Y

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Question No. 71

QID: 0095

Point Value: 1

l

De le 4(h

,

ESAS has actuated due to a LOCA.

y",9

RCS pressure has dropped to approxunately 1200 psig within five minutes of

,

l

pos t -tvum

Which of the following best desenbes the effects on the ICW

components it cods?

4 ^l

J'5

'

Y

a. All RCPs must be secured due to loss c(seal

b. ' CRD coohng pumps must be

to iardahaa ddiacharge path.

i

c. ICWBooster

protected by opemag dbypass valve.

I

d.

must be secured due to isolation dSW to ICW coolers.

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Questies No. 72

QID: 0096

Pelat Vaine: 1

Wluch of the following Reactor Buskhng systems are required to be operable whenever RB Integrity is

required?

a. Both trains c(RB Coolers

b. Hydrogen

aa===ad

,

n

c. Both RB Spray Pumps

i

l

d. RB Purge

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Question No. 73

QID: 0097

Point Value: 1

l

' What is the purpose of the overload setpoint of 2700 pounds on the Spent Fuel hoia?

l

'i

a. Prevents a fuel assembly from being dropped while grapple is --a9

b. Prever.ts damage to a fuel assembly ifit is stuck in place.

c. Keeps the bndse from moving in fast speed while transporting an assembly,

d. Stops downward mouon of hoist to allow the grapple to be engaged.

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ANO Unit 1 - 1998 Senior Reactor Operator License Exarn

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Questies No. 74

QID: 0098

Palat Value: 1

'

\\

What type of does rate is expected to be the highest folkmtag a fuel hearthat acculent causing damage to a

l

spent fuel assembly?

i

a. Sida dose rase

i

l

b. Whole body does rate

l

i

c. Extumanes dose rase

'

I

d. IAms of th$ Gyt doAB fee 8

Quesdes No. 75

QID: 0100

Pelot Value: 1

,

l~

The plant is operating at 90% power when a malamesma of the Main Turbine EH control system causes a

,

l

spunous OPC ars=wma

i

!

Wluck of the foliosnag would occur dunag the transient?

"

l

a. RCP seal hqjesmos flow would drop.

i

b. PZR spay Sow would drop.

l

c. PZR makeup flow would drop.

l

'd. FW flow to both OTSGs would rise.

l

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Quesdes No. 76

QID: 0101

Felat Value: 1

(

Whach of the followtag would be an appropnate action to take with only ONE SW pump running and the plant

at 10u% power?

a. Immahnamly trip the reactor and tutine to reduce heat lands

t-

.

b. Aliga SW pump =wsian to the emergency cooling pond.

l

c. Isolate idle or non-tial components cooled by ACW.

d. Open ICW Coolers Loop I & II bypass valves.

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Questnom No. 77

QID: 0103

Point Value: 1

Instrument Air pressure has been degrading for approximately 30 minutes. Suddenly, Inst. Air pressure drops

to <60 psig.

What action is required?

a. Isolate S/U Boder air system from Unit 1 Ins. Air

b. Isolate Unit 2 Inst. Air from Unit I

c. Plaos VSF-9 Outade Air dampw in RESERVE postion

d. Trip the reactor and full actunee EFW to both OTSGs

Quesdom No. 78

QID: 0105

Point Value: I

Who would be ri=paaah for i=Wiar a damage repair team intoransaianaeat during an emergency

event?

a. ShiA S%i - - '= =

b. TSC Director

c. OSC Director

)

d. EOF Director

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Questies No. 79

QID: 0106

Polat Value: 1

Given:

- Unit at 100% power

"A" OTSG pressure initiate bistable trips in "A" EFIC cabinet

- B" OTSG pressure initiate bissable trips in "C" EFIC cabinet

"

What will the EFIC response be?

a. Half trip on both EFW trains

b. Train "A" EFW =cenae==

i

c. Train "B" EFW actuation

'

d.~ Both trains will actuate EFW

Questies No. 80

QID: 0107

Point Value: 1

The plant is operating at 60% power with Delta Tc H/A station la Hand. All other ICS stations are in Auto.

If one RCP has to be inpped due to high winding teraperature, how will the ICS respond?

)

Assume no operator maion other than tnyping the RCP.

a. The ICS will runhack he plant to 45% load at 50%/ min.

t

b. The Delta Tc Integral is blocked so no re-ratio of FW occurs

i

c. Demand is less than the RCP runhack limit, no changes occur to FW.

l

d. The RC flow difference will re-ratio the FW flow demand

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Question No. 81

QID: 0108

Point Value: 1

Given:

Plant operating at 100% power

The instrwnent air line to Turbane Bypass Valve (CV 6688) valve operator is severed, causing the instswnent

air ====ta*ar for CV-6888 to depressurue

What afect will this have on CV 6688 openeos?

a. CV4688 hus OPEN.

b. CV 6688 fails AS-IS.

c. CV 6688 fails CLOSED.

d. CV 6688 will fi=maa nonnally.

Quesdenife, 82

QID: 0109

Pelet Value: 1

!

l

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r-

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- Plant operating at 95% power.

l

- Group 6 g-

- 's 'A' 24v power ogply has failed.

What would happen ifIALC tests DROPS channel 27

a. Nadung DROPS cutputs are defensed during teattag.

b. An AMSAC test would result in tripping the tubiac

c. A DSS test would cause Greg 6 rods to drop.

d. A DSS test would cause a turtune trip.

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Quesnos No. 83

QID: 0110

Point Value: /

The ONLY action statement in Tech Specs regarding Hydrogen concentration instruments operability (3.14.4)

states:

"With one of two hydrogen concentration instruments inoperable restore the inoperable analyzer to

OPERABLE status within 30 days or be in at least hot shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ."

Which of the following actions would be applicable if BOTH hydrogen concentration instruments were

inoperabic?

!

a. Place the plant in Hot Shutdown within one hour.

b. Follow the guadence provided by Techancel W 3.0.3.

c. Restore at least one analyzer to operable status in 15 days or be in Hot Stanchy within 6 brs.

d. Conunue operanon and subanit report to NRC within 7 days.

Question Na, 84

QID: 0111

Point Value: 1

A Small SmakIDCA has occuned.

- RCS pressure 1890 peig and falhas slowly

- RB pesesure is 1.5 peig and nsing slowly

1

Which of the following operator actions is appropnate for these conditions?

a. Immariannely actuate ESAS then verify proper actuation per RT-10.

b. Obtain concunence from CRS, then manually actuate ESAS and make announcement.

I

c. Announce parameter and immin-t ESAS actunuon, then venfy proper automauc actuation.

d. Obtain concurrence from CRS and then bypass ESAS prior to automatic actuation.

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Questice No. 85

QID:0/12

Point Value: 1

- Op /e /c)

d r:

During a FW transient, the CBCrr manually controls FW to stabdaze the plant.

l

Rx power is 101.5% for approxunately 10 minutes while the plant is brought

control.

['# .y Gr S

a n sl

l

Is this = -

,"l' or =7=hle?

-

a. This is '- ,"le to mitigate transaents for

periods of time per Conduct of Operations

b. This is un==re=hte due to '

on our fuel as WEad by Rahrrrir & Wilcox,

c. This is

short penods of tisme as specsfied by NRC w _f '- - with i lannaing

l

d.

is -

- , - " '- due to *=ading the " . - ~ thennal output in our operating license.

'

Questies Na, 86

QID: OllJ

Point Value: 1

The unit is operating at 100% power A synec:n engineer enters the control room with a condition report

I

stating the PZR code safety valve (PSV-1002), ruplaced dunas the last outage, was set by the vendor using out

of calibratica eqmpmend. De madaria= report estamates the seapoint for PSV-1002 could be as high as 2790

psig. The systeen engsamer r-===d= declanas PSV-1002 inoperable.

What acuos would you initiate?

a. Restore PSV.1002 to operable status within 15 minutes or be in Hot Shutdown

within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. Within one hour initiate a shutdown to be in Hot Standby within 6 hrs and be in Hot Shutdown

within maanher 6 brs.

c. Restore the safety to operable status within 6 hrs or place the unit in Hot Shutdown within

the following 12 hrs.

d. Restore safety to operable status within 12 hrs or place the unit in Hot Shutdown within

the following 12 hrs.

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Quandam No. 87

QID:0/14

Point Value: 1

Which of the following amana involvsag a hold carded MCC breaker is allowable per 1000.027 Hold and

Cauuon Card Control?

a. Ranoving "a" and "b" contact tersunahons

b. Racking a breaker in and out but not closang it.

c. IAsving the door opes as long as brumker is reinoved.

d. Perdarming a FM to lubrkase consaces.

Questie. M., 88

QID: 0115

Point Val.m 1

Which of the following accoes is required per Technical 9=nArank== if you discover that a safety linait had

been exceeded?

a. Place the unit in Hot Shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. Maimania stabic plast aa=dh until manar===r and cagineering detonnine a correct course of action.

c. IW begia a slow, conservaarve shmadown at <S9&mda.

d. Place the unit la Hot Shutdown within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Questics N6. 89

QID: 0117

Point Value: 1

Which of the following would N(7T require the use of a Temporary Alteration Package?

1

a. Inan=ltadam of a test gauge for a surveillance

b. Temporary power cables supplying tesuporary eqmpament.

c. Install ;g ajumper to prevent a malfuncoomag tastrument loop from acanting xpiipawar

d. Pd

of a blank flange with a vent flange

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Quesde No. 90

QIn: oils

reist vaine: I

Given the following 'A' Core Flood Tank (CfT) parameters with the plant is at 100% power.

- Level tmasmitter out of service

- CFT leven is 12.5 feet

- Boric acid concentration is 2300 ppm

- CFT presome is 585 peig

Whack of the above parameters makes the 'A' CFT INOPERABLE 7

.

l

a. I m ettr h

1

b. CPTisvol

c. Boric acid concentration

d. CFT prenews

Questies No. 91

QID: 0120

Point Value: I

Grves:

- A Site Area Emoryncy has been deciered on Unit 1.

- An Emergency Medical Temen seest emner a 50 REM /hr area to rescue a cntically iqpared employee.

- M team anembers have NO pronous expoowe for the year.

i

Which of the following is the MAXIMUM time the team can stay in this arca?

2

a.15 minutes

b. 30 mmunas

c. 45 nuauses

d. 60 aminutes

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Question No. 92

QID: 0121

Point Value: 1

l

Unit One refueling is in progress.

i

A Unit Two WCO tceource shared fuel handler is assigned to the Main Fuel Bridge from 0700 to 1200 on

l

Friday, kp=' := 11.

-

'

The local area does rate is 25 mR/hr

He has an accumulated yearly dose of

m.

Whose permismos must the WCO have to work on the Main Fuel Bridge?

a. Fwranrling the Admannstrative Dose Control W can NOI'be authorized.

b. Maanger, R=dineian Protection and Chastry AND Gomeral Manager, Plant Opendoms

c. Manager, Radiatma Protocean and Chemistry AND Genmal Manager, Plant Operations AND Vice

Premdent, Operstmas

,

d. Manager, Padiahan Protection and M7

l

Question No. 93

QID: 0122

Point Vaine: 1

A WCO is assigned to align "A" Decay Heat Removal during a shutdown.

It is estummeed thejob will take 40 =i-e=

High RCS actmey has created a whole body dose ruas of 2.5 R/br in this area.

The WCO has an =====l=aad expoeme of 0.225 Remi for the year.

'Ihe WCO makes the arnea-aae that he can complete the job without ~"- exposure limits.

Do you agree or disagree with the WCO's mentement?

l

a. Agree, the WCO will t,OT receive a dose sufficient to exceed the Administrative Dose Control Level.

b. Disagree, the WCO will exceed the Adamnarratave Doec Control Level aAer 38 minimma

c. Agree, the WCO is allowed to exceed 1:n Admimstrative Dose ControlImel by a maria == of 500 mR.

d. Disagree, the WCO will exceed the Administrative Dose Control Level aner 12 minutes.

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Page 42

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

j

'1

Q h No.94

QID: 012.7

Point Value: 1

l

t

!

Given

l

' Plant shutdown and cooldown in progress

-

- RCS Tave 185T

- RB Purge in progress to lower RB aunospheric activity

1

- RB Purge projected release durauon is 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months

.

- RB Purge release cr====<==i two (2) hours ago

l

- Nuclear Chenustry stated gaseous releases p.W to exceed quanerly object 2ves by 30%

- Release report ;:" ' 7 release rate 4.1 E4 cha

- Design flow rate 3.6 E4 ces to 4.1 E4 cen

,

l

Which dthe following would require RB Purge ternunation?

!

i

l

a. Actual (stabic) RB purge flow rate d3.9 E4 c6n.

i

b. RB A*P G==aana Detector trending upward.

c. SPING 1 indicates stack activity approaching NUE cntena over next 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

d. Less dDecoy Heat Rasmoval results in RCS termperature at 2207.

Question No. 95

QED: 0124

Point Value: 1

l

The reactor was at 90% power,100% flow, and a core deha T d48T when a Blackout occuned.

l

Natural circunstaan was amaahlinhad with Tave at $457 and a core delta T d 407.

!

With natural circulanon cooldown estaN shed, you would expect to see:

I

f

L Core exit ternperature ContinisinF to decrease

b. core delta T conunuing to increase.

c. had for EFW decrease to zero.

d. TBVs opening penodically to maintain pressure-

i

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Page 43

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ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Quesdem No. 96

QID: 0126

Polet Value: I

Given:

-N 16 monitor R 2691 in alarm

- Small SG Tube IAnk AOP in progress

-letdown at 45 spm -

-Maimup at 66 spm and rising

A reactor trip occurs and while perfonmag his acoces the CBOR ==aaaaaat SCM is 30*F.

Which d ahs huswing BOPS would pnwids guidemos to best udligste tids event?

a. RemotorTrip 1202.001

b. Imse d Subcochag Marpa 1202.002

.

c. Tube Ruptme 1202.006

d. ESAS 1202.010

,

Quesden No. 97

QID: 0127

Point Value: 1

Gives:

-Large Snak LOCAla prognes

- Core exit temperatwes umhcate an ICC randman in Repon II MFigure 4

(Figue 4 is os following page)

-EPWis avadable

e

' q the above enad% which dthe following strategies would be used in 1202.005, Inadequase

Core Cooling, to lower core exit temperatwes from Region 2 to Region I d Figue 47

a. Raise pnaery to secondary Delta-T to 90 to 110*F.

b. Start and run one RCPin eachloop.

c. Opca loop, Rx vesent, and PZR high point vents.

d. Open ERV until RCS to SG DP is less than or equal to 100 psig.

Page 44

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' O . T. 2

E0P PIGURES

REV 2

PAGE 4 of 6

.

. _ .

FIGURE 4

,

Core Exit Thermocouple Temperature for

Inadequate Core Cooling

,

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i

4

. - . - . - . - . -

- . -

. -

_ -

_ . .

1

' 2 :^J'

ANO Unit 1 - 1998 Senior Reactor Operator License Exam

Quesnos No. 98

- QID: 0128

Point Value: 1

)

Which of the fouowing would be clusified as a fission product barner failure?

a. RCS Idage indicates greater than 45 spm.

l

b. EOF Director believes the RB is breached.

c. CNIMT r=dianaa levels equal to Alert level from CNTMT Radiation EAL.

,

d. The inabdity to monitor two Fismos Product Bamers.

Question No. 99

QID: 0129

Point Value: 1

A small break IOCA has occurred with the fouowing indernenama-

- HPI flow ~250 gpm total

- CNIMr High Range Rad Maniaans reading $000 REM

'

- Indacannna c(leakage paa RB harge iaalasiana

What E-My Actica Imel should be declared?

-

a. NUE

b. Alert

c. SAE

d. GE

Question No.100

QID: 0130

Point Value: 1

For which EAL is a PAR required to w made?

a. N1.T

i

b. ALERT

c.SAE

d. G E

Page 45

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.

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1

1998 ANO Unit 1 Initial SRO Exam Key

Quesdes No.1

-QtD: 0001

Pelat Value: 1

Answer:

b. Transfer Group 7. Rod 3 to the Aux Bus and pull programmer control fuses for the Aux Power Supply.

Quesdes No. 2

QID: 0003

Point Value: 1

Answer:

b. OTSG levels will be rising at a rate of-4 inches per annuse to 300 to 340 inches.

Quesales Na, J

QID: 0004

Point Valso: 1

Answer:

b. CV 1000 should be cycled open and closed during oocidown to prevent thermal binding of the valve.

,

Quesdes No. 4

QID: 0006

Felat Vaine: 1

l

Answer:

d. Failme of more than one rod to fhlly insert into the core and reactor power dropping

,

Qassden No. J

QID: 0009

Point Value: 1

Answers

b. Start Auxiliary Feedwater Pump, P-75, and controt OTSG levels at 20 to 40 inches using the Startup

ControlValves.

Quesdem No. 6

QID: 0010

Point Vaine: 1

Answer:

d. Trip the turbine if vacuum falls below 24.5 inches.

Quesdes No. 7

QID: 0011

Point Value: 1

Answer:

a. IArs of subcooling margia, so HPI avadable, and reassor vessel head voids are idi'

'd

Quesden No. 8

QID: 0012

Point Value: 1

Answer:

b. Failed 50% open.

-

.

..

.-

.

-. __- - -. ..

. _ -

.

-.

i

I

1998 ANO Unit 1 Initial SRO Exam Key

Question No. 9

QID: 0013

Point Value: 1

Answer.

b. Increase in ICW Surge Tank level

__

Quw No.10

QID: 0014

Point Value: 1

Answer:

!

d. Refer to the ANO Pre-Fire Plan for the affected fire zone for a listing of affected rampanents

i

!

l

i

l

Qussties No Il

QID: 0016

Psist Value: 1

j

!

Answer:

!

l

b. Portable radnos avadable in the sleermees abuedows calmost.

1

l

Questies No.12

QID: 0017

Point Value: 1

Answer:

b. Self Powered Neutros Detector (SPND) outputs hrase progressive high and low swings

Qussties No.13

QID: 0018

Point Value: 1

l

Answer.

c. To psevent esosadang a 70% void frassoa and possible cose uncovery.

!

Qussties No.14

QID: 0019

Point Value: 1

Answer:

d. A marked drop by 40% in the GROSS / IODINE ratio.

Question No.15

QID: 0020

Point Value: 1

Answer:

a. Place the SG "B" FW Temp signal select switch to the (Y) position.

-_

__

Question No.16

QID: 0021

Polat Value: 1

Answer:

d. Control rods will withdraw and main feodwater flows will decnase

l

4

,

4

0

!

l

\\

-

.- -

. _, _. -

.. .-

.

--

. - .

.

-.

L

1998 ANO Unit 1 Initial SRO Exam Key

Question No.17

QID: 0022

Point Value: 1

Aaswer:

b. A dropped rod at <2% power

Questies No.18

QID: 0023

Point Value: 1

Answer:

a. Manually armaw "A" MSLI and EFW.

Queados No.17

QID: 0024

Point Valer. 1

,-

c. The speed of the control rods and core age.

Questies No. 20

QID: 0026

Polet Value: 1

Answer:

d. To limit plant heetup folkming a loss of heat siA.

_

Questies No. 21

QID: 0028

Point Value: 1

Answer:

d. No cooldownlumits apply

l

Question No. 22

QID: 0029

Palat Value: 1

Answen

a. Reflux Bothng

Questies No. 23

QID: 0030

Point Value: 1

Amewer:

a. Restoration of adequate mAccoling margin.

i

Quesdes No. 24

QID: 0031

Polat Value: 1

l

Answer:

d. The generator lockout relay trip will cause a " fast transfer" to SU-2 transformer and applicable loads

will be shed to limit the loading on SU-2 ti.ssivi

r.r.

,

E

l

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_

.

_ . _ .

_.._ __ .

_ _ _ _ _ _ _ _ _

_

1998 ANO Unit 1 Initial SRO Exam Key

Question No. 25

QID: 0032

Point Value: 1

Answer:

. c. IAss ofInstrwnent Air in LNPR

Question No. 26

QtD: 0033

Point Value: 1

Answen

d. Stainlize flow by throttling one of the discharge flowpath valves.

Quesden No. 27

OID: 0035

Penst vanme: 1

Answer:

c. Open ano power supply twenies on 003.

Quesdes No. 28

QID: 0037

Point Value: 1

Answen

c. To =*=a==

the RCS leak race isso the seeman generseor.

Questies No. 29

QID: 0038

Point Value: 1

Answer:

b. IAss than orequalto 100 T/ hour.

Questies No. 30

QID: 0040

Point Vaine: 1

Answer:

b. Pressmue slighdy and redum dwo rate.

Quesden No. 31

QID: 0041

Point Value: 1

Answer:

b. Manually acemate MSLI and EFW for both OTSGs and verify proper n=e6 and control.

Quesdes No. 32

QID: 0044

Point Value: 1

Answer:

b. Alat

,

. . ~ .

-

_ _

_ . _ . . _

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

_ _ ..

_ _

_

__

_

m

4

,

1998 ANO Unit 1 Initial SRO Exam Key

e

Question No. 33

QID: 0045

Palst Yahme: 1

Answer:

b. 1203.042, Re6xhng Abnormal Operanons

,

Question No. 34

QID: 0046

Pelat Value: 1

j

Answer:

c. Close ACWImopisolatica(CV-3643).

4

'

Question No. JJ

QED: 0047

PeletValues 1

j

Amewers

d. Fouowing an evahistion which will allow mannal RCS presume control to nenne.

i

,

i

'

j

Questies No. 36

QID: 0048

Point V ahme: 1

i

Answer:

)

C. whamW oM trip

,

'

i

Question No. 37

QID: 0049

Pehst Value: 1

,

1

Amewer:

, .

b. I.alslevel>340 A.and Amecastedlakelevelatsies>350 A.

.

4

Quamism No. 38

QID: 0051

Felat Value: 1

Answer:

a. All crew members should log into the nearest security card reader using the special

'

.nemnime.hinty code "0000'.

Questien No. JP

QID: 0052

Point Vsize: 1

b 5 to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

'

i

1

Questies Na 40

QID: 0054

Pelet Value: 1

j

heyeu wc) ** " 'k'

'

Answer:

6'

3

%

e ore n J ens e r ,

A D :'^- Tc .. . . ." t ..'.,; a cl. '_ :; " Tw ~ t - g A Tw lc 'r -- --;== af the ***1 "- _ __ usi .

e

-

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

__

_

.. _

_.

. _ . .

._.-

___

.._._

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1998 ANO Unit 1 Initial SRO Exam Key

Questies No. 41

QID: 0056

Point Vaine: 1

Answer.

i

c. The rahilam shall be perfonned and reviewed by the licensed operator and

m.:dar licensed operator perfonmag the startup

l

,

Question Ns 4'2

QID: 0057

Polat Value: 1

,

l

Answer:

i

,

1

,

b. Rmmoval of the RB Pressus BuKer Anspidier freen Analog Chamael 1.

l

Quessism No. 4J

QID: 0059

Palet Yahns: 1

Answer:

d. CET rendungs indumte superheat

i

>

Questies No. 44

QID: 0061

Point Value: 1

Answer;

b. RB temperature, RB pressee, RB bydrogma conosotratica

!

Questian No. 45

QID: 0063

Pelet Value: 1

Answer:

d. Pendwater loop A doemand is greater than isedwater loop B h

l

Questies No. 46

QID: 0064

Pelat Value: 1

l

..aswer:

c. EFIC train B will actusse, EFW pump P-7A is rummag.

Questles No. 47

QID: 0066

Felat Vabne: 1

Answer.

c. Esti:nate release flow rate using pump curves at least every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during tle release.

Questies No. 48

QID: 0067

Point Yahme: 1

,

Answer:

b. Keep C119 aligned to T-17 and commence makeup tank venting operations,

align C119 to T-18C if high H2/02 concentrations occur.

.

I

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_

_.

_

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

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1998 ANO Unit 1 Initial SRO Exam Key

i

Quesnos No. 49

QfD: 0068

Point Value: 1

Answen

a. AllIsolation dampers CLOSED, VSF4A/B OFF,2VSF4A/B ON, VSF-9 ON and 2VSF-9 OFF.

!

l

Question No. 50

QID: 0069

Point Value: 1

Answer:

l

a. OTSG tube rupture and stuck open MSSV

Quesden No. 51

QID: 0070

Pelat Value: 1

Answen

!

c.14ckout relay trips on 4160v A3 bus

!

-

l

Questies No. 52

QID: 0071

Point Value: 1

l

Answer:

a. 'Ihrostle *C" flow to within 20 gpm of"B"

l

Questies No. 5J

QID: 0072

Palat Vaine: 1

Answen

d. Trip the reecear

Question No. 54

QID: 0074

Point Value: 1

Answer:

t

l

d. Desernune valid level induumar and select it for control

!

Quesdes No JJ

QID: 0075

Point Value: 1

Answen

l

d. IAC decaergizes "C" RPS cabtact and "A" MFW pump contact buffer trip test switch

operated in "A" cabinet.

,

!

l

Quesdem No. 56

QID: 0076

Point Value: 1

Answer:

c. Reduce power to 60% of MWt for RCP combination then withdraw rod, keeping rate <3%/hr.

!

I

!

[

.

. .

.

- . . .-

.. --

. . . .

. .

.. . -. . .

. . . .

. . - .

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i

1998 ANO Unit 1 Initial SRO Exam Key

Queetnom No. 57

QID: 0077

Point Value: 1

b. IAap A Tave due to leop B Aow

Question No. 58

QID: 0078

Point Value: 1

Answer:

c. To prevent overload of the EDGs.

Quesdem No. JP

QID: 0079

Point Value: 1

Answer:

c. Use veut Bowpath via RB leek detector.

Questies No. 60

QID: 0000

Point Vahee: 1

Answer:

d. Fuel racks designed with baraSex plates and adequase specang.

Quesdom No. 61

QID: 0082

Point Value: 1

Answer:

b. Quench tank pasase stops increemag.

Questies No. 62

QID: 0083

Point Value: 1

Answer:

a. Reactor power will INCREASE, te+-- will DECREASE, and pressure will DECREASE.

Question No. 63

QID: 0085

Point Value: 1

Answer:

c. InverterY24 from B61

- -

Question No. 64

QID: 0087

Polat Value: 1

Answer:

p"q .a w ay

-- ett mits c

a --

a

o t- p was ( a v -a ,

g - -- -u u. 7 '-

.g

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1998 ANO Unit 1 Initial SRO Exam Key

Question No. 65

QID: 0088

Point Value: 1

Answen

d. EDG will i=*@ start cranking.

Qi=arla= No. 66

QID: 0049

Polat Value: 1

Answen

a. Verify no flow on Discharge to Flume, FI-4642

Questian Na, 67

QID: 0090

Point Vahme: 1

Aaswan

c. " FIRE *, K12.Al

Q==*4a= No. 68

QID: 0091

Polat Value: 1

.Answen

c. 50*F/hr

QuestianNa 69

QID: 0092

Point Value: 1

Answen

a. 'Ihe inseriodc wHl suow vahe opening.

Questies Na 70

QID: 0093

Point Value: 1

Answen

c. Code safety tailpipe temperature 215 *F

!

Dele M

Qh Ns. 71

QID: 0095

Polat Value: 1

s

)ve.x3

Answen

pov

e == -

l

b. CRD raaline

' _ ____6 due to inalatian of discharge path.

/ # # ' "

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Question No. 72

QID: 0096

Point Value: 1

Answen

b. Hydrogen Recombiners

.

-. .

.

__.

..

._

.

1998 ANO Unit 1 Initial SRO Exam Key

Questica No. 73

QID: 0097

Polat Value: 1

Answer:

b. P: events damage to a fuel assembly ifit i: stuck in place.

Q-=rian No. 74

QID: 0098

Point Value: 1

Answer:

a Skin dose rate

_

Questies No. 75

QID: 0100

Palat Vahat: I

Answer:

c. PZR makeup flow would drop.

Questies No. 76

QID: 0101

Polat Value: 1

Answer:

c. Isolate idle or non-eamential components cooled by ACW.

Questies No. 77

QID: 0103

Palat Value: 1

Answer:

b. Isolase Unit 2 Inst. Air fmsa Unit !

Question No. 78

QID: 0105

Point Value: 1

Answer:

e. OSCDirector

Questics No. 79

QID: 0106

Point Value: 1

'

Answer:

b. Train "A" EFW actuation

__

Questica No. 80

QID: 0107

Point Value: 1

Answer:

d. The RC flow difl'erence will re-ratio the FW flow demand

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1998 ANO Unit i Initial SRO Exam Key

Question No. 81

QID: 0108

Point Value: 1

,

Answen

a. CV-6688 fails OPEN.

l

Q 4 No.82

QID: 0109

Point Value: 1

'

Answen

c. A DSS test would cause Group 6 rods to drop.

i

Questies No. 83

QID: 0110

Point Value: 1

Answer:

b. Immaantely invoke Technical Wh 3.0.3.

Questies No. 84

QID: 0111

Felat Value: 1

Answer:

b. Obtana peruusson from CRS, then manually actuate ESAS and make annm neement

i

Questies No. 85

QID: 0112

Point Vaine: 1

-

"*

a-.

p,, # .y

Answer:

.ro-

d. This is - -

, * ' _ Mu=: the mann== thermal output in our operating Ikanse.

g , #.3;f

7

Q h No.86

QID: 0113

Point Value: 1

Answen

a. Restore PSV-1001 to operable status within 15 minutes or be in Hot oautdown

within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Q=*=*lan No. 87

QID: 0114

Point Value: 1

^ ^ " ' "

(Jo 54 - eyq A no O y 1 f,

i

d. Performmg a PM to lubncate contacts.

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Question No. 88

QID: 0115

Polat Value: 1

Answer:

l

d. Place the unit in Hot Shutdown within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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_ ___

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1998 ANO Unit 1 Initial SRO Exam Key

Question No. 89

QW: 0117

Polat Value: 1

l

Answen

a. Incrallahan of a test gauge for a surveillarw .

M No.90

Qm: 0119

Polat Value: 1

Answen

<

!

b. CFTlevel

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\\

f

Questies No. 91

QID: 0120

Pelet Value: 1

Answen

b. 30 anautes

Questies No. 92

QID: 0121

Point Value: 1

Answen

l

d. Manager, Radaanon Protection and F" y

1

,

l

Questies No. 93

QID: 0122

Point Value: 1

Answen

a. Agree, the WCO will NOT receive a does ==8Ema=* to exceed the Adadmastrative Does Coatsel Level.

l

Questies No. 94

QID: 0123

Point Value: 1

Answen

l

d. Loss of Docury Heat RL a41 results in RCS temperature at 220*F.

4

Question No. 95

QID: 0124

Point Value: 1

Answen

a. core exit ^+--e continuing to decrease

j

Question No. 96

QID: 0126

Point Value: 1

!

Answen

c. Tube Rupture 1202.006

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a

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1998 ANO Unit 1 Initial SRO Exam Key

Question No. 97

QID: 0127

Polet Value: 1

Answer:

a. Raise primary to My Delta-T to 90 to 110*F.

Question No. 98

QID: 0128

Point Value: 1

Answer:

b. EOF Director bebeves the RB is breached.

Questina No. 99

QID: 0129

Point Value: 1

Answer:

d. GE

Questies No.100

QID: 0130

Point Value: 1

Answer:

d.,GE

1

-

.

- - -

- - - - - -

- - - - - - - - ---

ML20154H058

Text

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