ML20147C282

Exam Rept 50-346/OL-87-02 on 871130.Exam Results:Four Senior Operator Candidates Passed Exams

ML20147C282
Person / Time
Site:	Davis Besse
Issue date:	01/06/1988
From:	Burdick T, Reidinger T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20147C279	List: ML20147C272 ML20147C282
References
50-346-OL-87-02, 50-346-OL-87-2, NUDOCS 8801190152
Download: ML20147C282 (88)

Text

e U.S. NUCLEAR COMMISSION REGION III Report No. 50-346/0L-87-02 Docket No. 50-346 License No. NPF-3 Licensee: Toledo Edison Company 300 Madison Avenue Toledo, OH 43652 Facility Name: Davis-Besse Examination Administered At: Davis-Besse Examination Conducted:

November 30, 1987

,h/$1 Date Uti kl[!6gy Approved By:

% rdick, Chief Operating Licensing Sectica Date/

Examination Summary Examination administered on November 30, 1987 (Report No. 50-346/0L-87-02)

Results:

Four candidates were administered written and operating examinations.

All candidates passed the Senior Operator's examinations.

4 8901190152 880111 PDR ADOCK 0500 6

l REPORT DETAILS 1.

Examiners T. D. Reidinger, Chief Examiner, NRC 2.

Exit Meeting vn December 3, 1987, at the conclusion of the replacement examinations, the chief examiner met with members of the plant staff to discuss generic findings made during the course of the examinations.

The following personnel attended the exit meeting.

Attendees Tim R?idinger, Chief Examiner - NRC Rick Simpkins, Operations Training Manager Cindy Blay, Nuclear Licensing Anthony Stallard, Operations Training Supervisor Ron Flood, Assistant Plant Manager, Operation Hel Steward, Training Director Summary of NRC Coc.ents The chief examincr presented the following facility strengths:

(1) The candidates were well versed in the applicati>n of Technical Specification LC0's and related surveillances requirement',.

(2) The candidates were technically strong in the applications of emergency and abnormal procedures as well as the administrative procedures.

(3) The candidates exhibited good conceptual understanding of radiation protection, accident analysis, and the facility's emergency plan.

No generic weaknesse:, were noted.

3.

Examinations Review The resolutions of comments are provided.

2

RESOLUTION OF COMMENTS - SRO EXAMINATION QUESTION 5.04 (1.00) 1.

What are the THREE most significant sources of hydrogen production in containment following an accident (e.g., LOCA)? (1.0)

ANSWER 5.04 (1.00) 1.

Radiolytic decomposition c; water.

2.

Zirc Water reaction.

3.

Zinc - boric acid reaction.

(0.33 ea. total of 1.0)

REFERENCE:

PWR-0CL-047.01 028000K503 (KA's)

RESPONSE 5.04 Lesson (PWR-0CL-047) doesn't indicate which three sources are most significant.

Recommend accepting for full credit any three of the four listed in the lesson plan.

This would add corrosive action of spray with aluminum as an acceptable response.

REFERENCE PROVIDED:

PWR-0CL-047 NRC COMMENT Do not agree.

Hydrogen production from aluminum is not a significant source.

4 The question is asking for significant sources of hydrogen prcduction.

QUESTION 5.06 (0.75) 1.

Answer EACH of the following questions concerning Centrifugal Pump Characteristics:

(0.75) a.

What happens to sys.em flow rate (INCREASE, DECREASE, or REMAIN THE SAME) when a second centrifugal pump is started in series with a running pump? (0.25) b.

What happens to pump head (INCREASE, DECREASE, or REMAIN THE SAME) if pump speed is doubled? (State the magnitude of the change, if any.)

(0,5)

P 3

ANSWER 5.06 (0.75) a.

Increases.

(0.25) b.

Increases [0.25] by a factor of 4 [0.25].

REFERENCE:

HTT-SRO-013, pgs. 6, 7, 13, Figure 13.15 HTR-0RC-021, pg. 6 004000K604 191004K114

.. ( KA ' s )

RESPONSE 5.06 Adding a second pump in series could produce two results depending on whether a "real" or "ideal" pt>1p is considered.

Recommend accepting for full crediv "remains the same" or "increases."

REFERENCE PROVIDED:

HTT-SRO-013 NRC COMMENT Disagree.

Will not accept "remains the same."

Reference figure 13.15 shows a significant change in flow rate when the second pump is started.

QUESTION 5.13 (1.50) 1.

The reactor has tripped and RCS temperature is being maintained at approximately 550 degrees F.

There is a precaution in Davis-Besse procedures which states if the cooldown is NOT started within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />,

)

Group 1 rods should be pul'ed before commencing the cooldown.

Why are l

Group 1 rods needed after 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />? (1.5)

{

l ANSWER 5.13 (1.50) l l

1.

The 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> is to assure that Xenon worth is sufficient to provide the necessary shutdown margin [0.75].

After 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, Xenon decay is inserting positive reactivity [0.75].

(total of 1.50)

REFERENCE:

PP 1102.03, Pc 2 001010K506 001000K538

..(KA's)

RESPONSE 5.13 l

The Questinn asks why Group 1 rods are needed after 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

Half credit is given for why Group 1 rods are required af ter 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> and half credit is given for why Group 1 rods aren't pulled before 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

Credit should not be taken away for answer that wasn't asked for.

4

NRC COMMENT Comment noted.

Credit will be awarded for the rod requirements required after 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

QUESTION 5.17 (2.00) 1.

A control operator 1.as just calculated a "shutdown margin" with the reactor critical.

The value he determined was -1.2% delta K/K.

If the reactor tripped, and he then added + 1.E% reactivity to his core, would the reactor necessarily be critical? Explain your answer.

(2.0)

ANSWER 5.17 (2.00) 1.

It would not necessarily be critical [0.75]. When calculating the shutdown margin while critical, a control rod is assumed to be stuck out of the core plus a 1% delta K/K requirement is accounted for.

Provided the operator does not have a stuck rod, he would actually be further shutdown by approximately -2.5% [1.0].

(Also, Xe, Sm, and ppmB will chsnge by the time criticality is achieved again.) [0.25] (total of 2.0)

REFERENCE:

BAT-OLC-256 192002K114 001010K535

...(KA'a)

RESPONSE 5.17 Last statement in key gives material in parentheses which is not normally required for full credit.

In this case, this material is required for final 0.25 pts of credit.

NRC RESPONSE Parentheses were erroneously incorporated in the answer.

Information contained in the parentheses will be required for full credit.

Question and answer were extracted from the Davis-Besse Examination Bank.

Recommend Davis-Besse revise this question and answer in their exam bank to delete the parentheses.

QUESTION 6.03 (1.00)

Why are the Main Steam Line radiation monitor detectors a scintillation detector vice Geiger-Mueller or ion chamber detectors like all other radiation monitors?

ANSWER 6.03 (1.00)

Gamma ray sensitive [.25], in that, a N16 gamma [.25] would cause tube to avalanche L.25], indicating an OTSG tube leak [.25].

(total of 1.0) 5

REFERENCE:

PWR-OLC-027, pg 20, paragraph 6c 000038A110 000338A204 000037A106

..(KA's)

RESPONSE 6.03 The advantage of the scintillation detector in this application is its ability to discriminate between different energy levels of ionizing radiation.

This allows the detectar to be sensitive to Nitrogen 16 gammas which are a prime indicator of a Steam Generator Tube Leak.

Recommend accepting for full credit a response that provides this information.

NRC COMMENT Will accept the alternative explanation as equivalent to the stated answer.

QUESTION 6.08 (1.50)

AB 1203.03.4, "Cooldown Without the BWST and No Offsite Power," has the Shift Supervisor explore all sources of borated water to provide cooldown inventory to the RCS.

List the different sources of borated water (manually or automatic alignment) for the Shif t Supervisor (assume all available plant inventory water is required).

ANSWER 6.08 (1.50) 1.

Makeup Tank 2.

Boric Acid Addition Tanks 3.

Core Flood Tanks (0.5 ea, total of 1.5)

REFERENCE:

AB 1233.03.4 G0P-OLC-001, Objective 01, pg. 2 P&IO 006000K601 006000K416 000074A101 000056A275 000056K302

..(KA's)

RESPONSE 6.03 Three additional sources are listed in AB 1203.03.4 which are not listed on j

the answer key.

The three additional sources are Pressurizer, Clean Waste Receiver Tanks, and Primary Water Storage Tank.

Reconnend accepting any three of the six for full credit.

REFERENCE PROVIDED:

AB 1203.03.4 l

6

(

NRC COMMENT Will not accept the Primary Water Storage Tank as additional Source.

The question asked for sources of "Borated Water." Primary Water Storage Tank is not a source of borated water.

QUESTION 6.11 (1.00)

If a control rod "in" movement signal is generated and the rods move in the OUT direction, what auto action results from this condition from the diamond station? (ICS in auto)

ANSWER 6.11 (1.00)

Diamond rod control station will transfer to manual.

REFERENCE:

ICS-OLC-001-00, pg. 25, para 2(c) 001000K402

.. ( KA ' s )

RESPONSE 6.11 This Question concerns the Direction Error feature of the Diamond Control Panel.

This feature is NOT connected at Davis-Besse.

Recommend Question be deleted.

REFERENCE PROVIDED:

1.

PWR-OLC-036 2.

Training Information Manual, Volume 3 NRC COMMENT The ICS 1esson plan as referenced lists CR0 motor fault as an input in transferring the ICS auto system to manual operation.

Subsequent telephone conversations with the utility reveals that the lesson plan was in error.

The question is deleted.

QUESTION 6.1S (2.0)

Buses "A" and/or "B" will automatically transfer to their selected source on five conditions.

List the five conditions.

ANSWER 6.15 (2.00) 1.

Fault on main generator i

2.

Fault on Aux 11 transformer 7

3.

Main generator trip due to lockout relay 4.

Opening of 34561/60 (main generator output breaker) if either was initially closed 5.

30 seconds af ter a main turbine trip (0.4 pts each total of 2.0)

REFERENCE:

13.8 KV dist., pg. 11, paragraph C, PWR-0'

93.01, pg. 4 062000K401

..(KA's)

RESPONSE 6.15 In addition to the answers in the key, additional responses fo* auto transfers from the referenced Lesson Plan should be accepted for ful' credit.

1.

J Bus Faults 2.

K Bus Faults 3.

S/U Transformer Differentials 4

S/U Transformer Sudden Pressure 5.

S/U Transformer Secondary Grounds REFERENCE PROVIDED:

PWR-0LC-053 NRC COMMENT Will not accept additional answers.

The question specifically asks for conditions that transfer Buses "A" and "B" to their selected source.

This question did not warrant the assumption that the plant was in other than a normal power electrical lineup, in other words, no assumptions could be made that Buses "A" and "B" selected sources were exhibiting faults that would impact the transfer of Buses "A" and "B" to their selected sources.

QUESTION 6.19 (1.50)

Disregard any other plant conditions or modes.

a.

List one makeup (MU) valve that cannot be controlled from the contrcl room by the operator on a loss of NNI-Y cabinets.

(0.5) b.

List two makeup (MU) valves that cannot be controlled Fy the operator from the control room on a los; of NNI-X cabinets.

(1.0) 8

ANSWER 6.19 (1.50) a.

MU-6, R0 Letdown Flow Control (0.5) b.

MU-32-M4 Flow Control Valve (0.5)

MU-19 RC pump seal injection flow (0.5)

REFERENCE:

SP 1105.06.10 A8 1203.41, pg. 8 GOP-OLC-001.00 004000K104 004000K117 004000K205 004020K302 004020K303 000022K302

..(KA's)

RESPONSE 6.19 Loss of NNI Y is insignificant when compared to a loss of NNI X.

EP 1202.01 provides specific guidance on operating MU-19 and MU-32 ca a loss of NNI X while references to MU 6 are more obscure.

The impact on plant operations on a loss of MU-b is insignificant compared to the loss of MU-19 and MU-32.

Rer:ommend deleting Part A from Question.

REcERENCES PROVIDED:

EP 1202.01 NRC COMMENT Disagree.

Davis-Besse abnormal procedures specifically address the loss of NNI Y cabitiets.

Part A is requirca for full credit, QUESTION 7.06 (1.00)

State and describe the preferred method per Plant S/D and C/D procedure to provide reactor vessel head cooling to collapse a compressed head bubble when on natural circulation.

ANSWER 7._06 (1.00)

Preferred Method "8 ump" a RCP (0.25) 1.

Start RCP per RCP procedure (0.25) 2.

Allow pump to run until amps stabilize (0.25) 3.

Shutdown the RCP (0.25)

(Equivalent wording acceptable) 9

REFERENCE:

PP 1102.10.16, pg. 45, step 8 000074K308 000074K201 002020K512 000074A106

..(KA's)

RESPONSE 7.06 During a normal plant S/0 and C/0, RCP's would be available, preventing formation of a head bubble.

Since this question states that a head bubble has formed when on Natural Circulation, students may assume Reactor Coolant pumps are not available.

PP 1102.10 Section 10.2 provides guidance on Natural Circulation Cooldown.

This section provides specific guidance on actions to take in the event a head bubble is formed (See caution 10.2.6; pg. 64).

Recommend accepting for full credit the additional responses listed in this section of the procedure.

REFERENCE PROVIDED:

PP 1102.10 Section 10.2 NRC COMMENT Will accept two additional responses; cycle pressurizer HEATERS and start the second makeup pump.

QUESTI0t' 7.07 (2.00)

List five (5) dif ferent methods of heat transfer recovery / core cooling contained within EP 32n2.01.04, Section 6, Lack of Heat Transfer, assuming reactor coolant pumps are !!'!AVAILABLE.

AN(WER 7.07 (2.00) 1.

MU/HPI cooling throJgh high point vents 2.

MU/HPI cooling through PORV 3.

Use of a main feed pump 4.

Use of an Auxiliary feed pump 5.

Atmosphere vent valves - 5/G 6.

Use of Turbine bypass valves - 5/G (0.4 pts each)

REFERbNCE, li FP 1202.01.04, G0P-OLC-003, ATT 5.01 000074K311 10

RESPONSE 7.07 Recommend accepting additional responses for full credit from EP 1202.01.

1.

Use Motor Driven Feed Pump (M0FP) EP 1202.01, step 6.1.1.

2.

Lower Steam Generator Pressure EP 1202.01, step 6.1.1.

3.

Raise OTSG Level per Specific Rule 3 of EP 1202.01, step 6.1.1 and Specific Rule 3.

REFERENCE PROVIDED:

EP 1202.01.6 NRC C0FWENT Will accept the additional responses.

QUESTION 7.13 (1.25)

For a containmer.t entry per HP 1603.00, during reactor operation, the SS should ensure tnat the PORV block valve be closed prior to entry.

Why should the PORV block valve be closed prior to entry? (1.25) i ANSWER 7.13 (1.25) 1.

Chack at facility.

2.

Option:

[The quench tank is designed to condense steam released by the PORV AND has a rupture disc discharge setpoint of 100 psig.] An accident I

or malfunctica with PORV could possible cause the rupture disc to reach setpoint of 100 psig [.625] and cause release of radioactive contents to containment atmosphere affecting people in containment [.625].

REFERENCE:

l SP 1103.17.5, pg. I 194001K103

..(KA's)

RESPONSE 7.13 Agree with option 2 as correct response; however, recommend not requiring rupture disc setpoint of 100 psig for full credit since this was not asked for in questino.

WRC COMMENT Utility's comment noted.

11

l QUESTION 7.16 (1,00)

An operator has to take certain steps to control Xenon oscillations when they occur after a recent transient.

Describe what calculations have to be performed by the operator to control Xenon oscillations and the bases for those calculations.

(Include timing ef those steps when implemented.)

ANSWER 7.16 (1.00) 1.

Calculate delta boron batch volume of primary water to drive rods from top of band to bottom.

(0.25) 2.

Calculate delta boron volume of boric acid to drive rods from bottom of band to top of band.

'0.25) 3.

As rods approach top, add primary water.

(0.25)

As rods approach bottom, add boric acid.

(0.25) (total of 1.0)

(Similar wording accepted)

REFERENCE:

G0P-0LC-002, pg. 16 001000K405

..(KA's)

RESPONSE 7.16 Recommend accepting for full credit additional responses dealing with movement of Axial Power Shaping Rods (APSR) to Control Imbalance and dampening oscillations.

Procedural guidance on movement of AlSR's from PP 1102.04 should be allowed for full credit in lieu of calculations requested.

RLFERENCES PROVIDED:

BAT-0LC-255 PP 1102.04 NRC COMMENT The utility provided a reference not previously noted by the NRC.

Will accept the additional response.

QUESTION 7.17 (1.50) 1.

List three requirements that must be met for all authorized entries into an Extremely High Radiation Area.

(Exclude instruments, meters, and clothing.) (0.75) 2.

List three of five people (by title) who may approve entry into an EHR area.

(0.75) 12

ANSWER 7.17 (1.50) 1.

a.

Continuous-health physics coverage by C&HP b.

Two man rule c.

Special REP (0.25 pts each) 2.

a.

Chem and HP Superintendent b.

HP Supervisor c.

Chem and Radiochemistry Supervisor d.

HP Specialist e.

SS (Any three at 0.25 pts each) (total of 1.5)

REFEhENCE:

HP 1601.04.13, pgs 6 and 7 HP 1603.00.00, pg. 3 HP 1601.03.09, pg. 2 194001K103

..(KA's)

RESPONSE 7.17 Since a key is required to obtain entry into an Extremely High Rad Area (EHR),

recommend accepting additional response for full credit of any wording addressing requirement for key.

REFERENCES PROVIDED:

HP 1601.04 Tech Spec 6.12.2 NRC COMMENT Will nct accept the response of acquiring a key as a requiremant.

This is an assumption not warranted by the question.

QUESTION 7.18 (1.50)

DESCRIBE the three actions an operator in the plant is directed to perform to

)

manually trip the turbine when the turbine has failed to trip per a reactor protection signal.

(Be very specific) (1.5) 13 i

s ANSWER 7.18 (1.50) 1.

Push-emergency trip button [0.25] - EHC panel No. 2 [0.25].

2.

Pull [0.125] and turn [0.125] manual trip actuator at Turbine Front Standard [0.25].

3.

Trip the operating EHC pumps [0.25] and place HIS switches in the lock-out position [0.25].

(Each answer.5 pts)

REFERENCE:

AB 1203.01.04, pg. 3 000029K306 045050K101 000007A107

..(KA's)

RESPONSE 7.18-Question asks for actions by "an operator in the plant." This could be interpreted to mean consider only actions outside the Control Room.

In the grading of this question, recommend considering any action which could produce the desired result (i.e., trip the turbine).

NRC COMMENT Will not accept, full credit for responses required is as stated.

QUESTION 8.03 (1.00)

(Assume 100% power, see attached Tech Specs 3.7.1.2)

Surveillance testing has just revealed to you that the Auxiliary Feedwater (AFW) Train 1 pressure switch setpoint has drifted low and is unable to hold its setpoint for the AFWP turbine steam line isolation.

AFW Train 2 has the identical pressure switches installed.

Which one of the following actions did Davis-Besse elect to follow?

a.

Technical Specification 3.0.3 applies because both trains are considered inoperable.

b.

With one auxiliary feedwater system inoperable, restore inoperable system to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HSD within next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c.

Technical specification 4.0.5 applies.

d.

Reduce reactor power to a point below 50% and commence repair of AFW Train 1 pressure switches.

ANSWER 8.03 (1.00) a.

14

REFERENCE:

TS 3.7.1.2 and LER 87-004 061000G005

...(KA's)

RESPONSE 8.03 Failure of a component in one train is not grounds to declare redundant train components inoperable.

In this particular case, Plant Management decided to test the other identical pressure switches.

It was the performance of the test that rendered the remaining Aux Feed train inoperable forcing entry into TS 3.0.3.

If the testing had not been performed, entry into TS 3.0.3 would not have been required.

Based on the information provided in the question, either answer A or B could have been correct depending on the course of action Plant Management decided to take.

Recommend accepting either answer for full credit.

REFERENCE PROVIDED:

LER 87-004 NRC COMMENT Comment noted.

Davis-Besse did not elect to follow answer b, but elected to follow part a.

QUESTION 8.06 (1.00)

During the performance of a surveillance test, a deficiency is noted.

Per AD 1838.02 - Surveillance and Periodic Tests, under what two conditions is the Shift Supervisor permitted to allow the test to continue to completion?

ANSWER 8.06 (1.00) 1.

Deficiency is minor.

2.

Deficiency does not affect operability of the equipment.

REFERENCE:

ADM-SR0-013.02, paragraph 4 194001A102

..(KA's)

RESPONSE 8.06 Recommend accepting for full credit a word description or example of minor deficiency such as "able to correct a malfunction with a simple adjustment" per reference provided.

REFERENCE PROVIDED:

)

AS 1838.02 15 l

NRC COMMENT Will accept equivalent response.

QUESTION 8.10 (2.00) a.

If a safety limit is violated, what three actions are required per AD 1839.00 Station Operations (include time limits if applicable).

(1,0) b.

If a safety limit is violated, what actions must be taken per Technical Specifications if plant is in mode 5?

(Include maximum time limit.)

(1.0)

ANSWER 8.10 (2.00) a.

1.

Notify Assistant Plant Manager-0perations (0.33) 2.

Notify NRC within one hour (0.33) 3.

Ensure operation is not resumed until approved by the NRC (0.33) b.

Reduce RCS pressure to within limit [0.5] within five minutes [0.5].

REFERENCC:

a.

AD 1839. Station Operations.

Objective 09, pg. 42 b.

T/S pg. 2-1 012000G006 RESPONSE 8.10 Since Tech Specs contain actions for Safety Limit violations and Tech Specs would take precedence over requirements in a Station Procedure, recommend accepting actions given in 6.7.1 from Tech Specs for full credit.

REFERENCES PROVIDED:

Tech spec 6.7 NRC COMMENT Will accept the alternative answers.

QUESTION 8.13 (1.00) j i

In riant Startup, PP 1102.02.25, a containment vessel local leak rate test should be performed prior to Mode 5.

LIST the THREE (3) types of leak rate tests mentioned in Technical Specifications or 10 CFR.

l 16 l

ANSWER 8.13 (1.00) 1.

Type A (measures primary containment overall integrated leakage rate).

2.

Type B (measures leakage across pressure - containing or leakage limiting (bounda ry).

3.

Type C (measure containment isolation leakage rates - containment isolation valves).

(.33 pts each total of 1.00) l s

REFERENCE:

I 10 CFR 50, Appendix J, pg. 550 T/S pg. 3/4 6-2 000069A202

..(ka's)

RESPONSE 8.13 j

When these Leak Rate Tests are conducted, they are not normally referred to as Type A, B, C.

Only two types of Leak Rate Tests are conducted at Davis-Besse.

Integrated Leak Rates (ILRT) which satisfies Type A Test Requirements and Local Leak Rate (LLRT) which satisfies Type B and C Test Requirements.

Recommend accepting for full credit these two types of tests or a word description of these two tests for full credit.

REFERENCE PROVIDED:

ST 5061.02 t

NRC COMMENT Reference provided lists Type A, Type B, Type C leak rate tests.

Will accept equivalent responses as noted.

QUESTION 8.14 (3.00) a.

List the five responsibilities that CANNOT be delegated by the Emergency Director per E plan.

(1.0) b.

List two responsibilities that can be delegated by the Emergency Director per E plan.

(1.0) c.

In the absence of the Emergency Director, what five positions could assume the duties and responsibilities of the interim Emergency Director per E plan? (1,0)

ANSWER 8.14 (3.00) a.

1.

Emergency Classification 2.

Off-site Protective Action Recommendation 17

s 3.

Compliance with station procedures 4.

Safety and well being of station personnel 5.

Ordering a station general evacuation (0.2 pts each) b.

1.

Emergency exposure authorizations in excess of 10 CFR 20 limits.

2.

On-site administration of Potassium lodide (KI).

(0.2 pts each) c.

1.

Emergency Plant Manager 2.

Emergency Assistant Plant Manager 3.

Shift supervisor 4.

Assistant Shift Supervisor 5.

Shift Technical Advisor (0.2 pts each)

REFERENCE:

D-B E-Plan, pgs. 5-7 194001A116

..(KA's)

RESPONSE 8.14c Recommend accepting for full credit the normal title of the person who fills these positions in an emergency for example.

1.

The Emergency Plant Manager is the Plant Manager.

2.

The Emergency Assistant Plant Manager is the Assistant Plant Manager-Operations.

REFERENCES PROVIDED:

Emergency Plan NRC COMMENT Will accept equivalent respon,es.

18 i

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The passind cr:rie requi rc a at l e a.: t '/ n i n e n : b c a t e.:g c ry nnd a final g ra cle c: M l-ut 80' i.xaminatic n p sim r., w 1 J 1 tc p i.+ e d up six (U) haurt

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t uc +> :ar..in at ion staru cy CATEGOLY L9 C A!:D: D ATL ' b CATEGURY

.__Yh2h_._lOlAh

.._ E 2bE

__ Yb L L!b._

C61b;90hY

_ Lid __ _ ;4 W Tillwhy oF NUCLEAR 1 uwE R L AN" t

U)'EHATIU!, FLUllt. A!;1' T Hi.hMODY 11 AMI Cd a'

m 3 ' Z,3 X_

..?

M U

l'LA!r: SYCTEM: DESIG!;.

1.-

'L.

A!JD 1 H.W1 RUMENT AT IUN 2' _ e___ _ _=ti

___.____ _ 7.

Pl:00EDUhEL - te>EU A L. A1 NOIJ :A.s EMERGENJY ANI hADIDLOGICAL Cut 1T EUL

_ut._ld.__ __=i_il

_..______ 6.

ADrilNISTRATIVL lb,CEDUhE CvNDIT10NO, AND alMITA"; Iv!L

/ / t?

_ E( d __

Tata1e Final Gram-Alj wor}* d '. u ; C:J t h; E e x 3'T.1119 t 1 D n

_5 M.V i Wii.

1 l! 4 ; +. neither Ci Y -'

n O r r ? + i V. '1 TJ i :

4 Candidat

's dignature p

f s..cu, p.,

." n ~

~

' 4.

t t' t

(

bM bk yd j

11RC hULES At1D GUIDEhltlES Fol: L I C Ells E E X A M 1 11 A "'1 0 !1 S r

lh!rire the administration of this examination the tollowinti rules apply 1.

Chentinc on th; ennination means an automatje de:nial of your applicaticn and could result in mor( severe penalties.

Res_levm trips are to be limited and only one candidate at a tim: io y leave.

You nia c t avoict all contacts with anyone outside the examira, tion rc:.m to avoid even the appearance or peccibility of cheating.

3.

U s,.

bla:h ink or darc pencil only to facilitate lecible reprodu: tion, 4.

Prin: your name in the blank prcv3ded on the cover sheet of the e x ati..a t ivn.

t Fill in the date on the cover sheet of th+ examination (11 necessary) t;.

Ute Only the paper provided for answerc.

7 Irint your name in th-upper right-hand corner c: the first page of Lach Lectiun of the antuer sheet S.

Ucncecutively numb.r ench anner sheet, write "End cf Category __

at apprc printt, Ctart each category cn a new page, write only on onc Oid.

of tne paper, and write

'L ast Page on the last answer cheet.

9,

!iumber ca:b ancwer ar tc c a t e g.' ry and number, for examplc, 1.4, 6./

1 ').

M*. i p a t 1._ar. three lines betwren "nch answer

11. 6ep rte-answer sheetc f rc n pad and place finish +d answer sheetc : o.-

dc wn c,i. your d :ch cr table

12. ult abbreviatlans only if they are commun1y used in !acility literature.

13. Tn point v:.lue for tach question is indicated in parcrithesec af ter t he ques'.ivr. and can b: used at a guide for the depth of answer required.

14. S h :,u all calculatiene, methods, or accumptions used to obtain an answer t,

mathematical problems whether indicated in the question or not I t-Partial credit may be given.

Therefore, A!1SWER ALL PARTL OF THE QUEST 10!; AfiD DO tk T LEAVE A!1Y At10WER BLA!;K I f:

11 partc of the examination are not cl.:ar as tc intent, nok questienc ::

the exan.iner on ly.

17. YcU mul+ 31f.n the S t a t*-me nt on the C0ver street tn3t II.d i C a t e f, t}4at t} te -

Work il yfur own and 704 h3ve not received Dr heen CiVen a$$iStanC-in comi.letinc the examinat t un.

This must be donc st t e:r the examina+ ion Lt L en cc",pleteJ.

o IA When you complete your exarninnticn, you shal]'

(

Assemble,vour examination ac followc:

(1:

Exam questions en t cp,

( L')

Exam aide - figures, tables, et.

(?)

Answer r at;es ineluding figures which art part of the ara.wer t,

Turn in your copy of th.: examinaticn and all pager used tc an.+_r the e>. amination questions c.

Turn in ali scrap paper and the balsnce or the paper that yen did nct use for answering the quectionc.

d.

Leave the examination area, at def5ned tiy the exariiner I f :- f t e r leavinf, you are found in thic area while the examination is still in prodress, your license may be denied or revoked.

4

Pces 1 c+ b

'8EBCIQS IBEQBY EQBt3ULeS:

UR R)

P=P' P=P lo O

o I I P = -------- gth SUR = 26.06/t 3.12 x 10 fissions /sec I

1 2

2 1

eff

-- ( B L N " ~~ * ~~~~--

=e th P

=

th 2

2 y

g +

y 1 + (B L

i K-1

-(B L 2)

=e f

p P,

K K

AP = in bbC#b--

,,-CN3Cl f]/tt y

K p

initial 3

= _ tit---p C

(1-Keff!) =c (1-xeff2>

g y

3 2

1 Ci!O*l--

y,

=

m=

initial 2

,__f _ + A L__th_,

6L 1 of 1 op 2

- -- + - __ - B a

=

7 f at p at at at W

-p K

=6 P pP fD P

=P

,, e

____O gj j

th 3

O d

P 1 eff J

l l

l l

_r.-

l l

Pogo 2 of 5 QBIG_HSEEI 6IBEBdQQYUed1CS_000_ELUIQ_dECOGUICS_EQBdVLBS:

. 6 = A sh 2W LaT Q = -----------------------

1 In R /R in R /R 2

3 3

2 d=UA (AT )

- + -------- + --------

K K

K 2

3 G = m. c (AT) 4 p

Q=a6AR n

_le. _h 0

y. __le___h-_eut_)tset__

(h

_eut Q

~

out) ideal in in actual 1 1 22

____ = ____

W T

T supplied 1

2 A = pAV pAV

=pAv 4

g g g 222 3

A = KA 4 4.P p

A

= KA J5 = KA ar E = KA ao 4 ae x

nc Q

AT (in) - AT (out) f th AT G=

= ------------------

m 9

aT (in) 8.Bx10 In

(--------)

AT (out)

Gr' kAaT T

-T

= ---

Q=

c1 ps 4k Ax

^O total Q = AX AX AX

-l a

b n

___ + ___ +,

+

K K

K a

b n

i

{

4

Pcgo 3 of 5 ROIG_SUEEI sCEUIB1EUGGL_Eude_LGWS:

N A

(Ng)

H W)

P g

g g

1 N

(N2)

H (N )

P 2

2 2

2 2

68Q18I1QN_eUQ. CUED 1516Y_EQBdVLe5:

= 1 e

CV

=Cv R/hr = 6CE/d I,

0 g g 22 C = Qllyttgn_Batt I

Ib O'

=

O Volume 10 O,- At A = AN A=A CQWE851QUS:

1 gm/cm

= 62.4 lbm/ft Density of water (20 C) = 62.4 lbm/ft 1 gal = 8.345 lbm 23 1 ft

= 7.48 gal Avogadro's Number = 6.023 x 10 1 gal = 3.78 liters Heat of Vapor (H O) = 970 Btu /lbm 2

1 lbm = 454 grams Heat of Fusion (ICE) 144 Btu /lbm

=

e = 2.72 1 AMU = 1.66 x lo-grams n = 3.14159 Mass of Neuteon 1.008665 AMU

=

j l

1 KW = 738 ft-lbf/sec Mass of Proton = 1.007277 AMU j

i 1 KW = 3413 Stu/hr Mass of Electron = 0.000549 AMU l

1 HP = 550 ft-lbf/sec One atmosphere = 14.7 psia = 29.92 in. Hg 1 HP =.746 KW

'F = 9/5 *C + 32 1 HP = 2545 Btu /hr

• C = 5/9 ('F - 32) 1 Btu = 778 ft-lbf

'R = 'F + 460

-6 1 MEV = 1.54 x 10 Btu

'K = 'C + 273

-21 h = 4.13 x 10 M-sec 1 W = 3.12 x 10 fissions /sec g

= 32.2 lbm-ft/lbf-sec c

= 931 MEV/ AMU 0

1 inch = 2.54 cm C=3x 10 m/sec

-0 r = 0.1714 x 10 Btu /hr ft R

l I

i

Page 4 of 5 QGIG_SbEEI 60VE800E_IbE80GL_CQUQUCI12LIY_1El Udt2CLdl' E

Cork O 025 Fiber Insulating Board 0.028 Maple or Oak Wood 0.096 Building Brick O.4 Window Glass O.45 Concrete 0.79 1% Carbon Steel 25.00 1*/. Chrome Steel 35.00 Aluminum 118.00 Copper 223.00 Silver 235.00 Water (20 psia, 200 degrees F) 0.392 Steam (1000 psia, 550 degrees F) 0.046 Uranium Dioxide 1.15 H311um 0.135 Zircaloy 10.0 d1SCELLGUEQUS_1NEQBdGIl-QU:

E = mc 2

KE = 1/2 mv 5

PE = mgh V

=V

+ at f

O Geometric Object Area Volume Triangle A=

1/2 bh

/////////////////

l 2

Square A=S fjjjjjjjjjjjjjjjj Rectangle A=Lx W

/////////////////

Circle k = nr#

/////////////////

Rectangular Solid A = 2(LxW + LxH + WxH)

V=Lx Wx H z

Right* Circular Cylinder A=

(2 nr2)h + 2(wr )

V = wr h Sphere A = 4 nr V = 4/3 (nr2) 2 Cube

/////////////////////////////

V=S

Page 5 of 5 QGIG SEEEI Q15CELLOUEQL5_1GEC3t9I1QU 1ccatLoutdt:

==_

10 CFR 20 Appendix 8 Table !

Table !!

7-Gamma Energy Col I Col II Col I Col !!

MEV per Air Water Air Water Material Half-Life Disintegration uc/ml uc/ml uc/ml uc/ml

-6

~

4x10 Ar-41 1.84 h 1.3 Sub 2x10

~#

~3

-3 Co-60 5.27 y 2.5 S

3x10 1x10 1x10~

5x10

~D

~IO

~#

I-131 8.04 d 0.36 S

9x10~

6x10 lx10 3x10

~#

Kr-85 10.72 y 0.04 Sub 1x10~

3x10 Ni-65 2.52 h 0.59 S

9x10 4x10 3x10 1x10 "

~#

-3

~0

~

0.008 S

2x10- 2

~"

-I"

-6 1 10 6x10 5x10 Pu-239 2.41x10 y

~D

-II

~#

~

Sr-90 29 y S

1x10 1x10 3x10 3x10

-6

~#

Xe-135 9.09 h 0.25 Sub 4x10 1 10 Any single radionuclide with T

> 2 hr

-5

-10

-6 decay by alpha br 3x10 9x10 g,gg 3 10

~

which does not spontaneous fission Neutron Energy (MEV)

Neutrons per cm Average flux to deliver equivalent to 1 rem 100 mrem in 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> D

thermal 970x10 670 6

0.02 400x10 280 (neutrons) 6 0.5 43x10 30 6

10 24x10 37 c,2

,,c i

Linear Absorption Coefficients p (cm-I)

Energy (MEV)

Water Concrete Iron Lead 0.5 0.090 0.21 0.63 1.7 1.0 0.067 0.15 0.44 0.77 1.5 0.057 0.13 0.40 0.57 2.0 0.048 0.11 0.33 0.51 2.5 0.042 0.097 0.31 0.49 3.0 0.038 0.088 0.30 0.47

5.

ISE(>BY OF Nyghg6ElWKh_P.h6N T OPE 8ATioth.

Pase 4

Eh!1HEA!!2 ISEBMUDYNAdlGE VJE3T10N b.01 (1.00)

Hcw does each of thc foll: wing paran.eter chances of f ect the DNt'l

hi rd t your answer to (INCREASE, DECREASE, or NO EFFECT) and-DO NOT corc2ider the transient effects or any control system or olerator actions.

a.

Pretsuricor temperature increases b degreec.

b.

Mass f]ow rate in the core increases 30%.

2.

10. power increare;.

d.

Incr-ase in core inlct t en.pe ra tu re.

QUESTION S.02 (1.UG)

Th-reactcr is producing 100% rated thermal power at a core delta T or 60 det;rt es and s taass flow rate of 100% when a station blacl:aut occ2rs.

Ibtur il circulation is established end b core delta T coes tc-40 deel e z:-

If t!4 core n;aar t!cw rhtc le 3 '., what le the de:a.V heat (in %)'

6.

1 3 ry c.

3.0 d.

4.2 GUES'ill !)

b.U3 (2.00' l

l State whether each of the followine acnditions would hinder nhtur31 l

eirculat.1:.n flov in t'.w RCS.

( TilUE /FAliE )

(Consider each selsal at ely )

i a.

An inerense in ther:nnl driving head b

A decrean: in cold lec density c.

A repid increate in t he_ tctal nass o1 feedwiter into the. OTid d.

A decreare in nucleate balling within the core i

(*****

CATEGOhY b CONTINUED ON NEXT PAGE ****a>

w w-w w

o-

L__IBE0ul_uLliMR LEAB _EGEEh.E AUI_0LEB6I10th I' ace 5

ELULDEu682..IHEBMOD186MIRS o

i QUESTIU!J b.u4 (1.00)

Whst are the THREE most significant cources c.f hydrogen producticn in containment following an accident (e.g.,

LOCA)?

I GUEST 10; b,05 (1.00)

Why does ] o s1 2 RC flow increase when only one RC pump in primary loop 1 is t'.ipp+dY

( Assume b0% pwer)

I QUEST 10!'

5.06 (U.7b)

Antwer EACH of the fcllowing questiens concerning Centrifugal Pump Characteristics:

a.

What happens tc. tystem flow rate (It1 CREASE. DECREASE, c.r EEt!A!!;

i THE CAME) when 8 second centrifugal pump is started in series wita a running punip'!

(O.Jb) b.

What happens to pump head (.11: CREASE. DECREASE. or LEMAI!1 THE SAME) 11 purc } - speed i t dcuhled'/

(State the m3gnitude of the change, if any.)

(0.b) i

('. bO )

j CUEST10!1 b.07 a

Explain why a dropped rod. (with all other control rodt out;, is worth approximately 128 p n while a stuch rod (with all other control rods in) is worth about 1200 pcm even though the same rod could be considered in both cases.

( :.. L ;

l i

)

QUESTI<Al 5.US (0.60) 1 For equivslent positive reactivity additior.s to a critical ro cter lvw in the intermediate range, will the SUlt b+

the (SAME, LARGER, or SMAL.,El;> at lab as c_,upared to EULY no explanation required')

(.bO)

(Chs.sse one l

I e

9 N

b.

T !! K6!b L W_tNg hg a B_ E9EE.B_.E 66tR _QLiB AIlgtL.

Page t;

Ebul.D M B!L_IUEBMoDYriaMiGi UUESTIlli S.09 (1.00)

The Delayed !1eutron I n.po rt ance Factor at Davie-Deste is.

thnn ene becaur.e ciol syed neu t ron s _____ _.___

(Choose the correct responce)

1.

Lesa; are les.t likely to lenh from the core.

b.

le t r, : du nc t cause Intt fission of U 238.

t ti re a t e r. a r.; loss likely te leak from the core.

d.

Gr+st

r. do not cause fart fiss. ion of U-235.

GUEST 10:1 5.10 (1.00).

Which O!1E of the fcllowinc statements concerning the power defe n it c :; r r. f t '

s l he pc.wer il :1 c t i t. the difference between the tueesured Icwi.r Coefficient nrt d thy predicted })-:'W *.* r C C 0 f f i c i e n t.

b l h.- Evwer defect increases the red worth requirementr nccor!.nry t.:

r. sin t a in th. desir<d shutdown margin follow 1n,7 a res tor r21 c.

E+ c w s-

t the hieher bcrcn concentration, t her power defect i.- o ira necsti' - at bedinninc o.t core lift.

d.

S h-power cef e ct necesnit ates the use of s conster.t Tavc rrcr.rnt to maintain an adequate husetor Coolant System cutcooling margin.

i

t. * * * *

• CATEGt'hY b CO:nI!!UED Ut? IJEXT PAGI

• • • • • 1 i

J

b.

T H MQBL QLtlM C L M6 Fl_ ER'd68_l%6[iLOEE86T I Ot1 Page 7

1 F__EU 1 LC.i_ A_N___I_)_T_.H_E_IC. _+.J..D._ Y_tJ.A!_1.1_C__S_

QUEST 1Ull S.11 (2.bu1 Answer each of the following True or False.

Equilibriu n Samarium concentration is a f unction of pow.er (0.51 a.

b.

Equilibriun Xenon re: activity 3s dependent upon core burnup.

tD.5) c.

X+non car.cer;tration initially increas-:s after a reactor trip.

(0.5) d L qu$ librium Camarium concentrntior af ter a trip is a functicn or the previour_ p wer level (O.b; t"

5'quilibriun Xenon c ' centration after a trip is a function or th.

previ:,us power 1e'.a-(V.b)

QUEET1071 5.12 (1.00)

Exp' ;n how and why the scu"ce rangc indientions would behavo durinc core v _> i d i n g fr:im a LT ; c a n d i +; *. u.

(

.0)

QUEST 1011 5.13

1.t9 Th t: r.actcr has tripycd and EC' tenperature is being maintained at approximately bbo degrees F There is a precaution in Davis-Becce procedures which etstes it the cocldown is t1UT started within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

Grun-1 rods should be pulled before commencing the cooldown.

Why are G~

1 rods neeCed atter 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />?

(1.5)

(+****

CATEGORY

$ CONT!120ED ON llEXT PAGF

• 6*+4

)

lu__THEul!Y_Qf _DilgbEb8_f0' DEB _PL AULOLENAllgth Page 6

ELUILE6BD.lHERUODYNAMES i

I t

QUESTION b.14 (1.SO1 i

l>uring o startup after a previous reactor trip, will the actual 'ratic50 position be nigher or lew r than the estimated critical position.'ECPi for the following conditicne?

(Corsider each as a separate occurrene and' explain each answer )

(Assume negative MTC)

(1.b)

The operator unintentionally c ver-f eeds a steam generator while t

u.

f reaching criticailte l

b Actual boron concentration is lower than the concentration used to figure ECP l

c Startup was delayed four (41 hours4.74537e-4 days <br />0.0114 hours <br />6.779101e-5 weeks <br />1.56005e-5 months <br /> beyc nd the ECP time; a shutdown time of sixteen (16) hours was used in the ECP t

GUEST!ON 5.1b (1.SUj r

List three (3) factors which can contribute to the reductic n of.shutdewr.

l margin I SD'l; when the reactor is in a shutdown mode.

QUESTION t.10

( '.. 0 0 )

After operatind in natural circulation for two (2) hours, a complett 15.s or natural circulation flow cceuro.

How will the following parameters change (INCREAGE. DECREASE, REMAIN THE SAME)?

Briefly explain your answer

Assume no further operator action.1 P

a.

Core delte T (0.5) b.

Core thermorouple (O. t )

c.

Steam generntor pressure

'O.hi d.

RCu pressur-(O.51 1

L 7'"'3T 10N b 17 (2.00)

A

'c ntrol operatur has just calculattsd a ' shutdown margin" with thc teactvr critical.

Thu value he determined was -1.24 delta K/K.

If the rev:t or t ri;. ped, and he then added 4

1. 2*4 rn.ctivity to his cc re, wou}d be necursarily b.

e r i t i c a l ':'

Explain your answer.

(2.0)

(*****

C ATEG01J' b CONTIMUFD ON NEXT PAGE

• • • • • 1 f

y

hu TUE2BX.it_UQ0LE68_D.MEB.ELANT._.QREE6TlQUt Page 9

FLU 10!iz6UU IBEhdODXU6tilM QUESTIU11 5.?8 (1.bO)

Control ruds are required to be maintained above a specified height during reactor operationc.

STA'l E three (3) res - ns for the control rod insertion limits.

(1.b)

P l

1

(**+**

Eb!D OF CATEGURY 5 **+++)

6.

ELAU.T_siYMEUs_.kE3] A__CollTRUL2_At4D INSTRUMEt4TATION Page 10 QUESTIO!4 6.01 (1.50) 1.

Which one of the following best lists the inputs BTU limits in the ICS?

( 7b) a.

Selected Th, turbine header pressure, OTSG level, RCS 1 low b.

Feedwater temperature, RCS flow, Tavg, feedwater demand c.

Selected Th, OTSG pressure, feedwater temperature, RCS ilow d.

OTSU prescure, neutron error, AFW flow, f ee.dwater temperature 2.

What is the primary purpose of BTU limits?

(.75)

QUESTI011 6. O '.:

(1.50)

With the unit o >eratin ' at 1004 power with all control systens in automatic, a turbine bypsse valve fails full open.

Indicate how the f ollowinc paran eterr, will change (It1 CREASE, DECREASE. REMAlti THE SAME) relative t., their initial values when plant conditions stabilize.

( Assum no reactor t rip)

(!!c explanntion required) a.

Tavg b.

MWC c.

Reactor Power QUESTIU!!

6.03 (1.00) the Main Steam Line radiation monitor detectors a scint i))ation Why are detector vice Geiger-Mueller or icn chamber detectors like all other radiation monitors'?

(*t+**

CATEGORY 6 C011Tir10ED Or1 11 EXT PAGE ***++)

0., _1%6MT SYSTEMS _DESIGHu _ CONTbl. 68D..lE81BMdEUIOT.lg3 Pap 11 UUESTJU!1 ti. 0 4 (1.00)

Which cne of the following will fluT cause the ICS to enter the TRACKllM raode cd operation?

flacing the Diamond Control Station in 14anual.

a.

b.

I' lacing P,UTH tiain Feedwater valves in manual control.

Providing the turbine with 45% more power than is being c.

produced by the generator d.

Feedwater Cross Limits in offcet.

QULSTIU!J ti. O b (2.00)

STATE whether the following statemente correctly describe the functions of t h.: cvmponent evvling surge tank safety vent system.

TRUE/ FALSE.

a.

The CCW atmospheric safety vent normally vents to atmosphere.

D.

The CCW atmospherir.' safety vent can be positioned to vent t h.:

miscellunctus waste gas tanh when high activity exists in t he C*N cy: tem c.

/ CCW uaiety vent vents. to the miscellaneous waste drain tank only in conditicns of high activity in the CCW sys terr..

d.

A CCW three way valve contro]s both the CCW safety vent tc. atmosphere and CCW st.fety vent to miscellaneous waste drain tank.

UUEST] O!1 6.06 (1.bu)

List the six modifications made to th heactor Protection System (either autcmatically or manually) when the shut down bypass ke" switch is placed in bypass (Setpoint5 not required)

(***44 CATEWAG 6 C0!1 tit 1UED 011 t1 EXT PAGE + + + * * )

PLAU'L.0YFIEM. _ DES 19)L_QQU1Bgb_6UD_lDSIBU.tjESTAI190 Page 12 2

y.

1

)

o QUESTIOt1 6.U7 (1.25)

Per AD 1303.1',05, Control Room Evacuation, the operators are dircett s to d

the Auxiliary Shutdown Panel to perform various actions.

State whethe the foflowing is an action the operator can perform from this panul.

(TRUE/ FALSE) a.

Actuate atmospheric vent valves b.

Control RCS pressure with pressurl er heater banks 2.

If conditions warrant, trip 1 RCP in

'D" Ic.op d.

Contr31 the auxiliary feed pinup turbine dovernor valves e

Isolate letdcwn with letdown isolation valve MU2B QUESTIUll 6.06 (1.60)

AD 1203.03.4.

'Gooldoun Without the BWST and tio Offsite Power" has th*-

Shift Supervisor xplore all sources of borated water to provide cooldown inventory to the RCS.

Lj st th-di!ferent si.*urces of borated water (manually

_'r butc matic alignment) for the Shift Supervisor (assume all available plant inventory water is required:

QUEST 10!;

6.09 (1.00)

Which one of the following is 119T a design difference between t h*: eafety reculatory control rods and th :: APShv/

Ou gn APEF dels s a small buttoa. on the segment arm prevents the leal a.

screw irem belag disengaged when power is lost b.

AlSR couplings have larger diametr rs and shorter keys tc. prevent coupling an APSM drive to a sa.'ety or regulatory rod or vice versa.

c.

AMih drives have ball valves and bypass ports, d.

AFGF do tk T have buffer springs in the buffer assen.v.

(*44**

CATEGORY

f. Col 1TIl10ED 011 NEXT PAGE *****)

6.

5 !T SYSTEMS DESIGNmRE]'8%_AND._it STRUMEt1TATlvN Pc ce 13 o

QUEDTION 6.10 (1.00)

List TWO possible causes for s*eam binding af the nuxiliary f eeciwate r pumps during normal pcwer operatirns, QU) 'TIUN 6.13 (1.00) 11 a control rod in" movement signal is generated and the rode movv i t, the OUT directier.

what auto action recults f rcm this condition f rom the diamond station'?

f I CH. in auto)

UUESTION 6.12 (1.00)

Which one of the following conditions would result in an GUT INHIPIT beine generated in the Rod Contral Logic?

a.

Safety kod Groups at the out. limit.

b.

Asymmetric fault with power level at 604.

c.

A startup rate of 2.1 dpm in the source rangt d.

High neutron error signal (2.b%)

f

(+44*+

CATEGORY 6 CON'lIN JED ON NEXT PAGE **"**)

t3.

_L'lehMIMdT4Md l!Edlyth..lyG181. 6ER._.l.lidIB!,108BI.1TI.QU Pate 14 QUEST 10!!

ti.13 (1.60)

Match each of the following inputs to its possible functions or controls, fone answer each)

Inputs Functions / Controls a.

T-hot (narrow) 1 RCP interlock b.

T-cold (wide) 3.

ICS BTU limit e

RC pressu.e Iwide) 3.

P2R Htr control d.

RC pressure (narrow) 4.

Adjust MFP speed to maintaan constant d/p across feedwater e.

Feedwater D/P control valves 5.

Core flood interlocks 6.

Provides the ICS the signal to adjust total and locp feedwater flows OUhN J.H b 14 (1.00>

The Snfety Actuation Monitorinc s3AM) lights aid in determining plsol.

condit.icnc after an SFAG trip.

Match the light status t <. the conditions.

Light Status Conditions 1.

Off A.

Bright conditions plus the equipment hac been placed in its Dim non-safety actuated position 2

3.

13right B.

Dim conditions plut. the bicek switch has been depressed allowine 4.

Flashing the operator to take normhl control of equipment C.

SFAS trip and the equipmer.t operated properly D.

No SFAE trip or SFAS trip and tw_

equipment did NOT oper-te

(****4 UATEGORY 6 CONTINUED ON NEXT PAGE *****)

l

)

l S.

PLANT SYMITh4fi_1RSIGN._.Q9BTB9Lu_.AUP_,1NSTRUMEUT6IlgU Page 15 2

QUEST 10N 6.16 (2.00' buses "A" and/or

'B" will automatically transf er to their select ec' source on fivo conditions.

List t he five conditions.

QUES' 1Uti 6.16 (1.00)

Explain the "KIRK KEY INTERLOCK" procedure on tha 480 VAC eseential power motor montrol center in transferring normal power to alternate power QUESTION f 17 (1.00).

List the two ur.interruptible distribution panels and their alternate-power supply distribution panel.

QUECTION 6.18 (2.00)

List four conditions that wilI cause a runi,ach of the automatic losd c1 the Unit Lc.ad Denand Subsystem (list one ty pe for each)

(Hates /s.:tpoints not required)

QUEST 10!!

U.19 (1.50, Disrecard any other plant conditions or modes, a.

List one makeup (MU) valve tnat cannot be controlled f rom the contrc l room by the opera *.nr on a 1. css of NN1-Y cabinets.

(0.b) b.

List two makeup (MU) valves that cannot be controlled by the operator from the control room on a loss of NNI-X cabinets.

(1.0)

(*****

CATEGORY 6 CONTINUED 011 NEXT PAGE &*4*4;

6.

PLhtJ1_1}Y_STElf_.IJ3EILith cut 1TB9]u At1D IriSJRUMEllTATIO!)

- bre 10 QUESTIGli 6.20 (1.00)

In which one of the following is automatic sequencing and overlap tlVT achieved ~.

9.

Regulating rod withdrawa] to criticality in manual from the diarnend sta'icn.

Reculating red motion achieved by placir.g the recetor demand. station c.

in tunnua l.

e 83fety rod withdrawal.

d.

As: mr atrj c rod ranback

)

i (4*+4*

EliD OF CATEGORY 6

• /

PROCEDURED - HORMAbu_APjiQld6L _Elig89EtJC.1 Page 17 t

AND RADlOLOGIChh_CONTROh 2

OUESTION

'/. 01 (1.50)

Per Steam Generator Overfill procedures, adverse effects on the secondary.

side will occur on severe overf111 to the OTSGs.

Describe three.adverne effects on the secondary side, other than water hammer effects.

(1.5)

GUEST 1oM 7.UP 11.00)

If the RUPs can be effective in cooling the core, even with two-phase flow, why must the RCP'c be tripped when the subcooling margin ia lo r/ *.'

QUESTION 7.03 (1.00),

Place the followinc Emergency Procedures in the. correct order of priority in which they are referred to when performing EP 1202.01, and which are continually monitored tuiti} plant conditions stabiliz.c.

(Assume that a S/G tube rupture was NOT the initial entry condition.)

1.

E.s. cess i ve lleat Transter 2.

Laer.

f Heat 'ir r.sfer 3.

Inadequate Core Cooling 4.

Steam Generator Tube Rupture QUESTION 7.04 (1.ro)

When both radiesetive monitors (RE 1878 A & B) tor miscellaneous liquid waste or ( h E 11'I '.i A&B) for clean liquid radwaste are inoperable, the SS shall ensure that three actions are performed prior to release.

List the 3 activne.

GUEST 10N 7.05 (1.00)

A precaution in Plant Shutdown and Cooldown Procedure states if a lots of AC pi>wer occurs during a plant cooldown to 260 degrees F causinc inadequat.: hest remova] capability, then m8ximum cooldown rate will be limited to IU degrees F during natural circulation due to _.

cooling considerations.

( * * * *a UATEGORY 7 CONTINUED ON DEXT PAGE

• • • • • )

-TT

7.

PhudistLUj;l;.ti_- _UUlitj6Lx_AktJQ8tjAbuhtiEEGEtJg1 Page 16 AULtB611L9692 96L_GRUIBOL QUEST 10!!

'/. 0 6 (1.00)

Gtate and describe the preferred method per Plant S/D and C/D procedure to provide r.: actor vessel head cooling to collapse a compressed head bubble when on netural circulation.

QUESTIuti 7.07 (2.00)

List five (b) difi.ent methods of heat transfer recovery / core coolinc contain+:d within EP 130:.'.11.04, Section 6, Lack of Heat Transf er, assuminc reactor coolant pumps are U11AVAILABLE.

QUEST 1Ull 7.08 (1.UU)

]n the Plant Shutdcwn/Cooldown Procedure, in a stcp prior to "Trip the h a c to r ' it states 'stop the cooldown by manually adjusting the turbine bypan loop controllers when RCS is 2100-2050 psic and maintains a cunctant Tave.

What is tite specif1. reo,on why the tu rb i n t-bypriss Ic.op controllers slioul d te in nanuai el a..

auto prior to tripping the reactor QUESTlOt;

'i.09 (1.00; A1: 2203.23.06, CIW Malfunctions, cautions the operator 140T to operate a stuck rod which is partially or fully withdrawn in JOG speed.

Explain the bneis Ior thi s caution.

l OUEST !vil 7.10 (1.00i At norr.ia l Pro cedure. Sm.sll RCS L<.aks, directs that the operator trip the re a ct..,r it pressuritcr level cannot be maintained above _ __ _ _

incher..

(9*+**

CATEGORY 7 cot 1TillUEl> 011 14 EXT PAGE * * * * * )

7-P h 0 C hl'Ul @ li__ _ Il2 h M 6 k t 6 0!!918.!8 k t _ E M E W.i K M g 1 Page 19 Auk _BA419Lgq1 CAL._G9BIMOL QUESTION Y.11 (O.60)

True or False.

On an emergency deviation from Technical Specifications, you are required to notity the IJRC prior to the deviation.

(U.b) 4 QUESTION 7.12 (1.50)

HP 1601.01.10 provides exposure limits to be used during an emergoney.

State the whoi.: body and extremities exposure limits to be used during an emergency and litcsaving conditiens.

QUESTION 7.13 (1.2b)

For a containment entry per HP 1603.00, durinc reactor operation, the SS shr:uld encure that the PORV bloch valve be closed prior to entry Why should the PURV block valve be closed prior to entry 7 (1.20)

QUESTION 7.14 (0.50)

Whose authorization is required for a unit restart to proceed if cause of rea tor trip, sequence Of events, or safety concerns identifled cannot be d e t e rmi n e d'.

( EO)

QUEST 10t!

7.15 (1.50)

Th c.

limits of the rate of power increase of 10% per hour below 204 power is to prevent expancion of f 2ol defects in possible water-logg :d f uc t pine per PP 1102.04 (Power Operations).

a.

Explain a ' water-logged' fuel pin.

(0.5) b.

Explain the basis of this ra t e.

limit of 10% per hour below 205 power (1.0)

L

(*****

CATEGOR't 7 CONTINUED ON 11 EXT PAGE * * * * * )

L __.thugEk!Rhb - 11Uh361o_6buQ8M6 k hdE.BgEug[

Pag.e 20 hul' RADIOLOGICAL CQrEhQL j

r }UE:1, TION 7 lu (1.00)

An operator has to take certain steps to control Xenon oscillationr. when they occur after a recent transient.

Describe what calculations that have to te performed by the operator to control xenon onceillations and the bases for those calculations.

(Include timing of those steps when implemented.)

OUEDTION 7.17 (1.50) a.

List three requirements that must be met for all authorised entries into an Extremely High Radition Area.

(Exclude instruments, meters, and clothing.)

( 75) b.

List 3 of L people (by title) who may approve entry into an EHR orca.

t 7b)

QUESTION 7.18 (1.5U)

DEGURIBE t h.: 3 action: an crerator iri the plant is directed to perform to manually tr.ip the turbine when the turbine has failed to trip per a resetor protection signsl.

(De very specific)

(1.b)

QUEST 1Ull 7.19 (1.60)

L$st the three (3) steps an operator is directed to perform five minutes after a loss of component cooling to all RCP's has occurred without CCW r -covery.

(1.b)

QUEST 1UN 7.20 (1.00)

When conducting a rapid plant shutdown at 25 MW/ min (Abnormal Procedure AB 120 3. 07 ), why is the operator required to add boric acid to the makeup tank as unit lcad decreases.

(1.0)

( * + +.e

• CATEGORY 7 CONTINUED CN NEXT PAGE

• • • • 4) i 1

I

7 l'Jf.Qggpj)[1EQ_;_UQBrjbLx_6LHQBijAL1_g[jgBggMgy Page 21 AND_BAM9L99EAL_WNTROL QULSTIUf1 7.21 (1.00)

Dorine an approach to criticality, criticality is achieved before the lower rod i n -t ex is reached.

The operator should:

(Choose the correct answer from the following choi ms.)

(1.0)

Trip the reactor and recalculate the ECP a.

b.

Stop rod motion and check ECP e.

Insert all rods.

d.

Insert the regulating rods.

4 QUESTIOli 7. d:1 (1.b0)

AccorJing to D/B Control hoom Evacuation (AE 1203.12), what actions should the primary side Reactor Operator perform prior to evacuation and where should Le cc af ter evacuation'!

(1.5)

(**++*

ENI) UF CATEGO!<Y 7

+44*t)

6.

AD!jly.10TBAllVE_PB99EDDEEL CONDlllOUL Page 22 AND Llt11 TAT 190;3 o

i QUESTION 8.U1 (1.00)

Recently this year with the unit in mode 1 with reactor power at !.@:.. the ine rc detector computer points were inadvertently deleted from ccan for apprcy.imatcly 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> without any operator actions.

Which one of the 1o1 lowing netions did Davic-Besse elect to follow?

a.

This constitutes a Technical Violation because a>;ial power irnbalance calculations were not completed per T/E.

b.

This constitutes a Technical Violation because Quadrant l'ower Tilt calculations were not completed per T/S.

c.

'I he inoperability of incere detectors and associated Quadrsnt Power alarm and imbalance alarm neither involved an LCO or constituted a T/S violation, d.

The inoperability of incore detectors scan points would be a T / '-

violatien if the incore detectors are being used to monitor cor.

parameters.

QUESTION O.U2 (i.00)

(Assume 100% p:,wer, see attached Tech Specs) (3/4.3.2)

Rucently 1&C personnel bypassed the Safety Features Actuation System (SFAO) Channe1 1 Co n t a i nn:e nt Radiation Trip Module while performinc poet maintenance tacting on the failed level detector (RE 2004).

Which one of the following actions should have been acccmpli.hed in accordance with Tech Specs?

a.

Action 10 b

/setion 9 c.

Act ion 11 d.

Action 12 e.

Action is

(*4***

CA'l EGOhY 8 CONTIUUED ON NEXT PAGE 44 +*+)

fi_.___6DMlG13It'611Y K_ EliOi!M D U BEB x _ gO U D LIlg tlfit Page 73 6BR_LitilT6T10t1S I

QUEST 1011 0.03 (1.00)

(Assume 100% power, see attached Tech Specs) 3.7.1.2)

Survei11ance testing has just revealed to you that the Auxiliary Feedwater (AEW) Train 1 pressure switch setpoint has drifted }ow and is unable tc huld its setpoint for the AFWP turbine steam line isolation.

AFW Train 2 has the identical pressure switches installed.

Which one of the following actionr. did Davis-Besse eleet to follew?

a.

Technical Specification 3.0.3 applies because both trains are considered inoperable.

b.

With one auxiliary f eedwater system inoperable, restore inoperable system to operable statas within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HSD within next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c.

Technica) Specif icatic n 4.0. 5 applies.

d.

Reduco reactor power to a point below 50% and commence repair of AEW Train 1 pressure switches, QUEST 1011 8.04 (1.ua)

Recently a transient at Davis-Lesee resulted in one main steSm safety valve failing to tully rescat in m'>de 3.

Which one of the fol]owing i t. applicable action in mode 37 a.

Operation in Mode 3 may proceed without any restrictions on the number of inoperable main steam safeties.

b operati>n in Mode 3 may proceed if within a certain time limit thc inoperable v slve is rest c red to operable s t stu.i c.

Operation in Mode 3 is t permitted. cold shutdown is required within a certain time limit.

d.

Pravision of specificction 3.04 is applic@lc l

i

(***4*

CATEGORY 8 CO!1TItlUED O!J 11 EXT PAGE *****>

6.

hMi U1E E 6Il y E._ W9C E lf.!h b b.,_CgN D I T 10!1 s t Page 24 6HIL.LIMLI6112 tis UUESTlot; 8.06 (1.00)

Assum.: full power operations and refer to the attached Tech Spec excerits t3/4 8.1) to answer the followins' In the event E n..:: r ce n c y Diesel Generator (EDG) 1 is taken out or service for scheduled preventive maintenance repair, which one of the following.

actions would be most cc rrect in accordance with Tech Spees'.'

a.

Demonstrate the operability of two diesel cencratora by performing ik 4.8.1.1.2.94 after BDG) is repaired after 1 day within 8 heurt ar.d at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.

b.

Demanstrate the operability of the remaining

.'.C sources by performing Sh 4.6.1.1.la within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereofter c

h st..re et lenst two diesel generators to operab)* status within it hours from time of initial loss.

d.

Resttrc at least one of the inoperable sources to operable stMur within 1::' hours or be in at least Hot Standby within the next 0 h4..u r s UUE::'T I UN 8 00 (1.001 Durine the performance of a surveillance ter,t a deficiency is noted.

ler AD 1630.U'

- Surveillance and Periodic Tests, under what TWO conditions is t h t_ Chift Supervisor permitted to allow the test tc. continue to con.p l e t i o n?

F QUES'l I UN 8.07 (1.UU>

l.ccordinc to AD 1606. Procedure Preparation and Maintenarice, whet is the maximum period of time thst temp.rary approval may be granted !cr a procedure' UUESTION e.00 (1.00)

According t.. Safety Taccing AD 1803. an annual physical audit is required L1 L._ perfermed on tags, in a locked High Radiation Area.

TRUE/FAL T l

l l

(44* ** CATEGURY 3 C0!JTlflUED ON 11 EXT l' AGE *****)

8.

A Dti l ti l ST R AT ly E _t 8QC1))!!BK'a_gOt1 D I T I ON F,.

Face :!b Ar1D Lit!1I6Tl2 tin QUESTION 8.09 (2.00)

According to the Sarety Tagging Procedure. AD 1803, when tagging a manual v a l v.- c l o s,2 d, it is mandatory that the valve be positively verified close.d prior to hanging the tag.

a.

What TWO methods must be used to verify a menual valve clcced prior to hanging tag.

(1.0) b.

What is the one mothed used to verif y a manual valve is open prior to hangine the tag?

(1.0) i QUEETION 8.10 (2.00) a.

If a safety limkt is violated. what three actions aree required p:r AD 1839.00 Station Operations (include time limits if applicable).

(1.0) b.

11 a safety limit is violated. what action (si must be tahen pr.r Technies1 Spec 1fications if plant ic !n mude S?

(Include mnximum iime limit)

(1.0)

WUESTIO!1 0.11 (1.00)

Durinc a surveil. lance test, IC reports that cont inment pressure high setpoint is less conservative than its allowable value.

List at least THREE actions stated per Technical Specifications or AD 1839.00, Otaticn Operitions, which must be d o ue ')

QUESTlv11 8.12 (1.00) i List 8 conditions when th<-

STA is required to be in control room per AD 1833, Station operat.ivus, within 10 minutes of notification.

1

CATEGOR'

8 Cut 1Til10ED Ull 11 EXT PAGE *****)

j l

j

L _ ADI1114iW1lEl.1 M _l'HggEbijhES CutID1TIQth Page 20 u

AtJD LIMITATIOt1S QUESTIO!1 8.13 (1.00)

In Plant Startup, PP 1102.03.26, a containment vessel local Jeak rete t.: s t should be performed prior to Mode 4.

LIST the TilhEE f 3 ) types of leak rate tests mer.tioned in Technical

.;pecifications or 10 CFl:

QUEST 101)

M 14 (3.OU' a.

List. the five responsibilities that CArir10T be deleceted ty the Emergen:y Director per E-plan.

(1.0) t List two responsibilities that can be delegated by the Emergency Director per E-plan.

(1.0) c.

In the absence of the Emergency Director, what five positions cou.td a s s urae the duti.::s and recronsibilities of the interim Emergency Director per E-plan.

(1.U)

QU ID.'.T I Oli t>

1 I-(1.UU)

True or False.

To downcrade Emergency Action Level conditiont, the existing conditions, must no longer meet the emergency criteria and it appears unlikely that conditions will deteriorate further

,OVEST1 vil 6.10 (1.00; What are thc bases per Technical Specifications f or maintaining at leatt 23 f r-e t et water..ver the top of t W-trradiated fuel assemblies n.mted in the storagc ra ck.-n (1.0)

(++***

CATEGORY 8 COtlT1110ED 01111 EXT PAGE 4i+*')

B.

ADM1GMTB6TlVE PBQCXpt)P,E_C12GDlIlOUE2, Pasc 27 AND LIMII6TIONS QUESTION 6.17 (1.00)

Technical Specifications 4.04 ensures surveillance activities asscc3ated with LCO's have been performed prior to entry into an operational node or other applicable conditions.

State the maximurn grsee period intervals that a surveillance may be extended.

QUESTION B.18 (1.00)

TRUE er FALSEY The Shift Supervisor,has made the emergency decision to deviate from an approved procedure.

He must have prior NRC concurrence per AD 1839.

St *.s tion Ope rs ti c ns.

VUESTiUN 8.19 (1.UU)

I'EUE or FALSE?

Satisfying the requirements of the action. statement of a Limiting Condition for vperation (LCO) constitutes compliance with an LCO and is not a violativa or the LCO.

(1.0)

QUE3 Tit?:

8.JU (U.LU)

According tc AD 1839.03, Operation and Control of Capped Valves. what

.: o l, r it used tc denote a capped valve?

(.5) i QUECTIM

8. 21 (1.00)

According tc. the afety Tagging Procedure AD 1803, when taccing a molded case breaker !1ik the ones un 40U V McC's), why is it necessary to phy s i ::211 y attempt to open the breaker (1.U) j i

l

(*****

END OF CATEGURY 8

• ++*d)

(********** END OF EXAMINATION 4+4**d'+**

)

b TlllWHY.12E_l!!NLE68 LQWEM._tL6MI.JLMBST10tl, Par; 2 :28 FLUl1G.AllD THERMODYt1AMICS y

3 b d.\\

At1SWER b.01 (1.00) n.

Increase [.25j.

b 11 crease [.25].

c.

Decrease [.2b].

d.

becrease L.2b].

REFERErlCE Technical Spreificaticn 3.2.b, llT & FF (Generel Phyeics)

IITT -SkU-00 3, pg.

10. HTF -ORO-UO b 193000K1U!.

IKA's1 l

a A!J3WER b.0L (1.00) b hEFERE!JCE HTC-000-011, pc.

't UDOUL.tiK101 00LUU0A106 (KA's)

AtlGWEh b.U3 (2.00) a.

Fals.

b.

T r a..

c.

Falte d.

True tU.b pts ea rli,

EEFEIS!h'E

{Y. b

.0 I

. c p

1930Uh.1J' 1930'.!bKILI (KA's1

(*****

CATEGORY b CO!JTItJUED O!i liEXT l' AGE 4 * * *

• I

TUMORY OF NUCLK61]._E0HEB_ELARI_QEEB6IlQtic Page 29 ELU1gi1.6t!D_IUKl.R12DXt!6t31G ANSWER b.04 (1.00) 1.

Radiolytic decomposition of water.

2.

Zire Water reaction.

3.

Zine - boric acid reaction.

(0.33 pts each)

REFEREllCE PWR-OLC ' 4 7. 01 J

028090K503 (KA's)

AN.3WER 6.05 (1.00)

Loop 2 RC iIc.w increases t>ecause there is less D/P [U.5] across the Rx vessel due te lower total RC flow [0.b] which allows the two RC pumps in loop 2 to provide greater RC loop flow in loop 2.

(Cimilar wordir.c acceptable)

REFEhEllCE ICS-RCP, pg. 3 10S-OLC-003~UO UU3UUUKSUL OU3000K301 (KA's)

At1SWER b.00 (0.7b) a.

Increases.

(0.25) b.

Increases (0.25] by a factor of 4 [0.2b].

REFERE!1CE llTT-Sh0--013. pgs.

6, 7,

13, Figure 13.15 IITR -ORC- 021. pg. 6 004UOUKUO4 191004K114 (KA's) t****4 CATEGORY b C011TINUED 01111 EXT PAGE *** n'.

.b..

lBE98L9f_ULTLEAh_.E9BEB_.ELABL9EEBA119L Psge 30 ELMl]JLAUD THEhMODYBatJ.LQ_S A11SWER 5.07 (2.by)

[ Rod worth is a function of the relative t}ux difference between the flox at the rod tip and core avsrege flux ]

When a rod is stuck out with all other rods inserted, that rod ' secs a

ruuch higher flux than the rest of the core, and would be worth 1200 pera.

(1.2b)

If a rod is dropped, that rod depresses the flux in the area it is in relative to the rett of the core, and would be worth only about 12tc pc tn

( 1. 2 t. )

(Similar wording will be accepted)

REFERENCE PP 1101.02.6, Figures 8, 10 RTH-SRU-006, pgs.

8, 9

00V0O3K120 001000A203 (KA's)

A!1SWER b.08 (9.50)

Smaller.

REFERENCE RTH SRO-010-00 E-1-b, pg. 8 RTH ERU-011-00 B-2, pg. L 192000K107 192003K104 IS2003K106

..(KA*t)

ANSWER 5.03 (1.00t t

REFERE!R'E RTH-GEU-010-00 192003K107 (KA's1

(**441 CATEGORY b CONTINUED ON 11 EXT PAGE

• • • 44

)

t.

TBE'2hX__QF_ NUghE63_,Eg' DER _EL6N1_QEEB6 TION.

Page 31 FLUIDS 6Bij_TijEBtjQRY!!AtjlGQ 1

l AllSWEh 5.10 (1.00) b REFERENCE RTH-SRO-00400, pg. 6 192004K113 (KA's)

ANSWER b.11 (C.50) a.

False b.

True c.

True d.

True e.

False (0.5 pts each)

REFERENCE RTil-Sh0-- U O 6, pcs.

O, 10 RTH-SRO-UO'/

001000Kb13 19200 6 K10'/

192V06K10b (KA's)

ANSWER S lu (l.00)

Count rate would significantly increase [0.5) with erratic oscillaticns due to the loss of neutron moderation and capture before reaching tae detectors {0.b).

REFERENCE D/D Exam Bank #01-72 191002K117 (KA's)

AN3WER b.13 (1.60i The 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> is to assure that Xenon worth is sufficient to provide the n:cessary shutdown margin [0.7b].

After 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, Xenon decay ic inserting positive reactAvity [0.7bj.

(*****

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o 6.

TB E0Bl_9 E_ UMgL h' Ah_ EQHEB..EL AU.T_9EE BollOU2 Page 32 FLylpS263D_THEBU9DXHAbifS REFERENCE pp 1102.03, pg. 2 001010Kbu6 001000Kb38 (KA's)

ANGWER b.14 (1.bu) a.

Lowering RC temp will add reactivity [0.25]; ACP will be lowcr

[0.2b].

b.

Lower boron concentration will require Jess reactivity removal

[U.2b];

ACP will be lower [U.2b].

e.

After sixteen (16) hours, Xenon is decaying, and less Xenon will have to be overcon e [0.25]; ACP will be lower [0.25].

REFERENCE DAT-OLC -Ob7 19200UK107

( 1; A' s )

ANSWER 5.15 (1.50) 1.

RCO tempcrature decrease 2.

Doron dilution 3.

Xenon decay REFERE!1CE l

BAT-OLC-266 292002K114

( KA ' t. !

i I

("***

CATEGURY b CO!1T1NUED ON NEXT PAGE +=***)

L___Idhl>lff_2E_UU.Cl E68 EQHEB_Eb6t1T OEEBATIO11 Page 33 4

ELLJ1LL6H0_I[lEBMQQ1t{6 MIGS A11SWER b.16 (2.00) 5.

Core delta T will increase [.25] - with no flow Th will incr-ase due to convection and Tc will stay the same- [.25].

b Core thermocouple will increase [.25] - the heat is not t,eine removed i.25) c.

S/G pressur. will decrease [.25] - with no RCS flow, no heat is being rem 3ved so the steam generator will e.9 heat to ambient which will reduce C/G pressure [.2b].

d.

RCG pressure will increase L.25] - cince Th is increarinc, pressuricer level will increase duc to expansion which will cause prescurizer tc increare L.2bj.

REFEREllCE BAT-OLC-360 002000E514 93008K121 (KA's)

ANWER b 17 I2.00i He would nut necessarily be critical LU.71J.

When calculating th:

shutdown m.2rcin while.ritical, a control rod is nesumed to be ctack out of the care plus a 1%

delta K/K requirement is accounted for l'rovi d e d the operatur does nat have a stuck rod, he would actually b2 t'urther shutdown by approximately - 2.6% [1.0].

,fAlso, Xe, Sm, and ppnD will change by the time criticality is achieved again./p

[0.2b]

REFERE!1CE BAT-ULU-2bt, l' 2002E114 UO1010Kb35 (KA's) 4 Al1SWER 5 10 (1.50) 1 Ensure that acceptable power distritution limits are maintained.

I tO.b-2.

Ensure that mininum shutdown marcin i-rnai n t ai n e d.

(0.5; i

c.

Limit the potential effects of a red ejection accident.

(0.b)

(*****

CATEGORY i CO!1T1!1UEli 011 i4 EXT PAGE * * * * * ;

4 km_IllhuliX_UE_.llllCLl?alilu!!ELLLLbtJT OPERATIOll l'a g e 34 u

ELU liciuA_l!D_TilERMUDY t!AMI CS REFEREt1CE T/S 3/4.1.3 19200bK116 19200SK11b 19200SR114

..(KA's) l l

(4****

Et1D OF CATEGORY b *****)

L_EoBI_M.YREU eE G L_R9dIBA_oulL IEMB!JUEUIAIl DU Pace 30 I

At4SWER U.01 (1.60) 1.

c.

2.

Ensure that steam from OTSG is heated to at least 35 degreer F '.bO:

above saturated ::onditione or temperaturec [.25].

t REFEREt10E I'& l D-I CS 1CD Lit Pict.ur.:, pg. 18, I WR-OLC-026. 01, pcs.

8, 24 i

0 3 b u l UK !.01 03bO10KiO9

( l'. A ' s )

A11SWER 6. 0.2 (1.bo) a.

Decrease b.

Decrt402..-

C.

IncrCase (0.6 pte each)

REFERENCE i

ICS-OLC-UU4, pc. 12 041000K10b 04102VKLU7 041000A292

..(KA'c) i AllSWEN U.03 (1.00) i Gamma rey sen.iitivo [.20), in that, a ti1G gamna [.2b] would cause tute io

[

avalanche L.2b], indicating an OT3G tube leak [.25].

i t

REFERE!1CE PWR-ULC-U27, pr. 20, paragraph 6c OU0038A11U U00036A204 000037A106

.(RA's) t

=

t 1

Af1SWER 6.04 11.to i

t.

t

?

• • CATEGORY 6 Cont 153UED Ol' 11 EXT PAGL * * * * * )

i i

i

--n p ~--

n,,

., s

L __thdGl_tIDilhdG_DEM19ih._CQUT8%_6UD_ludIlulMKUIATIQM l' ace 36 REFERENCE 103 Training Information Manual, Rev. O, pg. 24 Ob9000K107

, (1: A ' c )

A!1SWEl:

6.ob (2.001 a.

True b.

False c.

True d.

Tru PEFERElk:E P& ID M00' G A ( A-12 ), SP 1104.32.10, pc. 0 0'/ 30 00 h 101 006030A301 008000K103 008000A104 008000A204

..(hA's)

AR:JWEL ti. 0 t3 (1.50) 1.

bypass powi:r/imbalnnee/ flow trip 2.

by pM. m E wcr/ pun.pc trip 3.

1;y pans pressure /te.mperature trip 1

4.

Bypocc low / prec t.u re trip 5.

Adds shutdown bypass high RCS pressure trip U.

High flux setpoints reduced to SX (0.25 pts each)

RE"ERENCE PP 1102.10.U, step b, 2,

14 EP 110b.03.08, Ltep 6.2, UP 1106.02.00, pg. 11 j

01200t,K604 (KA*s) i i

(*****

CATEGORY 6 COllT114UED ON NEXT PAGE * * * *

• i 4

I

.i.lMUI_ Eld 1EUh._DESUllh._CO!!TEL At1D ltGTRybEUlb1 LOU I'aTo 37

's AtGWER 6.U?

(1.251 a.

False b.

True e.

Falsc d

True e.

Falsc REFEl:EllCE Al! 1203.129b, r.nracroph 4.e UHOU68K2U1 000068(1006 000U57A100 UUUUS7A106 (KA's' At1GWEH 6.00 (1.b0) 1.

tiukeup Tan U.

Buric Acid Addition Tanl:c lV6" W W W/k k$fWNY f0WW C5'A

}

) t pts each) 95-)

REFEt21CE I.. 12U3.03.4, GOl'-OLC- 0 U 1.

Objective 01, pc. 2 E'e l'a U 0 80001'.001 UU6000K410 OUUO74A101 00UUb6A27b 00Utle6K300 (KA El A11SWER 6.US (1.UU) c.

IGIEhEf1CE SF 1105.03.11, parntrreph 4.1.2.

pg 30 FWR-OL'?-U'E 91, pg.

7, pg.

9, para 1 c.,

pr. 12, para l' J

00100DE103 (KA's P

(.t * * *

• CATEGORY 6 CO!1TI!!UED ON 11EX1 FAiiE * * * * * )

!L.___L1hl4.Luldlli!h._UbMl'.3B&_.COUTROL _6HILlueIBufE.MI61108 Page 38 AtJSWER 6.10 (1.60)

Backlenkace of steam u.

Hi ch te.aperature-feedwater back]eakage thru check valve that flashes to n te:arn in the AFP casing (0.5 pts each)

REFERENCE

'dP 110 6. 0 6. 2 b. para 12, p t!. 39 FWR-uLC -0 2 9. U E, pg. 18 061UDUA206 9610DOK102 061000 V.10 3 (KA's)

A11SWER 6.11 (1.U0) 111 e n Ni') rccl

.1 1

t' ct trhns f er to nianual.

REFEREliOE ICC - OLC-6 01

'J U, pg. P f, para O(e)

Ut i1000K 4 U L IKA's; A!:3WEh 6.IL (1.u0) c.

REFEEEt1CE I WR-(>LC-U3 6. U I. pg. 06, pSragraph 6 0 U 10 00 K 4 0 '/

0010 v 054.0 3 001000K401 lKA's) l AllSWEh 6.13 (1.50) a.

2 b.

e d.

e, 4

U.

J pts e rg n ;

(*****

CATEGORY 6 CONTItJ!1El> ON 11 EXT PAGE *****'

L__ELoul_EX4IKUR DEElGtk_CQUIEA._6MILit!EIBD.UEUIAILOL4 Page 39 REFEl:.N!JCE l'WR-OLC - 0 3 5. 01, pg.

9, pg. 12 U53000A107 016000K101 016000G007 016000G004

..(KA's)

A.WWER 0.14 (1.UU) 1.

D d.

C 3.

P 4.

A (0.25 ptc each:

REFEREtK'E SP 110o.03.11 0l'009L10t (KA'c>

2 AtlE'n'Eh E.10

( 2. t 10 )

1.

1ault cn main cenerator 2.

Feult cn Aux 11 t ranst on.e r 3.

Ibin denerater trip due to lockout relay 4.

OpeninE of 34501/60 (main cenerator output bresher) if either was. initially :tosed b.

30 seconds after a main turbine trip t%#4b/ f?WCh b'9_4f

, 0>1 N I 5 ' $ y D THLiv s 6 / M y (vj &

f ty S~)

> h N M f 1*

hEFERE!JcE 13.e KV dist., pc. 11, paragraph C.

l'Wh - OLC - O b 3. 01. pc. 4 06200uK4U1 (KA's)

(*+***

CATEGOhY 6 COliTlt1UE1; Oli NEXT I AGE * *

• 4 * )

k l

k__tL6EI_dY4TEUS_ red 1MBm_GREIh2ht_68u_luSTRUUERI61108 Page 40 A!1SWER C.16 (1.00) 1 Trip breaker with key in look Remove key 3.

Insert key in lock for breaker to be closed 4.

Turn key b.

Close the breaker f.20 pts / step)

(Similar wording neceptable)

REFEREt1CE 480 VAC, pg. 13 062000K407 062000K403 002000A20b (KA'-)

ANSWEh 6.17 (1.0u) 11ormal Alternate l

YAU yak YbU YBR f.25 pts each) l REFEhE11CE 120 VAC. pg. 2 l'&lD E-7 062000K410 (KA's) i e

i ee 4

d fis _ _ P h allI _EXMT E!FLDEelG U.u.J20BIh'2 L t._AtlD_.18!iTB'R]E tf161108 ruhe 41 A11SWhh 6.18 (0.00) l 1.

Asyminetric rods 2.

ECP Lost, 3.

Loss of Feed Pump 4.

Low DA Tank Level L.

High MFP dischsrce liressure (Any 4 w U.b pt.s each)

REFEREMCE ULD, pg. 14. Fic ULD,-1 0 4 b o lK4 2b 04bouoK412 (KA'c)

At1SWER C 19 (3 50) n.

MU-0, he LctJuwn Fivw Control (0,b)

L.

MU M4 Flcw Control Valve (0.E)

MU-19 RC pump cual in.iection flori (U.5)

REFERE!JUE SP 110b.06.10 AB 1203.41, pg. e GOP-OLO- 001. 00 OU400VK104 004000K117 0040VOK00b 004020K302 00401'0K303 UUUU22K302 (KA's)

ArJ3WER 6. 2 i..

(1.u0) c.

REFEREtF.'E C1' 130b.09.00, pg. lb l'WR-OLC- 0 3 6. U I, I.c. 46 001090K402

.(KA'e)

)

(**++*

EllD OF CATEGORY 0 *****)

i

^-

-w-

a Zu._LifMEldhh : 09806Lu6BHOEUh EUMd:BGE Pege 42 AUR_BANOLMLGAL.S9BIL26 ANSWER 1.01 (1.b0) 3.

Thermal shcch will occar if tubcooled liquid enters the steam Jines.

L Watal carryover into the AFF turbines can cause severe damnge to thc tt. rb i n e s.

3 ielcht oi liquid can challen,'le the piping / supports integrity.

pioisture can damage the leading edges of the main turbine 4.

. e u, r. ve bladet b.

Twc Phase c'.incharge throuch secondary valves can 1asult in seat demigu"leaknge (Any 36: 0. b p*., s each)

(Sind l ar wording accepted)

REFEREW'F AB3003 34.

paragraph 4 Of.buv0K103 059000A20:1 (KA'ti AilEWEh "W

( 1. 00 )

To minitize 1:CS inventory depletion such [.2b] that if the RCP's were tripped L. S at a later time, core uncovery could occur [.50].

REF EhE!'CE Chapter l'. A, paracraph 2.1 (Tc-ch Basis Document) 000uliDoe

!LA~e)

AN:9WER 7.03

,1.00) 3, 2.

1, 4

(ninut.2b pt for esch Swit.ch to get correct order)

REFERE!PJE TiP 1Lui.01, Secticn 4,

pc. 43 Tcchnical :5pscification Basie Doc, Pg. A-3 00u.>07G012 (t'A c) i I

(*****

CATEGUhY 7 CCNTINULD ON NEXT PAGE *****;

1 I

a s

m v

d It.__.PROGE181BES_ _t!28t'Abt_6E89EM6Lt_EMEB!!EtEY Pase 43 6tJD_HAD10LOGlCAL C0tJI82k AtiSWEb' 7.04 (1.60) 1.

Greater than/equnl to 2 $ndependent samples of tank-analyzed E.

Greater than/ equal to 2 independent calculations of release rate reriorued 3

Greater than/ equal to 2 personne) independently checking valve.

lineup or independent veriIication or discharge valving.

IE E E HEtiCE ADM SHU-UI).U1, paracrsph b.n.4 ADM SRv-Ull 01, Objective #7 U 71 U u u R10 t, 071000A40t4 0'/1000 A3u 2 071000A424 (KA'sJ AtiSWER I.Ob (1,00) b r. s ci c r v+ s s c l h :a :] c.:>line c>nsid-rations vr (voiding in the hea1).

REFEhhih'E Prac a u t i c. n s 2.Lb, rc.

110'. 10.16.

p.

0 0u0074Alo2 OUUO74K301 (KA'sy A!! EWER 7.06 (1.00)

(

Preferred Method -

Bump a RCI (. 2 !.,

1.

t' t a r t hel' per RCP procedure (.2b>

2.

Allew pump tv run unt.11 amps stabiline ( 2b)

Ghutdown the hCP

(. P!- )

! E auive1 < :.t w:'rd i n g acceptibla>

h ret.:hnliCE 1

P f' 1 1 u '. 1 0. ] t'.

pc. 4L, s t e p s.

UUUU74h3Od U0016741',201 002U20Kbi' U00074Alu6

' Kit ' o )

)[

'9 p g p,e e&V f*" '

(*r***

C.;TEG01;Y 7 ColiTINUED ON NEXT PAGE J

.l'89CE.DMBE' _ _09hdhb2 h_4dChdhk1_EME89EBEY Pace 44 E

7 6BD_BAIMOL99E6L._99EIE91 A11SWER 7.07 (2.00) 1.

MU/HP1 cooling through high point vents 2.

MU/HPI coc, ling through PORY Uteofamainfeedpump[

j Af% #f 8M 3.

4.

Use of an Auxilinry feed pump 5.

Atmosphere vent valver - S /G G.

Use of Turbine bypass valves - S/G 7/WF 6' [

(U.4 pts ot.ch) o/ m onn&A REFERE11L.-z EP ' ':02.01.04 GOP-OLO-003. ATT b.01 0000-4E311 (KA's?

A!1SWEB 7.08 ii.00) p event increstine the main stean hender pressure centrol set pt int by T c.

c 146 p sic, preventing suddca maneuvuring of t he TEV, which would affect cocidcwn rat e.

Tnve, and R(

press.

(Sinilar wc..rdine acceptab.e, REFERE!1CE I'I 12n2.10.16 step 6.2.12, GOP-OLif-002 U 10LuE41;'

(KA's)

AtidWEh 7.09 (I.00)

,25) overloadin(eAthe 1

Chl> spider assembly [ 0,1b ) exists 12 th-The patibility of Chl>M is operated in M'i when the CRD is n:.t f r.-e runnir.g (0.5).

REFEREtiCE AB 12U3.23.UU, Caution 1,

pg. 3 UDuuubA2U2 (KA's; 1

CAiEGORY 7 t'Ot1TI!1UED Oli t' EXT PAGE * * * *

• 1 t e**4

• 4

'im__E8QCEDilREU__ ;__ UQBU6Lt_ ABNORM AL _EljERGEtJOY Page 4b t

AUU_B6PLQLMiKAL_@NThot ANSWEl:

7 10 (1.00) 10u inches.

REFERENCE Cmall Ri:S Leah-Operator Action 3.2 OUU009K310 000009A206 UOOOO9A204 (KA'c)

ANSWER 7.11 (U.LU)

Falee REFElst4CE 10 CFR 50.$4X 10 CFR f O.72E P 194001411C 1940u1A110 194001A102 (KA's)

Ath.WER l '.

( 1. t.u '

En.-: r c + 1rr y Linits:

1.

W.14 3:s.s than or equal to 25 rcr J

Ext r ar.ities less than or equal to 100 rem Litcsavinel:

I hE lesL than or segunl to 75 rem

' n remi ties less than or equal to 200 rem o

(. 3 7 t. pit ecchi nEFERENCE UP 1601.01 9 pc. 6 1n4util;,2U.:

(KA':i i

i

(*4 eei CATH (P.iRY 7 CUf;7IN1tEli ON NEXT I AGE =***=>

.~

a 1m l.'huCEDuhEli..;_U2806'._6MIRBUdh _EUEh'JENC1 Pace 40 6HM_BARl0 LOGICAL _W 8182k ANSWE):

7.13 (1.25) 1.

Check at tacility 2.

Uption:

[The quench tank is designed to cordense steam rcl eLscd ty the l'URY AND has a rupture disc discharge sotpoint of 100 psis.]

in accident or mal: unction with PORY could possibly cause the rupture air.c to reach setp.> int of 100 psig [.625) and cause release of radioactive centents to containment atmosphere affectinc pecple in containment [.625).

REF ERE!1CE SI' 110 3.17. 5, pg. 1 194001h103 (KA'sJ AtJSWER 7.14 (0.bo)

N0tT kCVNfd h&

SNb REFEF.EllCE G ul"- O LC - 00 J 0 U 000'/ d301 (KA'si ANSWEh 7.16 (1.tu) 3.

Cle.dding has a minute through-the-wn11 defect int o the f ud pin.

(U.b) f b.

(During a startup) - R C.- pressure causes coolant 3eakthrough the cladding and intc the fuel pin (upon return to power) the increased f u -I temperature causes this water te flesh to steam and presuri-e t h..

fuel pin.

(V.bi j

Th: ratc limit will al2cw thc stesm pressurc inside the fut1 pin tc nee; t ack into the RCS (O.b)

EEFERENCE GUP-OLU-Uu2, pg. 22 19200tK116 (EA's)

(*****

ATEGUhY 7 CONTINUED ON NEXT l' AGE

~-

L._ Eh20FD!!MEb t10 80 6 L t_h RllO BU 6h t_E ME RG EtX X Page 47 6t!D._h6219LOGl9AL_C2tlIB06 i

AllSWER

'/.16 (1.00) 1.

Calculate delta boron batch volume of pritwry water to drive rcdc from top of band to bottom.

(.25)

'J.

Calculate delta boren volume of boric acid to drive rods f rora botton ur band to top of band.

(.36) 3.

As rods approach top, add primary water.

(.26)

As rode opprooch bottora, add boric acid.

(.25)

(Sini1ar wording acceptedi REFEREIR{o

/) /$fdWd1MT 0f sf-f +b l0W4C shy /U 'N kO f)

GOl-OLC 000, pg. 16 UO1000Klub

( F. A ' s ',

A!1EWEh 7.17 (1 bO) a.

1.

Continuout henith physics ccversce by C&HP J.

L ran rule 3.

Specisl REP (U.'b pts eachi J

b 1.

Chem and HP Superintendent HP Supervisor 3.

Chem and Radiochemistry Supervisc r 4.

HP Specialist b

00 IAny three at.2b pts each; REFERElJCL HP 1601.04.13. pes. 6 and */

j HP 1603.UU.UU, pg. 3 HP 1001.03.09, pc. 2 194UU1K103 (KA's

(*****

CATEGORY

'/ ColliIllUE!) Ot111 EXT PAGE

• • • • • 1

Zm_l:bu'RW.lihd_; llRhMaku. 6Bt10Bd&L&_EMEliGEllGY Page 48 6t!Lj_R6D.I.9LW.K6b.._G'2t!I80k t

ANSWER 7.18 (1.bO) 1.

Puoh-emergency trip battc.n L.2b] - EHC panel No. 2 [.25).

Pol 1 [ 12b] and turn [.12b] manuil trip actuator at Turbino Front Standard L.2b].

3.

Trdr the ope 2.atinc EHC pumps [.25] and place HIS switcher in tht.

loc k -c>u t position [.2bj.

(Eru.:h antwer

.b pts)

EEFERE!!CE AB 1203.U1.04, pg. 3 UUUU::9K3UC 04bObpK101 000007A107 (KA's)

Ath3WER 7.19 (1.b0)

S.

1 rip the recetc r b.

Trip th.:- RCP's c.

Carry cut EP 1000.ul (U.b pts ench)

REFERENCE AB 1203.21.03 008030K30L 0000L6K303

.(KA's)

ANSWER 7.20 (1.00; Tu prevcnt a power inbalance tr$p.

REFEbENch A b 12 0 ';. U 7 UUUO24K102 U U O U 24 K.801 (KA's) r i

r ANSWER 7.21 (1.00) d.

P

(*****

CATEGJhY 7 CONTINUED ON 11Ey.'

lE

• • • $*1

l___L80 % DUBE3

_U2806ku_6P.t!OEUAbu_EMEBGENCY l' age 49 ABL!_E6LLOkuilCal _CQNIb2L 2

REFEREtit:E I'P 110 3. 0 8. 7, pg.

6.

Step 5.2.7 UO 1910 ALO

19200 t:K102 (KA'c)

A!!SWEh 7. 'J 2 (1.tU) 1.

Start a 2nd makeup pump (0.3) 2.

Isolate letdown (MU 2B)

(0.3) 3.

Manually trip reactor U.3) 4.

Verify all control reds (except APSR'r) inserted (0.3)

After evacuation, proceed tv Auxiliary

3hutdown pone)

(0.3)

REFEhEtiCE AT: 1203.12, pc.

5.

.s t < p 3.3.1 UOcuteE310 lKA's :

l'

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E!JI) OF CATE(Klei 7

• • • • • )

L_. AutilUWIh6T1YE_t:URLWDl2BIL.J.10l!Dlll2E Paae LO AND.11t!1IAIT ONS A113WER 6.01 (1.00) c.

REFEI1Et10h Voluntary Report, KA B7-0244, July 20, 1987 015000GU11 016000G006

( KA ' c. )

AtlGWER 6.U2 (1.00)

L.

REFEREt1CE LER 87-002 0100U00006 (KA's)

AtRWER e.03 (1.001 s.

REFERE!1CE TE 3. 'I.1. 2 and LER 67-004 061000000S (KA's)

A!1SWER 0.04 (1.00) b.

REFERENCE TS p.

3/4 7-1, LER - Merch 1967 03900VG011 039000G005 (KA'c' A!1SWER 8.0L t1.00) b.

(*****

CATEGORY 8 (JO!1T1t1UED Ot1 NEXT I AGI; + a + + + )

T

9 0.

butUIUOIB6HYLEBQREMBE GQMlllML Page 61 Atik_LltilI6110Liti

. O e

REFEREt1CE T/S 3/4.8.1, LER 87-007 064000G011

.(KA's)

A11SWER 8.06 t1.u01 1.

Deficiency ic minor 2.

Deficiency does not affect operability of the equipment REFEREt10E ADM-SRO-013.02, paracraph 4 194001A102 (KA's)

AtlCWEl:

E.07 (1.001 14 dayr REFEhEtiCE AD 180b ADIF Chu-012. 01, paracroph U c.

i 194001A30i 194001A101 (KA's)

A!1SWER 8.06 (1.00)

Falcc.

REFERE!4 E ADM - Sht -00 b. 01, paracraph 1.d.

AD 180 3.00 194001hlo2 1940U1K1U4 (KA's) 1 i

I I

l

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• • • • • J

5

_AWlttMIhAIn'E_FBygEWREL_go@l.TlWE 1%ce b2 AULLLlt:1 tot 19tib REFERE!;CE a.

1.

By visually looking at the sten 4 position (0.6) 2 by physically applying ivree to the handwheel (0.5) b.

Manual valves rnust be verified opan by applying physical t ore-in t iv: closed direction (1.0)

ADM-SRO-006.01, paragraph B ADM-SRO-006, Objective 2 194UOlri102 194001K101 (KA's)

AriSWER 8.10 (U.UU) a.

1.

Notify Assistant Plant Manager-Operations (0.33) 2.

110tif y !;hC* within one hour (0.331 3.

Ensure operation is not resume.d until approved by t h e !!hi?

(0.333 b.

Reduce RC:. pressore to within limit (0.5] within 5 rd n u t. 2 lu.!

REFERE!JCE a.

AD 1039. Station operations. Ubjective Os, pc. 42 b

'1/S pg..; - 1 U12000%u6 (KA'sJ l

Al;SWER 8 11 (1.00) 1.

Declare the channel ineperable i

2.

Place the inoperable channel in a tripped condition within one baur 3

Consult T/S 3.3.1.1 f or f urther netion sta*.en.cnts 4.

Ccnto rt 1&C to reesilbrate. t h ; hi.3 sitting b.

Notity Operations Superintendent 777f (Any 3 at.33 pts each)

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CATEGORY e CONT 1t1UED ON 11EX"' l' AGE * * * *

• 1

[.L.__61111tilslIESI1Xb_M92E RM8Ee uWtiR LIl0th Pace 53 AtlD_. Lit!LI6IW!!R a

REFEMEllCE ADM-ORU-001.01 Objeetive #09 AD 183P, pc. 10 012000Gulb 012000G002 012000G005 (KA's) e ANSWER 0.lu (1.60; 1

heactor Trip U.

Turbine Trip 3.

Unit kunback 4.

Unplanned Transient 5.

Loss of offsite' Power 7

6 NRC phone used 7.

LCO - Tech /Spee exceeded l

8.

Ut.ation Emergency covered by E Plan or E Procedures 9.

Satety Grade System /Compencnt declared inoperable (Any 8 + 0.2 pts each)

REFERE!4CE Ab 1839. Stativn operations ADM-Sh0-0VI.01 - Objective OU 045000G0lb 045000G914 04b00U0006

..(KA's)

ANSWEh 6.1J (1.00) 1.

Type is (me;sures primary containment overall integrated leshace rate).

L Type B (measures leakage across pressure - containing or leakage limiting boundsry1.

]

3.

Type C (reasures containment isolatien 3eShage rates - contSinment i tul ati< n valves )

t 33 }>ts obch1 1

(*****

CATEGORY B CUNTINUED ON NEXT I* AGE

• • • • • 1

h u__.6 MU1Hid1h Ally h. LBWE ullBhM;._WUDil19 BS u l'3 8 e 64 AUM_LltjllATIOris

.. a REFEREt1CE 10 CFli 60, Appendix J, pg.

6' 0 T/S pc. 3/4 6-2 000UU9ALUC (KA's)

A!16WEh 8.14 (3.00) a.

1.

Emergency Classification 2

Of f-site Protective A.: tion Recommendation 3.

Compliance with station procedures 4

Sufety and well being of station personnel b.

Ordering a staticn general evacuation (U.2 pts each!

b 1.

Energency exposure authorizatient. in excets of 10 CFR 20 limit!.

2.

On-site administrat icn of Petassium lodide (K1).

().b pte e ncl. )

1.

Emcreeney Plant Manan t 4-vmergency Ascistant Plant Manager Shiit 5uperv'ser 4.

A.:cistant Shift Supervisor b.

Ohift Technical Advisor (0.2 pts eachi REFERE!1CE 1)- D E-Plan, pc. b-7 194 001 A11. 6 (KA's) f 1

A!13WER 8.Ib

(!.UU)

True REFEREt1UE i

kb' bP'1 blIU. p e]. !)I 134'.> 01 A l l e (KA'L) i l

(4****

CATEGORY 3 C0!1 tit 10El> Ut; tlEXT PAGE * * * * * )

m o

l tL _Akt!1tiltiTBAILYh_tBP_GED!! BEL._CMU1TlWL.

Page 56 l

S.UR_hlti1IAll0tui e

AllSWER 8-10 (1.00) l Ensures that sufficient water depth is available to remove 99% of thez l

assumed 10% iodine crap activity released f rom the rupture of an i rradiated fuel assembly.

('is-optional )

REFERE!1CE l

'P/S Bases 3/4 9.10, pc. B-3/4 9-2 t

i 033UUDA203 U33uo0G000 194U010006

. (KA's) l I

i At4SWER 8.17 (1.00) i l

a.

thiximum all owable extension not to exceed 25% of the surveillence interval.

b.

Total maximum combined interval time for any 3 consecutive intervah not tu exceed (3.25) times the specified surveillance interval.

[

P REFEREt40E T/G 4.02. pc. 3/4 U-2 194901000b (KA'c) i 1

I At1CWEh 6.le (1.00)

False.

i REFERE!1CE AI) 1839, pc. b6 ADM-SRU-001.01, Objective #12 194001A102 (KA's) i r

At1SWER 3.19 (1.00) i Truu.

k i

(****4 CATEGOEY 8 cot 4T1!4UED 014 !iEXT PAGE * * * * * )

\\

F

~

~

j

~}

K __6DulGDilli611YK_thR9EDUBES&_CQURII198Gu Page Su

.,0D_bldLI6Il0GS 6

o-s REFEREllCE AD 1630 194001A103 194UO1A100 194001A101 (KA's)

Al2SWER 8.40 (u.60)

Blue REFEREt10h ADM-GRU-0U8 AD 1833.03, para b.1.2 lu40u1K101 194001K102

.(KA'c)

ANSWEh 8.21 (1.00)

It is necessary because the handles on some breahors have sufficient f rer:

movement in them to appear spen when they are actually closed.

REFERENCE ALM-SRO-005 194001K100 (KA's)

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END OF CATEGOLY P

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