Text

Exam Rept 50-280/92-301 Administered During Wk of 921005 for Units 1 & 2.Exam Results:Six Reactor Operators (RO) & Six Senior ROs Passed Exams
	ML18151A716
Person / Time
Site:	Surry
Issue date:	11/08/1992
From:	Aiello R, Lawyer L; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
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ML18151A717	List: IR 05000280/1992301; ML18151A716;
References
	50-280-92-301, NUDOCS 9211200009
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UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

.101 MARIETTA STREET, N.W.

ATLANTA, GEORGIA 30323

ENCLOSURE 1

REQUALIFICATION .EXAMINATION REPORT - 50-280/92-301

Facility Licensee:

Virginia Electric and Power Company

Facility Name:

Surry Nuclear Power Station

Facility Docket Nos.:

50-280 and 50-281

-

Written and Operating Requalificat* n Examinations were conducted at the Surry

Nuclear Power Station located,

Gravel Neck, Virginia:

Chief Examiner:

Approved By: .

SCOPE:

SUMMARY

D[/(t{gf;

'r/t/r-z- -

Date Signed

Requalification Examinations were conducted during the week of October 5,

1992.

Written and operat_ing examinations were administered to six Reactor

Operators and six Senior Reactor Operators.

RESULTS:

Six of the six (100%) Reactor Operatori passed the examinatton.

Six of the

six_ (100%) Senior Reactor-Operators passed the examination. Three crew

simulator examinations were administered. All crews were rated as

satisfactory.

Based on these results, the Surry Requalification Program hai been determined

to be satisfactory. *

Improvements *in the Surry Reqt.ial i fi cation Program were noted in the exam

administration process (Para. 4.F and 4.G).

Weaknesses:

A weakness was identified in the area of JPM administration.

(Para. 4.D.l).

q21120A0Dgg: 6~AA8~so

PDR

V

.

REPORT DETAILS

1.

Person Contact~d.

Licensee Employees

L. Baker, Senior Instructor, Nuclear

A. Bro~n, Supervisor Nucleai Training

B. DeLamorton, Supervisor, Nuclear Training (Simulator)

R. Dickey, Senior Instructor, Nuclear

A. Friedman, Superintendent, Nuclear Training

L. Gardner, Lead Simulator Instructor

L. Girvin, Vice President, Nuclear Services

J. Grau~ Senior Nuclear Instructor

L. Huskey, Administrative Assistant

W. Krehely, Senior Instructor, Nuclear

.

H~ Mccallum, Operations Coordinator, Training

J. McCarthy, Superintendent, Operations

D. Modlin, Shift Supervisor

A. Price, Assistant Station Manager

. *R. Sanders, Assistant Vice President Nuclear Operations

J. Spence, Senior Instructor

- T. Williams~ Manager Nuclear Training

Attended exit

2.

Examiners

R. Aiello, NRC, Region II, Chief Examiner

E. Lea, NRC, Region II*

W. Steinke, INEL

3.

Other NRC Personnel Attending Exit

M. Branch, Surry SRI

T. Liu, RII

4.

Discussion

a.

Program Evaluation

Based on the examination results, the Surry Requalification

Program meets the criterion ~stablished in NUREG~l021, ES-601.

b.

Reference Material

The examination team reviewed the reference material and

determtned that the refererice material was adequate to support the

examination.

The licensee supplied a sampling plan describing the

requalification cycle and the selection process used for the

topics included in the examinations.

,

' 2

c.

Proposed Examination

A review was conducted of the faci-1 i ty' s proposed written, wa 1 k-

through and dynamic simulator examinations.

It was determined

that the valjdation times for questions on both the static

simulator and open reference examinations reflected the time that

a typical operator would require to answer the questions.

The NRC

substituted new material for about ten percent of each section of

the examination. This was done in accordance with NUREG-1021. The

remainder of the examination was approved with minor changes.

(1)

JPMs

The JPMs were written to take advantage of training

resources such as equipment. simulators and mockups.

The

JPMs were well structured and formatted. The JPM bank

covered many subject areas that were important to plant

safety.

(2)

Simulator Scenarios

Review of the simulator scenarios was simplified by the

licensee's implementation of recommended changes during the

1991 NRC Requalificatipn Examination review._, The licensee's

pas it i ve response to these . recommen*dat i ans has* enhanced the

simulator scenarios and the examination process:

Critical tasks were all important and safety significant.

(3)

Written Examination

About 40% of the examination questions required the-examinee

to calculate, analyze, or evaluate; The written examination

exceeded the guidelines as outlined in the Examiner .Handbook

and ES-602.

The questions were easy to read and comprehend.

Very few technical or administrative modifications had to be

made to th*e examination. Question 10, on the part "B"

examination, had to be modified during examination

administration due to a revision change to the curve book.

d.

Operator Performance

(1)

JPM Performance

Operator performance was adequate.

However, .while

performing JPM 18.018, Locally Rack-In and Close a 4160V AC

Breaker, four of the 12 operators failed to verify control

power fuses were removed.

Four operators racked the breaker

in after the control power fuses were reinstalled.

3

The JPMs did not test on the SRO level of procedure

identification or ability to select procedures. During the

performance of JPMs, the evaulators.presented the operators

with a copy of the procedures needed to perform the tasks

identified in the JPMs.

Neither the SROs nbr the ROs were

required to identify or select which procedure should be

used to complete tasks identified in the JPMs.

This is

considered a weakness.

(2)

Simulator

As a whole, crew performance in the simulator part of the

examination was satisfactory. However, the operators did

not r~cognize off normal trends prior to the actuation of

the annunciators.

f.

Examination Administration

The licensee's administration of the examinations was well planned

and coordinated.

The licensee put a great deal of hard work into

the examination and examination process to assure the efficiency

of the examinations.

Improvements were noticed in this year's

examination process compared to the previously administered

requalification examinations.

The following improvements were

noted:

(1)

Adequate time was designated for time-critical JPMs.

(2)

Enhanched guidance was provided in the scenario's script.

(3)

Facility simulator malfunctions were improved.

g.

Facility Evaluators

All facility evaluators were fo*und to be satisfactory. There were

improvements in the evaluation process since the last requalifi-

cation examination.

The evaluators emphasized the need for the

operators to provide verification of indications during the

performance of JPMs.

The evaluators also gave proper cues to the

operators when needed.

h.

Simulator Fidelity

The examiners did not observe any fidelity items during the

cond~ct of the simulator portion of the operating tests.

i.

Laboratories and mock-ups

The facility is continuing to take significant steps to ensure

that station maintenance and operations personnel receive the most

effective training possible. Surry Nuclear Power Station has

- developed and is continuing to improve laboratories and acquired

...

4

equipment for hands-on training. The labs are equipped with both

plant and laboratory equipment .

. j. *

General Observations

The examination team observed that many of the labels on valves

are still "dog tag" type labels. A portion of the labels

presented a burn hazard.

The lack of adequate labelling was.

identified as an operations weakness during the reqtialification

examination administered in September of 1990 (50-280/0L-90-02)

.

and September of *1991 (50-280/91-300). The utility currently has* a

prog*ram in place to correct these labelling deficiencies..

However, little progress has been made on the secondary side of *

the pl ant.

Currently there are approximately 16,300 labels installed-at Surry

Power Station. Approximately 4027 labels are located within the

Rad Waste building. All accepted labels (approx. 1000) for the.

MC~'s (mdtor contrbl center) have been installed, however there .

are approximately 900 that remain to be approved and ordered.

*

The projected completion date for the labeling project remains

March 31, 1993.

At the end of the projected completion date, in

excess of 55,000 labels will have been installed at*surry.

Labels

ordered but not installed prior to this date will be turned over

to the Operations department for installation. at an appropriate

time.

k.

Inspection

The inspectors reviewed documentation and interviewed licensee

personnel to evaluate how the l.icensee implemented requalification

training requirements specified in 10 CFR 55.59.

The licensee's

Nuclear Training Program Guide for Licensed Operator

Requalification Program (LORP) provided the administrative

controls governing the implementation of requalification

requirements.

LORP was designed to assist the licensee in meeting

the intent of several documents, including 10 CFR 55.59.

A review

of the program guide indicated that all areas identified in 10 CFR

55.59 were addressed.

Documentation also indicated that operators

attended the required training and received remedial training when

necessary.

The inspectors also reviewed a random sample of individual

records. This review was performed to evaluate the licensee's

process for tracking licensed operator control evolutions

identified in 10 CFR 55.59 (C)(3)(i).

No deficiencies were noted

'in the records reviewed.

.1

5

The inspectors reviewed the licensee's 1992 Licensed Operator

Requalification Program Sample Plan.

The licensee's s~mple plan

was compared to NUREG~l021 ES-601 Attachment 2.

The results were

satisfactory with no-identified weaknesses or deficiencies.

(Closed) IFI 50-280/92-300-02, Failure to Maintain Contamination

Bouhdaries. * On March 18, 1992, an inspector and an RO candidate

observed two workers working in and around a contaminated area.

One worker was inside the boundary dressed out in full PCs.

The

other worker was assisting in maintenance troubleshooting from.

outside the boundary by leaning in without proper PCs, which is

contrary to procedure HP-6.2.10, Revision No. 2, Radiological

Control Area.

Health Physics was notified. There was .no

subsequent spread of contamin~tion.

The employee and other

maintenance workers were counselled, by his supervisor, regarding

the proper techniques for working in a contaminated area. This

was an isolated incident.

No generic weaknesses were identified.

(Closed) IFI- 50~280/92-300-01, Technical Sp~cification

Interpretation over Maximum RWST Temperature~

During the written

examination preview, conducted in March of 1992, the examiners *

discovered a conflict between two Tec~nical Specification.(TS)

provisions.

TS 3.4.C stated, "Should the refueling water storage

t~nk temperature fail to be m~intained at or below 45 degrees F,

the containm~nt pressure and temperature shall be maintained in

accordance with TS Figure 3.8-1 to maintain the capability of the

Spray System with the higher iefueling water temperature".

TS

Figure 3.8-1 previously contained.a provision for RWST temperature

to exceed 45 degrees F proVi~ed that.additional restrictions on

containment pressure and temperature were met.

This provision was

deleted from Figure 3.8-l; however, TS 3.4 was not revised

accordingly.

The licensee proposed to submit a TS interpretation

to resolve the issue.

The examiners reviewed the documentation. submitted by the

licensee.

The documentation contained the written interpretation

resolving the* conflitt between TS 3.4 and TS Figure 3.8-1 .. The

TS interpretation was submitted to NRC Headquarters, on August 7,

1992, for approval.

The submittal of the TS interpretation to HQ

for review adequately addressed the concefns of the IFI.

l~

Security & HP Inprocessing

No problems were encountered with either security or-health

. physics processing.

5.

Exit Interview*

At the conclusion of the site visit, the examiners met with the

representatiVes of the plant staff, indicated in paragraph 1, to discuss

the results of the examinations and inspection findings~

The licensee

6

did not identify as proprietary any material provided to or reviewed by

the examiners.

The examiners further described the areas inspected.

Dissenting comments were not received from the licensee.

ENCLOSURE 2

REOUALIFICATION PROGRAM EVALUATION REPORT

Based on the examination* results, the Surry Requa 1 i fi cation Program met the

criteria established in NUREG-1021, ES-601.C.2:b (Revision 7)~ and has been

determined to be satisfactory.

. A.

Reference Material and Proposed Examination

The examination team reviewed the reference material supplied by the

licensee and found it to be adequate to support the examination.

The

licensee supplied a sampling plan that described the requalification

cycle and the proces~ that was used to select examination topics.

Facility proposed written, walk-through and dynamii simulator

examination~ derived from.this sample plan were reviewed by the NRC

examination team .. The validation timei for questions on both the static

simulator and open reference exams were determined to reflect accurately

the time which a competent operator would have needed to answer

correctly the questions.

The examination team substituted new material

for about 10 percent of each section of the .examination according to

NUREG-1021.

I.

JPMs

The JPMs were written to take advantage of training resources st.1ch

as equipment simulators and mockups.

The JPMs were well

structured and formatted. The JPM bank covered many subject areas

~that were important to plant safety.

2.

Written Exams

About 40% of the examination questions required the examinee to

calculate, analyze, or evaluate. The written examination exceeded

the guidelines as outlined in the Examiner Handbook and ES-602.

The questions were easy to read and comprehend.

Very few

technical or administrative modifications had to be made to the

examination.

Question 10 on the part "B" examination had to be

modified ~uring examination .administration due to a revi~ion

change to the curve book.

3.

Scenarios

Review of the simulator scenarios was simplified by the licensee's

implementation of recommended changes during the 1991 NRC *

Requalification Examination review.

The licensee's positive

response to these recommendations has enhanced the simulator

scenarios and the examination process.

..

. '

Enclosure 2 .

*--

2

Crit.ical tasks were adequately identified by .the facility and were

safety significant.

B.

Operator Performance

1.

JPM Performance -

Operator performance was adequate.

However, while performing JPM

. 18.018, Locally Rack-In and Close a 4160V Breaker, four of the 12

operators failed to verify control power fuses were removed.

Four

operators racked the breaker in after the control power fuses wer~

reinstalled.*

. The JPMs did ~at test on the SRO level of procedure identification

or ability t6 select proc~dures. During the performance of JPMs,

the evaulators presented the operators with a copy of the

procedures needed to perform the tasks identified in the JPMs.

Neither the SROs nor the ROs were required to identify or select

which procedure should be used to complete tasks identified in the.

JPMs.

This is considered a weakness.*

2.

Simulator

Asa whole, crew performance in the simulator part.of the

examination was satisfactory. However, the operators didnot

recognize off normal trends prior to the actuation of the

annunciators.

C.

Examination Administration

The licensee's administration of the examinations was well planned and

coordinated.

The licensee put a great deal of hard work into the

examination and examination process to assure the efficiency of the

examinations.

Improvements were noticed in this year's examination

process compared t~ the previously administered requalification.

examinations.* The following improvements were noted:

1.

Adequate time was designated for time-critical JPMs.

2.

Enhanched guidance was provided in the scenario's script.

3.

Facility simulator malfunctions were improved.

D.

Evaluation of Facility evaluators _

All facility evaluators were rated satisfactory. There were

improvements in the evaluation process since the last tequalification

examination.

The *evaluators emphasized the need for the operators to

provide verification of indications during the performance of JPMs.

The

evaluators also gave proper cues to the operators when needed.

..

i

ENCLOSURE 3

SIMULATOR FIDELITY REPORT

Facility Licensee:

Surry Nuclear Power Station

Facility Docket Nos.:

50-280 and 50-281

Operating Tests Administered During:

The Week October 5, 1992

This form is used only to report observations. These observations do not

constitute, in and of themselves, audit or inspection findings and are not,

without further verification and review, indicative of noncompliance with 10

CFR 55.45(b). These observations do not affect NRC certification or approval

of the simulation facility other than to provide information which may be used

in future evaluations.

No licensee action is required solely in response to

these observations.

During the conduct of the simulator portion of the operating test~, no

fidelity items were observed.

,*," * ..

Submitted by:

Approved by:

SURRY POWER STATION

LICENSED OPERATOR REQUALIFICATION PROGRAM

ANNUAL COMPREHENSIVE EXAMINATION

RQ-92.7-XA-lS

Revision 2

ANSWER KEY*.**

///.-

I

\\_ .

J':*

~ ..

'

. GZHERIC P'tnmMElf'rALS EXAM.INATI:ONS SECTION

EOUATXONB AND CONVERSXONS HAHDOtrl' SHEET

BOUATIOHS

Q = 1Mb

..

Q = UMT

SUR = *26. 06/ r

SUR = 2 6 * o 6 Pett P >

(~ -

p)

p = P 10SUR(t)

0

p = p

(t/T)

oe

CCP

T = (1 / p) +

p = CKeff -

1) /Keff

p = t:J.{,eft/Keft

P) />*ettP]

cycle E~ficiency =

Net Work (out)

Energy (in)

SCR = S/ ( 1 -

Keft)

CR, ( 1 -

Ketf) 1 = CRz ( 1- Keff) 2

M = 1/ ( 1

~ Ketf) = CR1/CRo

M = (1

Ketf) o

(1 - Keft) 1

SOM = (1 - Kett) /Keft

Pwr = Wfm

P)

T' = 1 / (p

10*5

1

= 1 X

seconds

Aetf

0.1 seconds *1

=

. - 2

-

i!

u(Pe -

Pi) + (~ - ~) + g(ze -

Zt) = 0

2

COHVERBIOHS

1 curie

=

3 * 7 X 10 ,o dps

1 kg = 2.21 lbm

1 hp

=

2. 54 X 103 BTU/hr

l Mw = *3.41 X 106 BTU/hr

l BTU

= 778 ft-lbf

op

= 9/5 oc + 32

oc

=

5/9(°F -

32)

- "A

TO*T~ POINTS:

.(15. 0)

QUESTION#: A2003

APPLICABILITY:

Both

1.

Which ONE of the following is correct concerning the transient in progress

and the existing conditions?

(1. 0)

'

a.

"A" Main steam line break downstream of the steam flow element ..

b.

"C" Main feedwater line break.

c.

"C" Main steam line break upstream of the steam flow element.

d.

"A" Main steam line break upstream of the steam flow element ..

ANSWER:

d.

. "A" Main steam line break upstream of the steam flow

element.

[Simulator Indications]

QUESTION#: A2012

AP.PLICABILITY:

Both

2.

Which ONE of the following gives the approximate time for. 'Source Range

High Voltage to energize, given current unit conditions?

(1. 0)

.

a.

1. 5 minutes.

b.

4.5 minµtes.

c.

13.5 minutes.

d.

17.5 minutes.

ANSWER:

c.

13.5 minutes.

[NCRODP-62]

[E-0]

[Reactor Theory Reference Manual]

' RQ_.92. 7-XA-lS Key

Page 1

Revision 2

QUESTION#: A2018

APPLICABILITY:

Both

3. *

Which ONE of the following actions will establish boric acid flow to the

suction of the charging pumps from a boric* acid storage tank, given

current unit conditions?

(1.0)

a.

Opening l-CH-228 and opening FCV-1113A.

b.

Opening FCV-1113A and B.

c.

Opening 1-CH-228 with FCV-1113A closed.

d.

Opening FCV-1113A and opening FCV-1114B.

ANSWER:

a.*

Opening l-CH-228 and opening FCV-1113A.

[FM-88B, sheet 1 & 2]

[Simulator Indications]

QUESTION#: A2025

APPLICABILITY:

Both

4.

Which ONE of the following corresponds to an allowable indicated AFW flow

to EACH of the intact SGs if the team isolates AFW flow to the faulted SG,

given current unit conditions?

(1.0)

a.

175 gpm until an intact SG level is greater than 5%.

b.

250 gpm until an intact SG level is greater than *5%.

c.

175 gpm until an intact SG level is greater than 22%.

d.

250 gpm until an intact SG level is greater than 22%.

ANSWER:

d.

250 gpm until an intact SG level is greater than 22%.

[E-0]

[Surry Setpoint Do.cument]

RQ-92.7-XA-lS Key

Page 2

Revision 2 .

i L

.*',)

'

_ .

QUESTION#: A2029

APPLICABILITY:

B_oth

5.

Which ONE of the following generated the closure signal for TV-MS-101B?

'(1. 0)

a.

Phase II isolation.

b.

Header to Line AP.

c.

Phase III isolation.

d.

Hi Steam Flow with Low Main Steam Line pressure.

ANSWER:

c.

[E-0, Step 11]

. [FM-64A & B]

[DRP-004]

QUESTION#: A2031

Phase III isolation.

APPLICABILITY:

Both

6.

Which ONE of the following explains the response of OPAT and OTAT

setpoints to this event, assuming RCS Tayg was initially 574.4°F?

(1.0)

a.

OTAT setpoint increased due *to decreasing RCS pressure;

b.

OPAT setpoint increased due to decreasing RCS pressure.

c.

OPAT setpoint inc'reased due to decreasing RCS tempera~ure.

d.

OTAT setpoint increased due to decreasing RCS temperature.

ANSWER:

d.

OTAT

setpoint

increased

due

to

decreasing

RCS

temperature.

[DRP-004]

.[Tech Spec Section 2.3]

[Simulator Indications]

.*.

RQ-92.7~XA-1S Key

Page 3

Revision 2

QUESTION#: A2038

APPLICABILITY:

Both

.;,J-*

- ~ .

7.

Which ONE of the following identifies the design feature of the MS System

which prevents backflow to a faulted SG?

(1.0)

a.

Closure of_either the affected MSTV or NRV on Hi-Hi CLS.

b.

Closure of the affected MS NRV.

c.

Closure of either the affected MSTV or NRV on Hi CLS.

d.

Closure of the unaffected MS NRVs.

ANSWER:

b.

[FM-64 Series]

[NCRODP-23]

RQ-92.7-XA-lS Key

Closure'of the affected MS NRV.

Page 4

Revision 2

l,

't

l

~J

- - THE FOLLOWING QUESTIONS ADDRESS FUTURE UNIT CONDITIONS.***

QUESTION#: A2009

APPLICABILITY:

SRO

8.

- - THE FOLLOWING QUESTION ADDRESSES FUTURE UNIT CONDITIONS.***

Assume the CC headers are split between Unit 1 and Unit 2 and 1~cc-P-lA

trips on overcurrent 2 minutes following initiation of Hi-Hi CLS.

Which ONE of the following is correct?

(1. 0)

a.

1-.CC-P-lB will automatically start if the operator immediately takes

its pistol grip switch to "STOP/RESET" at1d releases it.

b.

1-CC-P-lB will start if the operator immediately takes its pistol

grip switch to "START" and releases it.

c.-

1-CC-P-lB will not automatically start until Hi-Hi CLS is reset.

d.

1-CC-P-lB will not automatically start until the RSST LTC TD RESET

pushbutton is depressed.

ANSWER:

[NCRODP-35]

QUESTION#: A2212_

b.

1-CC-P-lB will start if the operator immediately takes

its pistol grip switch to "START" and releases it.

APPLICABILITY:

Both

9.

- - THE FOLLOWING QUESTION ADDRESSES. FUTURE UNIT CONDITIONS.***

When the RO tries to close MOV-FW-151E, its breaker wiil thermal and will

not reset. FW-P~3A has tripped on overcurrent and the trip throttle valve

for FW-P-2 has tripped on overspeed.

Which ONE of the following actions must be taken to isolate AFW to "A" SG?

(1.0)

a.

Close FW-140, 155 and 170.

b.

Close FW-170 since* only FW-P-3B is running.

c.

Close FW-141; 156 and 171.

d;

Close FW-111 since only FW-P-3B is running.

ANSWER:

c.

Close FW-141, 156 and 171.

[FM-64A & B]

[FM 68, sheet 1.& 3 of 4]

RQ-92.7-XA-lS Key

Page 5

Revision 2

~-

.,

~ .

~

- - THE FOLLOWING QUESTIONS ARE UNRELATED TO CURRENT UNIT CONDITIONS. ***

QUESTION #: .A0533

APPLICABILITY:

Both

10.

- - THE FOLLOWING QUESTION IS UNRELATED TO CURRENT UNIT CONDITIONS.***

Which ONE of the following statements is correct considering two identical

size leaks, one in a steam line and one in the RCS?

(1.0)

a.

The RCS leak inserts more positive reactivi,ty because the RCS leak

provides a greater temperature difference between heat source and

heat sink.

b.

The steam leak inserts.more positive reactivity than 'the RCS leak

due to more heat removal by the steam leak. *

c.

The RCS le.ak inserts more positive reactivity due to cold makeup

water from eves offsetting the RCS leak.

d.

The steam leak inserts more posi'tive reactivity because a RCS. leak,

would always insert negative reactivity.

ANSWER:

b.

[Steam Tables]

[WOG Background]

RQ-92.7-XA-lS Key

The steam leak inserts more positive reactivity than the

RCS leak due to more heat removal by the steam leak.

Page 6

Revision 2

QUESTION#: B9034

APPLICABILITY:

SRO

11.

- - THE FOLLOWING QUESTION IS UNRELATED TO CURRENT UNIT CONDITIONS.***

. With. Unit 1 at CSD and Unit 2. at 100%. power,. maintenance personnel

inadvertently cut a section of AFW crosstie piping downstream of .drain

v~lve 1-Ftv-298.

Which ONE of the following statements identifies the LCO (if any) for this

event?

(1.0)

li.

Unit 1 - no action required. Unit 2 - The crosstie piping from Unit

1 to Unit 2 must be returned to "operable" status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

.

b. ,

Unit 1 - no action required. Unit 2 - The cross tie piping from Unit

1 to Unit 2 must be returned to "operable" status within 14. days.

c.

Unit 1 and 2 - The crosstie piping from Unit 2 to Unit 1 must be

returned to "operable" *status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ..

d. .

Neither Unit is in a clock since AF'tv crosstie capability is not

required when a Unit is below 350°F/450 psig.

ANSWER:

a.

[TS-3.6.F]

RQ-92.7-XA-lS Key

Unit 1 -

no action required.

Unit .2 -

The crosstie

piping froin Unit 1 to Unit 2 must be returned to

"operable" status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Page 7

Revision 2

QUESTION#: B90418

APPLICABILITY:

SRO

12.

- - THE FOLLOWING QUESTION IS UNRELATED TO CURRENT UNIT *coNDITIONS. ***

Which ONE of the following indicates the effect of N-41 faiiing high on

operation of the Rod Control System, assuming the unit is at 70% reactor

power?

(1.0)

a.

No Effect.

N-41 provides no input-to the Rod Control System.

b.

Auto and manual rod withdrawal will be blocked. *

c.*

Rods step "In" due to indicated reactor power greater than turbine

power.

d.

Auto rod withdrawal is blocked.

ANSWER:

b.

Auto and manual rod withdrawal will be blocked:

[Westinghouse Logics, sheet 9]

.[DRP-004]

[AP-4.00]

QUESTION#: A91226

APPLICABILITY:

Both*

'

13.

- - THE FOLLOWING QUESTION IS UNRELATED TO CURRENT UNIT CONDITIONS.***

During a response to "Loss of All, AC Power", an EDG is shutdown if it

cannot be loaded from the MCR.

Which ONE of the following does this action prevent?

(1.0)

a.

Depleting the EDG Base Tank since power to the makeup pumps has been

lost.

b.

Overheating the EDG since. the radiator louvers have no power.

c.

Damage to the EDG batteries due to loss of battery charging

capability.

d.

Rapid restoration of RCP seal cooling to hot RCP seals should .the

EDG suddenly load.

ANSWER:

b.

Overheating the EDG since the radiator louvers have no.

power.

[ECA-0.0 (SS) Step Difference Evaluation]

RQ-92.7-XA-lS Key*

. Page 8

Revision 2

QUESTION#: B92201

APPLICABILITY:* SRO

14.

- - THE FOLLOWING QUESTION-IS UNRELATED TO, CURRENT UNIT CONDITIONS.***

Which ONE of the f~llowing is the basis for main~aining indicated level

greater than 88% in the Emergency CST?

(1.0)

a.

To maintain * the Reactor Coolant System at HOT

SHUTDOWN

for

. approximately 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

b.

To maintain the Reactor Coolant System at HOT SHUTDOWN following the

opening of a steam generator safety valve and its subsequent failure

to close.

c.

To maintain the Reactor Coolant System at HOT SHUTDOWN for 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months

and then cooldown the Reactor Coolant System to 350°F.

d.

To maintain HOT SHUTDOWN for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months following a reactor trip and a

loss of off-site power.

ANSWER:

d~

To maintain HOT SHUTDOWN for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months following a reactor *

trip and a loss of off-site power.

[Tech Spec 3.6 Basis]

RQ-92.7-XA-is Key

Page 9

Revision 2

QUESTION#: B92302

APPLICABILITY:

Both

15.

- - THE FOLLOWING QUESTION IS UNRELATED TO CURRENT UNIT CONDITIONS.***

Tl;le following conditions exist:,

Initially both Units were at 100% power with the "A" CHG pumps

operating on both Units.

The "B" and "C" CHG pumps on both Units are in Auto.

A Loss of Off-site Power occurred.

l EDG Loaded on Unit 1.

. #3 EDG loaded on Unit 2 .

2 EDG failed to start .

Which ONE of, the following corresponds to the CHG pump configuration that

will be automatically established when #land #3 EDGs have loaded on their

respective busses?

(1. 0)

a.

Unit 1

b.

Unit 1

c.

Unit 1

running.

d.

Unit 1 -

ANSWER:

a.

[DC-91-021]

[OP-8 series]

[FE's]

-

"C" CHG pump running; Unit 2 - "B" CHG pump running.

"A" CHG pump running; Unit 2 - no CHG pumps running.

"A" and "C" CHG pumps running; Unit 2 -

"B" CHG pump

"A" CHG pump running; Unit 2 - "B" CHG pump running.

Unit l -

"C" CHG pump running; Unit 2 -

"B" CHG pump

running.

[AP-10.00 and AP-10.11]

RQ-92.7-XA-lS Key

Page 10

Revision 2

..

Submitted by:

Approved by:

SURRY POWER STATION

LICENSED OPERATOR REQUALIFICATION PROGRAM

ANNUAL COMPREHENSIVE EXAMINATION

RQ-92.7-XA-lR

Revision 2

ANSWER lCEY

/O /:.-/f"L-

.GENERIC Ftm'DAMEN'l'ALS E%AMIHAT%0NS SECTION

BOUATXONS AHD CONVERSIONS HABDOUT SHEET

BOUATXONS

_Q =

Q =

Q =

SUR

p =

T =

p =

mcP.t.T

m.t.h

UMT

= 26.06/T

= 2 6 * o 6 Pett P >

(/J -

p)

P lOStJR<t>

0

P e Ct/f')

0

(1 / p) + cc:S

(Keff - 1) /Keff

ti.Keff / Keff

- P) /'>*etfP]

cycle Erficiency = Net Work (out)

Energy (in)

sCR = S/ ( 1 -

K*ff)

CR, ( 1 -

Keff) 1 = CRz ( l- Keff) 2

M = l / ( l

-

Keff) = CR1 / CRo

M = ( l

-

Keff )o

( l

-

Keff),

Pwr = Wfm

T = 1 / (p - P)

5

1

= 1 x 10

seconds

= 0.1 seconds *1

- 2

1J (Pe -

P;) + ( "e

-

~ ) + g ( Ze -

Z i) = 0

2

COHVER.SIONS

~------------------------------------

1 curie

=

3 * 7 *x 1 o 10 dps

1 kg=

2.21 lbm

l hp

=

2.54 X 103 BTU/hr

1 Mw = 3.41 X 10

6 BTU/hr

1 BTU

= 778 ft-lbf

OF

= 9/5 ac + 32

oc

=

5/9(°F -

32)

QUESTION#: A2003

/t'

'L:

.APPLICABILITY:

Both

,*)'

'***-*

TOTAL POINTS:

(12.0)

1..

Which ONE of the following is correct concerning the transient in progress

and the existing conditions?

(1.0)

a..

"A" Main steam line break downstream. of the steam flow element.

b.

"C" Main feedwater line break.

c.

"C" Main.steam line break upstream of the steam flow element.

d.

"A" Main steam line break upstream of the steam flow element.

ANSWER:

d.

"A" Main steam line break upstream of the steam - flow

element.

[Simulator Indications]

QUESTION#: A2012

APPLICABILITY:

Both

2.

Which ONE. of the following gives the approximate time for Source Range

'High Voltage to energize, given current unit indications?

(1. 0)

a.

1.5 minutes.

b.

4.5 minutes.

c.

13.5 minutes.

d.

17.5 minutes.

ANSWER:

c.

13.5 minutes.

[NCRODP-62)

[E-0)

[Reactor Theory Reference.Manual]

.RQ-92.7-XA-lR Key

Page 1

Revision 2

,')' ..

..

=*

QUESTION#: A2018

APPLICABILITY:

Both

3.

Which ONE of the following actions will establish boric acid flow to the

suction of the charging pumps from a boric .acid storage tank, * given

current unit conditions?.

'

.* (1. 0)

a.

Opening l-CH-228 and opening FCV-1113A.

b.

Opening FCV-1113A and B.

c.

Opening l-CH-228 with FCV-1113A closed.

d.

Opening FCV-1113A and opening FCV-1114B.

ANSWER:

a.

Opening l-CH-228 and open~ng FCV-1113A.

[FM-88B, sheet 1 & 2]

[Simulator Indications]

QUESTION#: A2025

APPLICABILITY:

Both

4.

Which-ONE of the following corresponds to an allowable indicated AFW flow

to EACH of the intact SG.s if the team isolates AFW flow to the faulted SG,.

given current unit conditions?

(1. 0)

a*.

175 gpm until an intact SG level is greater than 5%.

b.

250 gpm until an intact SG level is greater than 5%.

c.

175 gpm until an intact SG level is greater than 22%.

d.

250 gpm until an intact SG level is greater than 22%.

ANSWER:

- d.

250 gpm *until an_intact SG level is greater than 22%.

[E-0]

[Surry Setpoint Document]

RQ-92.7-XA-lR Key

Page 2

Revision 2

QUESTION#: A2029

l .. '

'l..

APPLICABILITY:

Both

5.

Which ONE of the following ~enerated the closure signal for TV-MS-101B?

(1.0).

a.,

Phase II isolation.

b .

Header to Line 6.P.

c,

Phase ~II isolation.

d,

Hi Steam Flow with Low Main Steam Line pressure.

ANSWER:

c.

[E-0, Step 11]

[FM-64A & B] .

[DRP-004]

QUESTION#: A2031

Phase III isolation.

APPLICABILITY:

Both

6.

Which *oNE of the following explains the *response of OPti..T and OTti..T

setpoints to this event, assuming RCS Tavg was initially 574.4°F?

(1.0)

.

a.

OTti..T setpoint increased due to decreasing RCS pressure.

b.

OPti..T setpoint increased due to decreasing RCS pressure.

c.

OPti..T setpoint increased due to decreasing RCS te~perature.

d;

OTti..T setpoint increased due to decreasing RCS temperature.

ANSWER:

d.

OTti..T

setpoint

increased

due

to *decreasing

RCS

temperature.

[DRP-004]

[Tech Spec Section 2.3]

[Simulator Indications]

RQ-92.7-XA-lR Key

Page 3

Revision 2

-* .

L ____ _

QUESTION#: A2038

APPLICABILITY:

Both

,;,c),

J

7.

Which ONE of the following identifies the design feature of the MS System

~hich prevents backflow to a faulted SG?

(1.0)

a.

Closure of either the affected MSTV or NRV on Hi-Hi CLS.

b.

Closure of the affected MS NRV.

c'.

Closure of either the affected MSTV or NRV on Hi CLS.

d.

Closure of the unaffected MS NRVs.

ANSWER:

b.

[FM-64 Series]

[NCRODP-23]

RQ-92.7-XA-lR Key

Closure of the affected MS NRV.

Page 4

Revision 2

- - THE FOLLOWING QUESTION ADDRESSES FUTURE UNIT CONDITIONS.***

"J

_,

'**

C

QUESTION#: A2212

APPLICABILITY:

Both

8.

- - THE FOLLOWING QUESTION_ADDRESSES FUTURE UNIT CONDITIONS.***

When the RO tries to close MOV-FW-151E, its breaker will thermal and will

not reset. FW-P-3A has tripped on overcurrent and the trip throttle valve

for FW-P-2 has tripped on overspeed.

Which ONE of the following actions must be taken to isolate AFW to "A" SG?

(1. 0)

a.

Close FW-140, 155 and 170.

b.

Close FW-170 since only FW-P-3B is running.

c.

Close FW-141, 156 and 171.

d.

Close FW-171 since only FW-P-3B is running.

ANSWER:

c.

Close FW-141, 156 and 171.

[FM-64A & B]

[FM 68, sheet 1 & 3 of 4]

RQ-92.7-XA-lR.Key

Page 5

Revision 2

r)*,

,,

'

- - THE FOLLOWING QUESTIONS ARE UNRELATED TO CURRENT UNIT CONDITIONS.***

..

,,.

- QUESTION#: A0533

APPLICABILITY:

Both

9.

- - THE FOLLOWING QUESTION IS UNRELATED TO CURRENT UNIT CONDI~IONS. ***

Which ONE of the following statements is correct considering two identical

size leaks, one in a steam line and one in the RCS?

(.1..0)

a.

The RCS leak inserts more positive reactivity because the RCS leak

provides a greater temperature difference between heat source and

heat sink.

-

b.

The steam leak inserts more-positive reactivity than the RCS leak

due to more heat removal by the steam leak.

c.

The RCS leak inserts more positive reactivity due to cold makeup

water from eves offsetting the RCS leak.

d.

The steam leak inserts more positive reactivity because a RCS leak

would always insert negative reactivity.

ANSWER:

b.

[Steam Tables]

[WOG Background]

The steam leak inserts more positive reactivity than the

RCS leak due to more heat removal by the steam leak.

Page 6

Revision 2

QUESTION#: Bl0016

APPLICABILITY:

RO

10.

- - THE FOLLOWING-QUESTION-IS UNRELATED TO CURRENT UNIT CONDITIONS.***

A rod control "Urgent Failure" annunciator is received during a power -

escalation with rod control __ in automatic.

One rod in bank "D" is

indicating 28 steps lower than its group step ~ounter.

Which _ ONE of the following is the proper operator response in this

situation?

(1.0)

a.

Manually move the rods in the 1N direction to determine if the rod

is stuck or misaligned.

b_.

Immediately commence inserting the control rods to shutq.own the

reactor and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

Trip the reactor.

d.

Do not move the rods until the cabinet with the failure has been

identified.

ANSWER:

[ARP G-A-6]

[AP-1.00]

[AP-1.01]

RQ-92.7-XA-lR Key

d.

s

Do not move the rods until the cabinet with the failure

has been identified.

Page 7

Revision 2

)***.

,:! .*

QUESTION#: B91553

APPLICABILITY:

RO

11.

- - THE FOLLOWING QUESTION IS UNRELATED TO CURRENT UNIT CONDITIONS.***

Which ONE of the. following would be ineffective in preve~ting reactor

trips on low steam generator levels during Unit startups?

(1.0)

a.

Anticipate shrink and swell of SG levels.

b.

Chang~ feed flow to all SGs' simultaneously.

c.

Transfer to auto feed control when the turbine reaches sync. speed:

d.

Change feed flow to all SGs in incremental steps.

ANSWER:

c.

[TIR S91-114]

[SOER 84-04]

.RQ-92. 7-XA-lR Key

Transfer to auto feed control when the turbine reaches

sync. speed.

_Page 8

Revision 2

QUESTION#: B92302.

APPLICABILITY:

Both

12.

- - THE FOLLOWING QUESTION IS UNRELATED TO CURRENT UNIT CONDITIONS.***

The following conditions exist:

Initially both Units were at 100% power with the* "A" CHG pumps

operating on bo.th Units.

The "B" and "C" CHG pumps on both Units are in Auto.

A Loss of Off-site Pqwer occurred.

l EOG Loaded on Unit 1.

3 EOG loaded on Unit 2.

2 EOG failed to start.

Which ONE of the following corresponds to the CHG pump configuration that

will be automatically established when #l and #3 EOGs have loaded on their

respective busses?

(1. 0)

a.

Unit 1 -

b.

Unit 1

c.

Unit 1

running.

d.

Unit 1 -

ANSWER:

a.

[DC-91-021]

[OP-8 series]

[FE's]

-

"C" CHG pump running; Unit 2

"B" CHG pump running.

"A" CHG pump running; Unit 2 - no CHG pumps running.

"A" and "C" CHG. pumps running; Unit 2 -

"B" CHG pump

"A" CHG pump running; Unit 2 - "B" CHG pump running.

Unit 1 -

"C" CHG pump: rurining;. Unit 2 -

"B" CHG pump

running.

[AP-10.00 and AP-10.11]

RQ-92.7-XA-lR Key

Page 9

Revision 2

,,

..

,l

Submitted by:

Approved by:

i * ..

t.~

SUR.RY POWER STATION

LICENSED OPERATOR REQUALIFICATION PROGRAM

ANNUAL C.OMPREHENSIVE EXAMINATION

RQ.:.92.7-XB-lR

Revision 1

ANSWER KEY

~

Date:

--7-+-------=""------"----. -=-------

.~tTc:=__

--+-~--!.-I-~~~:!::~*====-=====------ Date:

Supervisor

l

7

GntER:IC P'tJHDMEH'r:lLS EDK:INATJONS SECTION

BOUATXQNS AHD CONVE'RSZONS HARDOU'l' SHEET

BOUA'l'IOHS

~-----------------------------------------------------

Q = 111M

.

Q = UA.AT

SUR= 26.06/T

SUR = 26.06PeffP)

(P -

P)

p = p lOSURCU

0

p = P e<tt,.,

. 0

( (jJ

T = (1 / p) +

p = (Kett -

l) /Keff

p = ti.Keff / Keff

-

P) / ).eff P]

cycle Efficiency= Net Work (out)

Energy (.1.n)

sCR = S/ ( 1 ~ K*ff)

CR,_( 1 -

Keff>, = CRz ( 1- Keff) Z

M = 1/ ( 1 -

Keff) = CR,/CRo

M = ( 1 -

Kett lo

( l

-

Keff),

Pwr = w,m

T = 1 / {p - P)

1* = 1 x 10*5 * seconds

1

.\\eff . = o * 1 seconds

-z

-2

*

u(Pe -

P;) + {V.

- ~) + g(Ze -

z,> = 0

2

CQHYERSIONS

~-----~------------

1 curie

=

3. 7 X 1010 dps

1 kg= 2.21 lbm

l hp

=

2 .54 X 103 BTU/hr

l Mw = 3.41 X 106 BTU/hr

l BTU

= 778 ft-lbf

OF

=

9/5 °C + 32

oc

= 5/9(°F -

32)

TOTAL POINTS:

(28.0)

QUESTION#:

B90220

APPLICABILITY:

Both

1.

The following conditions exist:

The team is in E-1 following a LBLOCA with a LOOP.

No CW Pumps are operating.

"H" Emergency bus is deenergized and can not be restored.

Containment Pressure is 13 psia and decreasing slowly with spray

systems operating.

Which ONE of the following is correct concerning*operation of the Spray

Systems?

(1. 0)

a.

The "B" SW Header from RSHXs should be isolated.

b.

SW to train "A" RSHXs should be isolated;

c.

The* "A" SW Header from RSHXs should be isolated.

d.

SW to train "B" RSHX's should be isolated.

/ANSWER:.

[E-1]

RQ-92.7-XB-lR Key

b.

SW to train "A" RSHXs should be isolated.

Page 1

Revision 1

QUESTION#:

Al625

APPLICABILITY:

RO

2.

The following meteorological conditions exist:

Wind Direction Upper - 445 degrees.

Wind Direction Lower - 50 degrees.

*

Wind Direction Backup - 425 degrees.

Delta T - (-)1.0 degrees celsius.

Sigma Theta - 19 degrees.

Which ONE of the following indicates the affected sectors and stability

class?

(1.0)

a.

Kilo

b.

Mike

. c.

Kilo

d.

Mike

ANSWER:

[EPIP-2.01]

-

QUESTION#:

A2202

Lima - Mike with Stability Class A.

November - Papa with Stability Class. A.

Lima - Mike wit~ Stability Class F.

November - Papa with Stability Class F.

a.

Kilo - Lima - Mike with Stability Class A.

APPLICABILITY:

Both

3.

A Safety Injection has occurred due to a fault on the "A" SG.

Which ONE of the following is the basis for adjusting intact SG PORVs pot

settings as determined by the highest THOT?

(1. 0)

a.

Prevents a "PTS" condition from occurring in the SGs.

b.

Initiates a cooldown at less than 100°F/hr following isolation of

the faulted SG.

c.

Assists in level control of the intact SGs.

d.

Limits the RCS heatup after dryout of the faulted SG.

J ANSWER:

d.

Limits the RCS he~tup after dryout of the faulted SG.

[EDP Step difference document]

RQ-92.7-XB-lR Key

Page 2

Revision 1

1-- ~.

- '

-"-------

.

-

QUESTION#:

A91223

,r,

~

.

'--

APPLICABILITY:

Both

4.

The following conditions exist:

A sustained loss of "lC" SS bus has*occurred from 15% power.

*

It is desired to crosstie the lighting busses.

Which ONE of the following corresponds to the amperage limitation when

crosstieing lighting busses?

(1. 0)

-

a.

1100 amps for the lighting transformer.

b.

550 amps th~ough the crosstie device.

c.

1100 amps on each iighting bus.*

d.

550 amps as read on 15A7.

I

ANSWER:

a.

1100 amps for the lighting transformer.

[AP-10.12, (07-02-92)]

QUESTION#:

A91226

APPLICABILITY: -

B'oth

5:

During a response to "Loss of All Ac* Powerll, an EDG is shutdown if it

cannot be loaded from the MCR.

Which ONE of the following does this action prevent?

(1. 0)

a.

Depleting the EDG Base Tank since power to the makeup pumps has been

lost.

b.

Overheating the EDG since the radiator louvers have no power,

c.

Damage to the EDG batteries due to loss of battery charging

capability.

d.

Rapid restoration of RCP seal cooling to hot RCP seals should the

EDG suddenly load.

ANSWER:

b.

Overheating the EDG since the radiator louvers have no

power.

[ECA-0.0 (S5) Step Difference Evaluation]

RQ-92 .. 7-XB-lR Key

Page 3

Revision 1

QUESTION#:

BOOl

APPLICABILITY:

Both

. 6.

The suction MOV and check valves between the "A" UIS! pump and the

Containment sump begin to leak.

The RWST is drained to the Containment

sump such that the RWST Level decreases from 95.8% to 90%.

Which ONE of the following is the* correct calculation of the final sump

level indicated on Ll-DA-llOA if it was initially dry?

(1. 0)

a.

13.0 inches.

b.

.16. 0 inches.

c.

19~0 inches.

/*

22.0 inches.

f ANSWER:

d.

22.0 inches ....

(From the curve book, the RWST level

has gone down 22,000 gallons. Also from the curve book,

the sump should now indicate 22. 0 .inches.)

[l-DRP-003, Curve Book]

RQ-92.7-XB-lR Key

Page 4

Revision 1

. '

QUESTION#:

B235

APPLICABILITY:

Both

7.

The following conditions exist:

E-1 is being implemented in response to a Large Break LOCA.

All Power Ranges Nis are< 5%.

IR SUR is +0.1 dpm.

No RCPs are running.

Containment Pressure is 10 psia after peaking at 48 psia.

CETCs are 715°F.

PZR level is 92%.

RVLIS Full Range is 40%.

All SG levels are< 5% NR.

Main Fe.ed Pumps are tripped.

Total AFW flow is 200 gpm.

Which ONE of the following corresponds to the next required procedure

transition?

(1. 0)

a.

FR-Z.1.

b.

FR-S .1.

c.

FR-C.1.

d.

FR-H.1.

/

ANSWER:

c.

(CSF Status Trees]

[E-1]

FR-C .1.

[WOG Rules of Usage]

[FR-S.1]

[FR-C.l]

[FR-H. l]

[FR-Z.l]

RQ-92.7-XB-lR Key

Page 5

Revision 1

QUESTION#:

A0421

APPLICABILITY:

Both

8.

A dropped rod in "A" shutdown bank has resulted in a runback from 100%

power.

The following conditions exist:

I

(1. 0)

Reactor power is 90%.

Turbine power is 70%.

Steam dumps are open to control RCS temp.

Rods are in auto with "D" bank at 200 steps.

Core age is 4500 MWD/MTU.

RCS Boron concentration is 1000 ppm.

Which ONE of the following would be the approximate final position of "D"

bank if rods alone were used to reduce reactor power from 90% to 70%?

(disregard changes in Xe).

(1. 0)

a.

110 steps.

b.

130 steps.

c.

150 steps.

d.

170 steps.

ANSWER:

b.

130 steps.

[Curve Book]

[Cycle 12 BOL Data]

RQ-92.7-XB-lR Key

Page 6

Revision 1

.,-)

.. __ ,.

QUESTION#:

B9046

APPLICABILITY:

Both

9.

Assume both Units are initially at 100% power with no systems inoperable.

~ huge tarpaulin falls into the intake canal against Unit 2A high level

trash grate, blocking flow through 2A waterbox.

Which ONE of the following gives the correct LCO for these conditions?

(1. 0)

a.

Both Units have 7 days to return that flow path to service.

b.

Both Units are in a 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months clock to HSD and then a 30 hour3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months clock to

CSD.

c.

Affected channel of intake canal low level protection must be placed

in trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

d.

Affected channel of intake canal low level protection must; be placed

in trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ANSWER:

d.

[TS-3.14)

[LER 89-029)

[TS-3.7, Tbl. 2)

RQ-92.7-XB-lR Key

Affected channel of intake canal low level protection

must be placed in trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Page 7

Revision 1

'J*;:

~~-; . .

QUESTION#:

B9076

APPLICABILITY:

Both

10.

The. team is on step 12 of ES-1.2 following a SBLOCA.

The "C" RCP is

operating and RCS subcooling is 35°F. RCS subceoling drops to 24°F during

the depressurization.

Which ONE of the following is required?

(1.0)

a.

Continue depressurizing . to recover * PZR level.

subcooli~g is allowed during this step.

Loss of RCS

b.

Stop the "C" RCP .. Reduce depressurization rate and increase cooldown

rate.

c.

Stop the depressurization and cooldown to recover. RCS subcooling .

. d.

Stop the "C" RCP and reinitiate SI.

Loss of RCS subcooling is NOT

allowed.

. ANSWER:

a.

Continue depressurizing to recover PZR level.* Loss of

RCS subcooling is allowed during this step.

[ES-1.2, Post LOCA Cooldown and Depressurization]

[WOG E-1 series background]

[RQ-89.6-SM-l]

QUESTION#:

B90816

APPLICABILITY:

Both

11.

A 'small fire occurs in the MCR and is quickly brought under control. The

Units are both stable, the MCR is habitable, and fire damage is limited to

the PAM Panel on Unit 1.

Which ONE of ~he following should be the plant controlling procedure?

(1. 0)

a.

FCA-1.00, Safe Shutdown Area Fire.

b.

FCA-17.00, Limiting Fire Cooldown.

c.

AP-48.00, Fire Protection - Operations Respon~e.

d.

AP-20.00, MCR Inaccessibility.

ANSWER:

[AP-48.00]

[FCA-1. 00]

. c.

AP-48.00, Fire Protection - Operations Response.

RQ-92.7-XB-lR Key

Page 8

Revision 1

.)-,

,.

QUESTION#:

B9088

APPLICABILiTY:

Both

12;

Which ONE of the following corresponds to the two main factors affecting

the severity of a Loss of All AC power?

(1.0)

a.

Duration* of the power outage and the response of, the RCP *seals to

the total loss of seal cooli~g.

b.

Duration of the power outage and the draw down of-the intake canal

due to SW usage in the station.

c.

Draw down of the intake canal due to SW usage in the station and the

response of the RCP seals to the loss of seal cooling.

d.

Response of the RCP seals to the loss of seal cooling and the

availability of AFW for maintaining the affected Unit at HSD.

ANSWER:

a.

Duration of the power outage and the response of the RCP

seals to the total loss of seal cooling.

[ECA-0.00)

[WOG Background]

QUESTION#:

B91210

APPLICABILITY:. Both

13.

The foilowing conditions* exist:

A sustained loss of Unit l's Semi-Vital Bus (SVB) has occurred.

The Electrical Dept. has determined that breaker 1Jl-17D-l has

failed and that no faults exist on the SVB.

Unit 1 is at 90% power *and stable.

Which ONE of t};le following courses of action is appropriate?

(1. 0)

a.

Verify both SVB supply breakers. open, place the manual *transfer

switch in the lHl-1 position, and clo_se breaker 1Hl-12A-1.

'b.

Reduce Turbine load to less than 70% then restore power to the SVB

from the alternate supply.

c.

Crosstie Unit 1 and Unit 2 SVBs by closing the cross tie breakers in

eac? of the Unit's SVB p~nels.

d.

Defeat the IRPI Rod Bottom Bistables then restore powe:r to the SVB

from the alternate supply.

ANSWER:*

d.

Defeat the !RPI Rod Bottom bistables then restore power

to the SVB from the alternate supply.

[AP~l0.05, (12/12/91))

RQ-92.7-XB-lR Key

Page 9

Revision 1

QUESTION#:

B91228

APPLICABILITY:

Both

14.

The following conditions exist:

Unit 1 experienced a "Loss of All AG" seven minutes ago.

l EDG started but could not.be loaded so the team placed it in the

cooldown cycle five minutes ago. '

Which ONE of the following courses of action should be taken when directed

by ECA-0.0 to "Initiate the AP-17 series procedures to restore the EDGs"?

(1.0)

a.

Immediately reset the EDG differential lockout relay if tripped,

then press the start pushbutton .

. b.

Immediately reset the Aux Trip Relay if tripped, then press the

start pushbutton:

c.

Strip loads from the lH bus as n*ecessary, then allow the EDG to

complete its cooldown cycle before attempting to-restore it.

d.

Press the start pushbutton and establish a gravity feed lineup from

the EDG. Day Tank to the EDG Base Tank.

ANSWER:

c.

Strip loads from the lH bus as.necessary, then allow the

EDG to complete its cooldown cycle before attempting to

restore it.

[AP-17.0l(C2)(03/28/91)]

[AP-17.03(C2)(03/28/91)]

[ECA-0.0(SB)(Rev.4-03/28/91)]

RQ-92.7-XB-lR Key

.Page 10

Revision 1

QUESTION#:

B91307

APPLICABILITY:

Both

-15.

. Currently, Unit 1 is at 100% with indications of a SG tube leak in the "A"

SG.

The first five steps of AP-16.00 have. been completed with the

following unit conditions:

CHG flow= 140 gpm.

Seal Injection flow= 8 gpm to each RCP.

PZR .Pressure= 2100 psig decreasing trend.

Tave= 574°F.

PZR Level= 54% stable trend.*

*

"A" SG Level = 44% stable trend.

Which _ONE of the following is the correct action to be taken next?

(1.0)

a.

Initiate AP-24.01, targe Steam Generator Tube Leak.

b.

Initiate Safety Injection and GO TO E-0.

c.

Trip the Reactor, manually initiate SI, and GO TO E-0.

d.

Stabilize unit conditions and initiate a unit shutdown in accordance

with.the appropriate plant operating procedures.

ANSWER:

c.

Trip the Reactor, manually initiate SI, and GO TO E-0. _

[AP-16.00, Excessive RCS Leakage]

RQ-92.7-XB-lR Key

Page 11

Revision 1

QUESTION#:

B91502

APPLICABILITY:

Both

16;

A reactor startup is in progress.

The team. is withdrawing the contro_l

banks and rod withdrawal has been stopped at t~ first doubling of source

range counts.

The second doubling of source range counts is projected to

be at 80 steps on bank "C".

Which ONE of the following actions is correct?

(1. 0)

a.

Maintain source range counts constant and borate the rods out until

the second doubling is projected greater than 23 steps on bank "D" ..

b.

Continue rod withdrawal to 98 steps on bank "C".

c.

Maintain source range counts constant and borate the rods out until

the second doubling is projected greater than 98 steps on bank "C".

d.

Trip the reactor and emergency borate.

ANSWER:

[OP-58.2.2]

[SOER-88-2]

b.

Continue rod withdrawal to 98 steps on bank "C".

QUESTION#:

B91505

APPLICABILITY:

Both

17.

Which

power

(1. 0)

a.

b.

c.

d.

ONE of the following reflects the correct startup rate if reactor

increases from 1 x 10-B amps to 5 x 10-7 amps in 2 minutes?

0. 95 dpm.

0. 90 dpm.

0.85 dpm.

0. 75 dpm.

ANSWER:

c.

0.85 dpui.

[Reactor theory notes]

RQ-92.7-XB-lR Key

Page 12

Revision 1

QUESTION#:

B91510

APPLICABILITY:

Both

18.

Which ONE of the following reflects Unit.l's Xenon concentration 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months

following a power reduction from 100% to 50%?

. (LO)

a.

Increasing.

)

b.

Decreasing.

c.

At equilibrium.

d.

Oscillating.

ANSWER:

b.

Decreasing.

[Reactor Theory notes]

QUESTION#:

B91552

APPLICABILITY: . Both

19.

On June 6, 1991, Surry Unit 1 exceeded 100% reactor power due to a' failure

in the main turbine governor control.circuitry.

Which ONE of the* following act.ions is required to prevent this from

reoccurring when the unit is at 100% reactor power?

(1.0)

a.

Operate the turbine in "Turbine Manual".

b.

Set the turbine Valve Limiter at about 100%.

c.

Operate the turbine in* "Imp Out".

d.

Set the turbine Valve Limiter at about 93%.

ANSWER:

d.

Set the turbine Valve Limiter at about 93%.

l-GOP-1.6 (Rev. 0, 08/06/91)]

[CTS-1389 (Limiter Operation)]

RQ-92.7-XB-lR Key

Page 13

Revision 1

QUESTION#:

B92205

APPLICABILITY:

Both

20.

The team. has just entered E-3 while responding to a SGTR when the RO

reports RCS subcooling is 28°F and PZR level is 10%,

and both are

decreasing.

Which ONE .of the following actions* is required?

(1.0)

a.

Manually operate SI -pumps as necessary and go to ECA-3.1 because

both of the E-3 CAP SI Reinitiation Criteria are met.

b.

Raise RCS pressure and dump steam from intact SGs to increase RCS

subcooling.

c.

Transition to FR-I.2 based on PZR level less than 15%.

d.

Continue with step 1 of _E-3 bec~use the SI Reinitiation Criteria

does not apply at this particular point in E-3.

ANSWER:

d.

[E-3]

[WOG Background]

[RK]

RQ-92.7-XB-lR Key

Continue with step 1 of E-3 because the SI Reinitiation

Criteria does not apply at this particular point in E-3.

Page 14

Revision 1

) .

..

QUESTION#:

B92206

APPLICABILITY:

Both

21.

Ten minutes

ago Unit 1 experienced an ATW'S

which caused an RCS

overpressure condition initiating a LBLOCA.

The team has arrived at Step

13 of FR-S.l with the following plant conditions:

RCS pressure= 8 psig.

CETCs = 240°F.

RCS subcooling = 0°F.

RVLIS full range= 49%.

SG levels= 17% NR.

CTMT pressure= 23 psia.

RCS cold leg Temp= 295°F.

AFW flow to EACH SG = 175 gpm ..

Which ONE of the following is the most appropriate procedure transition?

(1. 0)

a.

FR-Z.1, Step 1.

b.

FR-P.2, Step 1.

c.

FR-H.1, Step 1.

d.

E-0, Step 2.

ANSWER:

a.

FR-Z .1, Step 1.

[EOP Status Trees]

RQ-92.7-XB-lR Key

Page 15

Revision 1

~)

QUESTION#:

B92210

APPLICABILITY:

Both

22.

The following conditions exist:

Both Units were at 100% power when a dual unit trip occurred.

*

.The "LOAD SHED SYS" switch is in the enable position with the white.

light illuminated.

The "BUS D LOAD SHED" red light is illuminated.

Station Service busses 2B and 2C failed to transfer to RSS.

All three Unit 1 condensate pumps are operating and the Unit 1 "B

11 *

MFW pump is in operation.

Which ONE of the following actions must be taken on Unit l?

(1. 0)

a.

Stop all condensate pumps and the "B" MFW pump.

b.

Stop the "B" MFW pump.

c.

Stop the "A" condensate pump.

d.

Stop any condensate pump and/or the "B" MFW pump as necessary to

maintain HSD conditions.

. *ANSWER:

[AP-10.10]

RQ-:92.7-XB-lR Key

c.

Stop the"A". condensate pump .

Page 16

Revision 1

,,ll t}

QUESTION#:

B92212

APPLICABILITY:

Both

23.

The following conditions exist:

Reactor trip and SI in service due to SBLOCA.

RCS pressure is 900 psig.

CTMT pressure is 20 psia.

Which ONE of the following sets of conditions would require tripping the

RCPs?

(1. 0)

a.

70°F RCS subcooling by CETCs and PZR level is 11% and decreasing.

b.

25°F RCS subcooling by CETCs and PZR level is 11% and increasing.

c.

70°F RCS subcooling by CETCs and HHSI flow indicated to the RCS cold

legs.

d.

25°F RCS subcooling by c*ETCs and HHSI flow indicated to the RCS cold

legs.

ANSWER:

d.

25°F RCS subcooling by CETCs and HHSI flow indicated to

the RCS cold legs.

[E-0 Continuous Action]

R.Q-92.7-XB-lR Key

Page 17

Revision 1

..

QUESTION#:

B92220

APPLICABILITY:

Both

24.

The following plant conditions exist:

Unit 2 was shutdown on 11-23-91 at 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months .

A cooldown to COLD SHUTDOWN was completed.

*

At 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months on 11-27-91 a total loss of RHR cooling occurred.

The following pertinent plant conditions existed prior to the loss of RHR

coo;Ling:

RCS Tavg - 140°F ..

PZR temp - 150°F.

RCS level - mid-loop.

RCS press - atmospheric.

which ONE of the following represents the .approximate time it will take

the RCS to reach saturation?

(1. 0)

a.

7.5 minutes.

b.

10.0 minutes.

c.

85 minutes.*

d.

101 minutes.

ANSWER:

b.

10.0 minutes.

[AP-27.00, Attachment 4]

[SOER 88-3] *

RQ-92.7-XB-lR Key

Page 1a*

. Revision 1

I

QUESTION#:

B92505

APPLICABILITY:

Both

25.

A reactor trip has occurred because of spurious closure of all MSTVs. SI

has not been actuated. The RO is performing the immediate actions of E-0._

The foll*owing conditions exist:

PZR:Pressure is 1950 psig and_slowly decreasing.

Tavg is 551°F and slowly decreasing.

cTMT pressure is lOpsia.

All Steam Flows indicate approximately O. 3 X 106 and are decreasing.

All SG levels at 10% NR and rising.

SG pressures A-1040 psig, B-1035 psig, C-1040I>sig.

MS Header-pressure is 910 psig.

Which dNE of the following is correct concerning SI?

(1.0)

a.

Is required because RCS pressure is decreasing.

b.

Is NOT required by the above indications.

c.

. Is required because of abnormal steam flows and pressures.

d.

Is NOT required and should be blocked.-

ANSWER:

b._

Is NOT required by the above indications.

[E-0, immediate actions]

QUESTION#:

B92507

APPLICABILITY:

Both

26.

Assume simultaneous conditions exist requ1n.ng implementation of each of

the procedures within each of the foliowing four groups (consider each

group separately).

Which ONE of the following groups is arranged in the -correct * order of

priority?

(1.0)

a.

ES-1.3, FR-Z.l, E-1.

b.

ECA-0.l, FR-H:l, FR-C.l.

c.

ES-1.2, ES-1.3, FR-C.2.

d.

E-1, E-3, E-2.

ANSWER:

a.

ES-1.3, FR-Z.l, E-1

[WOG Users Guide]

[ ES .:1, 3]

RQ-92.7-XB-lR Key

Page 19

Revision 1

j

,~- .-

/":*'

,'

QUESTION#:

B92602

APPLICABILITY:

Both

27.

A unit trip has occurred caused by loss of MFW. The team is in FR-H. l

because of inadequate AFW flow.

Both MFW pumps have overcurrent trips.

Efforts to restore adequate AFW flow have failed due to apparent line

blockage.

Crosstie flow from Unit_ 2 is unavailable.

All SGs are at

approximately 25% wide range level and decreasing.

Which ONE of the following is preferred to restore heat sink?

(1. 0)

a.

Establish RCS bleed and feed.

b.

. Depressurize a SG and feed with a condensate pump.

c.

Feed the SGs from the Fire Water system.

d.

Feed the SGs from the AFW booster pumps.

ANSWER:

b.

Depressurize a SG and feed with a condensate pump.

[FR-H.l step 8)

QUESTION#:

B92603

APPLICABILITY:

Both

28.

Which ONE of the following must SG pressure be reduced to in order to

maintain a 100°F RCS subcooling margin when the RCS is being depressurized

to 785 psig?

(LO)

a.

265 psig.

b.

285 psig ..

c.

315 psig.

d.

335 psig.

ANSWER:

b.

285 psig

[ Steam tables]

RQ-92.7-XB-lR Key

Page 20

Revision 1

. ' ...

i * .. ,.

..

Submitted by:

Approved by:

ti

~

.

SURRY POWER STATION

' ": ;-.,

j"

LICENSED OPERATOR REQUALIFICATION PROGRAM

ANNUAL COMPREHENSIVE EXAMINATION

RQ-92.7-XB-lS

Revision 2*

. ANSWER KEY

--.-?..,,dvi("""**

---""--==-*-'"""""-"""""'*='.--""o,.----- Date:

.??~' .*

--~~~--L"::/....~:1'...~C.:.~~-~L~L::::::::=::::. ___ Date:

.Supervisor

GB!IERXC PtJ'NDAKEN'rALS EXAMXHATXONS SECTION

BOUATXO!fS AHP CONVERSJONS JIINPOO'l' SHEET

BOUA'l'IOHS

~------------

..

Q = mcP~T

Q = mAh

Q = U~T

SUR= 26.06/T

SUR

p =

T =

p =

= 26. 06 PeffP)

(/j -

p)

P 10SURCU

0

P e ct,,.,

0

((}

(1 / p) +

(Keff -

1) /Keff

ti.Ke ff/ Keff

-

p) />..eff/J]

cycle Efficiency= Net Work (outl

Energy _( 1.n)

sCR = S/ (1 -

Keff) .

CR, ( 1

-

Keff) 1 = CRz ( 1- Keff) 2

M = 1/ ( l -

Keff) = CR1/C~

M = ( l

-

Keff) o

( l

-

Keff) 1

SOM = ( 1 -

Kettl /Keff

Pw:r = w,m

T = 1 / (p - P)

1* = 1 x 10*5 seconds

)..eff

1

= 0.1 seconds

- 2

- Z

u(Pe -

P 1) + (V.

- ~) + g(Ze -

z1) = 0

2

CQHYDSJONS

~-----------------------------------------------------

1 curie

=

3. 7 X .10 ,o dps

l kg= 2.21 lbm

l hp

=

2.54 X 103 BTU/hr

1 Mw = 3.41,X 106 BTU/hr

l BTU

= 778 ft-lbf

OF

=

9/5 oc + 32

oc

= 5/9(°F -

32)

TOTAL POINTS:

(34.0)

QUESTION#:

B90220

APPLICABILITY:

Both

1.

The following conditions exist:

The team is in E-1 following a LBLOCA with a LOOP.

No CW Pumps are operating.

"H" Emergency bus is deenergized and can not be restored.*

Containment Pressure is 13 psia and decreasing slowly with spray

systems operating.

Which ONE of the following is correct concerning operation of the Spray

Systems?

(1. 0)

a.

The "B" SW Header from RSHXs should be isolated.

b.

SW to train "A" RSHXs should be isolated.

c.

The "A" SW Header from RSHXs should be isolated.

d.

SW to train "B" RSHXs should be isolated.

ANSWER:

b.

SW to train "A" RSHXs should be isolated.

[E-1]

RQ-92.7-XB-lS Key

Page 1

Revision 2

QUESTION#:

B91210

APPLICABILITY:

Both

2.

The following conditions exist:

A sustained loss of Unit l's Semi-Vital Bus (SVB) has occurred.

The Electrical Dept. has. determined that breaker 1Jl-17D-l has

failed and that no faults exist on the SVB.

Unit 1 is at 90% power and stable.

Which ONE of the following courses of action is appropriate?

(1. 0)

a.

Verify both SVB supply breakers open, place the manual transfer

switch in the lHl-i position, and close breaker 1Hl-12A-l.

b.

Reduce Turbine load to less than 70% then restore power to the SVB

from the alternate supply.

c.

Crosstie Unit 1 and Unit 2 SVBs by closing the crosstie breakers in.

each of the Unit's SVB panels.

d.

Defeat the IRPI Rod Bottom Bistables then restore power to the SVB

from the alternate supply.

ANSWER:

d.

Defeat the IRPI Rod Bottom Bistables then restore power

to the SVB from the alternate supply.

[AP-10.05 (03/28/91)]

RQ-92.7-XB-lS Kei

Page 2

Revision 2

QUESTION#:

A2202

APPLICABILITY:

Both

3.

A Safety Injection has occurred due to a fault on the "All SG~

Which ONE of the-following is the basis for adjusting intact SG PORVs pot

settings as determined by the highest THOT?

(1. 0)

.

a.

Prevents a "PTS" condition from occurring in the SGs.

b.

Init{ates a cooldown at less than 100°F/hr following isolation of

the faulted SG.

c.

Assists in level control of the intact SGs.

d.

Limits the RCS heatup after dryout of the faulted SG.

ANSWER:

d.

Limits the RCS hea~up after dryout of the faulted SG.

[EDP Step difference document]

QUESTION#:

A91223

APPLICABILITY:

Both

4.

The following conditions exist:

A sustained loss of "lC" SS bus has occurred from 15% power.

It is desired to crosstie the lighting busses.

Which ONE of the following corresponds to the amperage limitation when

crosstieing lighting busses?

(1. 0)

a.

1100 amps for the lighting transformer.

b.

550 amps through the crosstie device.

c.

1100. amps on each lighting bus.

d.

550 amps as read on 15A7.

ANSWER:

1100 amps for the lighting transformer.

[AP-10.12, (07/02/92)]

RQ;-92.7-XB-lS Key

Page 3

Revision 2

-*.

..

QUESTION#:

B90457

APPLICABILITY:

SRO

5.

'Which ONE of the following indicates the maximum allowable reactor power

AND maximum allowable setpoint for the PR High Flux Trip, assuming a

Radial Tilt of 1.3% exists?

(1.0)

a.

100% Power with a setpoint of 107%.

b.

98.7% Power with a setpoint of 105.7%.

c.

97.4% Power. with a setpoint of 104.4%.

d.

87% Power with a setpoint of 94%.

ANSWER:

a.

100% Power with a ~etpoint of 107%.

[Tech Spec 3.12.B.6.c]

QUESTION#:

BOOl

APPLICABILITY:

Both

6.

The* suction MOV and check valves between the "A. lliSI pump and the

Containment sump begin to leak.

The RWST is drained to the Containment

sump such that the RWST Level decreases from 95.8% to*90%.

Which ONE of the following is the correct calculation of the final sump

level indicated on LI-DA-llOA if it was initially_dry?

(1. 0)

a.

13.0 inches.

b.

16.0 inches.

c.

19.0 inches.

d.

22.0 inches.

ANSWER:

d.

22.0 inches ....

(From the curve book, the RWST level

has gone down 22,000 gallons. Also from the curve. book, *

the sump should now indicate 22.0 inches.)

[l-DPR-003, Curve Book]

RQ-92.7-XB-lS Key

Page 4

Revision 2

.

.....

. \\

')"'

/',.: .

-;.,. .

QUESTION#:

Bl0039

APPLICABILITY:

SRO

7. *

A 21 year old man has volunteered to receive emergency radiation exposure

to take corrective actions to prevent the release of radioactive mat.erials*

to the environment .

Which ONE of the following whole body exposures should the man be limj.ted

to?

(1.0)

a.

125 Rem.

b.

25 Rem.

c.

15 Rem.

d.

75 Rem.

ANSWER:

b.

25 Rem'.

[EPIP-5.06]

[Station Emergency Plan, page 3.14 Obj. E]

QUESTION#:

Bl69

APPLICABILITY:

SRO

8.

Unit 1 is at Refueling Shutdown and Unit 2 is at 100% power.

The service

building operator reports that the breaker for one of the * fuel oil

transfer pumps for #3 EDG has tripped and cannot be reset.

Which "ONE of the following corresponds to the Limiting Conditions for

Operation that exist?

(LO)

a.

3 EDG will remain operable since the redundant Fuel Oil Transfer

pump is operable." *

b.

With Unit 1 in Refueling Shutdown, #3 EDG is not required to have

both Fuel Oil Transfer pumps operable.

c.

3 EDG must be declared inoperable . when either of its Fuel Oil

Transfer pumps is out of service.

d.

3 EDG must be declared inoperable if the Fuel Oil transfer pump is

. not returned to service within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ANSWER:

d.

3 EDG must be declared, inoperable if the Fuel Oil

transfer pump is not returned to . service within 24

hours.

[Tech Spec 3.10, 3.16, and 3.0.2]

RQ-92.7~XB~lS Key

Page 5

Revision 2

QUESTION#:

B235

APPLICABILITY:

Both

9.

The following conditions exist:

E-1 is being implemented in response to a Large Break LOCA.

All Power Ranges Nis are< 5%.

IR SUR is +0.1 dpm.

No RCPs are running.

Containment Pressure is 10 psia after peaking at 48 psia.

CETCs are 715°F.

PZR level is 92%.

RVLIS Full Range is 40%.

All SG levels are< 5% NR.

Main Feed Pumps are tripped.

Total AFW flow is 200 gpm.

Which ONE of the following corresponds to the next required p_rocedure

transition?

(1. 0)

-a.

FR-Z .1.

b.

FR-S .1.

c.

FR-C .1.

d.

FR-H. l.

ANSWER:

c.

[CSF Status Trees]

[E-1]

FR-C .1.

[WOG Rules of Usage]

[FR-S.1]

[FR-C.l]

[FR-H.1]

[FR-Z.1]

RQ-92.7-XB-lS Key

Page 6

Revision 2

()

,f,)

~- .

QUESTION#:

A0421

APPLICABILITY:

Both

10.

A dropped rod in "A" shutdown bank has* resulted in a runback from 100%

power.

The following conditions exist:

Reactor power _is 90%.

*

Turbine power is 70%.

Steam dumps are open to control RCS temp.

Rods are in auto with "Q" bank at 200 steps.

Core age is 4500 MWD/MTU.

_RCS Boron concentration is. 1000 ppm.

Which ONE of the following would be the approximate final position of "D"

bank if rods along were used to reduce reactor power from 90% to 70%?

(disregard changes in Xe).

(1.0)

a.

110 steps.

b.

130 steps.*

c.

150 steps.

d.

170 steps.

ANSWER: ~

. [ Curve Book]

[Cycle 12 BOL Data]

RQ-92.7-XB-lS Key

Page 7

Revision 2

.

QUESTION#:

B9046

APPLICABILITY:

Both

11.

Assume both Units are initially at 100% power with no systems inoperable.

.. A huge tarpaulin falls into the intake, canal against Unit 2A high level

trash grate, blocking flow through 2A waterbox.

Which ONE of the following gives the correct LCO for these conditions?

(1. O)'

a.

Both Units have 7 days to return that flow path to service.

b.

Both Units are in a 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months clock to HSD and then a 30 hour3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months clock to

CSD.

c.

Affected channel of intake canal low level protection must be placed

in trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

d.

Affected channel of intake canal low l_evel protection must be placed

in trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ANSWER:

d.

[TS-3'.14]

[LER 89-029] .

[ TS - 3 . 7 , Tb 1. 2]

RQ-92.7-XB-lS Key

Affected channel of intake canal. low level protection

must be placed in trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Page 8

Revision 2

..

,;**.)

. ~-

'

QUESTION#:

B9076

APPLICABILITY:

Both

12.

The team is on step 12 of* ES-1.2 following a SBLOCA.

The "C" RCP is

qperating and RCS subcooling is 35°F. RCS subcooling drops to 24°F during

the depressurization.

Which ONE of the following is required?

(1. 0)

a.

Continue depressurizing to recover PZR level.

subcooling is allowed during this step.

Loss of RCS

b.

Stop the "C" RCP. Reduce depressurization rate and increase cooldown

rate.

c.

Stop the depressurization and cooldown to recover RCS subcooling.

d.

Stop .the "C" RCP and reinitiate *SI.

Loss of RCS subcooling is NOT

allowed.

ANSWER:

a.

Continue depressurizing to recover PZR level. Loss of*

RCS subcooling is allowed during this step.

[ES-1.2, Post LOCA Cooldown and Depressurization]

[WOG E-1 s*eries background]

[RQ-89.6-SM-l]

QUESTION#:

B90816

APPLICABILITY:

Both

13.

A small fire occurs in the MCR and is quickly brought under control. The

Units are both stable, the MCR is habitable, and fire damage is limited to

the PAM Panel on Unit 1.

Which ONE of the following should be the plant controlling procedure?

(1.0)

a.

FCA-1.00, Safe Shutdown Area Fire.

b.

FCA-17.00, Limiting Fire Cooldown.

c.

AP-48.00, Fire Protection - Operations Response.

d.

AP-20.00, MCR Inaccessibility.

ANSWER:

[AP-48.00]

[FCA-1.00]

RQ-92.7-XB-lS Key

c.

AP-48.00, Fire Protection

Page 9

Operations Response.

Revision 2

-._).

,.

'

'**

QUESTION#:

B9088

APPLICABILITY:

Both

14.

Which ONE of the following corresponds to the two main factors affecting

the severity of a*Loss of All AC power?

(1. 0)

a.

Duration of the power outage and the response of the RCP seals to

the total loss of seal cooling.

b.

Duration of the power outage and the draw down of the intake_ canal

due to SW usage in the station.

c.

Draw down of the intake canal due to SW usage in the station and the

response of the RCP seals to the loss of seal cooling.

d.

Response of the RCP seals to the loss. of seal cooling and the.

availability of AFW for maintaining the aff~cted Unit at HSD.

ANSWER:

a.

[ECA-0.00]

[WO~ Background]

QUESTION#:

B9116

Duration of the power outage _and the response of the RCP

seals to the.total loss of seal cooling.

APPLICABILITY:

SRO

15.

Which ONE of the fol_lowing requires a "one hour" NRC notification?

(1. 0)

a.

A safety injection caused by a header to line AP signal due to a

faulted SG.

b.

An unplanned automatic start of an EOG.

c.

The opening of reactor trip breakers in preparation for maintenance

on the rod drive MG sets with the unit at CSD.

d.

With PZR level at 22% at CSD, the discovery of a flaw in the design .

of the containment structure that could have led to premature

failure of containment.

ANSWER:

a.

[VPAP-2802]

RQ-92.7-XB~lS Key

A safety injection caused by header to line AP signal

due to a faulted SG.

Page 10

Revision 2

QUESTION#:

A0524

. APPLICABILITY:

SRO

16.

-Which ONE of the following would require declaring an Alert, with the unit

at HSD?

_(1. 0)

a.

0.27 gpm primary to secondary leakage in "A" SG.

b.

12 gpm non-isolable RCS pressure boundary leak rate.

c.

2 gpm RCS unidentified leakage.

d.

55 gpm RCS identified leak rate.

ANSWER:

[EPIP~l.01]

d.

QUESTION#:

B91228

55 gpm RCS identified leakrate.

. APPLICABILITY:

Both

17.

The following conditions exist:

Unit 1 experienced a "Loss of' All AC" seven minutes ago.

*

l EDG started but could not be loaded so the team placed it in the

cooldown cycle five minutes ago.

Which ONE of the following courses of action should be taken when directed

by ECA-0.0 to "Initiate the AP-17 series procedures to restore the EDGs"?

(1. O)*

a.

Immediately reset the EDG differential lockout relay if tripped,

then press the start pushbutton.

b.

Immediately reset the_ Aux Trip Relay if tripped, then press the

start pushbutton.

c.

Strip loads from the lH bus as necessary, then allow the EOG to

complete its cooldown cycle before attempting to restore it.

d.

Press the start pushbutton and establish a gravity feed lineup from

the EDG Day Tank to the EDG Base Tank.

ANSWER:

c.

Strip loads from the lH bus as necessary, then allow the

EDG to complete its cooldown cycle before attempting to

restore it.

[AP-17.0l(C2)(03/28/91)]

[AP-17.03(C2)(03/28/91)]

(ECA-0.0(SB)(Rev.4-03/28/91)]

RQ-92.7-XB-lS Key

Page 11

Revision 2

QUESTION#:

B91307

APPLICABILITY:

Both

18.

Currently, Unit 1 is at 100% with indications of-a SG tube leak in the "A"

SG.

The first five steps of AP-16.00 have- been completed with the

following unit conditions:

CHG flow= 140 gpm .

Seal Injection flow -

8 gpm to each RCP .

PZR Pressure= 2100 psig decreasing trend .

Tave= 574°F .

PZR Level= 54% stable trend .

"A" SG Level= 44% stable trend.

Which ONE of the following is the correct action to be taken next?

(1. 0)

a.

Initiate AP-24.01, Large St~am Generator Tube Leak.

b.

Initiate Safety Injection and GO TO E-0.

c..

Trip the Reactor, manually initiate SI, and GO TO E-0.

d.

Stabilize unit conditions and initiate a unit shutdown in accordance

with the appropriate plant operating procedures.

ANSWER:

c.

Trip the Reactor, manually initiate SI, and GO TO E-0.

[AP-16.00, Excessive RCS Leakage]

I

RQ-92.7-XB-lS Key

Page 12

Revision 2

..

------~------------------

'.* *)*

..:__.

QUESTION#:

B91502

APPLICABILITY:

Both

19.

A reactor startup is in progress.

The team is withdrawing the control

banks and rod withdrawal has been stopped at the first doubling of source

range counts.

The second doubling of source range counts is projected to

be at 80 steps on bank "C".

Which ONE of the following actions is correct?

(1.0)

a.

Maintain source range counts constant and borate the rods out until*

the second doubling is projected greater than 23 steps on bank "D".

b.

Continue rod withdrawal to 98 steps on bank "C". *

c.

Maintain source range counts constant and borate the rods .out until

the second doubling is projected_greater than 98 steps on bank "C".

d.

Trip the reactor and emergency borate.

ANSWER:

[OP-58.2.2]

[SOER-88-2]

b.

Continue rod withdrawal to 98 steps on bank "C".

QUESTION#:

B91505

APPLICABILITY:

Both

20.

Which ONE of the following reflects the correct startup rate if reactor

power increases from 1 x 10-8 amps to 5_x 10-7 amps in 2 minutes?

(1.0)

a.

0.95 dpm.

b.

0.90 dpm.

c.

0.85 dpm.

d.

0;75 dpm.

ANSWER:

c.

o._85 dpm.

[Reactor theory notes]

~Q-92.7~XB-1S Key

Page 13

Revision 2

.

,*)

QUESTION#:

B91510

APPLICABILITY:

Both

21.

Which ONE of the following reflects Unit l's Xenon concentration 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months

following a power reduction from 100% to 50%?.

(1.0)

a,

Increasing.

b.

Decreasing.

c.

At equilibrium.

d.

Oscillating.

ANSWER:

b.

Decreasing.

[Reactor Theory notes]

QUESTION#:

B91533

APPLICABILITY:

SRO

22.

Which ONE of the following correctly describes the type of leakage and the

action(s) required for an RCS leak of 1.1 gpm past the reactor vessel

flange inner seal?

(1. 0)

a.

Pressure Boundary Leakage; be in HSD within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and CSD within

the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

Identified Leakage; operation may continue until leakage exceeds 10

gpm.

c.

Pressure Boundary Leakage; reduce leak to within limits in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ,

or be in HSD within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d.

Non-isolable Fault Leakage; be in HSD within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and CSD within*

the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ANSWER:

b.

[Tech Specs 3.1.C]

[OPT-10.0]

RQ-92.7-XB-lS Key

Identified Leakage; operation may continue until leakage ..

exceeds 10 gpm.

Page 14

Revision 2

QUESTION#:

B91552

APPLICABILITY:

Both

23.

On June 6, 1991, Surry Unit .1 exceeded 100% reactor power due to a failure*

in the main turbine governor control circuitry.

Which ONE of the . following. actions is* required to prevent this from

reoccurring when the unit is at 100% reactor power?

(1. 0)

a.

Operate the turbine in "Turbine Manual".

b.

~et the turbine Valve Limiter at about 100%.

c.

Operate the turbine in "Imp Out.".

d.

Set the turbine Valve Limiter at about 93%.

ANSWER:

d.

Set the turbine Valve Limiter *at about 93%.

1-GOP-1.6 (Rev .. 0, 08/06/91)]

[CTS-1389 (Limiter O~eration)]

QUESTION#:

B92204

APPLICABILITY:

SRO

24.

The following conditions exist:

Both Units are at 100% power.

During a normal VCT makeup, l-CH-P-2A (Boric Acid Xfer pump) tripped

on thermal overload and cannot be reset.

Which ONE of the following is the most limiting LCO after determining

1-CH-P-2A. is inoperable?

(1. 0)

a.

Establish another boric acid flowpath or be in HSD within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

If immediate attention is directed to repair the pump, the pump can

be inoperable for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

Establish another boric acid flowpath or be in HSD within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d.

If immediate attention is ~irected to repairs Power Operation can

continue.

ANSWER:

a.

Establish another boric acid flowpath or be in HSD

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

[Tech Spec 3.2.B and 3.2.D]

. RQ-92. 7-XB-lS Key

Page 15

Revision 2

'*

..

QUESTION#:* B92205

APPLICABILITY:

Both

25.

The team has just entered E-3 while responding to a SGTR when the RO

reports RCS subcooling is 28 °F and PZR lev-el is 10%,

and both are

decreasing. .

Which ONE of the following actions is required?

(1. 0)

a.

_Manually operate SI pumps as necessary and go to ECA-3.1 because

both of the E-3 CAP SI Reinitiation Criteria are met.

b.

Raise RCS pressure and dump steam from intact SGs to increase RCS

subcooling.

c.

Transition to FR-I.2 based on PZR level less than 15%.

d.

Continue with step 1 of E-3 because the SI Reinitiation Criteria

does not apply at this particular point in E-3.

ANSWER:

d.

[E-3]

[WOG Background]

. [RK]

RQ-92.7-XB-lS Key

Contin1;,1e with step 1 of E-3 because the SI Reinitia:tion

Criteria does not apply at this particular point in E-3.

Page 16

Revision 2

...

,.

QUESTION#:

B92206

APPLICABILITY:

Both

26.

Ten minutes

ago Unit 1 experienced an ATWS

which caused an RCS

overpressure condition initiating a LBLOCA .. The team has arrived at Step.

13 of FR-S.l with the following plant conditions:

.RCS pressure -

8 psig.

CETCs = 240°F.

RCS subcooling = 0°F.

RVLIS full range= 49%.

.SG levels= 17% NR.

CTMT pressure -

23 psia.

RCS cold leg Temp = 295°F. *

AFW flow to EACH SG = 175 gpm.

Which ONE of the following is the most appropriate procedure transition?.

(LO)

a.

FR-Z.l, Step l,.

b.

FR-P.2, Step 1.

c.

FR-H.l, Step 1.

d.

E-0, Step i;

ANSWER:

a.

FR-Z.1, Step 1.

[EOP Status Trees]

RQ-92.7-XB-lS Key

Page 17

Revision 2

..

...

QUESTION#:

B92210

/

'J 'i..._

APPLICABILITY:

Both

27.

The following conditions exist:

Both Units were at 100% power when a dual unit trip occurred.

*

The "LOAD SHED SYS" switch is in the enable position with the white

light illuminated.

,

The "BUS 'D LOAD SHED" red light is illuminated.

Station Service busses 2B and 2C failed to transfer to RSS.

All three Unit l condensate pumps are operating and the Unit 1 "B"

MFW pump is in operation.

Which ONE of the following actions must be taken on Unit l?

(1. 0)

a.

Stop all condensate pumps and the IIB" MFW pump:

b.

Stop the "B" MFW pump.

c.

Stop the "A" condensate pump.

d.-

Stop any condensate pump and/or the "B" MFW pump as necessary to

maintain HSD conditions.

ANSWER:

[AP-10.10]

RQ-92.7-XB-lS Key

c.

Stop the "A" condensate pump.

Page 18

Revision 2

., ..

..

QUESTION#:

B92212

APPLICABILITY:

Both

28.

The following conditions exist:

Reactor trip and SI in service due to SBLOCA.

RCS pressure is 900 psig.

CTMT pressure is 20 psia.

Which ONE of the following sets of conditions would require tripping the

RCPs per the RCP Trip Criteria following the SI?

(1.0)

a.

70°F RCS

b.

25°F RCS

c.

70°F RCS

legs.

d.

25°F RCS

legs.

ANSWER:

d.

subcooling by CETCs and PZR level is 11% and decreasing.

subcooling by CETCs and PZR level is 11% and increasing.

subcooling by CETCs and HHS! flow indicated to the RCS cold

25°F RCS subcooling by CETCs and HHS! flow indicated to

the RCS cold legs.*

[E-0 Continuous Action]

RQ-92.7-XB-lS Key

Page 19

Revision 2

..

.. .

QUESTION#:

B92220

APPLICABILITY:

Both

29.

The following plant conditions exist:

*

Unit 2 was shutdown on 11-23-91 at 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months .

A cooldown to_COLD SHUTDOWN was completed.

At 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months on 11-27-91 a total loss of RHR cooling occurred.

The following pertinent plant conditions existed prior to the loss of RHR

cooling:

RCS Tavg - 140°F.

PZR temp - 150°F.

RCS level - mid- loop.*

RCS press - atmospheric.

Which ONE of the following represents the approximate time it will take

the RCS to reach saturation?

(1. 0)

a.

7.5 minutes.

b.

10.0 minutes.

c.

85 minutes.*

d.

101 minutes.

ANSWER:.

b.

10.0 minutes.

[AP-27.00, Attachment 4]

[SOER 88-3]

RQ-92.7-XB-lS Key

Page 20

Revision 2

. ,.

..

(

,:--:-*),

-

QUESTION#:

B92505

APPLICABILITY:

Both

30.

A reactor trip has occurred because of spurious closure of all MSTVs. SI

has not been actuated. The RO is performing the immediate actions of E-0.

The following conditions exist:

*

PZR Pressure is 1950 psig and slowly decreasing.

*

Tavg is 551°F and slowly decreasing.

CTMT pressure is 10 psia.

All Steam Flows *indicate approximately O. 3 X 106 and are decreasing.

All SG levels at 10% NR and rising.

SG pressures A-1040 psig, B-1035 psig, C-1040 psig.

MS Header pressure is 910 psig.

'Which ONE of the foliowing is correct concerning SI?

(1.0)

a.

Is required because RCS pressure is decreasing.

b.

Is NOT required by the above indications.

c.

Is. required because of abnormal steam flows and pressures.

d.

Is NOT required and should be blocked.

ANSWER:

b.

Is NOT required by.the above indications.

[E-0, immediate actions]

QUESTION#:

B92507

.APPLICABILITY:

Both.

31.

Assume simultaneous conditions exist requ1.r1.ng implementation of each of

the procedures within each of the following four groups * (consider each

group separately).

'Which ONE of the following groups is arranged in.the correct order of

priority?

(1.0)

a.

ES-1.3, FR-Z.l, E-1.

b.

ECA-0.1, FR-H.1, FR-C.1.

c.

ES-1.2, ES-1.3, FR-C.2.

d,

E-1, E-3, E-2.

ANSWER:

a.

ES-1.3, FR-Z.1, E-1

[WOG Users Guide]

[ES-1. 3]

RQ-92. 7-XB-lS Key*

Page 21

. Revision 2

"

...

({). .. -

QUESTION #: * -B92602

APPLICABILITY:

Both

.,~;)* .

,

'*.".~

32.

A unit trip has occurred caused by loss of _MFW. The team is iri FR-H. l

be_cause of inadequate AFW flow.

Both MFW pumps have overcurrent trips.

Efforts. to restore adequate AFW flow have failed due to apparent line

blockage.

Crosstie flow from Unit 2 is unavailable.

All SGs are at

approximately 25% Wid_e Range level and decreasing.

Which ONE of the following ispreferreci to restore heat sink?

(1.0)

a.

Establish RCS bleed and feed.

b.

Depressurize a SG and feed with a condensate p~p.

c.

Feed the SGs from the Fire Water system.

d.

Feed the SGs from the AFW booster pumps.

ANSWER:

b.

Depressurize a SG and feed with a condensate pump.

[FR-H.l step 8)

QUESTION#:

B92603

APPLICABILITY:

.Both

33.

Which ONE of the following must SG pressure be reduced to in order to

maintain a 100°F RCS subcooling margin when. the RCS is being depressurized

to 785 psig?

(1. 0) .

a.

265 psig.

b.

285 psig.

c.

315 psig ..

d.

335 psig.

ANSWER:

b.

285 psig

[Steam tables]

RQ-92.7-XB-lS Key

Page 22

Revision_2

.-.,.,...

QUESTION#:

B92604

APPLICABILITY:

SRO

34.

FR-H:l is in effect and the fpllowing conditions exist:

All SG levels at 5% WR.

CTMT pressure is* 12 psia.

CETCs are decreasing.

WR Hot Leg temperature is 560°F and decreasing.

AFW crosstie from Unit 2 has just been restored.

Which ONE of the following gives the required method of feeding the SGs?

(1. 0)

a.

One SG should be fed at the maximum available rate.

b.

Each SG should be fed at the maximum available rate.

c.

One SG should be fed at 70 gpm until its level is greater than 5%

NR.

d.

Each SG should be fed at 70 gpm until its level is greater than 7%

WR.

ANSWER:

d.

Each SG should be fed at 70 gpm until . :i:ts level is

greater than 7% WR.

(WOG Background for FR-H.l]

[FR-H.l CAP]

RQ-92.7-XB-lS Key

Page 23

Revision 2

ML18151A716

Text

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