Text

Exam Rept 50-338/OL-88-01 on 880216-25.Exam Results:All Candidates Passed
	ML20151X794
Person / Time
Site:	North Anna
Issue date:	04/14/1988
From:	Casto C, Moorman J, Munro J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20151X777	List: ML20151X772; ML20151X794; ML20151X829;
References
	50-338-OL-88-01, 50-338-OL-88-1, NUDOCS 8805040253
	Download: ML20151X794 (163)
	v • d • e

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ENCLOSURE 1 EXAMINATION REPORT 338/0L-88-01 Facility Licensee: Virginia Electric and Power Company Facility Name: North Anna Power Station Facility Docket No.: 50-338 and 50-339 Written examinations and operating tests were administered at North Anna Power Station near Mineral, Virginia.

Chief Examiners:

J.

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.tMoorman, III' 4.13. BB Date Signed J.d hf be 915 88 C. A. Ca to Date Signed Approved by: 5 J. F. Munro, CMef

/9[F Date Signed Operator Licensing Section 1 Sumary:

Examinations on February 16-25, 1988.

Operating tests were administered to 20 candidates; all of whom passed.

Based on the results described above, 10 of 10 R0's passed and 10 of 10 SR0's passed.

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l 8800040250 880427 PDR ADOCK 05000338 i

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REPORT DETAILS

1. Facility Employees Contacted:

M. Bowlino. 7.,sistant Station Manager

J. Stall, superintendent, Operations:

L. Edmonds, Superintendent, Nuclear Training

B. Delamorton, Superintendent - Training (Simulator)

T. Williams, Manager of Training

M. Crist, Supervisor - Training

D. Fellows, Lead Simulator Instructor

W. Shura, Lead Simulator Instructor

R. Stevens, Instructor

Attended Exit Meeting

2. Examiners:

J. Munro, Chief, Operator Licensing Section 1 K. Brockman, Chief, Operator Licensing Section 2

J. Moorman, III, Senior Examiner

C. Casto, Senior Examiner D. Lew, Examiner M. Morgan, Examiner G. Salyers, Examiner T. Guilfoil, Examiner, Sonalysts, Inc.

G. Weale, Examiner, Sonalysts, Inc.

1 F. Victor, Examiner, Sonalysts, Inc.

K. Parkingon. Examiner, Sonalysts, Inc.

Chief Examiner

3. Examination Review Meeting l At the conclusion of the written examinations, the examiners provided Mike Crist with a copy of the written examination and answer key for review. The NRC Resolutions to facility coments are listed below,

a. R0 Exam ,

(1) Question 1.15 Coment partially accepted. Contrary to the facility comment, the temperature at which the desired shutdown margin was to be calculated was specified. (i.e.... prior to cooldown). The answer key will be changed to reflect the usage of the correction far. tor for 500F, Additionally, since the candidates were instructed to use the nomographs, the candidates were not required to make assumptions concerning the !

concentration of the BAST.

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(2) Question 1.17 Coment accepted. The answer key has..been changed to reflect the correct change in Tavg.

(3) Question 1.19 Coment partially accepted. If a candidate states the assumption that they'are using the ICCM value to calculate the subcooling, they will not be penalized.

(4) Question 1.21 Coment accepted. The statement concerning minimum cell voltage will not be required as part of the answer. The facility's training guide (NCR0DP 90.3) should be updated, p) Question 2.01 Coment acknowledged.

(6) Question 2.06b Coment accepted. The answer key has been changed to require "FALSE" as the correct answer. l (7)-Question 2.08 l Coment accepted. The answer key has been changed.

(8) Question 2.09 Coment accepted. The answer key has been changed to accept the

additional shutdown signal.

(9) Question 2.10 Coment accepted. The answer key has been changed to accept additional l answers provided by the facility and to equally distribute the point values.

l (10) Question 2.11 l

Comment accepted. The answer key has been changed to accept the l answer provided by the facility. The facility should clarify the training material concerning this item.

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3 o (11) Question 2.12 Coment accepted. The answer key has been changed to accept'the answer recommended by the facility. The point value of the question has been reduced.

(12) Question 2.14 Coment accepted. The answer key has been changed to accept both signals as recommended by the facility.

(13) Question 3.02 Comment not_ accepted. Although the terminology in the question differs from that in the facility material, it is correct.

(14) Question 3,04 Comment partially accepted. The answer key has been changed to reflect the proper meter indication as the correct answer. The facility's training material should be clarified in this area.

(15) Question 3.07b Coment accepted. The answer key has been changed as recommended by the facility.

(16) Question 3.08 Coment accepted. The answer key has been changed as recommended by the facility.

(17) Question 3.13 Coment accepted. The answer key has been changed to accept 'Tavg' as the correct answer. The point value has been reduced accordingly.

(18) Question 3.14 Coment not accepted. The question specifically asked how the steam dumps would respond and whether they would or would not open. The suggested response provided by the facility does not completely answer the question.

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(19) Question 3.17 Comment acknowledged. Since the answers are equivalent, no change to the answer key is required.

(20) Question 4.15 Comment accepted. The answer key will be changed to reflect the additional answer provided by the facility. The point values have been redistributed.

(21) Question 4.17b 5 Comment acknowledged. The answer provided by the facility will be >

considered equivalent for grading purposes. No change to the answer key required.

(22) Question 4.18 Comment partially accepted. Since the question referred to the Unit 1 procedure, the answer key will be changed to accept only the bases as specified in the Unit 1 Technical Specificat.ons. The point value has been lowered accordingly. The facility is requested to provide the Technical Specifications for both units in future material submittals.

b. SR0 Exam

(1) Question 5.04 Comment accepted. The answer key has been changed as recommended by the facility.

l (2) Question 5.19 See Resolution for 1.17 (3) Question 5.21 See Resolution for 1.19 (4) Question 5.22 r i k See Resolution for 1.21 !

(5) Question 6.01

. See Resolution for 2.08 t

- . ~ , ... . _ _ _ _ _ ___,__._ _.. - _._ _._,,...... _ ,_ _ __ _ _ ____ ._,.__,,_,_.__._ __,._,__..._...,_._ _, ,

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t (6)1 Question 6.05 See Resolution for 3.02 (7). Question 6.11' ;

See Resolution for 3.04 <

(8) Question 6.12

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See Resolution for 2.10 (9) Question 6.13 See Resolution for 2.12 .

(10) Question 6.14 ,

See Resolution for 3.08 (11) Question 6.19 See Resolution for 3.14 (12) Question 6.21 See Resolution for 3.17 (13) Question 7.05b r Comment acknowledged. The answer key will not be changed. The i facility is cautioned to thoroughly research and understand any char.ges to policy or procedures prior to changing the training e program.

(14) Question 7.11 ;

Connent accepted. The additional answer will be added as recommended

- by the facility. The point value of the question has been increased

, accordingly. :

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(15) Question 7.12 See Resolution for 4.15 (16) Question'8.01' Comment accepted. Sinc there is no correct answer-to the question, the question-will be deleted. ,

(17) Question 8.19 See Resolution for 4.18 (18) Question 8.24a Comment accepted. The answer key will be changed as recommended by the facility. Part b of the question has been deleted and the points redistributed.

(19) Question 8.26 Comment partially accepted. The answer key will be changed to allow accepting the less conservative Unit 2 actions provided the assumption is stated by the candidate. Otherwise, the more: conservative Unit 1 answer will be required. '

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4. _

Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the results of the examination.

There were no generic weaknesses noted during the operating examinations.

Although not identified as generic weaknesses, procedure content and use of procedures was addressed. OP-63.1, Post Accident Thermal Hydrogen Recombiner was found to be' deficient and was updated before the examiners left the site. AP-33, Reactor Coolant Pump Seal Failure is written such that the operator cannot comply with Step 5.2. OP-8.3, Boron Concentration Control, is routinely not followed by the operators when they use Section 4.3 for Alternate Dilution.

Information concerning procedure quality and useage has been forwarded to the Resident Inspector and the Operational Programs Section for further i investigation.

Noted also was that one of the Remote Shutdown Panels was found unlocked during one walkthrough exam. Proper corrective action was taken by the facility for this.

Five of 16 (31%) comments requiring changes to the written exam were due to inadequate or insufficient reference material provided by your staff to the NRC for examination development.

! The cooperation given to the examiners, the accommodations provided for the examiners and the effort to ensure an atmosphere in the control room conducive to oral examinations was also noted and appreciated.

The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.

'C U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _NgBIU_GNN8_1[<2__________

REACTOR TYPE: __PWB-WEgg.________________

DATE ADMINISTERED: _@gf02/16________________

EXAMINER: _Mgg8 MANt _d CANDIDATE: _________________________

1NSIBUCIlgNS_IQ_g@NDID8IEL Use separate paper for the answers. Write answers on one side only.

Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY

__Y86UE_ _IgIGL ___SCg8E___ _YOLUE__ ______________C@IEGQBY_____________

. - J _0 0__ _25 $_ _ ___________ ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS

_____.___ 6. PLANT SYSTEMS DESIGN, CONTROL,

_E_9_*E_0__ $$ I__ _________._

AND INSTRUMENTATION

_ 3 _0 0 11__

1 E _ _ _ $ _Y ___________ ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL

_jDhf9__ _3._3'$_ ___________ ________ 8. ADMINISTRATIVE PROCEDURES, CONDIT'ONS, AND LIMITATIONS

_]/fu(9_ ___________ ________% Totals Final Grade All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

[h Itt

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

11 . _ Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

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

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

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

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

-6. Use only the paper provided for answers.

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

8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a ogw page, write gely 90 ggg side of the paper, and write "Last Page" on the last answer sheet.

9. Number each answer as to category and number, for example, 1.4, 6.3.

' 10. Skip at least thtee lines between each answer.

l11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table. ;

!12. Use abbrevi ations only if they are commonly used in f acility litgtatute.

l13. The point value for each question is indicated in parentheses after the i

question and can be used as a guide for the depth of answer required, jl4. Show all cal cul ati ons, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE [

QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

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

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

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

a. Assemble your examination as follows:

(1) Exam questions on top.

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

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

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

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

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

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.Mc__IUE98Y_9E_NU96E88_EgWEB_ELONI_gEgB8IlgNt _ELylpS 1_8NQ PAGE- :2 IUESM9DYN8bics 1

OUESTION -5.01 (1.00)

- Whi ch ' ONE -(1) of the following actions will INCREASE North Anna's thermodynamic cycle efficiency?

a. DECREASING power from 100% to 25% .

b. LOWERING condenser vacuum from 29" to 25".

c. REMOVING a'high pressure FW heater from service.

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d. INCREASING power from 25% to 100%.

QUESTION 5.02 (*. 00)

Which one of the following statements best describes Xenon behavior on a power decrease, over the first few hours, following 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months at 100% power?

NOTE: EXe3 denotes xenon concentration

, a. Direct CXe3 increases, indirect CXe] decreases, total [Xe3 decreases, i r

i b. Direct EXe] increases, indirect EXe3 increases, total EXe] ,

increases.

j c. Direct CXe3 decreases, indirect EXe] decreases, total CXe3 [

decreases. j j

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d. Di r ec t EXe3 decreases, indirect EXe3 increases, total CXe3 j increases.

e. Direct EXe] decreases, indirect EXe3 increases, total CXe3 l decreases. f i

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-St__IBEgBy_gE_ NUCLE 88_EgWE8_EL8NI_gEEB8IlgNt _ELUIDS t_8NQ PAGE 3 11bEBdQQyd801CS QUESTION 5.03 (1.00)

Which ONE (1) of the following describes reason for the height correction factor,.K(Z), used in the heat flux hot channel factor calculation?

a. K(Z) compensates for:the increased coolant temperatures that occur higher in the coolant channels ,

b. K(Z) takes into account that there is some delay in refilling the core completely following a small break LOCA

c. K(Z) is an uncertainty f actor to allow for conservatism since we ct.nnot accuately measure flow in the core

d. K(Z) allows for greater power production in the upper regions ,

of the core near the end of life due to axial flux shifting l QUESTION 5.04 (1.00)

N41 N42 N43 N44 Upper Detector - Actual Current 159.7 0* 139.5 147.1 Value i Lower Detector - Actual Current 166.0 0* 145.1 150.3 Value Upper Detector - 100% Current 266.6 252.7 262.9 254.3 Value Lower Detector - 100% Current 278.6 236.7 .270,0 252.3 Value Using the above data, select the correct OPTR from the choices listed 3

below.

NOTE: Power Range Detector N42 has been properly taken out of service due to instrumcent malf unction.

I a) 1.025 b) 1.043 I c) 1.052 i d) 1.079 4

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-St - THEORY'OF NUCLEAR POWER PLANT _QEEB8IlgNz_ELQ1DSt_8ND PAGE ISEBdQQyN801QS

, QUESTION 5.05 (1.00)

From the four (4) st.atements li sted below, select the one that correctly completes the following sentence: "As rods are withdrawn, the magnitude of the Moderator Temperature Coefficient (MTC) ... "

a) "

remains constant because MTC is a function of boron concentration and temperature only."

b) becomes more or less negative depending upon core age."

c) "

becomes more negative because fewer neutrons are absorbed by the control rocs."

l d) becomes less negative because MTC is less negative-for an unrodded core."

OUESTION 5.06 (1.50)

Indicate whether each of the following will INCREASE, DECREASE, or HAVE NO EFFECT on the available (actual) Not Positive Suction Head (NPSH).

a. Increasing pump flow rate

b. Increasing pump suction temperature

c. Increasing total system pressure QUESTION 5.07 (1.50)

.The reactor is operating at 25% power when one RCP trips. Assuming that no reactor trip or turbine load changra occur , indicate whether each of the following parameters will INCREASE, DECREASE, or REMAIN THE SAME.

a. Flow in operating reactor coolant loops 4

b. Corn delta T

c. Operating loop steam generator pressure

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Q. TH$0RY'OF NUCLE 68_BQWEB_PLONT_gPEB8TIQN t _ELUIQ$t_6NQ PAGE 5

-IHEBMQQYN8digg QUESTION 5.08 (2.00)

A motor driven centrifugal pump is operating at rated flow. You then start' shutting the discharge valve. State if each of the f ollowing will INCREASE, DECREASE, or REMAIN THE SAME.

a. Flow (0.5)

b. Discharge Pressure (0.b)

c. Differential Pressure Across The Pump (0.5)

d. Motor Amps (0.5, QUESTION 5.09 (1.00)

The reactor is operating at 50% power with the rod control system in MANUAL when a single Group A rod drops into the core. Assuming no reactor trip or operator actions occurs

1) Will final reactor power INCREASE, DECREASE or REMAIN THE SAME when compared to initial reactor power? (0.5)

2) Will final Tave INCREASE, DECREASE or REMAIN THE SAME when compared to initial Tave? (0.5)

QUESTION 5.10 (1.50)

THREE (3) reactor coolant pumps (RCP's) are operating in parallel, EACH having an individtal pump flow rate "m" and all THREE (3) having a total (combined) flow rate "M".

a) If ONE (1) RCP is secured the OPERATING RCP's individual flow rate "m" will (INCREASE, DECREASE, REMAIN THE SAME).

b) IF ONE (1) RCP is secured and the other TWO (2) RCP's remain operating, the total (combined) flow rate "M" will (INCREASE, DECREASE, REMAIN THE SAME).

c) IF ONE (1) RCP is secured and the other TWO (2) RCP's remain operating, the Delta-P (Differential Pressren) across the reactor core will (INCREASE, DECREASE, REMAIN THE SAME).

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5:__IHEQBy_QE_NUCLEOB_EQWEB_E68NI_QEEB8I1gN1 _E6UIDS1_9ND PAGE 6 IHEBMQDyNeL11gg QUESTION 5.11 (2.00)

For each of the following, indicate whether the Departure from Nucleate Boiling Ratio will INCREASE, DECREASE or REMAIN THE SAME.

Consider each case separately.

"T u)6 a) One reactor coolant pump trips resulting in ihnee loop power operation.

b) Reactor power decreases.

c) One main steam isolation valve inadvertantly shuts. (Assume rod control is in manual and no reactor trip occurs.)

d) Automatic pressurizer spray initiates.

QUESTION 5.12 (1.50)

Two identical reactors are taken critical. Reactor A has a rod speed of 40 steps per minute. Reactor B has a od speed of 30 steps per minute. Assuming a continuous rod withdrawal in each case, answer: A, B, or THE SAME to each of the following questions.

a) Which reactor will achieve criticality first?

b) Which reactor will have the highest critical rod height?

l I c) Which reactor will have the highest source range count at l criticality?

i OUESTION 5.13 (2.00)

For each of the following, indicate whether the differential rod worth of an individual control rod will INCREASE, DECREASE, or REMAIN THE SAME. Consider each case separately.

a) An adjacent rod is inserted to the same height.

b) Moderator temperature is increased.

c) Baron concentration is decreased.

d) Fuel adjacent to the control rod in depleted.

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OUESTION 5.14 (2.00)

An estinated critical position has been calculated for a reactor startup that is to be performed 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a trip from a 100 day full power run. For each of the f ollowing events / conditions, indicate whether the ACTUAL critical rod position is HIGHER _THAN, LOWER THAN or the SAME AS the ESTIMATED critical rod position. Consider each event / condition separately.

a) Steam dump pressure setpoint is increased by 30 psig.

,b ) Startup is_ delayed for approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

c) The present boron concentration is 30 ppm higher than that used in the ECP calculation.

d) Condenser vacuum increases by one (1) inch Hg.

-QUESTION 5.15 (1.00)

TRUE or FALSE for each of the followings

a. During'a RCS heatup, as temperature gets higher, it will take a smal l er letdown flow rate to maintain a constant pressurizer levei.

b. Increasing condensate depression (subcooling) will cause BOTH a decrease in plant efficiency AND an increase in condensate (hotwell) pump available NPSH.

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5 t__IME98Y_9E_ NUCLE 6B_EQWEB_EL@NI_QEEB911QNt_ELyIDSt_GNQ PAGE O ISEBd99YU6b1CS.

QUESTION 5.16 (1.50)

Assume'that the power range channels have been adjusted based on a calculated calorimetric. Answer each of the following statements TRUE or FALGE.

.a) If the blowdown

flow had been ignored in calculating the calorimetric, then actual reactor puwer would be higher than r indicated reactor power.

b) If the feedwater temperature used in calculating the calorimetric had been 10 degrees lower than actual feodwater temperature, then actual reactor power would be higher'than indicated reactor power.

c) If a main steam atmospheric relief valve had been leaking by during the data-taking portion of the calorimetric, then actual reactor power would be higher than indicated reactor power. ,

L QUESTION 5.17 (1.50) i Match the heat transfer process in Column A to the equation that applies to that process in Column B. ,

COLUMN A COLUMN B

a. Between cold leg and hot leg 1. O=UA (delta T) i of reactor (normal FC flow)

2. O= lbm (delta T)

b. Across S/G tubes (prim *ry to secondary) 3. O = lbm c (delta T)

c. Across S/G (feedwater to steam) 4. O = lbm (delta h) -

! 5. O = lbm c (delta h)

OUESTION 5.18 (1.00) .

L Primary system flow rate is many times greater than secondary system ,

flow rate while the heat transferred by the two systems is essentially the same. Explain how this is possible.

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5. ' THEORY OF-NUCLEAR' POWER PLGNT_QPER8TIQN t _FLUIQEt_GNQ PAGE 9-IHEBU99YUGUICS QUESTION S.19 (2.00) l 3 ,

.Given the following, calculate the required boron change to increase reactor power from 75% to 100% while maintaining constant rod position.

t (NOTE: Denote whether the "boron change" required is a "boration" or

- "dilution" AS WELL AS the "amount" of change)

Moderator Temperature Coefficient -15 pcm/ degree Doppler-only Power Coefficient -12 pcm/% power Void Reactivity change -25 pcm Xenon change -50 pcm Boron Coefficient - 9 pcm/ ppm i

QUESTION 5.20 (1.00) ;

i If reactor power increases from 1000 cps to 5000 cps in 30 seconds, what is the SUR7 SHOW ALL WORK r

l OUESTION H5.21 (1.00) {

I If North Anna Unit i reactor is operating at 100% power with Tave =

Tref, CALCULATE the RCS subcooling margin.

QUESTION 5.22 (1.00) ,

2 North Anna's station batteries are rated at 1650 ampere-hours. DEFINC the term "ampere-hour".

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e4t__PL8NI_gygIgd@_DESIONt _CQNIBQLt_8ND_INSIBUdENI8IlgN PAGE 10 QUESTION 6.01 (2.00) o LIST the FIVE design criterion (Acceptance criteria) for the Emergency Core Cooling Systems?

t QUESTION 6.02 (1.00)

Which ONE (1) of the following statements describing the design of the fuel transfer tube is correct?

a. A blind flange is used to close the transfer tube on BOTH the containment side and the spent fuel side,

b. A blind flange is used to close the transf er tube on the containment side and a valve is used on the spent fuel side, r

c. A valve is used to close the transfer tube on the contain-ment side and a blind flange is used on the spent fuel side.

d. A valve is used to close the transfer tube on BOTH the con-tainment side and the spent fuel side. ,

OUESTION 6.03 (2.00)

State the RCP seal flow rates for the following RCP seal flow paths. [

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a. Down shaft into the RCS I

b. #2 seal leakage

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c. 83 seal leakage

d. Through radial bearing and #1 seal i i i i l

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6t__eLeUI_SygIgug_pggigg1_CQUIBQLt_8ND_IUSIBudENI@llgN PAGE 11 QUESTION 6.04 (1.00)

Which ONE-(1) of the following completes this statement:

'During plant cooldown, FLOW from the RHR to the RCS is designed to be...:

, a) ... constant (around 4000 gpm) AND this total flow is maintained by controlling RHR heat exchanger flow bypass valve (FCV-1605)".

b) ... constant (around 4000 gpm) AND this flow is maintained by controlling the RHR heat exchanger outlet valve (HCV-1758)."

c) ... varied (to a flow that meets the desired cooldown rate)

AND this flow is maintained by controlling the RHR heat exchanger flow bypass valve (FCV-1605)."

c) ... varied (to a flow that meets the desired cooldown

ate)

AND thi s flow is maintained by controlling the RHR heat exchanger outlet valve (HCV-1758)."

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QUESTION 6.05 (1.00) :

l Which ONE (1) of the following correctly completes the next sentence? !

"By preventing the letdown i nolation valves f rom opening or shutting -

unless all three orifice isolation valves are r, hut - we prevent.."

a) ... exceeding design flow rates of the domineralizers."

I b) ... excessive heatup rates ac r osts the regen. heat exchanger."

f c) ... excessive pressure on thu shell of the regen. heat i exchanger."

i d) ... unnecessary lifting of relief valves downstream of the orifices."

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At__E66NI_SYSIEd@_ DESIGN1 _CQNIBQLt_8NQ_INSIBUdENI8I1QN~ PAGE 12 OUESTION 6.06 (1.00). .

4 From the FOUR (4) statements below, select the ONE (1) statement that-IS NOT a consequence of placing the "LEVEL TRIP" switch, on the source range drawer, in the BYPAGS position. Refer to Figure 1.2 as an aid.

4 a) Continuous power is fed to the RPS to maintain voltage to UV '

coils.

t b) The OPERATION SELECTOR switch is "enabled" (capable of being used).

t c) The LEVEL TRIP BYPASS indicating lamp, on the drawer, is 4

illuminated.

d) The CHANNEL ON TEST indicating lamp, on.the drawer, is illuminated.

F QUESTION 6.07 (1.00)

I Which of the following malfunctions will result in both a low Tavg indication and a low delta T indication?

a. Hot leg RTD failed high

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b. Hot leg RTD failed low [

c. Cold leg RTD failed high

! d. Cold leg RTD failed low !

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6 2__E6001_SYSIEL1S_DEgl@Nt_QQNIBQLt_88Q_1dSI69dg@l@IlQU FAGE 13 QUESTION 6.08 (1.50)

For each of the following circuits, STATE:

1) "NOT SUMMED" if it receives a signal directl y f rom the upper or lower Power Range Detector (i . e. no summing of signals involved)

2) "SUMMED" if it receives a signal directly from the summing and level amplifier circuitry

3) "NEITHER" if it DOES NOT receive either the individual detector nor the summing / level amplifier signal a) Low Power Trip c) PZR Level Control Circuitry b) OT Delta T Calculation d) High Power Trip e) Detector Current Comparator OUESTION 6.09 (1.50)

Indicate whether the following will cause a Rod Control System URGENT

> or NON-URGENT FAILURE al arm.

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a. !. css of Main 100 VDC Power in the Logic Cabinet

b. Slave Cycler fails to start counting upon receipt of 'GO' pulsen

c. Loose circuit card in the Power Cabinet

)

CUESTION 6.10 (1.00)

Answer (T) RUE or (F)ALSE to the following statements concerning Excore Nuclear Instrumentation.

a. An OVERCOMPENSATED Intermediate Range det?ctor could prevent the Source Range from automatically reenergizing following an at-power reactor trip.

b. When a power range drawer is placed in Test, the rod stop and trip functions are disabled.

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l QUESTION- 6.11 f 2. 00)-

Match thu following conditions with the expected indication provided by the rnd speed indication meter. (NOTE: The rod speeds listed may !

be'uned in'more than one condition.) !

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. 1) -Rods in AUTO with a 4 degree F a) O steps / min !

temperature mismatch.

b) 8 steps / min

2) Rods in AUTO with one of the c) 40 steps / min Tave control instruments j failed LOW.

d) 48 steps / min l C)-Rods in MANUAL with a 10 degree F ,

, temp mxsmatch, e) 72 steps / min

4) Rods in AUTO with no temp mismatch. f) 76 steps / min immediately bef ore an operator i removes N44 fuses due to a failed

high power range.

detector, i

QUESTION 6.12 (2.00) ,

If the TWO (2) Rod Control Startup Pushbuttons were mistakenly .

depressed to "Raset" the system during mode 1 operation, what FOUR (4) !

I components in the rod control system would have to be restored to the proper setting?

j QUESTION 6.13 (1.50) i List the THREE (3) safety design functions of the Steam Generator Staam Flow Restrictor.

QUESTION 6.14 (2.50) ,

1 List the instrument coincidence, setpoints AND flow sensing "conditions" required for a "Loss of Flow in TWO (2) RCS Loops" reactor trip.

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-QUESTION 6.15 (1.00) i Emergency Diesel Generator 1H has been run unloaded for nine hours. l Prior to shutting down the diesel, you.are required to run it loaded t at 2500 to 2600 KW for one hour. State the reason for this one hour {

run.

OUESTION 6.16 (1.50)

With renpect to the Residual Heat Removal (RHR) system ,

a. What interlock (condition) must be met prior to opening the RHR '

inlet line isolation valves (1700 or 1701)? (include setpoint)

(0.5)

6. What interlock (condition) will automatically close the RHR inlet line isolation valves? (include setpoint) (0.5)

c. What is the basis of the RHR inlet line relief valve capacity? l (0.5)

OUESTION 6.17 (1.00)

In regard to the Emergency Condensate Storage Tank (ECST):

a) What is the "backup" to the ECST (by Technical Specification) if the ECST is considered to be INOPERABLE 7 (.33) b) LIS' TWO (2) sources of water which may be available (and that are tied in" DIRECTLY) to the AFW pump suctions in the event the :

ECST IS NOT available.(.33 ea) !

OUESTION 6.18 (1.00)

What is the effect, if any, on Reactor Coo?.ont System chemistry if an unsaturated bed of H-OH resin was placed in service?

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62__eLeNI_sygIgMS_pggIgut_ggNIBgLt_GNQ_1NSIBUMENIGI1QU PAGE 16 OUESTION 6.19 (1.50)

The plant is generating 800 MWo & the steam dump system is inadvertently left in the STEAM PRESSURE CONTROL MODE of operation ,

("pot" is set to maintain header pressure at 1005 psig). The loss of a Main Feedwater dump requires an immediate power reduction to 400 MWe and produces a 12 degree Tref - Tryg error.

DESCRIBE how the steam dump system would react to the given situation AND STATE if the dumps WOULD/WOULD NOT open in response to the transient.

QUESTION 6.20 (1.00)

With the unit holding at 30% reactor power, instrument maintenance (IM) personnel receive permission to perform a calibration on the power range (PR) channel N-41. The IM mechanic mistakenly pulls the instrument power fuses to PR channel N-42 and suddenly realizing the error, reinserts the N-42 fuses. The mechanic then pulls the fuses for channel N the reactor trips. GRATE the cause of the trip.

QUESTION 6.21 (2.00)

Ccmplete the following statements:

a) "The OT (Overtemp) Delta T calculated reactor trip setpoint is designed to protect the core from ..." (1.0) power b) "The OP (Overy ms) Delta T calculated reactor trip setpoint is designed to protect the core from ..." (1.0) l t

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OUESTION 7.01 (1.00) ,

h A previously unexposed operator is working in a room where the gamma / beta

, dose rate is 500 mram/hr. His allowable quarterly dose has been extended to the maximum that is allowable by an HP Superintendent extention. Which one of the following is the maximum time the operator could work without exceeding the allowable-quarterly limits for whole body radiation as set by the HP Superintendent?

a) 1.0 hour0 days 0 hours 0 weeks 0 months b) 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months c) 2.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months d) 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months QUESTION 7.02 (2.00)

There are FOUR (4) conditions requiring stoppage of all work and i

) immediate evacuation of containment according to the precautions and j limitations i r, 1-OP-4.1, "Controlling Procedure for Refueling"?

LIST these FOUR conditions, t

QUESTION 7.03 (1.00)

, Prior to a reac;or startup, with the RCS at normal operating pressure

' and temperature, the following RCS leakages exist. For each leak listed below, indicate whether you could STARTUP or would have to ,

remain SHUTDOWN. (Treat each leak below as an independent event) a) A leak from an unknown source of 1.5 GPM.

' b) 6.0 GPM from a manual valve packing gland. ,

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QUESTION 7.04 (2.00) 3 Answer the following statements (T) RUE or (F)ALSE concerning usage of the Emergency Response Guidelines. *

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1. You are perf orming a high -level action statement in the ACTION / EXPECTED RESPONSE (lef t hand) column of and Emergency Operating ,

-Procedure (EOP). This step must be completed prior to proceeding to

< the next, step in the left hand column of the procedure.

2. . You are performing a stop in the RESPONSE NOT OBTAINED (right j hand) column of an EOP. The RNO action cannot be performed and no other RNO actions exist. The correct action in this instance is to

. return to the next step or substep in the ACTION / EXPECTED RESPONSE ,

column.

3. You are perf orming a high level action statement in the ACTION / EXPECTED RESPONSE column of an EOP. This step cannot be completed as stated in the procedure and no RNO actions exist. The correct action in this inst <nce is to complete the step in effect before continueing with the next stop in the ACTION / EXPECTED RESPONSE ,

column. ,

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i 4. You are performing a step in the RESPONSE NOT OBTAINED column of

an EOP. You have not yet completed the task required by the RNO step when a CSF Red Path requires transitioning to a Functional Restoration Procedure (FRP). The correct action in this instance is to complete .

the RNO action in progress prior to transitioning to the FRP. l i !

d OUESTION 7.05 (1.50) ;

! During an emergency condition, the STA reports the following concerning the CSF paths ,

1. Core Cooling -

C ange Path

2. Subtriticality -

Yellow Path i

3. Integrity -

Orange Path

4. Heat Sink -

Red Path

a. In WHAT ORDER shoul d the above conditions be addressed? i t

i -b. Ten minutes later the STA reports that the above conditions still l

- exist except that Core Cooling is on a Red Path. WHAT ACTIONS ,

should be taken and WHY7 1 !

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4 1 QUESTION 7.06 (2.50) ;

5 In accordance with 1-AP-15, "Loss of Component Cooling", one indication of a loss of Component Cooling is the 'CC Surge Tank Low t Level' Alarm. Li st F1VE . (5) . of the remaining 6 indications of a loss l

_of Component Cooling Water as specified by AP-15. t i QUESTION 7.07 (1.00) ;

In accordance with the Virginia Power General Employee Training handbook, an employee is required to leave a radiological work area if I their self-reading dosimoter becomes lost or is dropped. List the :

THREE (3) other conditions concerning a self-reading dosimeter that ;

2 ' require an employee to leave a radiological work area and report to l

, HP.

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a l QUESTION 7.08 (2.50)

State the High Level Logics for EP-3, Steam Generator Tube Rupture. {

I QUESTION 7.09 (2.00) l LIST the FOUR (4) SI Termination Criteria as stated in 1-EP-1, ' Loss of Reactor or Secondary Coolant

and 1-ES-1.1 'SI Termination'. l

. t QUESTION 7.10 (1.00) ;

1 l A Radiation Work Permit (RWP) contains information cuch as dosimetry j requirements. List FOUR (4) other TYPES of information that you can ,

find on an RWP. (NOTE: Si mi l ar items such as 'TLD requirements *, i j 'Self-Reading Dosimeter requirements' and ' neutron badge requirements' are not acceptable.) [

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QUESTION 7.11 (1.50) ;

l List the Immediate Operator Actions for failure of Power Range !

Instrument N-44 as specified in 1-AP-4.3, "Malfunction of Nuclear 3 Inttrumentation (Power Range)" f

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i QUESTION 7.12 (2.00) !

Immediate Action Step 4 of FRP-S.1, "Response to Nuclear Power Generation /ATWS" instructs the operator to "Initiate Emergency

-Boration of RCS:". List the actions required to accomplish this step.

NOTE: RNO actions ar e NOT required.

' QUESTION 7.13 (1.50) ,

One of the four Immediate Operator Actions in 1-AP-30, "Fuel Failure Ouring Handling" is ' Notify the Shift Supervisor'. ;

LIST the other THREE, i QUESTION 7.14 (1.50) !

In accordance with 1-AP-9, ' Reactor Coolant Pump Ulbration',

one' indication of excessive Reactor Coolant Pump vibration is ' Reactor Coolant Pump Vibration Danger Annunciator'. ;

LIST THREE (3) of the four remaining indications as !

specified by 1-AP-9. }

OUESTION 7.15 (1.00)

Power Range Chonnel N-41 han failed. Your crew has properly removed it from service in accordance with 1-AP-4.3, "Malfunction of Nuclear ;

Instrumentation (Power Range)". One of the actions required to remove [

N-41 f orm service is to remove computer points N0041A and N0042A from i

Scan. EXPLAIN why this action is necessary, i

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! OUESTION 7.16 (1.00) ,

Per OP-58 "Full Length Rod Control System", when INSERTING control l

' rods, caution must be taken to prevent rod drive mechanism damage ;

l while in Manual or Bank Select. At what point (steps) could this !

! damage occur AND how is it prevented?

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Z,. _EB9d5DW853_ _UO6dGLs._0ENDBdG6t_EdE6@ENGL8dp PAGE 21 B00196991GOL_GONIB96 QUESTION 7.17 (1.00)

A operator is manually starting 1H Emergency Diesel Generator. During the start an annunciator in the diesel room alarms "Fire Trouble".

Explain why the receipt of this alarm would not be abnormal under this condition.

QUESTION 7.18 (1.00) 1-ECA-0.0, "Loss of All AC Power" requires that the Reactor Coolant Pump Seals be isolated locall y. What is the bases for isolating the areal s?

OUE3 TION 7.19 (1.00)

ES 0.2A, "Natural Circulation Cooldown With Shroud Cooling Fans" requires that the cooldown rate be limited to <25 F/ hour. State the reason for this limitation.

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OUESTION 8.01 (1.00) i The f ollowing plant conditions have existed for the past twelvo (12) hours:

100 percent rated thermal power (RTP) ,

Normal Operating Temperature / Normal Operating Pressure Residual Heat Removal Heat Exchanger (RHR Hx) "A" -

INOPERABLE F

The maintenance supervisor reports that the suction from the containment sump to RHR Pump "B" is INOPERABLE. You concur. ;

Which one of the following most accurately describes the allowances and/or limitations imposed by the Technical Spec.fications?

NOTE: Technical Specifications 3.0, 3.4.1.3, 3.4.1.4, 3.5.2 and 3.5.3 are enclosed for reference.

a) No limitations are imposed by the Technical Specifications.

b) Restcre the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDDY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , c) Suspend all operations involving reductions in Reactor Coolant System (RCS) baron concentration and immediately initiate ,

corrective action to return loop to operation. !

d) Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , action shall be initiated to place the unit in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months & at least HOT SHUTDOWN '

in the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

e) Because of the inoperability of either the RHR Hx or RHR pump, restore at loast one ECCS subsystem to OPERABLE status or maintain RCS Tavg to less than 350 degrees by use of alternate ;

heat removal methods.

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= QUESTION O.02 (1.00) i The only people who may manipulate any control that directly affects reactivity or power level are those who ares a) ... in a training status to qualif y f or a reactor operating license, IN AN ABNORMAL OR EMERGENCY CONDITION ONLY

b) ... in a training status to qualify for a reactor operating license, or those holding an active NRC RO or dRO licence c) . . . management or techni cal non-licensed persons providing plant cupport functions in their field of expertise, WITH RO/SRO APPROVAL

, d) ... in a training status ta qualify for a reactor operating license - that are under DIRECT licensed operator supervision - or those holding an active NRC RO or SRO license DUEGTION 8.03 1.00)

! According to ADM-D.8, Temporary Changes / Procedure Deviations, which

one of the following is correct if the prior need for a deviation I cannot be anticipated prior to beginning the step and the procedure

cannot be stopped for operability.

a.) The nrocedure completed and a procedure deviation form initiated.

b.) The procedure completed and a memorandum initiated by the i Shift Supervisor.

c.) The procedure coinpleted and the Superintendent -

Operations permission obtained.

d.) The procedure completed and the deviation reported to the l

SRO on call as soon as possible.

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4 8.04 (1.00) ,

) 'OUESTION i Pressurizer PORV leakage falls under which one of the following (

Technical Specification leakage classifications. I a.) IDENTIFIED LEAKAGE r b.) PRESSURE BOUNDARY LEAKAGE

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. c.) CONTROLLED LEAKAGE [

1 d.) UNISOLABLE LEAKAGE l

e.) NONE OF THE ABOVE i

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I QUESTION 8.05 (1.00) 4 Which one of the following is NOT a required one hour reportable i event in accordance with ADM-16.1, Station Deviation Reports.

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a.) The initiation of a plant shutdown i n accordance with a ,

Technical Specification action statement.

b. Any event or situation, related to the health and safety of the l public or onsite personnel, or protection of the environment, ;

for which a news release is planned or notification of other

government agencies han been or will be made.

i c.) A deviation from Technical Specifications required in an ;

j emergency situation to protect the public health and safety l-when there is no action provisions i n the license conditions or ,

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, Technical Specifications to adequately provide the p"otection.

3 t d.) Any event that results in major loss of emergency assessment ,

! capability, offsite response capability, or i i communications capability.

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QUESTION 8.06 (1.00) f From the following statements, select the one that most accurately defines a CHANNEL CALIBRATION. .

I a) " the qualitative assussment of channel behavior during t operation by observation." !

" the adjustment, as necessary, of the channel output such b) that it responds with the necessary rango and accuracy to known values of the parameter which the channel. monitors."

c) " the injection of a simulated signal into the chann:1 as close to the sensor as practicable to gerify OPERABILITY ;

including alarm and/or trip functions. l r

d) "

the inj ection of a simulated signal into the sensor to !

verify OPERABILITY including alarm and/or trip functions." r f

e OUESTION 8.07 (1.00) ;

In reference to Technical Specification 3/4.7.15, Fire Barrier Penetrations, select the one phrase below that correctly completes the ;

following statement: " All fire barrier penetrations (including fire door) in fire zone boundarios protecting saf ety related areas shall be [

functional..."

a) "while in Modes 1 and 2." l b) "at all times," .

c) "whenever reactor coolant system (RCS) average temperature is [

greater than 350 degrees F." (

d) "whenever RCS average temperature is greater than 140 F"

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L OUESTION O.08 (1.00)

North Anna Power Station Technical Specifications require that the ,

overtemperature delta T Channel Functional Test be accomplished on a {

"monthly" basis. The.l'ast three dates on which this surveillance was !

performed are August 10, September 10, and October 8. From the dates listed below, select the latest date on which this surveillance can be [

4 accomplished without exceeding the periodicity required by technical j specifications.

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NOTE: August has 31 days; September has 30 days; and October has 31 {'

days. .

I a) November.7. j

@) November 8.

c) November 15.

I J d) November 18. ,

OUESTICN 8.09 (1.00) {

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i The only people who have the authority to DIRECT the Control Room

! Operator (CRO) performing operations that affect power level or ;

i core reactivity ares i a) Only those holding an active SRO license

! i i b) Only North Anna management personnel and those holding an .

l active SRO license c) Only NRC personnel and those holding an active SRO license t I

d) Only NRC personnel and those holding either an active RO or SRO license i l i

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f QUESTION G.10 (1.50)

Match the f acility with the most appropriate purpose / description r (NOTE: -The facility /conter may have more than one doucription/ purpose) e a) Technical Support Center __

1) Used to continually evaluate and coordinate activities re-b) Operations Support Center lated to the emergency. Located adjacent to the Training Bldg. '

c) Local Media Center Recovery operations shall be managed from this facility, d) Local Emergency Ops Facility

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~~ 2) Located in the THIRD (3rd) e) Emergency Control Center floor conference room of the Maintenance Building.

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3) Fire Team metabers report to this area to augment the on-shift Fire Team. Remain in ;

area until services are i needed. f

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4) The Control Room is des-ignated as the ________

upon i activation of North Anna's Emergency Plan.

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__ 5) Located approx. SIX (6) :

- miles from the site at !

Mineral Vol. Fire Dept ,

! Public Meeting Hall. Public i information personnel are briefed by VEPCO management.

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__ 6) Contains instrumentation ;

to denote station status to those responsible f or engneering and management

' support. Located adjacent to Unit 1 Control Room. L I

f QUESTION 8.11 l

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-Bt__0Ddlu1SIBoI1YE_EB9GEDVBESt_C9ND1I1QdSt_8ND_L1011811gNS PAGE 28 OUESTION 8.12 (1.00)

In accordance with ADM-14.1, Jumpers (Temporary Modifications), some jumpers are required to be innta11ed using approved procedures.

a. What types of jumpers are required to be installed using approved procedures?

b. Who makes the decision as to whether or not a procedure is required?

OUESTION .8.13 (1.50)

In accordance with ADM-14.0, Tagging of Systems and/or Components, when a request for tagging is made, one of the four actions the shift supervisor is responsible f or is determining if the unit conditions will support the removal of the system or special configuration and assess the potential impact of the tagout.

State the other THREE actions the Shift Supervisor shall take when a request for tagging is made according to ADM-14.0, Tagging of Systems and/or Components.

QUESTION 8.14 ( .50)

According to ADM-19.1, Operational Records Administration, Station logu are to be taken until a system / equipment is secured. State the one (1) parameter that is to be logged whether the equipment is operating or shutdown.

QUESTION 8.15 (1.00)

According to ADM-19.10 Limitations on Licensed Personnel Movement, a Control Room Operator shall not leave the "work" area without obtaining qualified relief except for two (2) instances. State the TWO (2) instances when a Control Room Operator can leave the "work" area WITHOUT obtaining quali fied relief .

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QUESTION 8.16 (1.00) {

In accordance with the North Anna Emergency Plan, the station manager has certain responsibilities during the implementation of the [

Emergency Plan. Some of these responsibilities can be delegated to l other individuals and some may not. There are FOUR (4) ;

responsibilities that MAY NOT be delegated, one of which is

'Rocommending protective measures *. State the other THREE.

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QUESTION B.17 (1.50) ;

The Shift Supervisor assumes the position of Interm Station Emergency {

Manager in the event of an emergency. According to the North Anna j Emergency Plan, the Station Manager is the principal individual who t can relieve the Shift Supervisor. State the three (3) other

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individuals, by title, who can also relieve the Shift Supervisor as ,

Station Emergency Manager, j i

t OUESTION 8.18 (1.00) i IN accordance with ADM 19.17, Independent Verification, independent .

verification is accomplished by either Direct or Indirect i verification. Adm 19.17 specifies TWO circumstances under which ;

s INDIRECT verification should be used. State these TWO circumstances, l f OUESTION 8.19 (2.00) J 3 !

j Concerning North Anna Operating Procedures 1-OP-1.5, "Unit Startup ;

From Hot Standby Condition (Mode 3) To Startup Condition (Mode 2) With ]

Reactor Critical At Less Than Or Equal To 5 Percent Power"; STATE the FIVE reason / bases f or the f ollowing "note"/ precaution l l

i l, 1 e i

a) "The lowest operating Reactor Coolant loop Tavg must be [

l greater than or equal to 541 degrees F within 15 minutes j

! PRIOR to achieving reactor criticality."

I i 5 t i :

i I

l t ,

J !

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~Ot__00d101SIBOIIVE_EBQGERUBESt_GONQ1Il0NSt_0ND_ lid 1IGIl0US PAGE 30 [

l i ,

QUESTION O.20' (1.00) ,

[

In order to perform core alterations near the reactor hot legs, the B-train RHR-loop was shutdown. The A-train RHR loop is unavailable 1 due to maintenance activities. Three (3) hours later, the core ,

alterations are ccmpletud and the B-train RHR loop is restarted. i Refering to_the attached Technical Specifications, state the violation t that has occured.

t QUESTION 8.21 (2.00) ,

According to Technical Specifications, North Anna is to limit the i primary-to-secondary leakage from any single steam generator to 500 i gallons por day and total leakage for all steam generators to 1 gallon ,

por minute.

}

State' Technical Specificaion basis for each of these two (2) limits. l QUESTION 8.22 (1.50) f i

According to ADM-19.17, Independant Verification, state how direct verification shall be accomplished for each of the following. ,

i a.) OPEN manually operated valves :

b.) OPEN THROTTLED valves ;

c.) FUSES OUEUTION 8.23 (1.00) j North Anna Technical Specifications 3.11.2.6 states: "The quantity of !

radioactivity contained in each gas storage tank shall be limited to ,

less than or equal to 25,000 curies of noble gases (considered as .

Xo-133). State the basis for this technical specification.

i c

i

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PAGE 31 9t__0901NISIBBIIVE_EB99EDUBESt_C9ND1110NSt_0NQ_ Lid 11GI1QNS QUESTION 8.24 (1.00)

At North Anna Power Station, Unit 1, the f ollowing events have occurred in the past seven hours 1)- At 5:00 AM, one FORV began leaking by while a reactor startup was in progress (reactor power at 10 exp -O amps).

2) At 5:45 AM, the leaking PORV's block valve was shut and power removed.

3) At 9:30 AM, Unit 1 was operating at 75% rated thermal power.

4) At 9:45 AM, the second PORV valve began leaking by.

5) At 10:15 AM, an attempt to close the block valve for the second PORV failed and the block valve was declared inoperable.

6) At 10:30 AM, a plant shutdown commenced.

7) At 12:00 PM (present time), the plant was placed in hot standby.

In reference to the above events, answer each of the following questions.

NOTE: APPLICABLE TECHNICAL SPECIFICATIONS ARE ENCLOSED.

a) Were any technical specification limits violated? If the answer is YES, explain.

b) Dy what time tomorrow must the reactor be in COLD SHUTDOWN 7 OUESTION 8.25 (1.001 North Anna Power Station Technical Specification 6.7 specifies the actions required to be taken if a SAFETY LIMIT is violated. State the two actions that are required to be accomplished within the FIRST hour.

QUESTION 8.26 (1.00)

North Anna Power Station Technical Specification 3.7.15 "Fire Barrier Penetrations" requiren that specific actions be taken within one hour if one or more fire barrier penetrations is nonfunctional. State these required actions as directed by this technical specification.

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

(*******644*** END OF EXAMINATION ***********6***)

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3/4 LIMITING CONDITIONS FOR OPERATION AND SURVE!LLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMIT!NG CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 ' Noncompliance with a specification shall exist when the requirements of the Limiting condition for Operation and associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.,

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour ACTION shall be initiated to place the unit in a MODE in which the Specification

.does not apply by placing it, as appitcable, in: '

1. At least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

2. At least HOT SHUIDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

3. At least COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . l Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the 'ndividual specifications. This specification is not applicable in MODES 5 or 6.

3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the ACTION requirements. This provision shall not prevent passage through OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual specifications.

3.0.5 When.a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergenc power source is OPERABLE; and (2) all of its redundant system (s), subsystem (y),s train (s), component (s), and device (s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1) e d (2) are satisfied, the unit shall be placed in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in at least COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . This specification is not applicable in MODES 5 or 6.

NORTH ANNA - UNIT 2 -

3/4 0-1 Amendment No. 46

8-M-60 SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shi ,1 be met during the OPERAT!0NAL MODES or other conditions specified for indi> idual Limiting Conditions for Operation unless otherwise state 4 in an indiv dual Surveillance Requirement.

4.0.2. Each Surveillance Requiremens shall be performed within the specified time interval with:

a. A maximum allowable extension not to exceed 255 of the surveillance interval, but

b. The combined time interval time for any 1 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillapec interval. .

4.0.3 Failure to perform a Surveillance Requirement within the specified time iriterval shall constitute a failure to met the OPERA 81LITY requirements for a Limitinft condition for Operation. Exceptions to these requirements are stated in the <ndividual specifications. Surveillance Requirements do not.have to be p

, erformed on inoperable equipment. ,

4.0.4 Entry into an OPERATIONAL H0DE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting-Condition for Operation have been performed within the stated surveillance interval or as otherwise specified. (

)

4.0.5 Surveillance Requirements for inservice inspection and testing of A5ME Code Class 1, 2 and 3 components shall be applicable as follows:

, a. Inservice inspection of ASME Code Class 1, 2, and 3 components and 4

inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g) 'except'where specffic written relief l

l has been granted by)the Commission pursuant to 10 CFR 5 Section50.55a(g)(6(1).

I NORTH ANNA - UNIT 2 3/4 0-2 4

i

8-21-40 APPL 1CA8ILITY SURVEILLANCE RE0V!REMENTS (Continued)

b. Surveillance intervels specified in Section XI of the ASNE loiler

.and Pressure Vessel Code and applicable Addenda for the inservice inspection end testing activities required by the ASME Soller and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications: .

ASMf Soiler and Pressure Vessel Required frequencies for Coce and acclicable Accenda performing inservice terminology for inservice inspection and testing inspection and testino activities activities Weekly At least once per 7 days Monthly At least once'per 31 days

' Quarterly or every 3 months At least once per 92 days Seef annually or every 6 months At least once per 184<ays Every 9 months At least once per 276 days Yearly or annually At least once per 366 days ,

c. The provisions of Srecification 4.0.2 are acclicable to the above required frequencies for performing inservice inspection and testing activities,

d. Performance of the 4 Dove inservice inscaction and testing acf.ivities shall be in aedition te other specified Surveillance Requirements.

e. Nothing in the ASME loller and Pressure Vessel Code shall te construed to supersede the requirements of any Technical Specification.

.l NCRTH ANNA - UNIT 2 3/4 0-3 t

~~

r..

8-31-80 REACTOR COOLANT SYSTEM SHUTDOWN .

LIMITING CON 0! TION FOR OPERATICN 3.4.1.3 a. At least two of the coolant loops If sted below shall be OPERA 8LE:

1. Reactor Coolant Loop A and its associated steam generator and reactor coolant pump," ,

2. Reactor Coolant Loop 8 and its associated steam generator and reactor coolant pump,*

3. Reactor Coolant Loop C and its associated steam generator and reactor coolant pump,"

4. Residual Heat Removal Subsystes A,**

5. Residual Heat Removal Subsystee S."*

b. At least one of the acove coolant loops shall te in operation.""" -

APPLICA8!LITY: MCCES 4 and 5.

ACTION:

a. With less than the above required loops OPERA 8LE, f amediately initiate corrective action to return the recuired locos to OPERA 8LE status as soon as possible; ce in COLD ShuTD0hN within 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

D. With no coolant loop in operation, suspend all operations involving a reduction in coron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.

'A reactor coolant pump shall not te started with one or more of the RCS cold leg temperatures less than or ecual to 340*F unless 1) the pressurizer water volume is less than 457 cubic feet or 2) the secondary watar tatoera-ture of each steam generator is less than 50*F acove eacn of the RC5 cold leg temperatures.

'"The offsite or emergency pcwer source say te inopernole in McCE 5.

"""All reactor coolant OLeps and residual heat removal sumos say to de-energi:ec for up to I hour proviced 1) no coerations are permitted that woulo cause dilution of the reactor coolant system Doron concentration, and 2) core outlet temperature is maintained at least 10*F oelow saturation temperature.

NORTM ANNA - UNIT 2 3/4 4-3

8-31-80 REACTOR COOLANT SYSTJ4

$URVEILLANCE REQUIRE.MENTS i

4.4.1.3.1 The required residual heat removal loop (s) shall be determined OPERA 4LE per Specification 4.0.5.

4.4.1.3.2 The required reactor coolant pump (s), if not in operation, shall be detensined to be OPERA 8LE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.3.3 The required steam generator (s) shall be determined OPERABLE by verifying secondary side water level to be greater than or equal to 17% at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.3.A At least one coolant loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

NCRTH ANNA - UNIT 2 3/4 4 3a

9-19-80 REACTOR CCOLANT SYSTEM

!$0 LATED LOOP LIMITING CCN0! TION FOR OPERATION 3.4.1. 4 The boron concentration of an isolated loop shall be saintained y greater than or equal to the boron concentration of the operating loops, unless the loop has oeen drained for maintenance.

APPLICA8fLITY: MCDES 1, 2, 3, 4 and 5.

ACTION:

With the requirements of the above specification not satisfied, do not coen the isolated loop's stop valves; either increase the boron concentration of the isolated loop to within the limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT STANC8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with the unisolated portion of the RCS corated to a SHUTDOWN MARGIN equivalent to at least 1.77% ak/k at 200'F.

l

$URVEILLANCE REQUIREMENTS ,,,...,

4. 4.1. 4 The boron concentration of an isolated Icep shall be cetermired to te ll greater than or equal to the boron concentration of the coerating loops at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and within 30 minutes prior to operdng either the hot leg or cold leg stop valves of an isolatec loco.

NORTH ANNA UNIT 2 3/4 4 4

3-21-$0 l

l REACTOR COOLANT SYSTEM RELIEF VALVE 5 LIMITING CCN0! TION 80R CPERAftcN '

3.4.3.2 5 shall be OPEAA8LE.Two power relief valves (PCRVs) and their associated block valve

_APPLICA8 t LITY: MODES 1, 2, and 3.

ACTICN:

4.

Wi'.h one or scre PCRV(s) inocerable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to CPERA8LE status r.r close the associated block valve (s) and remove power from the block valve (s); othemise, ce in i

ec least within HOT STANC8Y the fo11cwing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ,within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHU b.

With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the bloct valve (s) to OPERA 8LE status or close the Dieck valve (s) and remove power from the bicek valve (s); othemise, te in at least

.ithin theNOT STANC8Y following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COL 3 ShuTC s

$URVE!Lt.ANCE REQUIREWENTS 4.4.3.2.1 Each PCav shall be demonstrated CPERA8LE:

a.

At least once per 31 days by perfomnce of a CHANNEL FUNCTIONAL TEST, exclucing valve oceration, and b.

At least once per 18 months by :erformance of a CMANNEL CALI!RATICN.

4.4.3.2.2 92 days ey operating the valve trough one esmolete cycle of fu l

l NCRTH ANNA UNIT 2 3/4 4 7a i

r.

,g

$-21-60 REACTOR COOLANT $MTEM PRE 550RIZER LIN!T!NG CON 0!?!0N FOR OPERAf!ON 3.4.9.2 The pressurizer tasperature shall be limited to:

a. A saxieum heatup of 100'F or cooldown of 200'F in any one hour period, and

b. A saxieum spray water toeperature and pressurizer temperature dif ferential of 32CSF.

APPt.!CABILITY: At all times.

ACTION:

With the pressurizer temperature limits. in excess of any of the above limits, restore the temcerature to within the limits within 30 minutes; perfore an engineering evaluation to determine the offsets of the out of 11mit condition

, on the structural integrity of the pressurizer; determine that the pressurizer reasins acceptaale for continued operation or be in at les:t HOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce the pressurizer pressure to less than 500 psig within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVE!LLANCE REQUIREMtNTS 4.4.9.2 The pressurizer teaceratures shall be determined to be within the limits at least once per 30 minutes during system heatup or cooldes.9 The spray water temperature differential shall be determin&d to be within the limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during auxiliary spray operation.

l NORTH ANNA - UNIT 2 3/4 4-29

- - - - . - ~ , - - - -,-------,-,-.,a-,

. 1-li n REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS _

LIMITING CONDITION FOR OPERATION 3.4.9.3 At least be OPERA 8LE: one of the follow'ing overpressure protection systems shall a.

Two power operated relief valves (PORVs) with a lift setting of: 1) less than or equal to 520 psig whenever any RCS cold leg temperature is less than or equal to 340*F, and 2) less than or equal to 375 psig whenever any RCS cold leg temperature is less than 190'F, or b.

A reactor square coolant inches, or systen vent of greater than or equal to 2.07 c.

A saximum pressurizer water volume of 457 cubic feet with all RCS cold leg temperatures greater than or equal to 320*F.

APPLICA8ILITY:

When the temperature of one or more of the RCS cold legs is less than or equal to 340'F, except when the reactor vessel head is removed.

ACTION:

\

a.

With one PORV inoperable, either restore the inoperable PORV to OPERA 8LE status within 7 days or depressurize and vent the RCS through 2.07 square inch vent (s) within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; maintain the RCS status, OPERABLE in a vented condition until both PORVs have been restored to b.

With both PORVs inoperable, depressurize and vent the RCS through a 2.07 square inch vent (s) within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; maintain the RCS in a vented status, condition until both PORVs have been restored to OPERA 8LE c.

In the event either the 10RVs or the RCS vent (s) are used to mitigate a RCS pressere transient, a Special Report :nall be prepared and submitted 30 days. to the Commission pursuant to Specification 6.9.2 within The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent (s) on the transient and any corrective action riecessary to prevent recurrence.

d.

The provisions of Specification 3.0.4 are not applicable.

MORTH ANNA - UNIT 2 -

3/4 4-30 Amendment No. 60

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

8-21-80 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIRENENTS 4.4.9.3.1 Each PORY shall be demonstrated OPERA 8LE by:

a. Performance of a CHANNEL FUNCTIONAL TEST on the PORV actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORY is requirec OPERA 8LE and at least once per 31, days thereafter when the PORY is required OPERABLE.

b. Performance of a CHANNEL CALIBRATION on the PORY actuation channel, at least once per 18 sonths.

c. Verifying the PORY key switch is in the AUTO position and the PORV isolation valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months when the PORY is being used for overpressure protection,

d. Testing pursuant to Specification 4.0.5.

4.4.9.3.2 The RCS vent (s) shall be verified to 'Je optn at least once per

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months " when the vent (s) is being used for overpressure protection.

4.4.9.3.3 The pressurizer water volume shall be verified to be less than or equal to 457 cubic feet at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the pressurizer is being used for overpressure protection "Except wnen tnr: vent pathway is providad with a valve which is locked, sealed, or otherwise secured in the open position, then verify.these valves open at least once per 31 days.

t l

NORTH ANNA - UNIT 2 3/4 4-31

'. ~!,

6-7-84 REACTOR COOLANT $7 STEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1,2 4 3 COMPONENTS LIMITING CONDITION FOR OPERATION __

3.4.10.1 Ths structural integrity of ASME Code Class 1, 2 'and 3 components i shall be maintained in accordance with Spacification 4.4.10.1.

APPLICABILITY: ALL MODES.

ACTION:

a. With the structural integrity of any ASME Code Class 1 component (s) noc conforming to the above requirements, restore the structural integrity of the affected cesponent(s) to within its limit or isciate the affected component (s) prior to increasing the Reactor Coolant Systou temperature more than 50*F above the minimum temperature required by NDT considerations. ,

b. With the structural integrif.y of any ASME Code Class 2 component (s) not confoming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing che Reactor Coolan Syser' 'emperature above 200'F.

- I

c. With - 1 structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit cr isolate the affected component (s) from service.

d. The provisions of Specification 3.0.4 are not applicable.

[

l

! SURVEILLANCE REQUIRDENTS _

4.4.10.1.1 In additio'n to the requirements of Specification 4.0.5, the l l

Reactor Coolant pump flywheels shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14. Revision 1. August 1975.

4.4.10.1.2 In addition to the requirements of Specification 4.0.5, at least i one third of the main seaber to main member velds, joining A572 material, in l the steam generator supports, shall be visually examined during each 40 month

! inspection interval.

l NORTH ANNA - UNIT 2 3/4 4-32 Amendment No. 40 4

~_---.__,__,,.f-.. , - . , . - - , - . _ _ .m_ _ - - _--_..w,_%-. . . , . - . , . , , , - - , - _ - - - ---

s 8-21-80 EMERGENCY CORE COOLING SYSTEMS ECCS SU85YSTEMS - T,y, GREATER M 350*F LIMITING CON 0! TION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERA 8LE with each subsystem comprised of:

a. One OPERA 8LE centrifuga'l charging pump,

b. One OPERA 8LE low head safety injection pump,

c. An OPERA 8LE flow path capable of transferring fluid to the Reactor

, Coolant System when taking suction from the ref aaling water storage tank on a safety infection signal or from the containment sump when suction is transferred during the recirculation phase of operation.

APPLICA8ILITY: MODES 1, 2 and 3. .

ACTION:

a. With one ECCS subsystee inoperable, restore the inoperable subsysten a

to OPERA 8LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

1

b. In the event the ECC5 is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describ-

. ing the ci.*cumstances of the actuation and the total accuelated actuation cycles to date. The current value of the usage factor for each affected safety injection noule shall be provided in this Special Report whenever its value exceeds 0.70.

c. The provisions of Specification 3.0.4 are not applicable to Specifi-cations 3.5.2.a and 3.5.2.b for one hour following heatup above 340*F or prior to cooldown below 340*F.

SURVEILLANCE REQUIREMENTS l

4.5.2 Each ECCS subsystem shall be demonstrated OPERA 8LE:

4. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valve"

, are in the indicated positions with power to the valve operators removed:

f NORTH ANNA - UNIT 2 3/4 5-3

. 1 m _ . , . - . - - - _ -

, s 8-31-80 ENERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

Valve Number Valve Function Valve Position

a. MOV-2890A a. LHSI to hot leg a. closed

b. MOV-28908 b. LHSI to het leg b. closed

c. MOV-2836 c. Ch pump to cold leg c. closed

d. MOV-2669A d. Ch pump to hot leg d. closed

e. MOV-28698 e. Ch pump to het leg e. closed

b. At least once per 31 days by verifying that each valve (sanual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

c. By a visual inspection which veriffes that no loose debris (regs, trash, clothing, etc.) is present in the containment which could be ~

transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall ,

be performed:

g

1. For all accessible areas of the containeent prior to establish-ing CONTAINMENT INTEGRITY, and

2. Of the areas affected within containment, at the completion of each containment entry when CONTAI)#42NT INTEGRITY is established.

d. At least once per 18 months by:

1. A visual inspection of the containment sisep and verifying that i

the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.

e. At least once per 18 months, during shutdown, by:

1. Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal.

2. Verifying that each of the following pumps start automatically upon receipt of a safety injection test signal:

a) Centrifugal charging pump, and b) Low head safat'/ injectionpump.

i NORTH ANNA - UNIT 2 3/4 5-4

. e.

8-21-80 EMER';ENCY CORE COOLING SYSTEMS SURVEIILANCE REQUIREMENTS (Continued)

f. By verifying that each of the following pumps develop the indicated discharge pressure (after subtracting suction pressure) on recirculation flow when tested pursuant to Specification 4.0.5.

1. Centrifugal charging pump greater than or equal rc 2410 psig.

2. Lov head ~ safety injection pump great. than or equal to 156 psig.

g. By verifying that the following manual valves requiring adjustment to prevent pump "runout" and subsequent component damage are locked and tagged in the proper position for injection: (

1. Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following completion of any repositioning or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.

2. At least once per 18 nonths.

1. 2-SI-89 Loop A Cold Leg

2. 2-SI-97 Loop B Cold Leg

3. 2-SI-103 Locp C Cold Leg

4. 2-SI-116 Loop A Hot Leg

. 5. 2-SI-111 Loop B Hot Leg

6. 2-SI-123 Loop C Hot Leg

h. By performing a flow balance test, during shutdown, following completion of modifications to the ECCS subsystems that alter the subsystem flow characteristics ar.d verifying that:

1. For high head safety injection lines, with a single punp l

running:

a) The sum of the injection line flow rates, excluding the

! higheot flow rate, is 2 384 gpa, sud l b) The tot.41 pump flow rate is s 650 gpm.

i 1

i NORTH ANNA - UNIT 2 3/4 5-5 l

'. e.

8-25-86 EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T LESS THAN 350*F ava LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a. One OPERABLE centrifugal charging pump # ,

b. One OPERABLE low head safety injection pump', and

c. An OPERABLE flow path capable of automatically transf arring fluid to the reactor coolant system when taking suction from the refueling kater storage tank or from the containment sump when the suction is transferred during the recirculation phase of operation.

APPLICABILITY: MODE 4.

ACTION:

a. With no ECCS subsystem OPERABLE becausa of the inoperability of f either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within I hour or be in COLD SRUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b. With no ECCS subsystem OPERABLE because of the inoperability of the low head safety injection pump, restore at least one ECCS subsystem to OPERA 3LE status or maintain the Reactor Coolant System T* *8 less than 350'F by use of alternate heat removal methods.

c. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Conunission pursuant to Specification 6.9.2 within 90 days j describing the circumstances of the actuation and the total l

accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

A maximum of one centrifugal charging pump and one low head safety injection pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 340'F.

l l NORTH ANNA - UNIT 2 3/4 5-6 Amendment No. 71 I

a 5-:: .

EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - Tavg LESS THAN 350*F SURVEILLANCE REQUIREMENTS 4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.

4.5.3.2 All charging pumps and safety injection pumps, except the above required OPERABLE pumps, shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the temperature of one or more of the RCS cold legs is less than or equal to 340*F by verifying that the control switch is in the pull to lock position.

i l

l l

I NORTH ANNA - UNIT 2 3/4 5-7

.-- -- _,. -- _. , _ . - ~ . - .___,--, . , , , , _ , - - _ - _ _ _ _ , . - , _ _ , - - ,, --,7,

9-9-n l

EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 BORON INJECTION SYSTEM BORON INJECTION TANK LIMITING CONDITION FOR OPER)710N.

3.5.4.1 The boron injection . tank shall bv OPE"!.8LE with:

a.

A contained borated water volume cf at least 900 gallons,

b. Between 12.950 and 15,750 ppm of boron, and

c. A minimum solution temperature of II5*F.

g APPLICA8ILITY: MODES 1, 2 and 3.

ACTION:

With the boron injectit n tank inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in HOT STAND 8Y and borated to a SHUTDOWN MARGIN equivalent (

to 1.77% ak/k at 200*F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the tank to OPERABLE status within the next 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVE!LLANCE REQUIREMENTS 4.5.4.1 The boron injection tank shall b6 demonstrated OPERABLE by:

a. Verifying the contained borated water volume at least once per 7 days,

b. Verifying the boron concentratton of the water in the tank at least once per 7 days, and

c. Verifying the water temperature at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

NORTH ANNA - UNIT 2 3/4 5-8 Amendment No. 54

---,--r'

6-21-60 REFUELING OPERATIONS RESIOUAL NEAT REMOVAL AND COOLANT CIRCULATION ALL WATIA'LIVELS LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one residual heat removal loop shall be in operation.

APPLICA8ILITY: M00E 6.

ACTION:

a. With less than one residual heat removal loop in operation, except as provided in tr. below, suspend all operations' involving an increase in the reactor decay heat load or a reduction-in boron concentration of the Reactor Coolant Systes. Close all containment penetrations providing direct access from the containmente atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ,

b. The residual heat removal loop say be removed free operation for un- .

, to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

c. The provisions of Specification 3.0.3 are not applicable.

, , SURVEILLANCE REQUIREMENTS 4.9.8.1 A residual heat removal loop shall be determined to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 3000 gpa at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

l I .

l l NORTH ANNA - UNIT 2 3/4 9-9 i

l l

y 8-21-80 REFUE1.!NG OPERATIONS ,

Los WATER LEVEL "LIMITING CON 0! TION FOR OPERATION 3.9.8.2 Two independent Residual Heat Removal (RHR) loops shall be OPERA 8LE."

APPLICA8tLITY: M00E 6 when the water level above the top of the reector pressure vossa.1 flange is less than 23 feet.

ACTION:

a. With less than the required RHR loops OPERA 8LE, inunediately initiate corrective action to return the required RHR loops to OPERA 8LE status as soon as possible.

b. The provisions of Specification 3.0.3 are not applicable.

I l SURVEILLANCE RECUIREMENTS

~

\

i 4.9.8.2 The required Residual Heat Resoval loops shall be determined OPERABLE per Specification 4.0.5.

l l

l

'The normal or emergency power source say be inoperatie for each.RHR loop.

l NORTH ANNA - UNIT 2 3/4 9-9a

p --

Uz.._IUEQ6Y_QE_NUC6g88_EQWE8_ELeNI_gEggeI1gNt _E6MlQSt_8NQ PAGE 32 THERMODYNAMICS

., ANSWERS -- NORTH ANNA 1!42 -SS/02/16-MOORMAN, J

. ANSWER 8.01 (1.00) d REFLRENCE BFNP RANKINE CYCLE LP,P.5,7-8 AND N.A Training Guide NCRODP 83 Section 6.(Pgs 6.21 - 6.27), Objective H KAIP 2.5 193005K103 . . 04 A ' 9 )

ANSWER 5.02 (1.001 d (1.0)

REFERENCE VCS, RT BK III, RT-12, P 17-23, LO 9.

North Anna Training Guide 86.2 Section 4 (Pgs 4.5-4.13), Objective B Westinghouse Nuclear Training Operacions, pp. I-5.66 - 70 KA1P 3.4.

192006K106 ...(KA'S)

ANSWER 5.03 (1.00) b REFERENCE General Physics Heat Transfer and Fluid Flow Fundamentals p 249 AND N.A. Training Guide NCRODP 86.3 Section 3 (Pgs 3.7 - 3.9)

KAIP 2.9 193009K107 ...(KA'S)

ANSWER 5.04 (1.00)

C sff (1.0)

REFERENCE NCRODP-86.2,Section VIII, Objective D 192005K113 ...(KA'S) t i

Uz__ISE98Y_9E_UUGLE68_E9 WEB _EL6NI_9EEB6119Nt_E691D@t_8ND' PAGE 33

'IBEBd99YNed1GE ANSWERS ---- NORTH ANNA 1&2 ~88/02/16-MOORMAN, J ANSWER 5.05 (1.00) d) (1.0)

REFERENCE NCRODP-86.2,Section II, Objective C 001000K526 ...(KA'S)

I ANSWER 5.06 (1.50)

a. DECREASE (0.5)

b. DECREASE (0.5)

c. INCREASE (0.5)

REFERENCE NCRODP 83 Section 8 (Pg 8.17), Objective.D KAIP 3.2, 2.8 ,

191004K106 191004K120 ...(KA'S)

ANSWER 5.07 (1.50)

a. INCREASE (0.5)

b. INCREASE (0.5)

c. DECREASE (0.5)

REFERENCE Systems & Components (North Anna Trainee Reference - See NCRODP - 83)

AND North Anna Lesson Text NCRODP 83 Section 8 (Pgs 8.18-8.19)

Objective E and Section 9 (Pgs 9.5-9.15), Objectives C & D KAIP 2.4, 2.4 191004K104 191004K114 ...(KA'S)

ANSWER 5.08 (2.00)

a. DECREASE (0.5)

b. INCREASE (0.5)

c. INCREASE (0.5)

d. DECREASE (0.5)

REFERENCE Training Guido NCRODP 83 Section 8 (Pgs 8.8 - 8.13) Objective C KAIP 2.3, 2.4 9

I

~Ut__ISEQBY_9E_NUGLE88 E9 WEB _E66NI_9EEB8Il0Nt_ELUIDet_0NQ PAGE 34 ISEBd99YN0 DIGS ANSWERS -- NORTH ANNA 1&2 -88/02/16-MOORMAN, J 191004K105 -191004K114 ...(KA'S)

' ANSWER 5.09 (1.00)

1. Final power REMAINS THE SAME as initial power (0.5)

2. Final Tave will DECRCASE when compared with initial Tave (0.5)

REFERENCE NUS,' Nuclear Energy Training - Reactor Operation N.A Training Guide NCRODP 86.2 Sections 6 & 2 KAIP 3.1, 2.5 000003E104 000003E122 ...(KA*S)

ANSWER 5.10 (1.50) a) INCREASE (0.5) b) DECREASE (0,5) c) DECREASE (0.5)

REFERENCE Surry lesson plan ND-83-LP-8, Rev 1, 191004; K1.14(2.4)

N.A. Training Guide NCRODP 83 Section 8, Objectives B and E KAIP 2.4 191004K114 ...(KA'S)

ANSWER 5.11 (2.00) a) DECREASE (0.5) b) INCREASE (0.5) c) DECREASE- (0.5) d) DECREASE (0.5)

REFERENCE

! NCRODP-96.3,Section II, Objective B 193008K105 ...(KA'S)

ANSWER 5.12 (1.50) a) A (0.5) b) THE SAME (0.5) c) B (0.5)

L

.Di'__IBEQBy_QE_NUQ6E88_EQWEB_E60dI_QEEB811QNt _E6UlQQt_8NQ PAGE 35

-ISEBMQDYN@digQ ANSWERS -- NORTH ANNA 1&2 -88/02/16-MOORMAN, J REFERENCE NCRODP-86.2,Section VII, Objective I i I

192003K101 192008K103 192008K104 ...(KA'S) i l

I l

ANSWER 5.13 (2.00) a) DECREASE (0.5) b) INCREASE ~ (0. 5) c) INCREASE (0.5)

'd) DECREASE (0.5)

REFERENCE NCRODP-86.2,Section VI, Objective B 001000K502 001000K509 192005K107 ... (KA'S)

ANSWER 5.14 (2.00) a) HIGHER THAN (0.5) b) HIGHER THAN (0.5) c) HIGHER THAN (0.5) d) SAME AS (0.5)

REFERENCE NCRODP-86.2,Section VII, Objective I 001010A207 001010K526 192006K110 192006107 ...(KA'S)

ANSWER 5.15 (1.00)

a. FALSE

b. TRUE CO.5 ea.]

REFERENCE General Physics, HT&FF, pp. 155 & 320 and Subcooled Li quid Density Tables AND N.A. Training Guide NCRODP 83 Section 6, Objective H and Section 3, Objective I and Section 8, Objective D KAIP 2.4, 2.3, 3.4 002000K508 193003K102 193004K111 ... (KA'S)

4t__IUEQBY_QE_ NUCLE 86_EQWEB_ELOUI_9EE66II9Nt_ELUIDSt_8ND PAGE 36

>IUEBd99YN8dlCS ANSWERS -- NORTH ANNA 1&2 -88/02/16-MOORMAN, J ANSWER 5.16 (1.50) a) TRUE (0.5) b) FALSE (0.5) c)' FALSE (0.5)

REFERENCE 015000A101 015000K504 193007K106 193007K108 ...(KA'S)

ANSWER 5.17 (1.50)

a. 3 (the preferred answer) OR 4 (acceptable) (0.5)

6. 1 (0.5)

c. 4 (0.5)

REFERENCE Training Guide NCRODP 83 Section 9 (Pgs 9.25 - 9.32), Objectives B & C KAIP 2.5, 2.8, 2.8 193007K101 193008K101 193008K103 ...(KA'S)

ANSWER 5.18 (1.00)

In the secondary system there is a phase change (0.5 pts). A phase change requires a large delta h. With the larger delta h of the secondary, the same heat can be transferred with a lower flow rate (0.5 pts).

REFERENCE General Physics, HT & FF, Section 3.2 AND N.A Training Guide NCRODP 83 Section 1 and NCRODP 86.3 Section 2 KAIP 3.1, 2.5, 2.8, 2.8 002000K501 193005K103 193007K104 193008K101 ...(KA'S)

5:__ISEQBy_QE_NUGLE88_EQWE8_EL8NI_QEEB8119N t _ELylpS &_8ND PAGE 37 ISE80QQYN8 MIGS ANSWERS -- NORTH ANNA 162 -88/02/16-MOORMAN, J ANSWER 5.19 (2.00) 59.6 -N9.2f Tave : -9+:-+ X 0. 25 X - 15 = M pcc (O.4)

Power 25 X -12 = -300 pcm (0.4)

Void - 25 pcm Xenon: - 50 pcm Jotal -489 pcm (0.4)

.s2+2C s8.15 56-60 Baron -A91 / -9 = -5'.P ppm 45- 567 (0.4)

Dilution (0.4) 58.6 GS.25 (NOTE: -154c5 ppm implies the same as W "Dilution" and is acceptable)

(NOTE: Any "error" is to be carried forward)

REFERENCE Westinghouse Nuclear Training Operations, pp. 1-5.27 - 5.36 AND N.A Training Guido NCRODP 86.2 Section 5 (Pgs 5.16 - 5.20) Objectives C &

E KAIP 3.8 192008K120 ...(KA'S)

ANSWER 5.20 (1.00)

P = P(o) 10 Eto the exponent of SUR times TIME (in minutes)]

SUR = log P/P(o) divided by TIME SUR = log 5000/1000 (divided by .5 min)

SUR = log 5 (divided by .5 min)

SUR = .7 (divided by .5 min) = 1.4 DPM (0.5 pts. for using correct equation, 0.5 pts, for answer) (1.0)

(NOTE: Any error" is to be carried forward)

REFERENCE NUS, Nuclear Energy Training - Reactor Operation, p. 6.4-2 Westinghouse Reactor Physics, p. I-3.15 HBR, Reactor Theory, Session 43, p. 3 DPC, Fundamentals of Nuclear Reactor Engineering, p. 94 N.A Training Guide NCRODP 06.1 Section 8 (Pgs 8.12 - 8.13) Objective B KAIP 2.7. 3.2, 2.3 192003K105 192003K106 192003K109 ...(KA'S)

St__ISEQBY_QE_UUCLEGB_EQWE8_EL9NI_QEE68IlgN 1 _ELylQSt_8UD PAGE 38 ISE8MQDYNOMICS ANSWERS -- NORTH ANNA 1&2 -88/02/16-MOORMAN, J Y

$ l'h 0 %"*f g rg M M ed 4k M I M N O'0*f #

Aken anwer is lof.

ANSWER 5.21 (1.00)

TH=r

-'ccg-= 586.8 + 31 (+ or - 2) = 618.8 (+ or - 2) degrees (0.33)

Paat = 2250 psia, Tsat = 653 degrees (0.33)

Subcooling = 653 - 618.8 (+/- 2) degrees = 34.2 (+/-2) degrees (0.33)

(NOTE: Any "error" is to be carried forward)

REFERENCE N.A Precautions, Limitations, and Setpoints AND Steam Tables North Anna Training Guide NCRODP JPM LC036 AND North Anna Training Gui de NCRODP 83 Secti on 3 (Pgs 3.9-3.10), Objectivos C & E KAIP 30, 3.6, 3.9 002000A104 193003K117 193008K115 ...(KA*S)

ANSWER 5.22 (1.00)

The ability to deliver a certain number of amperes for a certain number of hours (before the cell voltage drops to a specific minimum value.)

REFERENCE N.A Training Guide NCRODP 90.3 Section 1 (Pg 1.17), Objective A KAIP 1.9, 3.0 063000A403 063000K501 ...(KA*S)

r 6 1__EL8NI_Sy@IEdS_DEglgN t_CQNIBgL t_8ND_1N@IBydENI8I1QN PAGE 39 ANSWERS -- NORTH ANNA i t<2 -88/02/16-MOORMAN, J ANSWER 6.01 (2.00) 5 at .40 each c,\ add i% g

1. The calculated peak c-,.tc,--1;aa temperature SHALL NOT exceed 2200 degrees F.

2. The maximum cladding oxidation SHALL NOT exceed 17 percent of the total cladding thickness.

3. The calculated total amount of hydrogen generated from the cladding reaction with water SHALL NOT exceed i percent of the amount that would be generated if all cladding surrounding the fuel reacted.

4. Calculated changes in core geometry shall be such that the core remains amenable to cooling.

5. It shall ahve the capability to maintain long term core cooling (reasonable wording accepted)

REFERENCE 10CFR50.46(b) AND North Anna System Training Text NCRODP 91.1 Section 1 (Pg 1.8), Objective A KAIP 4.5 006030A201 ...(KA'S)

ANSWER 6.02 (1.00) b (1.0)

REFERENCE Transparency (T-1.3); Objective Oection 1 ("final" section objective listed) KAIP 2.5 034000K402 ...(KA'S) i

4x__E60NI_SYSIEMS_DEelGN t_CQUI6QLt_8NQ_IN@18UMENI8IlgN -PAGE 40 1

ANSWERS -- NORTH ANNA 1&2 -88/02/16-MOORMAN, J ANSWER .6.03 (2.00)

a. 5 gpm (0.5)

b. 3 gph (0.5)

c. 100 cc/hr (0.5)

d. 3 gpm (0.5) 1 REFERENCE-LObjective C KAI? 3.3 033000K103 ...(KA*S)

ANSWER 6.04 (1.00) a)

REFERENCE North Anna Systems Training Text NCRODP 88.2 Section 1 (Pgs 1.9-1.11),

Obj ective B t< C KAIP 3.4, 3.4, 2.9 005000A402 005000K402 005000K403 ...(KA'S)

ANSWER 6.05 (1.00) c) (1.0)

REFERENCE North Anna Systems Training Text NCRODP 88.3 Section 1 (Pg 1.6),

Obj ective B KAIP 3.3, 3.0 004000K405 004020K403 ...(KA'S)

ANSWER 6.06 (1.00) d) (1.0) t

REFERENCE North Anna Systems Training Text NCRODP 93.2 Section 2, Objective C KAIP 3.0, 4.3, 3.9 ,-

015000A403 015000K405 015000K406 ...(KA*S)

/6 2__eLeNI_gygIgdg_pggigN _GQUIBQ6t_eND_INSIBydgNI8Ilgd t PAGE 41-

ANSWERS - NORTH ANNA 1&2 -88/02/16-MOORMAN,-J ANSWER 6.07 (1.00)

B

-REFERENCE

-NCRODP-80.1, Section 6, Objectives D,I 002000A109 ...(KA'S)-

ANSWER 6.08 (1.50) i a) SUMMED ('3. 30) c) NEITHER (0.30) b) NOT SUMMED (0.30) d) SUMMED (0.30) e) NOT SUMMED (0.30)

REFERENCE North Anna Systems Training Text NCRODP 93.2 Section 1, Objectives E &

G AND Section 2, Objective E KAIP 2.6, 2.9, 3.1 915000K601 015000K603 015000K604 . . . (KA'S)

ANSWER 6.09 (1.50)

.50 each t

a. Non-urgent

b. Urgent

c. Urgent REFERENCE NCRODP-93.5,Section II, Section Objective C 001010K605 ...(KA*S)

ANSWER 6.10 (1.00)

.50 each

a. F

b. F t

h e

,ry,--c%.-r~,.e - _ . , _ . , . , _ . . _ . _ ~

6 t__eLeNI_@ySIEUS_ DESIGNt _CgNIBQ6t_6ND_lNSIBydENI@I1QN PAGE 42 ANSWERS -- NORTH ANNA 1&2 -88/02/16-MOORMAN, J REFERENCE NCRODP-93.2 Section I, Objective D Section II Objective D 1, E.3 015000K406 015000K602 ...(KA'S)

ANSWER 6.11 (2.00)

1. c (0.5)

2. je (0.5)

3. d (0.5)

4. / b(0.5)

REFERENCE North Anna Systems Training Text NCRODP 93.5 Section 2 Part D.2.,

Objective C KAIP 2.6, 3.3, 3.9 001010A301 001010K404 001050K501 ...(KA'S)

ANSWER 6.12 (2.00)

Asy d ea r- N T o f & c gggy of . 5 0 eac(

Bank overlap unit (0.5) MO 7' # U""

P-A converter (e,5) Jn4unq[ n[ arm A</ /WfMd'/

Group step counters (0.5)

S? ave cycler counters (0.5)

(NOTE: Give 0.1 credit for either "Logic cabinet master cycler" or "Internal alarm and memory circuit"; total point value of question is not to be greater than 2.0).

REFERENCE C.1.c, Objective B KAIP 3.0, 3.'

001000G013 001050A403 ..,(KA'S)

6 1__PL8NI_SYSIEMG_QESIGN t_ CONI 6g61_8ND_INGIBUMENI8IION PAGE 43 ANSWERS -- NORTH ANNA 1&2 -88/02/16-MOORMAN, J

().0 0 )

ANSWER 6.13 (.1.d wr7" (0.5 each)

1. Limits blowdown rate of S/G upon main steam line break.

L -R a d u _ m U patc. L. al tF~c,L i v r u u- .., xvcr' .f m r;pu f a 21 -

1 jf. Provides a venturi to permit measurement of steam flow.

REFERENCE North Anna Systems Training Text NCRODP 89.1 Section 1 (Pgs 1.35 L1.5), Objective B and Westinghouse Training Material - S/G and Main Steam KAIP 3.1 035000G007 ...(KA'S)

ANSWER 6.14 (2.50)

- Two Loop Loss Of Flow Reactor Trip -

2/4 power r an g es /. 25) da d #[2- Ia/'ilif (0,5) l above 10% power ( P ->d) BUT less than 30% power (P-8) (1.0) l 7

AND 2/3 fic.4 elements in TWO (2) loops sense (0,5) less than 90% flow in each of the loopt (0.5)

REFERENCE North Anna Systems Training Text NCRODP 93.10 Section 1 (Pg 1.16),

Objective B North Anna Precautions, Limitations, and Setpoints (Pgs 20-22)

KAIP 3.9 012000K402 ...(KA'S)

ANSWER 6.15 (1.00)

This will remove accumulated funi oil and lube all in the exhaust system (1.0)

REFERENCE 1-OP-6.3, p 4 of 6 C64 BOO 40lO ,,,(6A'5)

6t__EL6MIiSYSIEd5_QEgl@Nt_CQUIBQLt_8UQ_INSIBydgNIGIlgN PAGE 44 ANSWERS'-- NORTH ANNA 162 -88/02/16-MOORMAN, J' ANSWER 6.16 (1.50) a.. .RCS pressur'o less than 418 psig (0.5)

b. RCS pressure greater than 582 psig (0.5)

c. Discharge combined flow of all (three) charging pumps. (0.5)

REFERENCE North Anna Systems Training Text NCRODP-88.2 (Rev 3) Pgs 1.4-1.6 & ;

1.11 Obj ective B KAIP 3.2 005000K407 ...(KA'S)

P 3

ANSWER 6.17 (1.00) a) Condensate Storage Tank (CN-TK-2) (0.33) b) Fire Protection Water Main (0.33) and Service Water System (0.33)

REFERENCE North Anna Systems Training Text NCRODP 89.4 Section 2 (Pgs 2.6-2.7), ,

Obj ective D & H; North Anna Technical Specification LCO 3.7.1.3 and Bases KAIP 3.9 i 061000K401 ...(KA'S) 1 ANSWER 6.18 (1.00) r 5

Deboration of the RCS REFERENCE I

B.7 & G KAIP 2.6, 3.4 004020A213 004020K504 ...(KA*S) e l

4 4

. -, - - . - - , . , - - - _ - - e,---- - , - . . _ . _ , . , , , , , - - , , _ , ~ ,.,,.._,--,..-,.--.,-n-.,-.,,-_.-,re,----,,,,-.n,---.n.,-_

n-. - - . - .

bi__EL8NI_@ySIEd@_DE@lgNt_CgNI896,_8dD_18@IBydgNI@IIgN PAGE 45 1 ANSWERS - . NORTH ANNA 1&2 -88/02/16-MOORMAN, J ANSWER 6.19 (1.50)

Gteem dumps will remain closed until header setpoint is reached. .

3

- ( 1. 0)

Dumps (WOULD) cycle open.

(0.5)

NOTE: Any references to Tavg mode of control or.that the dumps would ,

remain shut throughout the transient should. result in point I deduction.

REFERENCE North Anna Systems Training Text NCRODP 93.11 Section 1, Objectives listed KAIP 3.1, 3.3, 3. 2 041900G015 041020A102 041020A302 ...(KA*S)

ANSWER 6.20 (1.00) b) PR Rate Trip - N-42 PR channel not properly reset - 2/4 logic met (Loss of Power to N Neg rate trip B/S "IN" and not reset prior to pulling of N-41 fuses) ,

REFERENCE North Anna Systems Training Text NCRCDP 93.10 Section 1 (Pg 1.11),

Objective B & C AND North Anna Systems Training Text NCRODP 93.2 Section 2, Objective E .

KAIP 3.5, 3.1 015000A201 015000A202 ...(KA'S) l i

I

6 h

1 l

6:__E68NI_@ySIEd@_D@ SIGNt _CQNIBg61_GND_lN@lBydE_NI6110N PAGE 46 ANSWERS -- NORTH ANNA 162 -88/02/16-MOORMAN, J l

l I

ANSWER 6.21 (2.00) a) ... Low DNBR due to adverse combinations of high temperature, low pressure,high flux difference, and power." (1.0)

(NOTE: Give full credit if inference to "low DNBR" is expressed.)

{ cr *preatsk W(5 )

b) ... damage due to excessive reactor power output." (1.0)

(NOTE: Give full credit if inference to "excessive reactor power" ) .

i s (or provileg expressed.8 g g uranet o [mel in4d3NI T)

REFERENCE North Anna Systems Training Text 93.10 Section 1 (Pgs 1.13-1.14),

Objective B KAIP 3.9 012000K402 ...(KA'S)

I fZe PROCEDURES - NORMAL _AENQBMAL t _EMEBGENQY_8NQ t PAGE 47 BODIQL9GIC06_CggIBg6 ,

ANSWERS -- NORTH ANNA 1&2 -88/02/16-MOORMAN, J +

ANSWER 7.01 (1.00) d.)

REFERENCE STANDARD DOSE RATE CALCULATIONS. Virginia Power GET Handbook, ,

194001K103 ...(KA'S)

P ANSWER 7.02 (2.00) -

4 AT'.5 EACH e

1. "hi fluk at shutdown" alarm actuated during fuel movement. ,

2. Lons of audible neutron count rate (< .two tones per minute) with fuel in the core [

t

3. The station evocuation alarm sounds. i

4. Evacuation is announced over the station intercom i

i REFERENCE 1-OP-4.1, p 15.

000036G001 034000G002 ...(KA'S) t ANSWER 7.03 (1.00) a) Shutdown (+.5 ea) I b) Startup i REFERENCE NA TS 3.4.6.2 i OO2000G011 ...(KA'S) f l

r I

ANSWER 7.04 (2.00)

1. F i

2. T

3. F 4 =. F !

F l

i 5

z

Zt__EBQCEQUEES_ _NQBd8(z_8BNQBd86t_EUEBGENCY_8NQ PAGE 48

~ .889196ggIC86_QQNIBQL ANSWERS -- NORTH ANNA 1&2 -88/02/16-MOORMAN, J REFERENCE NCRODP - 95.3 Emergency Response Guidelines, Objective B ANSWER 7.05 (1.50)

( .25) for each swap needed to place in correct order

a. 4 1 32

b. Tha Core Cooling Red Path should be immediately addressed (.25) because it is of higher priority than the Heat Sink Red Path (.25)

REFERENCE NA NCRODP 95.3, Emergency Response Guidelines,Section II, CSF and FRPs, Objective B 001000G015 002000G015 035000G015 103000G015 ...(KA'S)

ANSWER 7.06 (2.50) any 5 @ .50 each CC pump auto trip alarm CCW low flow discharge header alarm CCW low pressura discharge header alarm Reactor coolant pump low flow /high temp alarm Excess letdown HX low flow /high temp Non-regenerative HX high temp REFERENCE NA AP-15, p 2, 10-25-84

-008000G015 ...(KA*S)

ANSWER 7.07 (1.00) all 3 at .33 each If dosimeter: 3/4 of scale off scale any malfunction REFERENCE North Anna GET handbook 194001K103 ...(KA'S)

17t _EBQgEQUBES_ _NQ8d6Lx 9hdQBdQLt_EdEBGEdgy_GUQ PAGE 47 800106991GG6_G9 NIB 96 si i

.$. 4 w2RS -- NORTH ANNA 1&2

-88/02/16-MOORMAN, J

ANSWER 7.08 (2.50) all 5'at .50 each 1.) Identif y and : isolate the . ruptured S/G's 2.) Cooldown the RCS to establish subcooling margin 3.) Depressurize the RCS to restore inventory 4.) Terminate SI 5.) Prepare for cooldown to cold S/D.

REFERENCE .-

NCRODP-95.3 pg 1.23 Section 1 (11-21-86) Section Objective 'C'

,035010A201 ...(KA'S)

ANSWER 7.09 (2.00)

1. RCS pressure - stable or increasing (.50)

2. RCS subcooling greater than 30F (.50)

3. PZR levul greator than 15% (.50)

4. Food flow to intact steam gens. >340 gpm (.25) or NR level in at least one SC >10% (.25)

REFERENCE EP-1, Loss of Reactor or Secondary Coolant ES 1.1 SI Termination NCRODP 95.3 Section I Objectives A,C 006050K401 ...(KA'S) i ANSWER 7.10 (1.00) [

any 4 at .25 each radiological conditions at the job site

- Respiratory protection requirements Anti-C requirements ,

necessary HP coverage .

special instructions Job location brief description of the job t ,

REFERENCE

Virginia Power GET handbook 194001K103 194001K104 ...(KA*S) i.

L

Z c _ _EBgC g D yB F,6._:_UR Bd86 t _89 UO Bd 86 t _E DE 6 g E MQ Y _QNQ PAGE 50 802106901GGL_GRUIB06 ANSWERS -- NORTH ANNA 1&2 -89/02/16-MOORMAN, J (2. 06)

1.LG1 ANSWER 7.11 place rods in manual (.50) place feedwater bypass FCV's in manual (.50) suspend power increases (.25) and rod withdrawal (.25)

W he teatdor h,6 Acigped, o h e.P. 6 C.fo)

REFERENCE 1-AP4.3 015000G014 015000K302 015000K400 ...(KA'S)

ANSWER 7.12 (2.00) all '@ .5 each Verify that 1t least one charging /SI pump is running Place the BATP in fast speed Open MOV-2350 Verify neutron flux-rapidly decreasing t h e cl( pre m rger pecuwre 4 2'5'55 p8g REFERENCE FAP-G.1, Response to Nuclear Power Generation /ATWS 000024K302 0010001014 ...(KA'S)

AN3WER 7.13 (1.50)

ALL 3D .50 EACH

1. place fuel in a safe place (.25) and secure all fuel transfer operations (.25)

2. Evacuate all personnel from the affected area

3. Notify the Heal th Physi cs Dept.

l REFERENCE i 1-AP-30, Fuel Failure During Handling l 034000G014 ...(KA'S) l l

t l

l 1

Z5__EBOCEDUBED_:_UQBdeL>_0kUQB00Lt_EdEBQgNQY_8UQ PAGE 51

,609106991GOL_G9dIB96

-ANSWERS -- NORTH ANNA 1&2 .-88/02/16-MOORMAN, J 5

h ANSWER 7.14 (1.50) any 3 & .50 each

1. Reactor Coolant Pump vibration indication >/= 5 mils soismic (.25) and 20 mils proximate (.25) i

2. RCP Motor current fluctuating

3. RCP bearing temp high

4. RCP oil temp high REFERENCE 1-AP-9, Reactor Coolant Pump Vibration 015017G011. ...(KA'S)

ANSWER 7.15 (1.00)

L This prevents an erroneous flux penality f rom the delta flux program.

REFERENCE North Anna AP-4.3 p. 5 of 10 l 015000A1ES 015000A303 ...(KA'S) t r

ANSWER 7.16 (1.00)

At the last 5 steps prior to the fully inserted position CO.53 jog the control rods in CO.53 REFERENCE North Anna OP-58.2, p 7 of 8 ,

001010K404 ...(KA'S) 1 i ANSWER 7.17 (1.00) ,

4 C1.03 '

The EDG logic has locked out the fire protection system heat rietector REFERENCE 4

North Anna OP 6.3 p. 46

...(KA'S) i 064000G008 1

i

l': Zs.i._P8QQEDURES - NO8dALt_8BNQ8d86t_gdgBQgNQy,,,8NQ PAGE 52 609196901C86_QQNI6QL ANSWERS -- NORTH ANNA i t<2 - -88/02/16-MOCRMAN, J i

i J-

ANSWER 7.18 (1.00) !

Prevent thermal'~ shock and related pump damage or reduce the adverse f offects of RCP seal failure i f

REFERENCE ;

WOG Background Information for ECA-0.0 003000A201 003000G007 ...(VA'S) j.

i ANSWER 7.19 (1.00) ;

To prevent possible void formation in the upper head REFERENCE l WOG Background Information for ES-0.2, p41 002000K515 ...(KA'S) i 1

i I

f f

l t

p t

b

! e l .

! P

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

Ot__0DuldlSIBBIIVE_PBQCEDUBEG t_ggNQ111QUSt_8NQ_(1d11811gNG PAGE 53 ANSWERS -- NORTH ANNA 1&2 -88/92/16-MOORMAN, J ANSWER MP -+ht*et-

[ ( 1. 0) @ ELETED REFERENCE North Anna Nuclear Plant Unit 2 Technical Specifications; Section 3/4, "Limiting Conditions for Operation and Surveillanco Requirements";

Specifications 3.0, 3.4.1.3, 3.4.1.4, 3.5.2 and 3.5.3. NCRODP-88.5 Terminal Objective 1 906000G005 006000G011 ...(VA'S)

ANSWER 8.02 (1.00) d RF "ENCE is R 55.13 194001A103 ...(KA'S)

ANSWER 8.03 (1.00) c.)

REFERENCE ADM-5.8 pg 3 of 10 (08-11-87) NCRODP-100, Terminal Objectives 194001A102 ...(KA'S)

ANSWER 8.04 (1.00) a.)

REFERENCE Nor th Anna TS Def i ni ti on 1.:4, NCRODP-88.3,Section II, Section Objective A 002000G011 ...(KA*S)

ANSWER 8.05 (1.00) b.)

St__GDd101GIBOIIVE_EBQCEQUBE@t_QQUQlIlQd@t_88Q_LIUll811QUQ PAGE $4 ,

ANSWERS 4- NORTH ANNA 1t42 -88/02/16-MOORMAN, J '

1 REFERENCE 10 CFR 50.72 ADM-16.1 Attachmant E (01-20-67), NCRCDP-100, Terminal Objectives ANSWER .8.06 (1.00) ,

b) (1.0) t REFERENCE North Anna Technical Specifications, Section'1.0, Definitions.

012000A301 012000K101 012000K602 012000K605 ...(KA'S)

ANSWER B.07 (1.00) b) (1.0)

REFERENCE Technical Specifications 3/4.7.15, NCRODP-88.5, Terminmal Objectives ,

800067A215 000067G003 000067G007 000067G008 ...(KA'S) ;

ANSWER 8.08 (1.00)

+

c) November 15. (1.0)

REFERENCE North Anna Power Station Technical Specifications Soction 3/4.3, NCRODP-89.5, Terminal Objectives r 012000G011 ...(KA'S) i ANSWER 8.09 (1.00) I a

i REFERENCE ,

-ADM-19.4, NCRODP-100, Terminal Objective 194001A103 ...(KA'S) f Y

W l

t L

1

' 9 __0Dd1UleIBBI1YE_EBgCggysggt_ggug111 gust _sup_ bid 11GI190s PAGE 55 i

ANSWERS -- NORTH. ANNA 1&2 -88/02/16-MOORMAN, J t

ANSWER 8.10 (1.50)

.25 EACH (NOTE

1) "a" 4) "e"

2) " b 5) "c" *

3) "b' 6) "a" REFERENCE t Emergency Response Organization Continuing Training,Section II, Section Objectives G,H,I KAIP 3.1 194001A116- ...(KA*S)

ANSWER 8.11 r

4 t

I hedi0n b' i

l ANSWER 8.12 (1.00)

.33 oath

a. 1) Jumper 2 which aro "complex"

2) jumpers which require multiple steps to complete (reasonable wording accei ited)

b. the shift supervisor REFERENCE ADM-14.1 p 3 of 14 NCRODP-100, Terminal Objectives i

(o H2__6Db1NISIB8IIYE_EB9CEDWBESt_G9dD1II96Si_8ND_biblIBI19NS PAGE 56

-ANSWERS'-- NORTH ANNA 1&2 -GB/02/16-MOORMAN, J ANSWER O.13 (1.50)

.50 each

1. Determine the impact on unit Technical Specifications

2. Assign the task of developing the tags and Tagging Record to qualified personnel

~

3. Identify the boundaries to be tagged, the purpose of the tags and any special considerations.

REFERENCE ADM-14.0 pg 4 of 15 (08-21-87) NCRODP-100, Terminal Objectives 194001K102 ...(KA'S)

ANSWER B.14 ( .50)

Lube oil levels REFERENCE ADM-19.1 pg 2 of 16 (11-05-86) NCRODP-100, Terminal Objectives 194001A106 ...(KA'S)

ANSWER B.15 (1.00)

.50 EACH

1. To verify receipt of an annunicator

2. initiate corrective action in the event of an emergency.

REFERENCE ADM-19.10 pg 1 of 3 (03-31-83) NCRODP-100 Terminal Objectives 194001A103 ...(KA'S)

ANSWER B.16 (1.50)

.50 each 1.) Classifying the emergency 2.) Notifying NRC, State and Local agencies 3.) Authorizing emergency exposure limits k

p . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _

.!l

j et__8DUINISIBOIlyE_E69GEQUBgSz_CgNp1I190gi_88Q_ Lid 1IGI190@ PAGE 57

. ANSWERS -- NORTH ANNA 1&2 -88/02/16-M00RMAN, J REFERENCE North Anna Emergency Plan 5.2.1.1 pg 5.10 (12-04-86) 194001A116 ...(KA'S)

ANSWER 8.17 (1.50)

.50 each The Assistant Station Manager (Operations)

The Superintendent Operations The Superintendent Technical Services REFERENCE North Anna Emergency Plan 5.2.1.1 pg 5.10 (12-04-86) 194001A116 ...(KA'S)

ANSWER 8.18 (1.00)

.5 each

1. When direct verification is not possible

2. When ALARA or other concerns make direct verification impractical REFERENCE ADM 19.17 p4 of 9 194001A103 ...(KA'S)

(/.50 )

ANSWER 8.19 .'?'

f % 50 all y at A vach

1) the moderator temperature coefficient is within the analyzed temperature range

2) the protectivo instrumentation in within its normal operating range

3) the P-12 interl ock is above setpoint

" 4 -

+1e n4 h- .:tg . . . m, UFunsocL '-t;: ai t;, ; t .. m .- , c :; S b 1 '_'

. _? t h c-- w+c- 7m . u 'om=n1 4 r

- b e- ' + itc ,,. n i--i4U T ts rp.

REFERENCE North Anna Operating Procedures 1-OP-1.5, AND North Anna Technical Specification LCO's and Bases 3.1.1.5, AND North Anna Training Lesson Plan NCRODP 86.2 Gection 6 001010K501 001010K506 001010K526 001010K536 ...(KA'S)

I

7-Ha__0DDINESIB8I1YE_EB99EDUBESx_GQNQlIlgNQt_889_LidlIGI1QNQ PAGE 58 ANSWERS -- NORTH ANNA 1&2 -88/02/16-MOORMAN, J ANSWER 8.20 (1.00)

RHR loop shutdown for > 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in 8 while in Mode 6

. REFERENCE North Anna TS 3.9.8.1 NCRODP-CD.5, Terminal Objectives 006000G011 ...(KA*S)-

ANSWER 8.21 (2.00) 1.0 each 1.) 1 GPM for all S/G's.

Ensures that douage contribution in event of SGTR or MSLB im limited to small fraction of 10 CFR 100 limits.

2.) 500 GPD per S/G Ensures tube integrity in the event of a LOCA or MSLB.

REFFRENCE North Anne TS 3.4.6.2 and Basen 000037G004 002000G006 ...(KA'S)

ANSWER 8.22 (1.50)

.50 each a.) Operating the valve in the CLOSE direction for at luast 1 turn, then return the valve to the normal OPEN position.

b.) Visually inspecting the valve to determine if the valve As OPEN.

c.) Proper fuses removed and labeled.

REFERENCE ADM-19.17 pg 1 of 9 (08-14-86) NCRODP-100, Terminal Objectives 194001K101 ... (KA'S)

Oc__09d1NIQIBOIlyE_P8QCgQQBES t_CQNQ1IlgN@t_GNQ_ Lid 1IeI1QNS PAGE 59 ANSWERS -- NORTH ANNA 12<2 -88/02/16-MOORMAN, J ANSWER 8.23 (1.00)

(Restricting thu quantity of radioactivity contained in each gas decay tank provides assurance that) in event of an uncontrolled release of the tank's contents, the resultin0 total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem in an event of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . (1.0)

REFERENCE Technical Specification 3/4.11.2.6, Bases, Gas Storage Tanks, NCRODP-88.5, Terminal Objectives 0710004209 071000G006 ...(KA'S)

ANSWER 8.24 (1.00) a) 4< technical specifications wgne vi ol ated. (0.5)

':,,,m, ,v.,, >' n1,nt mu es t bo in en1 a + m L J u .. r. 10.5) 4, L, _ : c'_n OM .

RtMos; T{S 3 08 dots sof otiouuno4! c ka*J#S (r easwd!! "*'d'\) *"'t 40 NS)

REFERENCE Ncrth Anna Technical Specification 3.4.3.2, 3.0.3, NCRODP-88.5, Terminal Objectives 002000G005 010000G205 ...(KA'S)

ANSWER 8.25 (1.00) a) The unit shall be placed in at least hot standby. (0.5) b) The NRC Operations Center shall be notified (by telephone as soon as possible and in all cases within one hour). (0.5)

REFERENCE North Anna Power Station Technical Specification 6.7., Safety Limit Violation, NCRODP-88.5, Terminal Objectives 002000G003 002000G005 ...(KA'S)

8:_.0Dd1NISIBBIIVE_E8gCEDUSES1 _CONQ1IlgUSt_GUQ_LldlIGIIQUD PAGE 60 ANSWERS -- NORTH ANNA 1242 -88/02/16-M00RMAN, J kANSWER O.26 (1.00) a) Establish a continuous fire watch (0.25) on at least one side of the af f ected penF; ration (0.25)

(or) b) Verify the operability of fire detectors (.20) on at least one side of the nonfunctional fire barrier (0.10) and establish a hourly fire watch patrol (0.20).

REFERENCE U"

NCRODP-89.5, Terminal Objectives 8600 L l ou epf ee a;ce f ($ yn,'+ 2 l$ $(4c, (fre , g }L em,'t;

$ fhW)th A yj % a,g

%f -(eiteJ.s 4 auca , tw.k ..s Ore M o- J I'a5+ "" 5'W < / N wik I L o""

a % c k / peartu h h l

l-

U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _Ng8TU_6NNA_1h2_,,________

REACTOR TYPE: _PWR-WEgg________________

DATE ADMINISTERED _ bbl @2/lb________________

EXAMINER: _MQRGAN t _M_______________

CANDIDATE: _________________________

INSIBUGIlgNS_Ig_CONDIDOIE1 Une separate paper for the answers. Write answers on one side only.

Staple question cheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papern will be picked up cix (6) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY

__YOLUE_ _IGIOL ___SGQGE___ _YGLUE__ ______________CSIEQQBY_____________

_20t@@__ _32t1_ ___________ ________

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW

_2Edl___ _3$t9.. ___________ ________ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS

_3Edl___ _35t__9 ___________ ________ 3. INSTRUMENTS AND CONTROLS

_2Edl_'.._ _35,12 ___________ ________

4. PROCEDllRES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 118jl___ ___________ ________% Totals Final Grade All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

[b Ili

)

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following ru;9s apply

- 1. Cheating on the examination means an automatic denial of your rpplication and could result in more severe penalties.

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

3. Use black ink nr dark pencil gely to facilitate legible reproductions.

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

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

6. Use only the paper provided for answers.

7. . Print your name in the upper right-hand corner of tha first page of gegh section of the answer sheet.

G. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a Ogg page, write go.1,y 90 gag 4Ldg of the paper, and write "Last Page" on the last answer sheet.

9. Number each answer as to category and number, for example, 1.4, 6.3.

I 10. Skip at least th tgg lines between each answer.

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

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

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

I

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

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

l l

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

l

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

l l

1 i

I ;

10. When you complete your examination, you shall:

a. Asraemble your ex ami nati on an follows:

(1) Enam quentions on top.

(2) Exam aidn - figuren, tables, etc.

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

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

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

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

9 J

m

~1t__EB1URIELES_9E_BUGLEBB_E0 WEB _ELGNI_QEg88I10Ut PAGE 2 ISEBUDDXU901GSt_UEGI_IBONDEEB_GUD_ELWID_E69W 4

OUESTION 1.01 (1.00)

Which ONE (1) of the following actions will INCREASE North Anna's thermodynamic cycle officiency?

a. DECREASING power from 100%-to 25% .

b. LOWERING condensor vacuum from 29" to 25".

c. REMOVING a high pressure FW heater from service.

d. INCREASING power from 25% to 100%.

QUESTION 1.02 (1.00)

Which one of the following statements best describes Xenon behavior on a power decreaue, over the first few hours, following 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months at 100% power?

NOTE: EXe3 denotes xenon concentration

a. Direct CXe3 increases, indirect CXe] decreauen, total CXe3 decreases.

b. Direct CXe3 increases, indirect EXe] increases, total CXo3 increases, i c. Direct CXe3 decreases, indirect EXc3 decreases, total i CXe3 decreases.

l

) d. Direct CXe] decreases, indirect CXe3 increases, total CXu3 increases.

e. Direct EXe3 decreases, indirect EXe3 increases, total CXe3 decreases, i

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l l (***** CATEGORY D1 CONTINUED ON NEXT PAGE * ***4) ;

i

,,--~,.--n-., c- . - . _ . - - - .

, - , - . - - . , . , , . , , -- .-n-, ,---.n,,,,-,-.., n.- - ,. . - - - - - - , . . - . . - - ,

k

-it_iEBINCIELES_DE_SUGLEGB_E99EB_EL8UI_0EEB8I19dt PAGE 3 -

ISEBb99YU851 cst _bEGI_IB8USEEB_GUD_ELUID_EL9W o :

l OUESTION 1.03 (1.00)

Which ONE (1) of the f ollowing describes reason for the height correction factor, K(2), used in the huat flux hot channel factor calculation?

a. K(Z) compensates for the increased coolant temperatures that occur higher in the coolant channels.

b. K(Z) takes into account that there is some delay in 1 refilling the core completely f ollowing a small break 3 LOCA.

c. K(Z) in an uncertainty factor to allow for conservatism since we cannot accuately measure flow in the core,

d. K(Z) allows for greater power production in the upper

= regions of the core near the end of life due to axial flux shifting.

QUESTION 1.04 (1.50)

Indicate whether each of the following will INCREASE, DECREASE, or HAVE NO EFFECT on the available (actual) Not Positive Suction Head (NPSH).

I

a. Increasing pump flow rate

b. Increasing pump cuttion temperature

c. Increasing total system pressure

j. QUESTION 1.05 (1.50)

The reactor is operating at 25% power when one RCP trips.

Acuuming that no reactor trip or turbine load change occur,

! indicate whether each of the following parameters will INCREASE, l DECREASE, or REMAIN THE SAME.

j

a. Flow in operating reactor coolant loops

b. Core delta T

c. Operating loop steam generator pressure 1

i

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

i t

lt _ _EB10G1 ELE S _Q E _ U LJ G L E O S _E0W E B _EL O UI_0 E E601109 t PAGE 4 IUEBUQDYUG01GDt_UEGI ISQUEEEB_00D_ELVID_ELOW-OUESTION 1.06 (2.00)

.A motor driven centrif ugal pump is operating at rated flow. You than start shutting the discharge valvo. State if each of the following will INCREASE, DECREASE, or REMAIN THE SAME.

c. Flow (0.5)

b. Discharge Pressure (0.5)

c. Differential Pressure Across The Pump (0.5)

d. Motor Amps (0.5)

QUESTION 1.07 (1.00)

The reactor is operating at 50% power with the rod control cystem in MANUAL when a single Group A rod drops into the core.

Assuming no reacto.- trip or operator actions occurt

1) Will final reactor power INCREASE, DECREASE or REMAIN THE SAME when compared to initial reactor power? (0,5)

2) Will final Tavo INCREASE, DECREASE or REMAIN THE SAME when compared to initial Tave? (0.5)

OUESTION 1.08 (1.50)

THREE (3) reactor coolant pumps (RCP's) are operating in parallel, EACH having an individual pump flow rate "m" and all THREE (3) having a total (combined) flow rate "M".

a) If ONE (1) RCP is secured the OPERATING RCP's individual flow rates "m" will (INCREASE, DECREASE, REMAIN THE SAME).

b) IF ONE (1) RCP is secured and the other TWO (2) RCP*o remain operating, the total (combined) flow rate "M" will (INCREASE, DECREASE, REMAIN THE SAME).

c) IF ONE (1) RCP is secured and the other TWO (2) RCP's remain operating, the Delta-P (Differential Pressure) across the reactor core will (INCREASE, DECREASE, REMAIN THE SAME).

($4*46 CATEGORY 01 CONTINUED ON NEXT PAGE *****)

la__EBINGIELES_9E_UUGLEGB_E0bEB_ELSUI_9EE8011Dui PAGE 5 IUEBd9DXUGU1GSt _UEGI_IBOUSEEB_0ND_ELUID_ELOW OUESTION 1.09 (1.50)

~

Indicate whether each of the following statements concerning rod worth are TRUE or' FALSE.

a. One reason f or overlapping rod groups is to minimi:e the effects of rod shadowing on total rod worth,

b. Both an increase in RCS temperature AND a buildup of fission product poisons will DECREASE rod worth.

l' c. The maximum differential rod worth occurs at the point where the integral rod worth is-maximum.

QUESTION 1.10 (1.00) j TRUE or FALSE for oach of the followings

a. During a RCS heatup, as temperature gets higher, it will take a smaller letdown flow rate to maintain a constant 1 pressurizer level.

b. Increasing condensate depression (subcooling) will cause DOTH a decreano'in plant efficiency AND an increano in condensate (hotwell) pump available NPSH.

4

) QUESTION 1.11 (1.50) i i

Indicate whether each of the following statements concerning Xenon 135 (Xe-135) are TRUE or FALSE.

a) FOLLOWING A REACTOR TRIP, the peak value of Xe-135 and j the time to reach the peak value condition depends on j the initial equilibrium Xe-135 concentration.

b) FOLLOWING A REACTOR TRIP, the Xe-135 has essentially

)

j "decayed away" some 60 to 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months after event.

c) FOLLOWING A STEP DECREASE IN REACTOR POWER from 30 percent to 20 percent power, the Xe-135 reacti vi ty reachen an equilibrium value some 40 to 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months after the step change.

s

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1&__E81NGIELES_0E_UUGLE98_ERWEB_ELBNI_9EEBBI19Ni PAGE 6 IUEBb99YN001GSt_MEDI_IG005EEB_8ND_ELUID ELOW -

QUESTION 1.12 (1.50) :

Match the heat transfer process in Column A to the equation that opplies to that process in Column B. ,

COLUMN A COLUMN B

a. Between cold leg and hot leg- 1. O=UA (delta T) of reactor (normal FC flow)

2. O = lbm (delta T)

b. Across S/G tubes (primary to secondary) 3. O = lbm c (delta T) l

c. Across S/G (feedwater to steam) 4. O = lbm (delta h)

5. O = lbm c (delta h)

L QUESTION 1.13 (2.00) !

C Match the term in column A with the correct definition in column [

B.

Column A Column B t a) Specific Entropy 1) BTU / lbm-dog R [

b) DNDR 2) Ratio of local O to to CHF :

i l i

c) Quality 3) Internal energy of a ;

substance d) Enthalphy r

4) % steam mass to total !

steam and w-'ter mass

5) BTU / deg F 6

6) Ratio of cri ti cal O to :

l oc al O

7) Internal Energy plus Flow [

! Energy of a substance ;

i

0) O/(delta T) lbm [

t

9) % steam volume to total h steam and water volume ,

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.e-r..r .--,r,--.,_m_._-.--,#.. ..- . . . . ._ , , , . _ ,_ _ . _ - _ , , . .

li__EBING1ELES_DE_UUGLEBB_EDWEB_ELBUI_QEEBBIlgN t PAGE 7 IEEBdQQYU0dlGet_UEGI_IBONSEEB_SUO_ELUID_ELQW OUESTION 1.14 (1.00)

Primary system flow rate is many times greater than secondary syUtem flow rate while the heat transf urred by tt e two systems is eauentially the same. Explain how this is possible.

QUESTION 1.15 (1.00)

How many gallons of boric acid must be added to the RCS in order to add a (-)2200 pcm of roactivity prior to plant cooldown?

Assume present boron concentration = 1000 ppm (DOL condition),

500 degrees F and differential boron worth (DDW) = (-)7.6 pcm.

NOTE: Use attached nomograph Figures 1.1, 1.2 and 1.3.

QUESTION 1.16 (1.00)

What is the quality of a 540 degree F vapor-liquid mixture whose specific enthalpy is 1175 BTU /lbm?

OUESTION 1.17 (2.00)

Given the following, calculate the required boron change to increase reactor power f rom 75% to 100% While maintai ning constant rod position.

(NOTE: Denote whether the "boron change" required is a "boration" or "dilution" AS WELL AS the "amount" of change)

Moderator Temperature Coefficient -15 pcm/degr ere Doppler-only Power Coefficient -12 pcm/% power Void Reactivity change -25 pcm Xenon change -50 pcm Doron Coefficient - 9 pcm/ ppm OUESTION 1.18 (1.00)

If reactor power increasen from 1000 cps to 5000 cps in 30 seconds, what in the SUR7 SHOW ALL WORK

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it._EBINGIELED_DE_UUGLEGB_E9 WEB _ELONI_QEgBOI1QUt PAGE B !

IUEBd99YUGUIGD4_UEGI_IBOUSEEB_0ND_ELUIP_ELQW l I

i "OUESTION 1.19 (1.00) !

If North Anna Unit 1 reactor is operating at 100% power with Tave

= Truf, CALCULATE the RCS subcooling margin. !

l 1

QUESTION 1.20 (2.00) i i

a. CALCULATE the amount of reactivity (in pcm) required to !

increase Koff from 0.97 to 0.985. SHOW ALL WORV !

.i

b. By what= factor will a COUNT RATE chango as a result of j increasing Keff from 0.97 to 0.985? SHOW ALL WORK [

t OUESTION 1.21 (1.00) i North Anna's station batteries are rated at 1650 ampere-hours. ,

DEFINE the term "ampero-hour". ,

OUESTION 1.22 (2.00) ;

DEFINE "Axial Flux Difference" AND "Quadrant Power Tilt Ratio". j r

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{ ($**** END OF CATEGORY 01 *****) !

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4 2a__ELGUI_ DES 10N_INGLUDIUQ_HOEEIY_GND_EDEBGEUGY_SYDIEUS PAGE -9 OUEGTION 2.01 (1.00)

Which CNE (1) of the following flowpaths best describes how power is normally supplied to a typical vi t al 120 VAC bus.

a. 480 VhC from vital bus, rectified to 125 VOC, inverted to 118-120 VAC, and supplied to vital 120 VAC bus,

b. 480 VAC from vital bus, rectified to 118-120 VAC, and supplied to the 120 VAC instrument bus,

c. 480 VAC from vital bus, transformed to 118-120 VAC, and supplied to vital 120 VAC bus.

d. 125 VDC from battery, supplied to battery bus, rectified to 118-120 VAC, and supplied to vital 120 VAC bus.

QUES 110N 2.02 (1.00)

Which DNE (1) of the following statements describing the design of the fuel transfer tube is correct?

a. A blind flange in used to close the transfer tube on i

BOTH the containment side and the spent fuol side.

b. A blind flange is used to close the transfer tube on j the containment side and a valvo is used on the spent t

fuct side.

l l c. A valve is used to close the transfer tube on the i contairment side and a blind flange is used on the

! Epent fuel side.

d. A valve is used to close the transfer tube on BOTH the

! containment side and the spent fuel side.

I i.

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2&- ELONI DgSION_INGLUDIUQ_S6Egly_6UD_gdgBQgNCy_SYSIEMS PAGE .10 OUESTION 2.03 (1.00)

Match the RCP_ seal finw paths in Column 4 to the appropriate design flow rate in Column B.

COLUMN A COLUMN B

a. Down chaft into the RCS 1. 10 cc/hr

2. 100 cc/br

b. #2 seal leakage 3. 3 gph

4. 5 gph

c. #3 seal leakage 5. 3 gpm

6. 5 gpm

d. Through radial bearing and #1 seal OUESTION 2.04 (t.00)

Which ONE (1) of the following completes thin statement:

"During plant cooldown, FLOW from the RHR to the RCS is designed to be...:

! a) ... constant (around 4000 gpm) AND this total flow is i maintained by controlling RHR heat exchanger flow l bypass valve (FCV-1605)".

l b) ... constant (cround 4000 gpm) AND this flow is maintained by controlling the RHR heat exchanger outlet valve (HCV-1758)."

l c) ... varied (to a flow that meets the desired cooldown rate) AND this flow is maintained by controlling the RHR heat exchanger flow bypass valve (FCV-1605) . "

l l d) ... varied (to a flow that meets the desired cooldown rate) AND this flow is maintained by controlling the RHR heat exchanger outlet valve (HCV-1750)."

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2x__ELOUI_DEG100_10CLUD100_S8EEIX 8BD_EbESDEUGY_HYSIEUS PAGE 11 i

QUESTION 2.05 (2.00) l l

YRUE or FALSE (For each of the following signals) .- The given {

i s i g n a l ~, independent of any other signal, WILL automatically trip 4

SHUT the main feodwater regulating valves (FCV-1478, 1488, 1498) ,

AND their bypassen (FCV-1479, 1489, 1499), t a) P-14, steam generator Hi-Hi Lovel (2 of 3 narrow-range level detectors greater than 75 porcont on 1 of 3 steam

. generators).

b) Low Tavg.(auctioneered high) as sensed by either-train A or train B of reactor protection.

t c) Reactor Trip (1 of 2 Rn trip.breakern with its bypass breaker open).

d) Any plant condition that actuates safety injection.

J c

0 l

OUESTION 2.06 (2.00) i l TRUE or FALSE 1

a) Completo train separation i s maintained at all times in the I Component Cooling (CC) Water System.

b) A Component Cooling Water Surge tank, when isolated, is protected from a vacuum by a rupture disk.

l c) Component Cooling water passes through the shell side of j the CC heat e>! changer and heat is rejected to "tube-side i Service Water System fluid.

d) The relief valvo downstream of the CC heat exchariger I relieves at 2500 psig - this protects the cystem from RCP "thermal barrier pressure".

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PAGE 12 L2a._ELONI_ DES 100_10CLUDING_S8EEIY_6UD_EUEBQEUGY_DYSIEUS QUESTION 2.07 (1.25)

Match the Reactor Coolant System (RCS ) penetrationn in Column A to the correct locations in Column D.

COLUMN A COLUMN B

a. PZR Spray Line 1. Loop 1 Hot Leg

. :2. Loop 2 Hot Leg

b. CVCS Letdown 3. Loop 3 Hot Leg

4. Loop 1 Cold Leg

c. RHR Cooldown Suction 5. Loop 2 Cold Leg

6. Loop 3 Cold Log

d. P:r Surge Lino QUESTION 2.08 (2.50)

LIST the FIVE (5) Emergency Coro Cooling System (ECCS) engineering design criteria.

QUESTION 2.09 (1.00)

State the TWO (2) d i est.1 engine / generator shutdown signals that are enabled (maintained) during an emergency start of the diesol?

OUESTION 2.10 (2.00)

If the TWO (2) Rod Control Startup Pushbuttons were mistakenly depressud to "Reset" the system during mode 1 operation, what FOUR (4) components in the rod control syctem would have to be restored to the proper setting?

QUESTION 2.11 (2.00)

One of the purposes of North Anna's Critical Safety Functions is to ensure that the plant's "multiplo barriers" remain antact and that the policy of "defense in depth" in maintcined. What are these FOUR (4) "multiple barriors"?

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

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iF f.1si5iEL9BI_ DES 10N_IUGLUDIUD_20EEIX_GUD_EUEB9@iGY_SYSIEUS PAGE 13 !

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C

[

-QUESTION 2.12 .(1.50) !

h ) List THREE'(3) saf ety design f unctions of the Steam Generator i t

Steam Flow Rostrictor,

!L

) DUESTION 2.13 (1.50) i With respect to the Residual Heat Removal (RHRi systemt a) What interlock (condition) must be met prior to opening the .

I RHR inint line isolation valvos (1700 or 1701)7 (inc1' udo uetpoint) (0.5) j b) What interlock (condi ti on) will automatically close the RHR inlet line isolation valves? (include setpoint) (0.5) l I

c) What is the basin-of the RHR inlet line relief valve ,

capacity? (0.5) l i

i

) OUESTION 2.14 (2.25)

What si gnal (u) /condi ti on (s) must be present for an AUTOMATIC switchover of the suction of the RHR system from the RWST to the :

4 containment sumps to occur?

4 Give setpoint(s) and coincidenco(s) if applicabic.

l QUESTION 2.15 (2.50) i

a. What are thrco reasons f or having/ maintaining Rod Insertion I

Limitu? (1.5)

I J

r 1 b. With respect to the Rod Insertion Limits, "...the steamlinn l 1 break acc. dent imposes the highest shutdown margin l J requirement." Explain why this is a true statement. (1.00) {

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2t__ELONI=.QEU10N 1NGLUDidG_SGEEIY_QUQ_EdE60ENGY_SYSIEUS PAGE. 14' f i

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OUESTION 2.16 (2.00) j State the motive force (driving force) for the RCS through the !

following:

k 1. PZR Spray Lines 4

2. Th RTD manifold '

i

3. Tc RTD manifold

4. Au>tiliary PZR Spray Linn

}

i.

i QUESTION 2.17 (2.50) ;

]

In regard to the Emergency Condentate Storage Tank (ECST): }

1 !

a) State th> bases for the storage tank minimum water volume {

requirement.

b) What in the "backup" to the ECST (by Technical l Specification) if the ECST is considered to bo INOPERABLE 7 ;

i

! c) LIST TWO (2) sources of water which may be available (and j that are "tied in" DIRECTLY) to the AFW pump nuctions in the :

I event the ECST IS NOT available. i j -

!' t DUESTION 2.18 (1.00) !

l l What in the effect, 2f any, on Peactor Coolant System chemistry ;

j if an unsaturated bed of H-CH renin was placed in servi ce?

O

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(***** END OF CATEGORY 02 **64*)

3z__1USIBUdEUIS_6UQ_CQUIBOLS PAGE 15 OUESTION 3.01 (1.00)

From the FOUR (4) statements below,- select the ONE (1) utatement that IS NOT a consequence of placing the "LEVEL TRIP" switch, on the source range drawer, in the BYPASS position. Refer to Figure 3-2 as an aid.

a) Continuous power is fed to the RPS to maintain voltage to UV coils.

b) The OPERATION SELECTOR switch is "enabled" (capable of being used).

c) The LEVEL TRIP DYPASS indicating lamp, on the drawer, is illuminated.

d) The C ANNEL ON TEST indicating lamp, on the drawer, is illuminated.

QUESTION 3.02 (1.00)

Which ONE (1) of the following correctly completes the next sentence?

"By preventing the letdown isolation valves from opening or shutting - unless all three orifice isolation valves are shut -

we prevent.."

a) ... exceeding design flow rates of the demineralizers."

b) ... excessive heatup rates across the regen. heat exchanger."

c) ... excessive pressure on the shell of the regen. heat g

exchanger."

l d) ... unnecessary lifting of relief valvos downstream of

! the orifices."

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4t__INGIBUDEUIS_GND_QQNIBQLS PAGE 16

- OUESTION 3.03 (2.50)

For each of the following circuits, STATE:

1)' "NOT SUMMED" if it receives a signal directly from the upper or lower Power Range Detector (i . e. ; no summing of signal s involved)

2) "SUMMED" if it receives a signal directly from the summing and level amplifier circuitry

3) "NEITHER" if it DOES NOT receive either the individual detector nor the summing / level amplifior signal a) P-13 (Turb. Plant "At Power") input d) Low Power Trip b) OT Delta T Calculation e) High Power Trip c) Channel Current Comparator f) Detector Current Comparator QUESTION 3.04 (1.25)

Match the following conditions with the expected indication .

provided by the rod speed indication meter. (NOTE: The rod speeds listed may be used in more than one condition.)

1) Rods in AUTO with a 4 degree a) O steps / min F temperature mismatch.

2) Rods in AUTO with a 1 degree b) 8 steps / min F temperature mismatch.

3) Rods in AUTO with one of the c) 40 steps / min Tave control instruments failed LOW.

d) 48 steps / min

4) Rode in MANUAL with a 10 degree F temp mismatch e) 72 steps / rain

5) Rods in AUTO with no temp mismatch. Immediately before f) 76 steps / min an operator removes N44 fuses due to a failed hi PR detector.

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

~31__IUSIBUdENIS_ONQ_GQUIBQLD PAGE 17-QUESTION 3.05 (1.50)

Match the following SIX (6) Incore Detector Selector Switch positions with the condition which best describes the function of the position.

1) OFF a) 5-path rotary transfer device is positioned to originally designated 10-path rotary device,

2) NORMAL b) 5 path rotary transfar device is positioned to next seq.tentially

3) CALIBRATE lettered 10 path device.

4) EMERGENCY c) 5-path rotary transf er .ievice is positioned to shielded concrete) holding area.

5) COMMON GROUP d) 5 path rotary transfer dtvice is posi ti oned to C "10-path rotary

6) STORAGE transfer device.

e) 5-path rotary transfer device is positioned to normal 10 path rotary device - ability to move detector is inhibited.

, f) 5 path rotary transfer device is positioned to normal 10-path tube f or adjustment - ability to move detector varies as calibration proceeds.

g) 5-path rotary transfer device is positioned to wyn units for movement into adjustment tube / path.

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Iz__INSIBUUE.UIS_GUD_GQNIBQLS , PAGE 18 QUESTION 3.06 (1.25)

MATCH the f ollowing ',tatements with the appropriate Nuclear Instrumentation Sy'4com (i'f a,y) listed. (NOTE: A single system may apply to more than_one statement.)

a) Uses an "opposi ng-current" techni que to 1) Source Range eliminate the ef f ects of gamma radiation.

2) ' Intermediate

- Range b) Operates in the Proportional reginn of the Gas-filled Detector curve. 3)-Power Range c) Uses "pulse-height discrimination" 4) Neither the techni que to eliminate the of f ects Source, of gamma radiation. Intermediate nor Power Range d) Covers eight (8) decades of noutron flux.

e) , Shares a common instrument thimble but only covers the lower core area.

QUESTION 3.07 (2.50) a) List the FOUR (4) plant parameter input signals to the Overtemperature Delta-T (OT delte T) protection circuit. ;

(1.0) b) List the circui t logics / coincidences and variable / calculated setpoints associated with:

l l 1) The Overtemperature Delta-T Reactor Trip (0,5) i

! 2) The Overtemperature Delta-T Control 'nterlock "C-3" (0.5) c) What occurn upon actuation of the Overtemperature Delta-T Control Interlock "C-3"? (0.5) l OUESTION 3.08 (2.50)

List the instrument coincidence, setpoints AND flow sensing "conditions" required for a "Loss of Flow in TWO (2) RCS Loopn" reactor trip.

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34__luSIBudEUIS_GND_G9BIBQLS PAGE 19 OUESTION 3,09 (2.30)

. List the logic coincidence associated with each of the following Reactor Protection and Control Signals.

a) Permissive - Coincidence of Intermediate Range (IR) required to DLOCK P-6 Source Range (SR) high flux trin during an approach to power.

b) Permissive - Coincidence of IR required to UNBLOCK SR high flux trip P-6 during shutdown.

c) Control. Interlock - Coincidence of IR required to stop outward rod motion C-1 (Hi Flux Rod Stop).

d) Control Interlock - Coincidence of Power Range (PR) required ,

'to stop C-2 outward rod motion (Hi Flux Rod Stop).

e) Reactor Trip - Coincidence required to for a high PZR prossure PZR HI PRESSURE Reactor Trip.

QUESTION 3.10 (1.50)

LIST the pressuriter (PZR) pressure CONTROL or PROTECTIVE ACTION for the following control and protecticn sotpoints.

a) 2385 psig b) 2335 psig c) 2230 psig d) 2210 psig e) 2000 psig f) 1765 psig QUESTION. 3.11 (1.00)

When containment pressure increases to 27.75 psia (3/4 channels) a CDA si gn -1 is generated. What FOUR (4) major components in the Quench Sprey System (DS) react to thi s signal and how do they respond to the signal?

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

4t__INSIBUMENIS_GNQ_GQNIBQLS' PAGE 20 QUESTION 3.12 '(2. 00)

Wide Range temperature instruments have a control input to the NDT Protection Circuitry. List TWO (2) reasons why the Narrow

' Range temperature instruments-are NOT desirable for use in this ciruitry?

OUESTION '3.13 (1.00)

What plant parameter is used to generate / calculate the reference level in the Pressurizer (PZR) Level Program?

QUESTION 3.14 (1.50)

The plant is generating 800 MWe and the steam dump system is inadvertently left in the ETEAM PRESSURE CONTROL MODE of operation ("pot" is set to maintain header pressure at 1005 psig). The loss of a Mai n Feedwater Pump requires an immediate power reduction to 400 MWe ar.d produces a 12 degree Tref - Tavg error.

Using Figure 3-1.for guidance, DESCRIBE how the steam dump system would react to the given situation AND STATE if the dumps WOULD/WOULD NOT open in response to the transi ent.

OUESTION 3.15 (1.50)

The plant han just completed a startup, output breakers are shut, the steam dump system is in the Tavg mode of operation and load is being increased from 120 MWe to approximately 300 MWe, The plant experienceu a Turbine Trip / Reactor Trip due to a loss of condenser vacuum.

Using Figure 3-1 for guidance, DESCRIBE how the steam dump system would react to the given situation AND STATE if the dumps WOULD/WOULD NOT open in response to the transient.

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1,.__INSIBUMEUIS_GND_GOUIBQL@ PAGE 21 OUESTION 3.16 (1.00)

With the unit holding at 30% reactor power, instrument maintenance ~ (IM) personnel receive permission to perform a calibration on the power range (PR) channel N-41. The IM mechanic mistakenly pulls the instrument power fuses to PR channel: N-42 and suddenly realizing the error, reinsorts the N-42

, fuses. The mechanic then pulls the fuses for channel N the reactor trips.

STATE the reason for the reactor trip.

QUESTION 3.17 (2.00)

- Cornpl ete the following statements:

a) "The OT (Overtemp) Delta T calculated reactor trip setpoint is designed to protect the core from ... " (1.0) b) "The GP (Overpress) Delta T calculated reactor trip setp' int is designed to protect the core from ..."(1.0)

QUESTION 3.18 (2,50)

Gi ven the f ollowing, LIST, in the correct order, the "proper" components contained within the Source Range (SR) instrument signal processing string.

- SOME COMPONENTS LISTED BELOW ARE NOT PART OF THE PROCESSING STRING -

(NOTE: End the processing string with SR level meter)

SR Detector Pulse Shaper Log Pulse Integrator Pre-Amplifier SR Level Meter Discriminator Pulne Counter Level Amplifier Log Level Amplifier Pulse Driver Pulse Amplifier Blocking Circuit (Crowbar)

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

ida__EBQGEQUBEQ_ _N9Bd86t_GDUQBd8Lt_EdEBGENGY_GNQ .PAGE '22

-B3D1969[11G86_G9dIB96

.OUESTION 4.01 (1.00)

The only, people allowed to manipulate any control'that'directly affects. reactivity or power.lovel are those who are:

a) ... in a training status to qualify for a reactor operating license,IN AN ABNORMAL OR EMERGENCY CONDITION ONLY.

b) ... in a training status to qualify for a' reactor operating license, or those holding an NRC RO or SRO

_ license c) ... management or technical non-licensed persons providing plant support functions in their field of expertise, WITH RO/SRO APPROVAL d) ... in a training status to qualify for a reactor or senior reactor operati ng license - that are.under direct F licensed operator supervision - or those holding an NRC RO or SRO license OUESTION- 4.02 (1.00)

The only people who have the authority to direct the Control Room Operator (CRO) . performing operations that affect power level or core reactivity are a) Only those holding an SRO license i

b) Only North Anna management personnel and those holding an SRO license c) Only NRC perscinel and those i Iding an SRO license d) Only NRC personnel and those holding either an RO or SRO l, license i

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jdz__EBOGEDUBES_:_UDBUBLi_8BNgBM86t_GUEBGENCY_8UD 'PAGE _23

-88D196991G86_G9dIB06

.UUESTION 4.03 (1.00)

Pressurizer PORV' leakage would fall under which one of the

. f ollowing Technical Specification leakage classifications?

a) IDENTIFIED LEAKAGE b)-' PRESSURE BOUNDARY LEAKAGE c) CONTROLLED LEAKAGE d) UNISOLABLE LEAKAGE e) NONE OF THE ABOVE QUESTION 4.04 (1.00)

Which .ONE (1).of the following most accurately defined by the following. statement?:

"A _________________________________ is the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors."

a) CHANNEL CALIBRATION b) CHANNEL CMECK c) CHANNEL FUNCTIONAL TEST d) CHANNEL QUALITATIVE ASSESSMEMT e) CHANNEL SIMULATION TEST

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di__EB9GEDUBES_:_N9Bdebt_0DN9BdGLt_EdEBgENgy_6NQ PAGE 24 809196991GOL_GQNIBQL OUESTION. 4.05 (1.00)

Procedure ~1-ES-0.2D "Natural Circulation Cooldown Without Shroud .

Cooling Fans", cautions the operator -> "DO NOT depressurize the plant below 400 psig before the entire RCS is less than 200 degrees F when conducting a Natural Circulation cooldown." The reason for this is to... (choose one):

a) ... reduce combined therma / pressure stresses on the reactor vessel."

b) ... prevent void formation in the reactor vessel."

c) ...be within design transients specified in Sec. 5 of the Tech Specs."

d) ... prevent the reactor vessel from entering a condition susceptible to brittle. fracture."

(***** CATEGORY 04 CONTINUF.D ON NEXT PAGE *****)

4 16t__BBgggDUBES_ _ NORMAL1 _0969BMAl _gMEBQgNQX;8NQ t PAGE 25

'88DIOLOO1G86_GONIB06

! QUESTION 4.06 (1.50)

Matchf the f acility with the most appropriate purpose / description (NOTE: The facility /conter.may have more than one description / purpose)-

a) Technical Support Center- (TSC) __ 1) Used to continually evaluateand coordinato b)-Operations, Support Center (OSC) activities related to the emergency. Located

.c) Local Media Center (LMC) adjacent to the Training Bldg. Recovery

.d) Local Emergency Ops Facility (LEOF) operations shall be

! managed from this

j. e) Emergency Control Center (ECC) facility.

ll .

2) Located in the THIRD (3rd) floor

- conference room of the Maintenance Building.

__ 3) Fire Team members

. report to this area to augment the on-shift a Fire Team. Remain in

, this area until I services are needed.

2

, __ 4) The Control Room is designated as the

______.._ upon activation of North Anna's Emergency Plan.

3) Located approx. SIX (6) miles f rom the site at Mineral Vol. Fire Dept Public Meeting Hall.

- Public information i personnel are briefed by VEPCO management.

__ 6) Contains I nstrumentation to denote station status to those responsible for engneering ant' management support.

Located adjacent to Unit 1 Control Room.

(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

r i

di__EBOGEDUBEE :_NDEd8(t_8Byg8d66t_EdE8ggNgy_8NQ PAGE 26 BG0106091G06 GOUIBOL

. QUESTION .4.07 (1.50) a) FILL IN THE BLANKS (Numbers Only - NO.explainations.

of exceptions are necessary)

- Minimum shift crew composition -

With Unit'in~ Mode 5 or 6'or Defueled Posi ti on Number of individuals requised to fill position Modes 1, 2, 3, and 4 Modes 5 and 6 SS ___ ___

SRO ___ ___

RO ___ ___

AO ___ ___

STA ___ ___

- - - - - - - - - - - - - . . - - - - - - - - - ~ ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

b) (TRUE or FALSE)

"Except for the Shift Supervisor (SS) AND the Shift Technical Advisor (STA), the Shift Crew Composition may be-one less than the. minimum requirements of Table 6.2-1 (in Technical Specifications) for an indefinite period of time in order to accommodate unexpected absente of on-duty shift crew members...".

1

(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

t t

l

-t.

3t__EB9GEDURES - NORMAL 1_8DNQBd8L _EMEBGENgy_8ND 1 PAGE 27 B8D196991G8L_GONI696 QUESTION 4.08 (1.00)

Compl'ete'the following statements concerning Refualing operations by filling in the correct number.

a) At least ______ feet of water shall be mrintained over the top of the reactor (Rx) vessel flange during movement of fuel assemblics. (0.25) h) No movement of irradiated fuel in the reactor shall be accomplished until the reactor has been subtritical for a period of at least _____ hours. (0.25) c) The baron concentration of all filled' portions of the Reactor Coolant System, the refueling cavity, and the rofueling canal shall be maintained .... to ensure that Keff is less than or equal to _____ or greater than or equal to ________ ppm. (0.5)

-Ot!ESTION 4.09 (2.00)

FILL IN THE BLANKS (Number and Units)

According to Technical Specifications, North Anna is to minimize (l i mi t ) the primary-to-secondary leakage to (NOTE: Denote exact values of the amount by "less than", "greater than" and/or "equal to" symbols) through any ONE (1) Steam Generator AND

[< >m3 (amount) (unit)

(0.05) (0.20) (0.25) i

________ ________ ______ TOTAL for all Steam Generators

-(0.05) (0.20) (0.25)

HOWEVER; in accordance with Standing Order #155 (Rev 2 - November i 10, 1987) the following limits are "in force" and are consistent l with PT-46.2, "Primary-To-Secondary Leak Rate Determination" test criteria from an i ndi vi dual Steam Generator AND (0.05) (0.20) (0.25)

________ ________ ______ TOTAL leakage (0.05) ( 0. '40 ) (0.25)

(**itt CATEGORY 04 CONTINUED ON NEXT PAGE *****)

t

c ds__PBgggDUBgS_ _NQBUGL1_GQUgBMGgt_gdg8GgygY_80p PAGE 28 68D196991006_G9bfB96 QUESTION 4.10 ( 1. 00 )'

According to North Anna's Emergency Plan, what are.the TWO (2) situations which would warrent the augmentation of the on-shift Emergency Organization? (i . e. ; When would the Station Emergency Manager commerice call out for supplementary emergency response personnel?)

OUESTION 4.11 (2.00) n) The Emergency Procedures "Critical Safety Functions" have an order of importance (priority) associated with and assigned to them. Rearrange the Safety Functions below in descending order of importance. (NOTE: Assign M1 to thE function of highest priority, followed by #2, etc...)

Containment Heat Sink Subcriticality Inventory Core Cooling Integrity b) What is the purpose of "Color Coding" the Critical Safety Functions?

OUESTION 4.12 (1.00)

According to ADM-19.10, "Limitations on Licensed Personnel

. Movement", a Control Room Operator SHALL NOT leave the "work" area without obtaining quali fied r elief - with the exception of TWO (2) situations. LIST the TWO (2) situations ("instances")

when a Control Room Operator can leave the work area WITHOUT obtaining a qualified relief.

QUESTION 4.13 (2.00)

LIST the FOUR (4) SI Terminati on Cri teria as stated in 1- EP-1 "Loss of Reactoror Secondary Coolant" and 1-ES-1.1 "S1 Termination".

(*'**** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

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- - , . ~ , . .

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

ist__EBQCgDUBEgi ;UQBdGL1_GDNgBd661_gdg8Ggdgy_GNQ '

.PAGE: 29

~BGD196091CGL_LOUIB06 1 (OUESTION 4.14 (2.00)

LIST FOUR - (4) of the FIVE (5) High Level Logics for EP-3, Steam

,3enerator Tube Rupture.

OUES' TION '4.15 - (2.00)

Immediate Action Step 4 of FRP-S.1, "Response to Nuclear Power Generation /ATWS" instructs the operator to "Initiate Emergency Boration of RCG:". LIST the actions required to accomplish this-step.-

i OUESTION 4.16 (1.00)

In accordance with 1-AP-9, ' Reactor Coolant Pump Vibration *, !

one indication of excessive Reactor Coolant Pump vibration is ' Reactor Coolant Pump Vibration Danger Annunciator'.

LIST TWO (2) of the FOUR (4) remaining indications as ,

specified by 1-AP-9.

OUESTION 4.17 (2.00)

Concerning North Anna Operating Procedures 1-OP-1.5, "Unit Startup From Hot Standby Condition (Mode 3) To Startup Condition (Mode 1) With Reactor Critical At Less Than Or Equal To 5 Percent Power"'AND 1-OP-58.2 "Full Length Control Rod Operation"; STATE the reason / bases for the f ollowing "notes"/ precautions a) "The Shutdown Rod Banks must be veri fied f ully withdrawn t within 15 minutes PRIOR to withdrawal of ANY rods in control banks A,B,C, OR D during approach to Reactor ;

criticality." (1.0) 1 b) "Rods must always be withdrawn in the prescribed -

sequence; SBA then SBB then CBA then CBB then CBC then CBD with proper bank overlap except during special test or withdrawing a dropped rod." (1.0) :

1 t :

?

e l (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

?

I I l

dt__EBQGEgyBE@_ _NQBdQLg_GENOBdGLt_gdgEGENGy_GNQ PAGE 30 B0010L901G06_GOUISQL QUESTION 4.18 (2.00)

Concerning North Anna Operating Procedures 1-OP-1.5, "Unit Startup From Hot Standby Condition (Mode 3) To Startup Condition (Mode 2) With Reactor Critical At ess Than Or Equal To.5 Percent

. Power"; STATE FOUR (4) of the FIVE (5) bases +or the following "note"/ precaution:

"The lowest operating Reactor Coolant Icop Tavg must be greater than or equal to 541 degroes F within 15 minutes PRIOR to achieving reactor triticality."

QUESTION 4.19 (1.00)

Why does T.S. (3.5.1) require THREE (3) SI Accumulators to be "on-line" when the contents of only TWO (2) Accumulators need be injected in order to partially cover the core?

QUESTION 4.20 (1.50)

In regard to thu Waste Gas (WG) Disposal System:

!- a. Techni cal Specification LCO 3.11.2.o governs the quantity of radioactive material in the WG Disposal Tanks to <

_..______ _________ of Noble Gas.

(amount) (units) (0.5)

b. Why would we restrict the quantity of radioactive material contained in the WG Disposal Tanks? (0.5) i c. Technical Speci fication LCO 3.11.2.5 limits the concentration of oxygen in the WG Disposal Tanks, at all timen, to less than or equal to TWO (2) percent by volume whenever the hydrogen concentration exceedo FOUR (4)

E percent less than 96 percent by volume.

l l Why limit the oxygen concentration in the WG Disposal

! Tanks 7 (0.5)

I i

(***** CATEGDRY 04 CONTINUED ON NEXT PAGE *****)

k

!$t__E89 QED (JRES' -' UQBd861_8DNOBM86t_EdgBGENQy_8ND PAGE' 31 BBDIOLOGIGGL_GQNIBQL J

QUESTION 4.21 (1.50)

Given the followinO "out-of-order" procedural tasks, NUMBER them in the proper sequence that would be required to parallel a diesel generator to a live bus.

STEP NUMBER. TASK Turn the synchronizer switch to the "ON" position.

Start the EDG.

Turn the synchronizer switch to the "OFF" position.

Operate the governor (speed) cont r ol suitch so that the synchroscope moves slowly in the fast direction.

Close the generator output breaker when the '

synchroscope needle passes the 11 o' clock position.

Operate the exciter control switch to match incoming voltage to running voltage.

1 b

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

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

r

--- NRC NOP.TH ANNA REACTOR OPERATOR EXAM -- ,,

. 1-SC-2.2

. . FIGURE l-1 Page 1 of 1 09-27-85 s .. 700 o 3000 600 2500 500 2000 400 2500 1500 300 1200 1000 200 700 150 2000 500 N ' 100 VB " 8 13 I"I12.950-Cf 12.950-Ci }

~

1500 000 -

Whe re -

' M = mass of liquid

in RCS (LBS) 50 200

... 40

-- - ~~ ~ ' - 1000 Cf =~ final desired boron .

concentration (PPM) 30 100 20 500 50 100 10 10 -

l BORIC ACID PPM BORON C L T VOLUME, GAL ADDITION I

(Cj )

(VB) (Cf - Cj) l BORON ADDITION (Referfactors correction to following) TABLE for APPROVED BY: . .

Chaiman Station Nuclear Safety and Operating Comittee

[

l l

~

,, l, , , ,

-- NRC NORTI: ANNA REACTOR OPERATOR EXAM - ,

FIGURE l-2 1-SC-2.3 Page 1 of 1 09-27-85 s

L 10 100 300 20

~

250 ---

15 500 200 180 160 -

140 10 9

1000 120 -

dC 8 g = 500X g (12,950-C) _

100 7 90 -

g -- 6

- 1500 70~ 5 Where:

60 -

M = mass of liquid 4 in RCS (LBS) 50 2000 40 3 30 2

2500 20

, 3000 i PPM BORON IN BORON ADDITION BORIC ACID COOLANT RATE, PPM /HR FLOW, GPM (C) (dC/dt) (X)

BORON ADDITION RATE (Refer to following TABLE for correction factors) f APPROVED BY: ,

Chainnan Station Nuclear Safety and Operating Comittee

F 1

-- NRC NORTH ANNA REACTOR OPERATO'l EXA'! -" 1-SC-2.6 08-25-76 FIGURE 1 -3 Page 1 of 1

~

s NOM 0 GRAPH CORRECTION FACTORS Plant Conditions s Correction Factor Pressure T (AVG) (K)

(psig) , (*F) Pressurizer Level (See Note) 2235 547-570 Normal Operating 1.00 1600 500 No-Load 1.05 1200 45^ No-Load 1.10 800 400 No-Load 1.16 400 350 No-Load 1.18 400 300 No-Load 1.20 400 300 Solid Water ,

1.35

~, 400 200 No-Load 1.28

-'- 400 200 Solid Water 1.40 400 100 Solid Water 1.47 NOTE: CORRECTION FACTORS ARE APPLIED. AS FOLLOWS:

(n) Boron Addition and Dilution Total Volum Nomor,raphs

~ *

(Corrected) (Nomograph)

(b) Boron Addition and Dilution Race Nonograph.*

(Corrected) (Nonog ra ph)

=

f. x.

l APPROVED BY: h'd CHM 9AN STATION NUCLEAR SAFETY l AND OPERATING COMMITTEE 4

LOAO MEJECT TUDOINC T RIP ~

300 GANKO I U04 OAOK ,

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n __ CONTROLLER PRESS / TEMP /Teve CONT NOT DEDU NDANT g 3, g.p y --> 1 1*F A T' ~ > 1 0** A T W REDU'NDANT AT ( > 2 0*F A T ) PW 4 4 8 +d 6 y

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2/3 (P - 12 ) TURBlNE TtvG 2/3 T AVG TRIP i

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O1 O1 TEMP.

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, PRESS TCV-MS TCV-MS (n o r m a lly d o en e r giz e d) y 408 408 DEMAND . '

BNDIC ATOR A.G,C,D, AA8 STM.

E.F.G & H SOV SOV SOV DUMP I O T E S: 1 -T R AIN A OPERATES SOV 1 (H BUS) S S-TRAIN 8 OPERATES SOV 2 (J SUS) SUPP 2-STEAM DUMP VALVES ARE P O SITIO N E R TO A B R -T O-O P E N. VENT WENT CONDENSERS B00 STERN "

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1m__EBING1ELES_DE_UUGLEGB_E9 WEB _ELGUI_QEEB8IlgN,. PAGE 32 IUEBdQ9YN0 DIGSt _UEGI_IB8USEgB_8NQ_ELylp_ELQW ANSWERS -- NORTH ANNA i t<2 -88/02/16-MORGAN, M ANSWER 1.01 (1.00) d REFERENCE BFNP RANKINE CYCLE LP,P.5,7-8 AND N.A Training Guide NCRODP B3

'Section 6 (Pgs6.21 - 6.27), Objective H KAIP 2.5 193005K103 ...(KA*S)

ANSWER 1.02 (1.00) d (1.0)

REFERENCE VCS, RT BK III, RT-12, P 17-23, LO 9.

North Anna Training Guide 86.2 Section 4 (Pgs 4.5-4.13),

Objective B Westinghouse Nuclear Training Operations, pp. 1-5.66

- 70 KAIP 3.4.

192006K106 ...(KA*S)

ANSWER 1.03 (1.00) b REFERENCE General Physics Heat Transfer and Fluid Flow Fundamentals p 249 AND N.A. Training Guido NCRODP 86.3 Section 3 (Pos 3.7 - 3.9)

KAIP 2.9 193009K107 ...(KA'S)

ANSWER 1.04 (1.50)

a. DECREASE (0,5)

b. DECREASE (0.5)

c. INCREASE (0.5)

I REFERENCE l General Physics, H 7 t4 F F , p. 320 AND N.A Training Guide NCRODP 83

! Section 8 (Pg 8.17), Objective D KAIP 3.2, 2.8 191004K106 191004K120 ...(KA*S)

t 12__EBIBCleLEg_gE_UyCLEGB_EQWEB_ELGNI_QEEBGIlgN S PAGE 33 ISESUDDYUGd1GS1_UEGI_IBOUSEEB_8ND_ELUID_ELOW ANSWERS -- NORTH ANNA 162 -88/02/16-MORGAN, M ANSWER 1.05 (1.50)

a. INCREASE (0,5)

b. INCREASE (0.5)

c. DECREASE (0.5)

REFERENCE General Physics, HT and FF - Fluid Flow Applications f or Systems and Components (No-th Anna Trainee Ref erence - See NCRODP - 83)

.AND North Anna Lesson Text NCRODP 83 Section 8 (Pos 8.18-8.19)

Objective E and Section 9 (Pgs 9.5-9.15) Objectives C and D KAIP 2.4, 2.4 191004K104 191004K114 ...(KA'S)

ANSWER 1.06 (2.00)

a. DECREASE (0.5)

b. INCREASE (0.5)

c. INCREASE (0.5)

d. DECREASE (0.5) >

REFERENCE General Physics, HT and FF, pp. 319 - 334 AND N. A Training G:.ide NCRODP B3 Section 8 (Pos 8.8 - 8.13) Objective C KAIP 2.3, 2.4 ,

191004K105 191004K114 ...(KA'S)

ANSWER 1.07 (1.00)

1. Final power REMAINS THE SAME as initial power (0,5)

2. Final Tave will DECREASE when compared with initial Tave (0.5) ;

REFERENCE NUS, Nuclear Energy Training - Reactor Operation i N.A Training Guide NCRODP 86.2 Sections 6 and 2 KAIP 3.1, 2.5 000003E104 000003E122 ...(KA'S) 1

r

-1m__ESIUGleLg8_DE_UUCLge8_egggB_eLeUI_gegBeI1gN2 PAGE 34

'IMEBd9DYU8b1GSt_bgeI_IBeOSEgB_8UD_ELUID_EL9W

. Ab3 /4ERS --' NORTH ANNA 1&2 -88/02/16-MORGAN, M l ANSWER 1.08 (1.50) a)' INCREASE (0.5) b) DECREASE.(0.5)-

c)' DECREASE (0.5)

REFERENCE Surry l essen plan ND-83-LP-8, Rev 1, 191004; K1.14(2.4)

N.A. Training Guide NCRODP 83 Section 8, Objectives B and E KAIP 2.4 191004K114 ...(KA'S)

ANSWER 1.09 (1.50)

a. FALSE (0.5)

b. FALSE (0.5)

c. FALSE (0.5)

REFERENCE Westinghouse Nuclear' Training Operations, p. I-5.36 - 43 N.A. Training Guide NCRODP 86.2 Section 6, Objective B KAIP 2.8, 3.5 001000K505 102005K105 ...(KA'S)

ANSWER 1.10 (1.00)

a. FALSE

b. TRUE CO.5 ea.]

REFERENCE General Physics, HTLFF, pp. 155 and 320 and Subcooled Li quid

-Density Tables AND N.A. Training Guide NCRODP 83 Section 6, Objective H and Section 3, Objective I and Section 8, Objective D KAIP 2.4, 2.3, 3.4 002000K508 193003K102 193004K111 ...(KA*S) 4 x

Elz__EBINQIELES_QE_Ugg(E8B_EQWEB_EL8NI_QEEB8IIQUt PAGE 35 IUEBUgQyN8dIGSt_UE81_IB8NEEEB_8UD_ELUID_ELOW ANSWERS - ' NORTH ANNA 1&2 -8G/02/16-MORGAN, M ANSWER 1.11- (1.50)

a. TRUE (0.5)

b. TRUE (0.5)

.c. TRUE (0.5)

REFERENCE Westinghouse Nuclear Training Operatic.ns, p. I-5.36 - 43 N.A. Trair.2ng Guide NCRODP 86.2 Section 4 (Pgs 4.6-4.8),

Objective B KAIP 3.4

'192006K106 ...(KA*S)

ANSWER 1.12 (1.50)

a. 3 (the preferred answer) OR 4 (acceptable) (0.5)

b. 1 (0.5)

c. 4 (0.5)

' REFERENCE General Physics, HT and FF, pp. 180 and 181 AND N.A Training Guide NCRODP 83 Section 9 (Pgs 9.25 - 9.32), Objectives B and C KAIP 2.5, 2.8, 2.8 193007K101 193008K101 193008K103 ...(KA'S)

ANSWER 1.13 (2.00)

.a) 1 (0.5) b) 6 (0,5) c) 4 (0.5) d) 7 (0.5)

REFERENCE Surry lesson plan ND-83-LP-(1-10) AND N.si Training Guide NCRODP 83 Sections 1 Objective J and Section 2, Objective J KAIP 2.9, 2.3, 2.3, 2.3 l 193003K113 193003K118 193003K119 193008K110 ...(KA'S)

~- . , _ .

I

lt__EBIUCIELES_OE_UUCLEGB_EOWEB_EL8NI_OEE89I1092 PAGE 36 ISEBOODXU001GSt_BE91_IB9NSEEB_90g_ELylp_ELgW ANSWERS -- NORTH ANNA 1242 -88/02/16-MORGAN, M ANSWER 1.14 (1.00)

In the secondary system there in a phase change (0.5 pts). A phase change requires a large delta h. With the larger delta h of the secondary, the came heat can be transferred with a lower flow rate (0.5 pts).

REFERENCE General Physics, HT and FF, Section 3.2 AND N.A Training Guide NCRODP G3 Section 1 and NCRODP 86.3 Section 2 KAIP 3.1, 2.5, 2.8, 2.8 002000K501 193005K103 193007K204 193008K101 ...(KA'S)

ANSWER 1.15 (1.00)

-2200 pcm

___________ u Baron addition DBW (0.25)

-2200 pcm

= Boron addition (0.25)

-7.6 pcm ppm 1

= approximately 289.5 ppm ' 'ni ng nomograph: this would ruquire an approximate add of 1200x21.05 +/- 50) gallons of Doric Acid. (0.5)

(ERROR CARRIED FORWARD)

REFERENCE N.A. Training Guide NCRODP 86.2 Section 5 (Pgs 5.21-5.22),

Objective DN.A. Training Guide NCRODP JPM LC-010 AND Ops Pr ocedur e 1-OP--8. 3 and Stati on Curve book kAIP 3.O, 7.2 004000A402 004000K506 ...(KA'S) l l

m l

1 It__E81NGIELES_QE_NyGLE88_EgWE8_ELOUI_QEEB8IlgN t PAGE 37 ISEBdgQyN8MIGSt_SEGI_IB8NSEEB_8NQ_ELylD_ELgN

-ANSWERS -- NORTH ANNA 1&2 -88/02/16-MORGAN, M ANSWER 1.16 (1.00)

. h = h (f ) + X h(f g) where X = percent quality steam X = h - h (f) divided by h (f g) 1175 - 536.8 (enthalphy at 0% quality - 540 degrees F) = 638.2 (0.33) 638.2 divided by 657.5 (diff between sat. liq enthalphy and sat.

vapor) (0.33)

= .9706 or 97% (+/- 1%) (0.33)

(NOTE: Any "error" is to be carried forward)

REFERENCE Steam Tables AND N.A Training Guide NCRODP 83 Section 6 (Pgs 6.39-6.40), Objective G KAIP 3.3 193003K125 ...(KA'S) r ANSWER 1.17 (2.00)

Tave : 39.8 X 0.25 X -15 = -149. 25. pc m (0.4)

Powers 25 X -12 = -300 pcm (0.4)

Void - 25 pcm Xenon: - 50 pcm i

Total -524.25 pcm (0.4)

Baron: -524.25 / -9 = 58.25 ppm (56-60) (0.4)

Dilution (0.4)

(NOTE: -58.'25' ppm implies the same as 58.25 "Dilution" and is acceptabic)

(NOTE: Any "crror" in to be carried forward)

REFERENCE

, Westinghouse Nuclear Training Operations, pp. 1-5.27 - 5.36 AND N.A Training Guide NCRODP 86.2 Section 5 (Pgn 5.16 - 5.20)

Objectives C and E KAIP 3.8 192008K120 ...(KA'5)

Lic__EBldGIELES_DE_UUGLEGB_E0 WEB _ELGNI_QEEbnIlgth- PAGE 38

'IBESd99XNQUlGSS_UEGI_lBOUSEEB_QNQ_EbylL_E(QW ANBWERS -- NORTH ANNA 1842 -88/02/16-MORGAN, M ANSMER 1.18 (1.00)

P = P(o) 10 (to the exponent of SUR times TIME - it 4 minutes)

SUR = log P/P(o) divided oy TIME SUR = 109.5000/1000 (divided by . 5 min)

SUR = log 5 (divided by .5 min)

SUR = .7 (divided by .5 min) = 1.4 C'M (2.5 ptsi. for using correct equation, 0.5 pts. for an swer ) ( 1. 0)

, (NOTE: Any "error" is to be carried forward)

REFERENCE ,

NUS, Nuclear Snorgy Training - Reactor Operation, p. 6.4-2 Westinghousu Reactor Physics, p. I-3.15 :

HDR, Reacter Thuory, Session 43, p. 3 DPC, Fundamental s of Nuclear Reactor Engineering, p. 94 N.A Training Guide NCRODP 86.1 Section 8 (Pos 8.12 - 8.13)

. Objective B i KAIP 2.7, 3.2, 2.3 192603K105 192003K106 72003K109 ...(KA'S) f ANSWER 1.!9 (1.00)

Tavo = 586.8 + 31 (+ or - 2) = 618.8 (+ or - 2) degeces (0.33)

Psat = 2250 psi a, Ttat = 653 degrees (0.33) 4 Subcooling = 653 - 618.8 (+ or - 2) degrees = 34.2 (+ or -2) degrees ~(0.33)

(NOTE: Any "error" is to be carried forward)

REFERENCE

, N.A Precautions, Limitations, and Sotpoints AND Steam Tables l Nt '

Anna Training 'ui de NCROUP JPM LCO3r AND No-th Anna ning G ,7 NCRODP 83 Section 3 (Pgs 3.9-3.10), Objectives C E

l 3 9 L -

193003K117 193008K115 ...(KA'S)

- '.on 1.19. IF assumption is stated that "ICCM" of 635 F J. " .,uple temperaturn is used, THEN an answer of 18 y subeiol-f

. .11owable.

t 1

li_rtBIOGIELES_DE_UUGLE88_E9 WEB _EL8UI_9EEB8I1961 PAGE 39 IUEBM90%U8dIGDt_UEBI_IB8UEEEB_GUD_ELUID_EL9W ANSWERS -- NORTH ANNA.1&2 -88/02/16-MORGAN, M i i

a ANSWER 1.20 (2.00) -i a) Delta reactivity = K(f ) -

K (o) divided by K(f ) X K(o) i Delta reactivity = .985 - .970 / ( . 985) ( . 970)

Delta reactivity = .015699 X 1100,0001 = 1569.9 (+/- 5) pcm

-(Calculation worth 0.5 and answer worth 0.5) b) Counts final ./ Counts initial = 1 -

Keff initial / 1'- Keff

-final C (f ) /C (o)- = Count Rate Change Count Rate Change = 1 --Keff initial / 1 - Keff final Count Rate Change = 1 -

.970 / 1 - .985 ,

1

= .030 / .015 = TWO (2) 4 a factor of TWO (2) - or "double" (Calculation warth 0.1 and answer worth 0.5)

(NOTE: Any

error" is to be carried forward)

REFERENCE

, Westinghouse Theory Review AND North Anna Training Guido NCRODP 06.2 Section 7, Objectives C and D AND NCRODP 86.1 Section 6, i Objective E

! KAIP 2.2, 2.7 l 192003K101 192003K102 ...(KA'S)

ANSWER 1.21 (1.00)

The abilitv to deliver a certain number of amperes for a certain number of hours .

A REFERENCE N.A Trathing Guidu NCRODP 90.3 Section 1 (Pg 1.17), Oojective A KAIP 1.9, 3.0 063000A403- 063000K501 ...(KA'S)

m a

~

nit __EBINGIELED_DE_UUGLEAR PgsgB_ELgNI_DEEBOI1ON t PAGE: - 40 3 IUEBURDYNGU1GSz_UEGI_IBGUSEEB_86D_ELUID_ELQH

-LANSWERS ~~ NORTH ANNA 1&2 ~88/02/16-MORGAN, M I

' ANSWER 1.22. (2.00)

Axial Flux Difference - "the difference in normalized flux signals, expressed in percent of RATED THERMAL POWER between. the top: and bottom halves of a TWO section excore neutron ,

detector" - (1.0)

'Duadrant Power - - "the ratio of the maximum upper excore detector Tilt Ratio calibrated output to the average of the, upper encore detector i calibrated outputs (0.4) .OR; the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs -r (0.4) whichever i s greater. (0.2) !

r (NOTE: the OPTR definition goes on to say "With one excore *

, detector inoperable, the remaining three detectors shall be used l

for computing the average"; HOWEVER; this IS NOT nacessary for full credit) ,

REFERENCE N.A. Technical Spe;ification Section 1; "Defini ti onn" AND North Anna PT 1-PT-20.1 AND 1-PT-23 KAIP 3.0, 2.9 ,

, Guido NCRODP PT 192005K110 192005K113 ...(KA'S)

. I l

t 4

I i

f r

i $

1 e

k 4 , ,, ,,s- .,,,-,-----n.- , - , . . . . , - . - . , . . . , , , , - . . , .n..,,.,,,,.n , ,_, , . , , , e, -a,-,., --n - . . - , - . , - - , ,

2i__ELeb!_DESIRB_IUCLUDING_SOEEIY_GUD_EdE69ENCY_SY@IEOS: ' PAGE' 41 .

ANSWERS --_NORTHLANNA 1&2 -88/02/16-MORGAN, .M' ;

t i

' ANSWER 2.01 (1.00)'

I

,- a-(1.0) i REFERENCE- _

North Anna Systems Text NCRODP-90.3 (Hov-1) section i .( Pg s 1. 0 --

1.21), Objectiven-A and b

-KAIP 2.4 062000K409 ...(KA'S) 4 i

ANSWER 2.02 (1.00) 4 b (1.0)

REFERENCE North Anna-System Training Text NCRODP-91.2 Part C.6(b) and ;

Transparency (T-1.3); Objective Section 1 ("f inal" section ;

objective listed KAIP 2.5 .

034000K402 ...(KA'S) _!

t ANSWER 2.03 (1.00)

a. 6 (0.25)

b. 3 (0. 25) -

. c. 2 (0.25)

d. 5 (0. 25) i REFERENCE

. North Anna Systems Training Tnat NCRODP 88.1; Sectian 3, Objectivu C -

KAIP 3.3

I 003000K103 ...(KA'S)

I

!. ANSWER 2.04 (1.00) i a) -

t j HEFERENCE f North Anna Systems Training Tuat NCRODP 88.2 Section 1 (Pgs i I

1.9-1.11), Objective D ar.d C KAIP 3.4, 3.4, 2.9 i

l-

?

E

,,--r-,,w..,w-.,r.--r,%r.,,,-,3,,~,, w ,y_-. - .

2t__ELOUI_0ES100_1UCLVDINQ_S8EEIY_86D_EdEBggdGY_EY@lEUS' PAGE 42 ANSWERS -- NORTH ANNA it<2 -88/02/16-MORGAN, M 005000A402 005000K402 005000K403 ...(KA'S)

ANSWER 2.05 (2.00) a) TRUE (0.5) b) FALSE (0.5) c) FALSE (0.5) d) TRUE (0.5)

REFERENCE North Anna Systems Training Text NCRODP 89.4 Ustction 1 (Pgs 1.10-1.11), Objective F and G KAIP 3.2, 3.4 059000K412 059000K419 ...(KA'S)

ANSWER 2.06 (2.00) i' a) FALSE (0.5) b) FALSE (0.5) c) TRUE (0.5) d) FALSE 10,5)

REFERENCE North Anna Systems Plant Manual Volume i System Description 12-7 North Anna Operations Procedure (s) 1-OP-51 and 1-OP-51.1 l KAIP 3.3 008000G007 ...(KA*S)

ANSWER 2.07 (1.25) l l a. 4 and 6 (0.5)

! b. 4 (0.25)

c. 1 (0.25)

d. 3 (0.25)

REFERENCE North Anna Systems Training Texts NCRODP B0.1, 80.2 and 88.3 AND Drawings 11715-FM 093A (all three sheets)

KAIP 3 7, 4. 1, 4.5 002000K106 007000K100 002000K109 ...(KA*S)

24.__ELGUI_DED190 10GLVDIUO_SGEElLOUD_EUEBOE UGX_SYSIgd5 PAGE 43 ANSWERS -- NOR_TH- ANNA it<2 -38/02/16-MORGAN, M

' ANSWER 2.08' (2.50)

1) The calculated peak CLAD temperature SHALL NOT exceed 2200 degreen F. (0.5)

2) The maximum cladding oxtdation SHAtL NOT exceed 17 percent of the total cladding thicknnss. (0.5)

5) The calculated total amount of hydrogen generated from the cladding reaction with water SHALL NOT exceed 1 percent of the hypothotical amount that would be generated if all cladding surrounding fuel reacted. (0.5)

4) Calculated changes in core geometry shall be such that the core r emains amenable to cooling. (0.5)

5) After any calculated nuccessful initial operation of the ECCS, the calculated core temp shall be maintained at an acceptably low value and decay heat shall be removed for (an) ret tended peri od of time... -- Long Term Cooling. (0.5) ,

REFERENCE 10CFR50.46(b) AND North Anna System Tratning Text NCRODP 91.1 Section 1-(Pg 1.0), Objective A KAIP 4.5 006030A201 ...(KA'S)

ANSWER 2.09 (i.00)

Accept any TWO (2) of the following (worth 0.5 each)

1. Di enel Overspeed.

2. Generator Differential. -'

3. Emergency Stop Manual Pushbuttons REFERENCE North Anna Gystems Training Text NCRODP 90.4 Sect i >n 2 (Pg 2.24),

Objective C KAIP 3.9 064000K401 ...(LA*S)

I

- 8,;__ELOUI_ DES 10t!_10GLUDIUQ_SOEEIL8BD_EUEEGEUGLEXSIEd5 PAGE 44 ANSWERS -- NORTH-fNNA 1 t<2 -88/02/16-MORGAN, M ANSWER - 2.10 (2.00) .i Any FOUR (4) of the following (worth 0.5 each)

Bank over1op unit i P-A convertor ,v. ,

Group step counters Slave cycler counters ..

MaLter Cycler Counter ,

f Internal Alarm and Memory Circuit REFERENCE '

North Anna Systems Training Text NCRODP 93.5 Section 2 Part C.1.c, Objective B KAIP 3.0, 3.7 OG1000G013 001050A403 ...(KA*S) i ANSWER 2.11 (2.00) f

1. fuel cladding (matrix) (0.5) i i

2. reactor coolant nystem (piping) (0.5)

3. reactor building / containment (0.5)

4. fuel matrix / pellet (0.5)

REFERENCE North Anna Systems Tr aining Text NCRODP 91.1 Section 1 (Pg 1.5),

Objective A North Anna Systems Training Text NCRODP 95.3 Section 1 (Pg 2.4), Objective A

- KAIP 4.1 0920006015 ...(KA'S)

8 2. . CLQU I _ D E S lC2N _ ld CLU D idC1_SOEE IY _QU Q _C.d E B Q E dg y _S Y SIF dS PAGE 45 ANSWERS -- NORTH ANNA 1 !< 2 -88/02/16-MORGAN, M ANSWER 2.12 (1. 0)

(0.6 each)

1. Limits blowdown rate of S/G upon main steam line break.

2. Pr ovi dan a ventur2 ta permit measurement of steam fIow.

REFERENCE North Anna Systems Training Text NCRODP 09.1 Section 1 (Pgs 1.35

&1.5), Objective B and Westinghouse Training Material - S/G and Main Steam KAIP 3.1 03SOCOG007 ... (KA*S)

ANSWER 2.13 (1.50) a) RCS pressure less than 418 psig (0. 5) b) RCS pressure greater than 582 psig (0.5) c) Prevent _ overprensurining a colid plant on inadvertant GI -

capacity based on combined discharge flow of all charging p uinp u . (0.5) 1 REFERENCE Ncrth Anna Systems Training Text NCRODP-85.2 (Rev 3) Pgs 1.4-1.6 and 1.11 Objective B KAIP 3.2 005000U 4 Lr/ ...(KA*G)

2t__ELONI_DESIEU_INGLQQ1NG_$@EEIX_@ND_EMEBGENQY_@YSIEd6 PAGE 46 ANSWERS -- NORTH ANNA 1142 -88/02/16-MORGAN, M ANSWER 2.14 (2.25)

SI Recirc Mode Signal OR Safety Injection Signal (0.45 pts. )

AND (0.2 pts.) (NOTE: The une of other conjunctive terms, such as "WITH" is acceptable 2/4) (0.25 pts.)

RWST Lo-Lo level (0.45 pts.)

less than 25.3% (0.25 pts.)

AND (0.2 pts.)

at least ONE (1) of the respective pump's recirc i solation MOV's cloned (0.45).

REFERENCE North Anna Systems Training Text NCRODP 91.1 Section 2 (Pg 2.26), t Objective E MAIP 3.2 005000K402 ...(KA'S)

ANSWER 2.15 (2.50)

a. To ensure adequate trip reactivity. (minimum SDM) (0.5)

To limit the potential effects of rod ejection or nisalignment. (0,5)

To assure power distributico limits are met. (0.5)

b. Due to the large value of positive reactivity inserted by MTC during the resulting uncontrolled RCS cooldown. (1.00)

REFERENCE North Anna Systems Training Text NCRODP 86.2 Section 9 (Pgs 9.6-9.9), Objective C; North Anna Systems Training Text NCRODP 93.5 Section 2 Part F.6 and North Anna Technical Specification , 3.1.1.1 and 3.1.1.2 and Bases KAIP 3.9 .

001000K500 ...(KA*S)

+

r t

b P

e----- , - - - , -<- m,

-2i_.ELOUI_DEQlGU_INGLUDING_EGEEIY_GUD_EdEBGENGY_HYSIEd5 PAGE- 47 4

ANSWERS -- NORTH ANNA 1842 -88/02/46-MORGAN, M

' ANSWER 2.16 (2.00)

1. Delta-P_butween the RCP discharge and PZR (NOTE: Delta-P across the core and water level in the PZR also acceptable)

(0.5)

2. - Th - Delta-P across the S/G (0.5)

3. Tc - Delta-P across the RCP (0,5)

4. CVCS discharge (Charging pump discharge) pressu e (0.5)

REFERENCE North Anna Systems Training Text NCRODP 88.1 Section 2 (Pgs 2.9 and 2.1b), Objective C; North Anna Systems Training Text NCRODP

-88.1 Section 5 (Pgs 5.13-5.15; Objective E KAIP 3.4 092000A105 ...(KA*S)

ANSWER 2.17 (2.50) a) It ensures that a sufficient water volume is available to maintain the RCS at hot utendby for EIGHT _(8) hours with -

utoam being discharged to the atmosphere concurrent with a total loss of offsite power. (1.0) b) Condensate Storage Tank (CN-TK-2) (0.5) c) Fire Protection Water Main (0.5) and Service Water System (0.5)

REFERENCE North Anna Systems Training Text NCRODP 89.4 Section 2 (Pgs 2.6-2.7), Objective D and H; North Anna Technical Specification LCO 3.7.1.3 and Bases KAIP 3.9 061000K401 ...(KA*S)

t

-2___EL6NI_ DESIGN _INGLUDIN0_S6EEIY_GUD_EUEBGENGY_SYSIgdg PAGE 48

' ANSWERS -- NORTH ANNA I t<2

-88/02/16-MORGAN, M k

ANSWER 2.10 (1.00)

Deboration of the RCS REFERENCE North Anna 'iystems Training Text NCRODP 88.3, Objectiven B.7 and G r KAIP 2.6, 7. 4 * .

004020A213 004020K504 ...(KA'5) t

.f

42_ 10SIBUMENIS_GUQ_G9dIBOLS PAGE 49 ANSWERS ---NORTH ANNA 1&2 -88/02/16-MORGAN, M ANSWER 3.01 (1.00) d) (1.0)

REFERENCE North Anna Systems Training Text NCRODP 93.2 Section 2, Objectivo .

C

.KAIP 3.0, 4.3, 3.9 015000A403- 015000K405 015000K406 ...(KA'S) i ANSWER 3.02 (1.00) c) . ( 1. 0) NOTE: Telephone call to M. Crist on 3/10/88 confirmed "c" as correct daswer.

REFERENCE North Anna Systems Training Text NCRODP 88.3 Section 1 (Pg 1.6),

Objective B KAIP 2.3, 3.0 004000K405 004020K403 ...(KA'S)

ANSWER 3.03 (2.50)

L a) NEITHER (0.25) d) SUMMED (0.25) b) NOT SUMMED (0.25) e) SUMMED (0.25)

L c) SUMMED (0.25) f) NOT SUMMED (0.25)

REFERENCE North Anna Systems Training Text NCRODP 93.2 Section 1, Objectivos E cod GAND Section 2, Objective E KAIP 2.6, 2.9 3.1 L O!5000K601 015000K603 015000K604 ...(KA'S) i I

(

i l

l l

l r

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

3t__INSIBUdEUIS_809_G90IBQLS PAGE 50' ANSWERS -- NORTH ANNA 1&2 -88/02/16-MORGAN, M ANSWER 3.04 (1.25)

1. c (0.25)

2. b (0.25)

, 3. b (0 25)

4. d (0.25)

5. b (0. 25)

REFERENCE North Anna Systems Training Text NCRODP 93.5 Section 2 Part D.2.,

-Objective C KAIP 2.6, 3.3, 3.9 001010A301 001010K404 001050K501 ...(KA*S)

ANSWER 3.05 (1.50)

1) e (0.25)

2) a (0. 25)

3) o (0.25)

4) b (0.25)

5) d (0.25)

6) c (0.25)

REFERENCE North Anna Systems Training Tc.(t NCRODP 93.3 Section 1, Objectivos C.2 and C.3 KAIt' 2. 5, 3.3 01S000G007 01SO20K501 ...(KA*S)

ANSWER 3.06 (1.25) a) 2 (Intermediate) (0.25) b) 1 (Source) (0. 25) c) 1 (Source) (0.25) l d) 2 (Intermediate) (0.25)

( e) 1 (Source) (0.25)

REFERENCE North Anna Systems Training Text NCRODP 93.2, Objectives A,B,C,D,F and G l KAIP 2.9, 2.6 1 075000M602 075000K607 ...(KA'S) l l

(

L-

32__10SIBUMENIS_GN9_G9BI6960 PAGE 51 ANSWERG'-~ NORTH ANNA i t<2 -88/02/16-MORGAN,'M

ANSWER 3.'07 (2.50)

'a ) Tavo, Delta T, Pressure, Del ;a 1 (0.25 each).

b) Overtemperature Delta-T Reactor Trip Logic - '2/3 channels (0.25)

I Setpoint - Variable / Calculated 126.4% + and . penalties i- OR;(0.25)

(this is also acceptabic) 126.4% - Tavg input + Press input - function of Delta I input Gvertemperature Del ta-T Control Interlock "C-3":

Logic - 2/3 channels (0.25)

Setpoint - Variable / Calculated 123.4% + and - penalties OR; (0.15)

(this lu also acceptable) 123.4% - Tavg input + Press input - function of Detita f input c) Stops any outward control rod motion (auto or manual) and initiates a turbine runback. (0.5)

REFERENCE North Anna Systems Training Text NCRODP BG.1 Section 6 (Pos 6.3-6.11), Objectiven B, C, D, and E Nerth Anna Precautions, Limitations, and Setpoints (Pos 15-16)

KAIP 3.3, 2.9 01200CK501 012000K611 ...(KA*S) l 1

I j

1 a

I 4

1 4

3 t__IUSIBUDEUIS_8BD_G9 BIB 96$ PAGE 52

.c ANGWERS -- NORTH ANNA 162 -88/02/16-MORGAN, M ANSWER 3.08 (2.50)

Two Loop Loss Of Flow Reactor Trip -

2/4 power ranges (0.25) AND 1/2 impulse channels (0.25) above 10% power (P-7) DUT lecc than 30% power (P -8) (1.0)

AND 2/3 flow elements in TWO (2) loops sense ( 0. f 5) '

lens than 90% flow in each of the loops (0.5)

REFERENCE North Anna Eystems Training Text NCRODP 93.10 Sec ti cn 1 (Pg 1.16), Objective D North Anna Precautions, Limitations, and Setpoints (Pos 20-22)

KAIP 3.9 0120G0K402 ...(KA'S)

ANSWER 3.09 (2.50) a) 1/2 (0.5) b) 2/2 (0,5) c) 1/2 (0,5) d) 1/4 (0,5) >

e) 2/3 (0.5)

REFERENCE North Anna Gystems Training Text NCRODP 93.2 Set:lon I, Objective G AND North Anna Syntems Training Text 14CRODP 93.8 Section I (Pg 1.17. Objective D ,

KAIP 3.1, 3.9 ,

010000K101 015000K604 ...(KA'S) t i

L l

I

4 ,-

fl L

= 3t_ lUDI69dEUID_eND_GONIBQLS PAGE 53- ;

LANSWERS -- NORTH ANNA 1&2 -88/02/16-MORGAN, M ANSWER 3.10 (1.50) i j a) Reactor Trip (0. 25) b) PORV's Open (0.25) 4 Ec ) Normal Sutpoint for PZR pressure control band (0. 25) -

d) Deckup Heaters ON _

(0.25) u) P-11 Permissivo f or Saf ety Injection Block (0.25) f) Safety' Injection (0.25)

REFERENCE a North Anna Traini ng Guide NCRODP 93. 0 Section 1 3 Objectives D i ana E KAIP 3.4 010000G007 ...(VA'S) i I

ANSWER 3.'11 (1.00) i j a) OG pumps receive signal to start (0.25)

L b) OS pun.p nuction valves receive signal to cpen (0.25) .

c) QS pump thscharge valves receive signal to open (0.25) l d) Chemical Add Tank (CAT) discharge valves receive signal to f open (0.25) (NOTE: This occurs after 5 minut o time del ay - r j thin IS NOT roquired for full credit for this portion REFERENCE North Anna Training Guide NCRODP 91.1 Eccti on 3, Ob.jectivu D l

, LAIP 4.5, 4.4 i 0260?OA203 02600en301 ...(KA'S) !

I t

i

i ANSWER 3.12 (2.00) !

< t

1. When the NDT Protection Circuitry is in service, the RCP'n [

are not operating, therefore the Narrow Ranga instruments, j i which are locatrd in the bypsss manifold, wculd not be !

reliable. (1.0) [

I

{ 2. The reinge of the narrow range temperatut e inst rument e dces a not extend to below 450 degroos F. (1.0) i REFERENCE i

[

Nor t h Anna Systoms Tr ai ni no To t t NCFsOl+ 88.1 Sett1 enc 2 (Pg ?.23) l and 6 (Pg 6.3) AND North Anna Systems Training Text NCRODP 93.8 (

Sect i c n 1 (Pgs 1. J 0- 1. '.0 , Object A ve E !

MAIP 4.2, '.3 {,

e02eeen.n e meiem4 ...(-8, i

1&_,10SIBUDEUIS_sdD_G9 BIB 969 PAGE 54 ANSWERS -- NORTH ANNA t&2 -86/02/16-MORGAN, M i

r ANSWER 3.13 -(0.5) i t

i Averane Reactor Coolant System Temperature (0,5) - }

i REFERENCE North Anna Systems Training Text NCRCDP 93.8 Section 2 (Pg 2.9), !

j Objective A l l -KAIP 3.0 +

011000K404 ...(KA*S) i i !

ANSWER 3.14 (1.50) +

! [

i Steam dumps will remain closed until header setpoint is eached. !

(1.0) ;

j Dumps (WOULD) cycle open. (0.5)

i j NOTE: Any reference to Tavg mode of control or that the dumps [

j would romain shut throughout the transient should result in point !

deduction. I

! h i

hEFERENCE ;

North Anna Systems Training Text NCRODP 93.11 Section 1, .

Objectives listed l KAIP 3.1, 3.3, 3. 2 i 041000G015 04102L4102 041020A302 ...(KA'S) {

t i

-34__1USIGUbEUIS GUQ_GQUIBQLS PAGE 55 ANSWERS -- NORTH ANNA 1842 -89/02/16-MORGAN,~M A.7SWER 3.15 (1.50)

Whilo a signal 'would have been gone; ated to "arm" and actuate steam.dumpsL- using turbine trip controller and reducing Tavg to No-Load-sutpt - the C-9-input (Condenser Interlock) prevents the operation of the system due to loss of condenser vacuum.

(1.0)

. Dumps (WOULD NOT) open. (0.5)

NOTE: Any references to Steam; Dump mode of control or that the dumps would open during the transient should result in point deduction.

REFERENCE-

[ North Anna Systems Training Text NCRODP 93.11 Section 1, 1 Objectivos listed

! KAIP 3.1, 3.3, 3.2 f 041000G015 041020A102 041020A302 ...(KA*S) l i

ANSWER 3.16 (1.00) l PR Rate Trip - N-42 PR channel not properly roset - 2/4 l logic mot (Loas of Power to N Nog rate trip B/S "IN" and not reset prior to pulling of N-41 fuses)

REFERENCE North Anna Systems Training Text NCRODP 93.10 Section 1 (Pp 11 11), Objective B and C AND North Anna Systems Training Text NCRODP 93.2 Section 2, Objective E K4IP 3.5, 3.1 015000A201 015000A202 ...(KA's)

L.__10SIBWENIS_6ND_G9 BIB 960 PAGE 56 ANSWERS -- NORTH ANNA i t<2 - -88/02/16-MORGAN, M ANSWER 3.17 (2.00)

-a) ... Low DNBR due to adverse combinations of high temperature, low pressure,high flux difference, and power." (1.0)

(NOTE: Glive full credit if inference to "low DNBR" is expressed.) (Give full credit if "prevent DNB'is expressed.)

b) ... darna0e due to excessive reactor power output." (1.0)

(NOTE: Give full credit if inference to "excessLve reactor power" is expressed.) (Give full credit if "provides assurance of fuel integrity, is expressed.)

REFERENCE North Anna Systems Training Text 93.10 Section 1 (Pgs 1.13-1.14),

Objective B KAIP 3.9 012000K402 ...(KA'S)

ANSWER 3.18 (2.50)

ER Detector -> Pro-Amp -> Pulse Amplifier -> Pulse Shaper ->

Pulso Driver

-> Log Pulse Integrator-> Level Amplifier -> Bl oc ki ng Ci rcui t - >

SR Level Motor (0.25 for each correct component - DO NOT credit Detector or Meter)

(0. 75 f or correct order)

(-0.25 for each swap needed to pl ace components in the proper order)

REFERENCE North Anna Systems Trai ni ng Te>:t NCRODP 93.2 Section 2, Objective C

MAIP 2.6, 3.4 015000GC04 015000K603 ...(KA'S) i 9

9 4

da _EB9CEDUBES_:_NQBM6Li_8DNQBd@Lt_gdggggNGY_6ND PAGE. 57 609196991G86_CONIB96 ANSWERS - ' NORTH ANNA.Itd! -88/02/16-MORGAN, M ANSWER 4.01 (1.00) d)

REFERENCE North Anna Operation Standards Memorandum dated Oct. 6, 1987-and 10CFR55.4 10 CFR 55.13 KAiP.2.5 194001A103 ...(KA*S)

-ANSWER 4.02 (1.00) a (1.0)

REFERENCE North Anna Operation Standards Memorandum dated Oct. 6, 1987 and

, 10CFR55.4 ADM-19.4, NCRODP-100, Terminal Objective KAIP 2.5 1940016103 ...(KA'S)

, -ANSWER 4.03 (1.00) i l a) IDENTIFIED LEARAGE, since, by Technical Specification

. dofinition, this Icakage IS into a controlled system. The

! loakage IS captured and sent to the PRT.

t

REFERENCE North Anna Technical Specification Definitions Section 1 AND NCRODP JPM LC-033 4 AND PT-52.2 KAIP 3.6 002000G005 ...(KA'S)

ANSWER 4.04 (1.00) a) (1.0)

REFERENCE North Anna Technical Specifications; Section 1.0, "Definitions" Page 1-1 ,

KAIP 2.4 3.7 012000G013 012000K605 ...(KA'S)

f A__E60GEDLJ8ES_ _N980GLi_GDNOBdGLi_EdEBGEN9Y_8ND PAGE 50 i 50D196901G06_C9 NIB 06 {

' ANSWERS'-- NORTH. ANNA i t<2 -98/02/16-h0RGAN, M !

i t

ANSWER 4.05 (1.00)

b. .

REFERENCE N.A. Emerqency Procedure 1-ES-0.2B, (Pgu-6_and 9)

KAIP 2.4, 4.1- .

002020KS12 193003K102 ...(KA*S)' ,

i ANSWER 4.06 (1.50)

1) "d" (0.25) 4) "o" (0.25)

2) "b" (0.25) 5) "c" (0.25) j

3) "b" (0.25) 6) "a" (0.25) r REFERENCE -

North Anna Power Station Emergency P1an Section 1, "Definitiona" ;

4 KAIP 3.1 194001A116 ...(KA'S) i

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i 1

I f

i I

1 .

. 1 1

4 5

i i i e i !

I i

i r

5

d&__EBOGEDUBES_:_NOBUGLt_GEUQBd8Lt_EdEBGENRY_GNQ PAGE !??

B0010L901GOL_G9 BIB 96 ANSWERS -- NORTH ANNA 1&2 -80/02/16-MORGAN, M ANSWER 4.07 (1.50) i With Unitoin Mode 5 or 6 or Defueled Position Number of individuals required'to fill. position Moden 1 2, 3, and 4 Modes 5 and 6 SS _1_ _1_

SRO _1_ _0_ (or "None")

RO _2_ _1_

AO _2_ _2_

STA _1_ _0_ (or "None")

NOTE: The following is also an acceptable answer:

"The minimum shift crew, regardless of operatir,q modo shall bes

- ONE (1) Shift Supervisor with an SRO license

- ONE (1) Assistant Shift Supervisor with a SRO license

- THREE (3) Control Room Operators with a Reac Operators license

- FOUR (4) Control Room Operators unlicenEed

- ONE (1) Shift Technical Advisor

- ONE (1) Comenuni cat er b) FALSE REFERENCE North Anne buclear Plant Technical Specifications; Section 6,

" Administrativo Control s"; Specification 6.2.2, "Unit Staff and

- ~ _.

n

- 4

1. !

s

'es__EBQCEDUBES_:_UOBdObz_00U9BdOLt_EdEBGENQy_GNQ PAGE 60 l B001060GIGOL_GQUIBOL ANSWERS -- NORTH ANNA 1842 -89/02/16-MORGAN, M t

Table 6.2-1 "Minimum Shift Crew Compos). tion" AND Standing Order I

137 AND North Anna Admin Procedure 19.4 KAIP 2.8 -

194001A103 ...(KA*S) ,

t ANSWER 4.08 (1.00) ,

f a) 23 (0.25) :

b) 150 (0. 25) j c) .95. (0.25), 2300 (0.25) L 1

REFERENCE North Anna Operator Training Lesson NCRODP 92.5 Section 2, Objectiven A and C AND North Anna Technical Specification LCO's and Bases 3.9.1, 3.9.3, 3.9.10 and 3.9.11 KAIP 2.4, 3.3 034000G011 034000G015 ...(KA'S1 ANSWER 4.09 (2.00) less than ____500__ __CPD___ through any ONE (1) Steam Generator or equal to AND (0 05) (0.2) (0.25) less than _____1___ __GPM,,__ TOTAL for all Steam Gencrctors or equal to (0.2) (0.25)

(0.05) less than ____100_GPD___ from an individual Steam Generator AND (0.05) (0.2) (0.25) less than ____300__ __GPD___ TOTAL Leakage (0.05) (0.2) (0.25)

REFERENCE North Anna Technical Specification LCD 3.4.6.2.C; Standing Order

1551 PT-46.2 AND NCRODP JPN LC-033 KAIP 4.3, 3.5 002000A201 002000A401 ...(MA'S)

PAGE 61~

l St__BB9sEDUBES_:_N9BdGLt_02N9Bd8Lt_EbEBQENCY_GND l B00196991GOL_G9 NIB 96 ANSWERS _-- NORTH ANNA 1L2 -88/02/16-MORGAN, M ANSWER 4.10 (1.00)

1) Should the plant conditions degrade and cause escalation of the emergency classification to an Alert,, Site Area Emergency, or General Emergency.(0.5)

2) When the Station Emergency Manager deems it necessary (i . e. ;

deemed "necessary" during an Unusual Event emergency) . (0.5)

REFERENCE North Anna Emergency Plan Section 5.0 "Organizational Control of Emergencies" KAIP 3.1 194001A116 ...(KA*S)

ANSWER 4.11 (2.00) a) (-0.5 for each swap to place in correct order)

1. Subcriticality

2. Core Cooling

3. Heat Sink

4. Integrity

5. Containment

6. Inventory b) Color coding is used as a mechanism to immediatedly inform the operator that a CSF is in jeopardy and to indicate the relative severity of the challenge. (NOTE: Words to indicate the intent / idea of this sentence should be expressed for full tredit) (0.5)

REFERENCE North Anna Training Lesson NCFDDP 95.3 Section 2 (Pos 2.4-2.6)

Objectives Aand B KAIP 4.1 194001A102 ...(UA'S)

t st__EBQGEDUBES_:_NOBdGLt_8ENQ8dQLx_EMEBGENGY_ObQ PAGE 62 l GSDEDL991GGL_GOUIB96 ,

ANSWERS -- NORTH ANNA - it<2 -

-88/02/16-MORGAN, M i

.i I,

l 4

ANSWER 4.12 (1.00)

-s

1) To verify receipt of an ' annuni cator . - (0. 5)

2) To initiato corrective action in the event of an emergency.

(0.5) :

. REFERENCE !

l North Anna Administrative Procedure ADM-19.10 (Pg i of 3). -

KAIP 2.5, 2.7, 2.8

194001A103 194e01A1e9 194e01A110 ...(KA S>

2 r

j ANhWER 4,13 (2.00) l a) RCS Pressure - Stable or Increasing (0.5) b) RCS Subccoling greator than 30 degrees F (0,5) c) PZR Levn1 greater than 15 percent (0.5) h 4

d) Either ONE (1) or TWO (2) below is satisfied (f or Heat Sink Criteria): ,

1) Total Feed Flow to intact S/G's gre Ater than 340 gpm ;

(0.25) ,

OR i'

l

2) Narrow Range Level in at least ONE (1) S/G greater than l

i. 10 percent (0.25) l REFERENCE !

I North Anna Emergency Procedure 1-EP-1 "Loss of Reactor or l Secondary Coolant"AND 1-ES-1.1 "SI Tarmi nat i on" AND North Anna i

Training Guide 95.3 Section 1 (Pg 1.19), Objectives A and C i i RAIP 3.9 !

] 006050K401 ...(KA'S) ]

! l l

1

.' I 4

i i

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i :

l !

- St._EBQGEQUBES_ _UQBUGLt_ODUQBdGLt_EdEBQENCY_689 PAGE 63 B8D10L90lG8L_GOUIB06 q ANSWERS -- NORTH ANNA 1&2 -89/02/16-MORGAN, M I ANSWER 4.14 (2.00)

I Any FOUR (4) of the f ollowing FIVE (5) at 0.5 each 1.) Identify and isolate the ruptured S/G's 2.) Cooldown the RCS to establich subcooling margin 3.) Depressurizo the RCS to rentore inventory 4.) Terminate SI 5.) Prepare far cooldown to cold S/D.

REFERENCE NCRODP-95.3 pg 1.23 Section 1 (11-21-86) Section Objective 'C' KAIP 4.5 035010A201 ...(KA'S) ,

ANSWER 4.15 (2.00)-

l all 3 94 4 reach Verify that at least one charging /SI pump is running Place the DATP in fast speed Open MOV-2350 (or MOV-1350)

Verify neutron flux-rapidly decreasing Check PZR pressure less than 2335 PSIG l' REFERENCE FRP-S.1, Responne to Nuclear Power Generation /ATWS !

KAIP 4.2, 4.1 000024K302 001000G014 ...(KA*S)

ANSWER 4.16 (1.00) any TWO (2) et the following FOUR (4) 9 0.50 each a

1. Reactor Coolant Pump vibration indication >/= 5 mils seism 2t (.25) and 20 m:1s proximate (.25)

2. RCP Motor current fluctuating 1 I 1 3. RCP bearing temp high i

4 RCP oil temp high i

5 1

I t

- - - - - , -,-----,,-_.--,,,---n , , , , , . - , . . , . , . . _ ~ , , , , , , ,

,.yw ,--n __ ,,- - - - - - - - . , . . .

4t__EBQGEDUBES_:_NQBdGLt_GENQBdBLt_EdEBGENQY_GUD PAGE 64 6801DLQOIG96_G9dIB96 .

ANSWERS -- NORTH ANNA 1&2 ~BB/02/16-MORGAN, M -t REFERENCE 1-AP-9, Reactor Coolant Pump Vibration ;

KAIP 3.5, 3.~ 1 000015E123 00015G011 .. (KA*S)

ANSWER 4.17 (2.00) a) On a reactor trip, the shutdown rods casure that the reactor is actually shutdown - ensures that at least desired shutdown margin is achieved. (1.0) 1 j

b) Proper sequence and overlap required as part of an assumption in the accident analysis of reactivity addition ,

rate for control rods and proper power distribution (i . e. ;

uniform AFD and DRW) (1.0)

NOTE: "to insure hot channel factor limits are maintained" is acceptable REFERENCE North Anna Operating Procedures 1-OP-1.5, and 1-OP-50.2 AND North j Anna Technical Specification LCO's and Bases 3.1.3.1~and 3.1.3.5 AND North Anna Training Lesnon Plan NCRODP 86.2 Section 6, Obj ective C KAIP 2.7, 3.3 001010K501 001010K506 ...(KA*S) ;

i

.- ~ .. . . . . . . .-

4. PROCEDURE 9 - NnRMAL 3 Ar<NORMAlm l:MERGENCY AND PAGE 6S ,

t RADIOLOGICAL CONTROL,

't ANSWERS -- NORTH ANNA 1&2 -OG/02/16-MORGAN, M s

ANSWER 4.10 (1.5) !

r v

Limitation required to ensures J) the moderate remperature coefficient is within the analyzed l tem pra r a tu re eange (0.5)

2) protective ins truerea to tion is within normal operating range (0.5)

!. ) the P-12 .tnterlock is above setpoint (0.5) '

r e

z s

h PEFF.RENCE 4

Narth (noa opor atinn Procodore 1-OP-1.S AND North Anna Technical I Sp>-c i f i c a t ion L CO's and Danes 3.1.1.5 AND North Anna Training j' i m on Plan NCPODF fM.2 Section 2 Objectives Fi .i n d E KAIF- '.4 1

003010L536 . . . (i A ' 9 )

A N G WF T' 4.17 !1.CO) l 4

I Tli t h l e-d .ccumulator is o s s u rie,d to dump out t hr ough the cold leg )

) hi e is at.d bypwn t he- corn. (1.0) !

1 l 3

i j RUT RENC E North f.n n o Trainiig Guide NCRODP 91.1 Dection 2 (Fgs 2.12-2,12), j Objective, A end L AND North Anna Technical Specification LCO and l

!',n ,

S.i l

! L'AIP 3,4 N6dOW ele 2 . .(i.A'G) l 4

J 4

1 i

s I

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

. . . _ - _ . . - . _ _ _ _ . . . _ _ . . _ _ . ~ . _ . . . _ _ _ . . _ . _ _ _ . . _ _ _ _ . - - _ . . . _ _ . . _ . . . _ . _ _ _ _ _

e . . . . . . _ _ -_._:l

} .

l Q' i

, 4. PROCEDOREG - NORMAL . . ABNORMAL. EMERGENCY AND PAGE 66 -l f,1@JOLOG I CALj;ON TROL, j i I f ANSWERS -- NORTil ANNA 1&2 -GG/02/16-MORGAN, M !

! l

i

. t I i

) !

l !

ANSWER 4.20 (1.50) i l I i i

! i

a. 25 3 000 Curies (0.25 for amount and 0.2S for unit) l i

l b. In the event of an uncontrolled release of the tank contents, '

l j the resulting total whole body exposure to en indivadual at .;

j the nearest exclusier' area boe.ndary will not exceed 0.5 j mi111 rem. (0,5)

c. To ensure that the concentration of potentially explosive gas j j m i x. tu re c contained in the holdup tanks is maintained below 7 4

the flammability limits of hydrogen and oxygen. (0.S) I 1 !;

REFrRENCE 1

i j North Anne Gyntems Training Text NCRODD 92.4 Gection 1 (Pg 1.33)

Objectives D, F and G l j K41P 2 . 1, 3.0. 2.5 T.1 0710 C'O A 4 26 071000A429 071000G011 071000K504 ...(UA'G) t

] .

I d

ANSWER 4.21 (1.50) j 1

a t Steps *>hould be listed in the this order 1

2 1, 6, 4, 5, 3 i l

-0.5 for each swap to place in correct order) !

t REFERENCC l j Nor th Anna Ops Procedere 1-OP-6.1 Gettion 4.2 AND North Anna JPM

{

NCRODP JPM LC-030 ;

KAlr 3.$ i

0640004203 ...(kA'S)

I l

1 i

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