Text

Exam Rept 50-309/88-02(OL) Administred on 880211.Exam Result:One Senior Reactor Operator Passed
	ML20148M742
Person / Time
Site:	Maine Yankee
Issue date:	03/23/1988
From:	Eselgroth P, Norris B; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20148M739	List: IR 05000309/1988002;
References
	50-309-88-02OL, 50-309-88-2OL, NUDOCS 8804060116
	Download: ML20148M742 (78)
	v • d • e

{{#Wiki_filter:.._. _ _ _ _ _ _ _ - _ _ _ _ _ __ _ . _ _ _ _. _ _. _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ __ . , e . U.S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT N0.

50-309/88-02(0L) FACILITY DOCKET NO.

50-309 FACILITY LICENSE NO.

OPR-36 LICENSEE: Maine Yankee Atomic Power Company 83 Edison Drive Augusta, Maine 04336 FACILITY: Maine Yankee EXAMINATION DATES: February 11, 1988 CHIEF EXAMINER: pfm ,,FJ _ V g 6 _[rry$4 Norris Date ~ B Senior Operations Engineer APPROVED BY: ' f

3-U-f8 Peter W.

roth, Chief Date PWR Secti Operations Branch Division o Reactor Safety, Region I . SUMMARY: A written re-examination was administered to a Senior Reactor Operator (SRO) candidate. He passed the examination.

I i t l l l l 8804060116 880320 j PDR ADOCK 05000309 i

. M rerJe

_ - _ _ _ - _ _ _ _ _ _ _ _ . . . . DETAILS TYPE OF EXAMINATIONS: Replacement EXAMINATION RESULTS: l SRO l , l Pass / Fail l , l l . I l I ' l Written I 1/0 l l l l

I I (Operating I waived I I I I

i l l (Overall l 1/0 l l l l CHIEF EXAMINER AT SITE: B. S. Norris, USNRC OTHER EXAMINERS: D. T. Wallace, USNRC

No exit meeting was held since only a single written examination was administered.

The facility was provided a copy of the examination questions and answer key for review. The f acility coments ( Attachment 2) and the NRC resolution of the comments (Attachment 3) are enclosed.

Attachments: 1.

SRO Written Examination and Answer Key ' 2.

Facility Comments on Written Examination 3.

NRC Resolution to Facility Comments

. A'17%te Alr??h/7 " _ . P ' ~ U. S. NUCLEAR REGULATORY C0m!SS10N SENIOR REACTOR OPERATOR LICENSE EXAMINATION

FACILITY: MAINE YANKEE REACTOR TYPE: PWR-CE DATE ADMINISTERED: 88/02/09 EXAMINER: GRUEL, R.

' CANDIDATE: ANSWER KEY INSTRUCTIONS TO CANDIDATE:

Use separate pa)er for the answers. Write answers on one side only.

Staple question s1eet on top of the answer sheets.

Poin~ts for each question are indicated in parentheses after the cuestion.

The passing grade requires at least 70% in each category anc a final grade of at least 80%. Examination papers will be picked upsix(6) hours after the examination starts.

k 0F CATEGORY % Or CANDIDATE'S CATEGORY ' VALUE TOTAL SCORE VALUE CATEGORY , _25.00 - 25.00 5.

THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS , 25.00 25.00 6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION 25.00 25.00 7.

PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL , 25.00.

25.00 8.

ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITA,T,10NS _ 100.00 % Totals ,

- Final Grade - , - . , All work done on this examination is my own.

I have neither given

nor received aid.

Candidate's Signature

,

l ' .. - _ -. _ . - . . _ _ _ _ ... ._ _ _. _ _ _ - - - _ - _ _. _ - - -.

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

. . . .. NRC RULES AND GU10ELINES FOR LICENSE EXAMINATIONS s . . During the administration of this examination the following rules apply:

1.

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

2.

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

3.

Use black ink or dark pencil only to facilitate legible reproductions.

4.

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

5.

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

. 6.

Use only the paper provided for answers.

7.

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

-

8.

Consecutively number each answer sheet, write "End of Category _ " as appropriate, start each category on a new page, write only on one 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 three lines between each answer,

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table, j 12. Use abbreviations only if they are comonly used in facility if tarature.

13. The point value for each question is indicated in parentheses m.,er th[s , ' l l question and can be used as a guide for the depth of answer required.

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

, J.

\\ . l 15. Partial credit say be given. Therefore, ANSWER klL PARTS OF THE . . , JJESTIONANDDONOTLEAVEANYANSWERBLANK.

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

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

l -.. . _. _ .- - _ -____--. . .. _ .. ..- - - ... -.

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ - _ _ , E . . ' . -

18. W$en you complete your examination, you shall ' a.

Assemble your examination as fellows: (1) Exam questions on top.

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

! i - > (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 erea, as defined by the examiner.

If after ~ leaving, you are found in this area while the examiriation is still in progress, your license may be denied or revoke >d.

- f , - g a Wb

n

_ _ _ _ _ __-_____ ___ __ - _________________ ___ _ _ _____ ________ ____________-____ _ _____ . _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

. ,

'

5.

THEORY OF NUCLEAR POWER PLANT OPERATION, FLU!DS, AND PAGE

THERMODYNAMIC 5 . l I , QUESTION 5.01 (2.50) A reactor startup is in progress. Given the following information shutdown and regulating groups fully withdrawn RCS is at no load temperature and pressure Keff = 0.95 countrate = 60 cps o a.

HOW MUCH negative reactivity is in the core? SHOW all , calculations.

(1.0) The control room o)erator begins RCS dilution.

Later the operator notices t1at the countrate has increased to 110 cps.

,. b.

HOW MUCH negative reactivity is present in the core? SHOW all calculations.

(1.5) QUESTION 5.02 (3.00) The reactor has a startup rate (SUR) of 0.7 decades per minute (DPN)atBOC.

a.

HOW long will it take after passing 100 watts to reach 5 megawatts? (1.0) b.

Ifthesameamountofrejetivityaswasaddedinparta.

is added to the reactor 4t EOC, WHAT would be the resultant SUR7 STATE assumptions and SHOW calculations.

(2.0) ,,. a - QUESTION 5.03 (1.00) HOW does the fuel temperature coefficient (FTC) plutonium-239.

The Maine Yankee nuclear reactor core produces respond to increases in Pu-239 and WHY7 (1.0) , (""* CATEGORY 05 CONTINUED ON NEXT PAGE *"**)

._ - . .

'

5.

THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 3' THERMODYNAMICS . QUESTION 5.04 (2.00) ANSWER the following questions on the production of xenon and its affects on core reactivity.

a, HOW is xenon produced in the core? (0.5) b.

HOW is xenon removed from the core? (0.5) c.

STATE the relationship between equilibrium xenon reactivity and reactor power level. WHAT is the main reason for this relationship? (1.0) . QUESTION 5.05 (1.50) After a spent fuel assembly had been in the spent-fnel )ool for two years, it was surveyed and it was determined that t1e dose rate at one foot was 70,000 R/hr. One and one-half years later (after 3-1/2 years in the pool), the dose rate at the same ,, N'

location was found to be 7000 R/hr. CALCULATE the effective- ' half-life, t-1/2 of the fuel assembly.' SHOW calculations.

(1.5) , l QUESTION 5.06 (1.00) Following a reactor trip from sustained operation.M 100% power, the power (neutron flux) level drops.immediately te about (SELECT the correct answer) (1.0) l (a.) 6% because about 94% of the neutrons are prompt neutrons.. .[f l (b.)6%becauseabout0.4to5.5%ofthinestrons'aredelayed-' ^2 ~ -

l neutrons. _ _ ,. g l 3.)99.5to99.6%becauseabout0.4-to0.5%oftheneutronsare

, l delayed neutrons.

(d.)99.5to99.6%because99.5to99.6%oftheneutronsareprompt l neutrons.

' h . l (***** CATEGORY 05CONTINUEDONNEXTPAGE*****) ' l _ -. . - -. - - - - - - -. -. - - - - - _

. .' .. , ' 5.

THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE

THER% DYNAMICS . - P QUESTION 5.07 (3.50) The reactor is at 3*% power, Group 5 rods at 100 steps, equilibrium xenon and samarium, boron concentration is 1200 ppe and BOC.

Using the attached figures from the Maine Yankee Technical Data book determine WHAT the final boron concentration will be if power is raised to 8W, ARO, equilibrium xenon and samarium? STATE all assumptions, SHOW all work, and IDENTIFY any figures used.

(3.5)

QUESTION 5.08 (3.00) The reactor is operating at 100% power.

STATE the INITIAL effect that each of the following will have (INCREASE, DECREASE, NO EFFECT) on fuel center-line temperature and BRIEFLY JUSTIFY your answer.

a.

Decrease in reactor coolant flow (0.75) b.

Increase in steam flow

(dIb)I -

l c.

Increase in RCS pressure (0.75) d.

Decreasing fuel / cladding gap thickness (0.75) QUESTION 5.09 (2.50) The Maine Yankee reactor has tripped due to loss of offsite .- power.- ' + n-a.. LIST four~ (4) indications which verify est'ablishment of.- ? J.'s l i natural circulation flow.

INCLUDE.the parameter AND its- . . ~. - l expected value or trend.

- (2.0).

' ~ ~ _.. b.

W 17 should SG pressure be to bring initial core tempera-l ture to 532 degrees F7 (0.5) .

(***** CATEGORY 05CONTINUEDONNEXTPAGE*****) - - . .. - - -

'

. . ~ 5.

THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE

~ THERMODYNAMICS . QUESTION 5.10 (1.50) For each of the following concerning centrifugal pump operation, STATE whether available NPSH INCREASES, DECREASES or REMAINS THE SAME. Consider each item separately.

a.

Suction temperature is reduced.

(0.F) b.

Discharge valve is closed slightly.

(0.5) , c.

Suction valve is closed slightly.

(0.5) QUESTION 5.11 (1.00) STATE WHY an HDFP (P2A or P28) must be isolated and depressurized before its associated recirc valve can be stroke tested.

(1.0) ~ e rp QUESTION 5.12 (2.50) 1he plant is at 100% sower. The regenerative heat exchanger E-67 is operating wit 1 a letdown temperature of 316 degrees F.

The charging flow enters the regenerative heat exchanger at ! 120 degrees F and is heated before entering the RCS.

ASSUMING ! that the specific heat of water is constant at 1 BTU /lb-F, l ANSWER the following heat transfer questions regarding this ! component. CLEARLY state ALL assumptions used in your l calculations.

' [ a.

. CALCULATE the nominal heat transfer rate (Q) for this heat,

' exchanger in BTU /hr.

(1.0): -' > , .. . . x L CALCULATE the temperature oflthe RCS charging flow as it . exits the regenerative heat exchanger.- (1.0).

, c.

WHAT is the pressure corresponding to 20 degrees F sub-cooled at the outlet of the letdown side of the regenerative heat exchanger.

(0.5).

. (*****ENDOFCATEGORY05*****) l l

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

y ..' . ' 6.

PLANT SYSTE!4S DESIGN. CONTROL, AND INSTRUMENTATION PAGE

. - QUESTION 6.01 (1.00) ANSWER TRUE or FALSE to the following statements about the CEA Control System.

a.

Regulating Group 5 is divided into two subgroups, 5A and 5B. Group 5B CEAs are trippable while Group 5A CEAs are not.

(0.5) b.

The Shutdown CEAs move at 27 steps per minute (20 inches / minute) while the Regulating CEAs move at 40 steps per minute (30 inches / minute) (0.5) d QUESTION 6.02 (1.50) , LIST the three (3) CEA withdrawal prohibit (CWP) signals generated by the RPS AND the conditions under which EACH can be disabled.

(1.5) QUESTION 6.03 (3.00) ANSWER the following regarding the reactor power level (variable overpower) portion of the reactor protection system.

a.

STATE HOW reactor power is determined by this system.

INCLUDE input parameters as well as those inputs used for compensation.

(2.0): b.

Briefly DESCRIBE WHAT operator actions (if any) related to this system are necessary during: , , _ 1.

power increases (0.5) < ' 2.

power decreases (0.5) . o > (***** CATEGORY 06 CONTINUED ON NEXT PAGE *"**) _.

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

. . ~ ' 6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE

. - QUESTION 6.04 (3.25) ANSWER the following regarding the Emergency Diesel generators.

a.

After the 11.5-minute cooldown period, diesel engine RPM increases unexpectedly to 700 RPM, and spurious engine alanns including Low Oil Pressure, Hot Engine, and Low Lube Oil level are generated. The engine remains unloaded.

Briefly EXPLAIN WHAT prompt action is necessary to si,utdown the engine.

(0.75) b.

During the diesel AUTO START loading sequence, the diesel generator comes up to rated speed cuickly.

EXPLAIN HOW an , engine overspeed condition is avoiced.

(1.0)

c.

EXPLAIN the sequence of operation of BUS / breakers P-29A and P-29C (service water pum) breakers) during a diesel auto loading sequence, AND tie reason (s) for that operation.

(1.5) QUESTION 6.05 (1.75) ANSWER the following regarding the Main Steam System.

, , l a.

WHAT is the primary purpose of the EFCVs? (0.75) i b.

EXPLAIN how the NRV vacuum assist system operates.

INCLUDE the conditions under which it would be used AND why it is used at that time.

(1.0) , l . J' ~ l ...' " l , ! - ! l

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****) i . _ - - ..%

~

~.,, - - -,,, _ .._--._.._...-__-_.-..,,,,,,,,.___,__..,s.w .- ,y -,,. ,,..-.-% -m , _ _. -.__.

-

' ' . . ' 6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE

' ' . QUESTION 6.06 (2.50) ANSWER the following regarding the Service Water and the Primary and Secondary Component Cooling Water Systems (PCC and SCC).

a.

Normally two service water pumps are operating.

WHAT are the two (2) temperature setpoint conditions requiring the start of an additional pump? (0.5) b.

The PCC and SCC centain in-line process type radiation monitors (RM-3401 for PCC, and RM-1701 for SCC).

DESCRIBE HOW these monitors interlock with other PCC and SCC components.

(1.5) . c.

WHAT steps r.iust be taken if either the PCC or SCC system is inoperative? (0.5) QUESTION 6.07 (.50) STATE WHY Maine Yankee uses a pressurizer level program that varies with reactor power.

(0.5)

, QUESTION 6.08 (1.50) The letdown pressure control valve LD-F-16 closes automatically , l on a high differential pressure signal.

i i a.

AcrossWHICHcomponent(s)isthedifferentialpressure l measured? (0.5) l b.- WHAT valve opens upon closure of LD-F-16 and WHERE is the . - letdown flow redirected?- (1.0), , , b l l o I (***** CATEGMY 06 CONTINUED ON NEXT PAGE *****) . _. _-_.

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

.' , . . ' 6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE

. QUESTION 6.09 (2.80) ANSWER the following regarding the RHR/LPSI system.

~ a.

Briefly EXPLAIN HOW the RCS coolant can be purified when the RHR system is in operation.

(1.0) b.

LIST the RHR pressure setpoint interlocks on both increasing AND decreasing RCS pressure.

(0.8) c.

HOW is full LPSI flow capability through LSI-F-59, RHR control valve, ensured during at power conditions? (1.0) > QUESTION 6.10 (2.70) l ANSWER the following regarding the HPSI system.

a.

LIST three (3) operational attributes of the P-14S HPSI pump which make it different from the other two HPSI pumps.

(1.2) b.

LIST the functions (or valve numbers) of three (3) HPSI/ CVCS valves which close on an SIAS and reopen when the SIAS signal is RESET.

(1.5) l l l l QUESTION 6.11 (1.50)

Maine Yankee Procedure 3.1.2, ECCS Routine Testin2, states that l the LPSI pump breaker should not be racked down when P-61S is being used as a spray pump in the same train.

. ,

' a.- LIST'the two (2) consequences of not observing this guidance.

(1.0).

< b$ STATE the condition under which these consequences would occur., (0.5) l ' l l (***** CATEGORY 06 CONTINUED ON NEXT PAGE *****) , - _,, _ - -. - -. -.., - - -, y- - --, -

*-r e---

- - - ' - - --- - -,.--.----r ,m _ - _,

.. . ' 6.

PLANT SYSTEMS DESIGN, CONTROL. AND INSTRUMENTATION PAGE 10 . QUESTION 6.12 (3.00) Foreachofthefollowingconditions(a.,b.,andc.) LIST those actuation signals and trips (1. through 5.) that should have automatically occurred. CONSIDER each condition separately.

Each cordition may have for its answer none, one, or several actuation signals or trips.

(3.0) 1.

SIAS 2.

CSAS 3.

RAS 4.

CIS 5.

Main Feedwater System Trip , a.

A steam line break has occurred in containment and containment pressure = 7 psig containment radiation = normal background S/G levels = 60%, 60%, 30% Pzr pressure = 1800 psia S/G pressures = 700 psia, 700 psia, 550 psia RWST level = 250,000 gallons t i b.

A LOCA has occurred and ' containment pressure = 25 psig containment radiation = 6 R/hr S/G levels = 38%, 38%, 38% Pzr pressure = 1300 psia S/G pressures = 380 psia, 450 psia, 450 psia l RWST level = 85,000 gallons c.

A feedwater problem has occurred l l containment pressure = 1 psig containment radiation = normal background i S/G levels = 63%, 63%, 31%

,'

l Pzr pressure = 2180 psia l S/G pressures = 730 psia, 730 psia, 640 psia - ' RWST level = 300,000 gallont - . _ . (*****ENDOFCATEGORY06*****) l l

. - . _ -

' .. , ' 7.

PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 11 RADIOLOGICAL CONTROL . - QUESTION 7.01 (1.50) LIST two (2) reasons why an isolated loop is maintained in an overpressure condition per procedure 1-10-5, "Cooldown of an Isolated Loop." ASSUME the isolated loop has insignificant coolant loss.

(1.5) QUESTION 7.02 (1.50) . Procedure 1-10-7, "RCP Operation," allows deviations from "normal" parameters under very specific conditions. ANSWER the following regarding RCP operation during off-normal conditions.

a.

By procedure, RCP operation with excess seal leakoff (i.e., > 5 gpm) is allowed, provided that the lower seal cavity temperature is maintained at approx. 150 degrees F.

HOW does one maintain this seal temperature specification? (0.5) , b.

A sudden reduction in RCP seal leak'off flow to below its normal value is considered more serious than a sudden increase.

EXPLAIN WHY a sudden reduction in RCP seal leakage flow is serious to RCP operation, AND IDENTIFY the expected result should the condition go unaltered.

(1.0) QUESTION 7,03 (1.00) Procedure 1-11-6, "CVCS Operation," CAUTIONS that "Only one HPSI Pump control Switch shall be out of the' PULL-TO-LOCK

l position when the RCS temperature is less than 430 degrees F."

j.

EXPLAIN the reason for this CAUTION statement.

- (1.0).

, b e l (***** CATEGORY 07CONTINUEDONNEXTPAGE*****) ._ . . . . -.. . . . -

. - .: . ~ 7.

PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE

RADIOLOGICAL CONTROL . . QUESTION 7.04 (1.50) Procedure 1-22-2, "Battery and Vital Bus Operation," identifies three (3) major inadvertent plant responses which could occur as a result of a "voltage spike" generated during the cross connection of vital buses (necessitated by either inverter failure or required maintenance) during power operation.

LIST the three (3) major inadvertent plant responses which could occur.

(1.5) J QUESTION 7.05 (1.50) In accordance with Operations Memo 9-D-11, turbine backpressure should be reduced when unit load is less than 30% power.

a.

WHAT value of turbine backpressure should be maintained? (0.5) b.

WHAT is the reason for avoiding high backpressure during low power operation AND WHAT would result from such operation? (1.0) QUESTION 7.06 (1.25) ANSWER the following regarding containment operations during l abnormal plant conditions.

a.

If an automatic containment isolation valve is not operable, WHAT action is required to maintain containment integrity? (0.5) b.

WHAT post-LOCA containment condition can lead to a containment pressure spike? IDENTIFY limits in your j, answer.

- (0.75).

. - l i l . l (***** CATEGORY 07CONTINUEDONNEXTPAGE*****) . _ - _ .. ..-__ - _ _.

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

. __ -. - - _ - . . .: . ' 7.

PROCEDURES - NORNML, ABNORMAL, EMERGENCY AND PAGE 13 RADIOLOGICAL CONTROL . QUESTION 7.07 (2.00) ANSWER the following which address operator actions to be taken during abnormal plant conditions.

a.

WHAT two (2) operator actions MUST be taken immediately after a loss of control air? (1.0) b.

WHAT operator action MUST be initiated no later than 10 minutes following the discovery of a Main Control Room Fire to protect the RCS7 (0.5) a , c.

WHAT alternate source of water MAY be aligned to the SGs "as a last resort" during the performance of an RCS cool-down from the Auxiliary Shutdown Panel (ASP)? (0,5) QUESTION 7.08 (4.50) E-0 "Emergency Shutdown from Power or Safety Injection" provides ' entry into the Maine Yankee E0Ps. ANSWER the following regarding E-0.

a.

NAME the five (5) "criteria" provided on the E-0 foldout page.

Specific setpoints or values do NOT need to be included.

(1.5) b.

A reactor trip has occurred and two (2) rod bottom lights are not lit.

LIST the immediate actions that are to be conducted. ASSUME the two rod bottom lights remain unlit and reactor power remains greater than 2%. (2.0) c.

ASSUME the Containment Puge Isolation valves cannot be manually closed. WHAT action should you take? INDICATE j, . ' specific plant locations in your response.

(1.0).

' - h . (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****) - - -. .

, . . - . - . . ABNORMAL, EMERGENCY AND PAGE I4 ' RA L 4t C QUESTION 7.09 (1.50) ANSWER the following regarding ES-0.2, "Natural Circulation Cooldown."

a.

The Step 5 CAUTION states: "00 NOT run more than two CEDM cooling fans at one time."

EXPLAIN the reason for this caution statement.

(0.75) b.

WHAT is the primary function of the CEDM cooling fan operation during ES-0.27 (0.75) . l QUESTION 7.10 (3.25)

Once an SGTR event has been properly diagnosed, entry into the Emergency Procedures for recovery from an SGTR is made (i.e., E-3, ES-3.1,ES-3.3). ANSWER the following regarding this set of SGTR ' l procedures.

a.

E-3, "Steam Generator Tube Rupture," requires the isolation of the faulted steam generator, which includes stopping the faulted loop's RCP.

Under WHAT condition (s) MUST the faulted loop's RCP continue to be operated? (0.5) b.

Three main objectives of E-3 are to isolate the faulted SG, i cooldown the RCS, and depressurize the RCS.

For the cooldown and depressurization initiated in E-3, l ! 1.

WHAT is the basis for establishing the RCS target l pressure? (0.75) 2.

WHAT is the basis for establishing the RCS target (0.75), temperature? j.

. .., _ c.

Both ES-3.1, "Post-SGTR Cooldown Using Backfill," and "

ES-3.3, "Post-SGTR Cooldown Using Steam Dum),".are entered-l - via Step 42 of E-3, at the discretion "of tie plant staff."

' l 1.

WHICH is the preferred procedure? (0.5) l 2.

Under WHAT conditions should the alternate procedure be used?- (0.75)' , I (***** CATEGORY 07CONTINUEDONNEXTPAGE*****) t

- - .. . ' 7.

PROCEDURES - NORMAL. ABNORMAL, EMERGENCY AND PAGE 15 RADIOLOGICAL CONTROL t - . l QUESTION 7.11 (2.00) If an. emergency boration of the RCS becomes necessary during normal core reloading operations, a.

WHAT source of borated water would be used? (0.5) b.

WHICH pump (s) would be used to inject the borated water? (0.5) c.

WHAT flow path would be used for injection of the borated water into the RCS? (1.0) e QUESTION 7.12 (1.50) During refueling operations, Maine Yankee operating procedures describe a method for manipulator crane position indication alignment WITHOUT the TV camera.

a.

HOW is this alignment performed? (0.75) b.

WHAT is the major disadvantage of this alternate alignment procedure? (0.75) . QUESTION 7.13 (2.00) A contaminated tank located 15 feet from a work area in the RCS has resulted.in a~ gamma radiation dose rate of 100 ares /hr in the > ek area. One layer of lead bricks will reduce the radiation level to 50 ares /hr. The work area radiation level is to be lowered to below 4 mres/hr.

j.

a.

HOW MANY layers of lead bricks are necessary to accomplish - the radiation level reductionf SHOW WORK.

(1.0) b.

SHOULD the resultard area (about 4 mres/hr) be posted as a Radiation Area? WHY or WHY NOT7 (1.0) . ' (***** END OF CATEGORY 07 *****) _ __ . - -.. . -

. . ~ 8.

ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 16 . QUESTION 8.01 (2.00) ANSWER the following regarding the DEFINITIONS section of the Maine. Yankee Technical Specifications.

a.

WHAT single operating condition change defines the transition from Condition 3 to Condition 47 (0.5) b.

WHAT single operating condition change defines the transition from Condition 5 to Condition 67 (0.5) c.

WHEN is the reactor considered critical (for purposes ofadministrativecontrol)? (0.5) , d.

WHY does the cold shutdown Boron concentration differ from the hot shutdown Boron concentration? (0.5) QUESTION 8.02 (4.50) ANSWER the following regarding the Plant Shift Superintendent (PSS),theShiftOperatingSupervisor(505),andtheControlRoom Operator (CRO).

a.

WHAT is the minimum license requirement per Maine Yankee Technical Specifications for the 5057 (0.5) b.

LIST five (5) actions the oncoming PSS shall take prior to assuming the shift.

(1.5) c.

ARE the following actions of shift staff proper? JUSTIFY <our answer.

(1.5) The SOS and a CR0 are alone in the control room. The SOS: ~ enters the bathroom. DuringthistimetheCR0sitsattheJOS ' desk while he updates his logs. The SOS returns to his desk - . and the CR0 gets his lunch from the kitchen area.

- E Under WHAT conditions may the PSS briefly leave the control room during accident situations? (1.0) / (***** CATEGORY 08CONTINUEDONNEXTPAGE*****) -- -_- -_--. -. . - _. -. _. .. . - - . --.

. . _ - _ - . - . . ~ 8.

ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 17 . QUESTION 8.03 (2.00) You are the on-duty PSS. ANSWER each question separately.

kn A0 calls and infoms you that a normally locked shut a.

ECCS valve has been tampered with. WHAT action should you immediately take? (1.0) b.

You are conducting an approved procedure when the SOS informs you that an entry in the Night Orders pertains to the next step of the procedure.

The procedures and Night Orders do not agree. WHICH do you follow? (0.5) a c.

You are on shift, out in the plant and a fire alam occurs.

WHAT should you do? (0.5) l QUESTION 8.04 (3.00) Regarding the use of "White Tags," a.

1.

Under WHAT conditions is independent verification of proper tagging requi hd? (0.75) 2.

WHAT exception exists to this practice? (0.75) b.

HOW can a White Tag be cleared if the "person to whom apparatus is tagged" is unavailable? (1.0) l c.

HOW often are outstanding White Tags reviewed for their l continued applicability? (0.5) QUESTION 8.05 (1.00).

j.

The PSS must get authorization' from WHAT two (2) individuals, r k title, to allow a loop entry at power? (1.0)

l (***** CATEGORY 08CONTINUEDONNEXTPAGE*****) f . .. _ _ _ . . ._ _ _ -. _. _ , _ _... _ _ _ ... . . _ _ _. _ _ - --

. . _ .; . ~ 8.

ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 18 . QUESTION 8.06 (3.00) ForEACHofthefollowingconditions,STATEWHATaction(s) (if any) are to be performed per the Maine Yankee Technical Specifications.

INCLUDE any associated time rec uirements.

ASSUME all other plant conditions are normal anc the reactor is in Condition 7.

Actions required beyond a four-hour period are NOT required.

a.

SIA-H-21 (safety injection tank isolation valve) is closed for testing.

(0.75) b.

LPSI pump P-12A is taken out of service for maintenance.

(0.75) , c.

The auxiliary feedwater aump is out of service for main- , tenance and a common pro)1em is found that renders both ! emergency feedwater pumps INOPERABLE.

(0.75)

d.

CEA subgroups SA and 5B differ by 12 steps.

(0.75) l QUESTION 8.07 (3.00)' l Containment pressure and temperature must be maintained in order to support various FSAR analyses.

l a.

STATE the allowable containment pressure for Condition 7 operations AND its basis.

(1.5) ' b.

STATE the allowable containment temperature AND LIST four (4) i actions that can be taken if containment temperature is too high.

(1.5) , \\ _ _ y - . QUESTION 8.08 (2.50) - D SWER the following regarding CEA operational and shutdown margin limits during Condition 7 operation.

i a.

WHEN is a CEA considered to be fully withdrawn? (0,5) b.

TRUE or FALSE. Operation of CEAs in the automatic mode is prohibited in the Maine Yankee Technical Specifications.

(0.5) c.

Under WHAT conditions is continued operation with inoperable CEA(s) permitted? (1.5) (***** CATEGORY 08CONTINUEDONNEXTPAGE*****)

.* . ~ 8.

ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 19 . QUESTION 8.09 (4.00) ANSWER the following regarding the Maine Yankee Emergency Plan.

a.

NHO on back shift serves as the Emergency Coordinator during an emergency? (0.4) b.

WHO (by title) are authorized to act as Emergency Coordinator upon their arrival on site? (1.2) c.

WHAT duties of the Emergency Coordinator cannot be delegated? (1.6) e d.

WHAT offsite organization is first notified of an emergency and WHEN must this notification be made? (0.8) r - . - ! . (***** END OF CATEGORY 08 *****) (*************ENDOFEXAMINATION***************) ,__._.

_ - _ _. _. - _ _ .. .... .._________._._____._____.______.____.___._-..-_;

' .- , 5.

THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 20 - THERMODYNAMICS ' ANSWERS -- MAINE YANKEE-88/02/09-GRUEL, R.

ANSWER 5.01 (2.50) a.

rho = (Keff - 1)/Keff = (0.95 - 1)/0.95 rho = -5.26% delta k/k [+1.0) b.

CR2/CR1 = (1 - K1/1 - K2) = K2 = 1 - CR1/CR2 (1 - K1) K2 = 1 - 60/110 (1 - 0.95) = 0.973 [+0.5] rho = (Keff - 1)/Keff = (0.971 - 1)/0.973 = -2.80% delta k/k [+1.0] b k k-i altmo n +sa endH-] , REFERENCE 1.

Maine Yankee: ELO # CRC-0101-58.

192008K104 ...(KA'S) ANSWER 5.02 (3.00) a.

P=Po10**(SU (T) ()10* * (0.7 5 x 10"6 = (1 5x10**4))T) - T = (1/0.7)1og T = 6.7 min [+1.0) . b.

assume beta (eff) = 0.006 at BOC = 0.005 at E0C (fullcreditforreasonablevalues) t = 26/SUR = 26/0.7 = 37 sec rho = beta (eff)/(1 + lambda t) = 0.006% delta k/k/(1 + (0.08)(37))[+1.0] rho = 0.152% delta k/k EOC: T = (beta - rho)/(lambda * rho) = (0.005 - 0.00152)/ (0.08)(0.00152)see- >, T = 28.6 sec , SUR = 26/28.6 = 0.909 dpa [+1.0] , REFERENCE 1.

Maine Yankee: R0 Rx Theory LP No. R0-L-1.10 and ELO fCRC-101-63.

192003K106 ...(KA'S) , < . -. - ...--.,. ... - - -. - -. -.. -. .. -. - -. - -,.,.. - - _.. _ _ _ _ _., - -. -.,_.._..,_. _,,,.-_ _.. -,-,--.-._--.--, - -..,

' .. . 5.

THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 21 THERMODYNAMICS ' ' ANSWERS -- MAINE YANKEE-88/02/09-GRUEL, R.

ANSWER.

5.03 (1.00) FTC increases due to Pu-239 buildup [+0.5]. This is because of the increased resonant capture in Pu-239 compared to U-235 [+0.5]. REFERENCE , 1.

Maine Yankee: ELO # CRC-0101-42.

192004K107 ...(KA'S) . ANSWER 5.04 (2.00) a.

from fission fragments decay [+0.4] and directly from fission [+0.1] b.

burnout [+0.25] and decay [+0.25] c.

At higher reactor power, equilibrium xenon reactivity changes less with a change of power than at' lower reactor power [+0. 5]. As power increases, the burnout and production terms become dominant, so at high power, production and removal terns become more linear [+0.5].

REFERENCE 1.

Maine Yankee: R0 Rx Theory LP No. R0-L-1.12 and ELO ,

CRC-101-90.

l 192006K103 192006K104 192006K111 ...(KA'S) ANSWER 5.05 (1.50) j, . E = Al e**-(0.693 t/(t-1/2)) [+0.5] InA2/A1=-0.693t/(t-1/2) t-1/2 = 0.693 (1.5) yr/1n (70,000/7,000) t-1/2 = 0.45 yrs [+1.0] , REFERENCE 1.

Maine Yankee: ELO # CRC-0101-11.

033000A102 ...(KA'S)

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

' .- . 5.

THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 22 THERMODYNAMICS ANSWERS -- MAINE YANKEE-88/02/09-GRUEL,R.

. ANSWER 5.06 (1.00) (b.)

[+1.0] REFERENCE . 1.

Maine Yankee: ELO # CRC-0101-54.

192008K123 ...(KA'S) . ANSWER 5.07 (3.50) (Figure 2.1.2.1)] reactivity due to FTD: -0.81 -(-0.38) = -0.43% drho [+0.4 reactivity due to MTO: (Figure 2.2.2.1? +0.02 - (+0.035) = -0.015% drho

+0.4]

reactivity due to xenon: (Figure 2.3.1.5 or Figure 2.3.1.2) -2.4-(-1.7)=-0.7%drho [+0.4] reactivit3 ue to samarium: (Figure 2.3.2.1) at power equilibrium is d constant .+0.4] reactivity due to rods: (Figure 2.6.2) 1.49 - 1.08 = 0.41% drho [+0.4] total reactivity change: sum of above: -0.74% drho [+0.4] boron worth at 1200 ppa: (Figure 2.7.2.1.orFigure2.7.1.2) -11.2% drho/1200 ppa = -0.0093% drho/ppe [+0.4] new boron concentrations (Cb - 1200 ppa)(-0.0093% drho/ppe) = +0.74% drho [+0.3] r Cb = (-0.74/0.0093 + 1200)ppe = 1120 ppe [+0.4] , REFERENCE-l '1.

Maine Yankee: R0 Rx Theory LP No. R0-L-1.13.

2.

Maine Yankee: TLO # CRC-101.C.

l 3.

Maine Yankee: Procedure No. 1-4, "Operations at Power," Section 5.

l l.

4.

Maine Yankee: Technical Data Book, Figures 2.1.1.2, 2.1.2.1, 2.2.1.1, l 2.2.1.3, 2.2.2.1, 2.2.2.2, 2.2.2.3, 2.3.1.2, 2.3.1.5, 2.3.2.1, 2.6.1, 2.6.2, 2.7.1.2, and 2.7.2.1.

192008K117 ...(KA'S) , - . ., - -. _ , _ _ _.. - - -., - - _ - -, _ _,,,., - _.. - _. _ _ - - - -. - .-. -. - - - -.. _, - _.-. ,, . ..-

r - . . ~ 5.

THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 23 THERMODYNAMICS ' ' ANSWERS -- MAINE YANKEE-88/02/09-GRUEL, R. " \\ , ANSWER.

5.08 (3.00) a.

Increase [+0.25]. Q is proportional to the mass flowrate, so as flow decreases moderator and therefore fuel must heat up [+0.5]. Decrease []+0.25]. b.

Increase in steam flow will decrease RCS Tayg [+0.5 temperature)(which will tend to decrease fuel center-line . A is..n er t 'I.~d' E,,,s r3 a,,u,-.u..n.3 :-,..-4 p..- d.. e. nye u,i/s t...o.

, ,

c.

No effect [+0.25]. Subcooled heat transfer is not affected by pressurechanges[+0.5]. d.

Decrease [+0.25]. Q is proportional to delta-T/L (gap width) --> delta-T is proportional to QL, so as L decreases, delta-T (and fuel center-line temperature) decreases [+0.5]. . REFERENCE 1.

Maine Yankee: R0-L-7.3, PPH-109, PPM-102, ELO fPPM-103-4.

193008K116 ' ...(KA'S) ANSWER 5.09 (2.50) a.

1.

core delta-T less than full power delta-T, but greater than zero 2.

T-cold constant or decreasing, but greater than SG T-sat i.- 3.

T-hot constant or decreasing . 4.

core exit TCs trending with T-ho~t i 5.

core subcooling greater than 12 degrees F 6.

heat removal via steam flow +, sV r sse ss e..ske o dureww >, j Any four (4) [+0.5] each, +2.0 maximum.

L SG pressure should be about 900 psig [+0.5] (slightly lower l

values are acceptable due to core delta-T) REFERENCE i l 1.

Maine Yankee: Heat Transfer R0-L-7.5, pp. 5 and 6 of 10, Rev. 1.

ns ne. bakest G S 0. l, As 7,.jp te, $ 4 gi., g,,, s, % n ! SE.

Steam Tables.

000017EA12 002000K515 193008K122 ...(KA'S)

- . ~ 5.

THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 24 THERMODYNAMICS ' ' ANSWERS -- MAINE YANKEE-88/02/09-GRUEL, R.

ANSWER _ 5.10 (1.50) ' 0. 5' a.

increases + ' 0. 5' b.

increases + c.

decreases 0.5l REFERENCE 1.

Maine Yankee: Lesson R0-L-7.4, ELO iPPM-104-5.

191004K106 ...(KA'S) . ANSWER 5.11 (1.00) To limit the potential for and consequences of waterhammer [+1.0]. REFERENCE 1.

Maine Yankee: OPS Memo 9-D-3, Rev. 1.

059000G001 ...(KA'S) ANSWER 5.12 (2.50) a.

assume nomal letdown flow = 80 gpe [+0.25] 553- , assume RCS T-cold at 100% = inlet temp to regen Hx = 55( F t l [+0.25]

, =(80 ps)(ft**3)(550 F]- 316 F))(1 ft**3/7.48 gal) 1 BTU /lb-F)(60 min /hr Q(511( bf Q = f E 6 BTU /hr [+0.5 assume nomal charging f$b = 65 gpa [+0.5] b.

,

Tin = 120 F w Tout = 120 F + (9.4 E 6 BTU /hr)/((65 gps)(1 BTU /lb-F))(1 ft**3/7.48 gal)(6e - _ Tout = 409 F [+0.5] ti (can be alternative 1f det' ermined by flow / delta-T comparison) c.

T = 316 F = 20 F sub' cooled --> T-sat = 336 F [+0.25] P-sat (336 F) = 112 psia (approx.)

[+0.25] , REFERENCE j ...(KA'S)p.101,Rev.SA.

1.

Maine Yankee: NS-4, 004020K502 ... .. . - - ... - - - _...- .. _.. _ . . ... __

.. - . , -.. _

. ,

6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 25 ANSWERS -- MAINE YANKEE-88/02/09-GRUEL, R.

, ANSWER 6.01 (1.00) a.

False (5BNOTtrippable) [+0.5] b.

True [+0.5] REFERENCE 1.

Maine Yankee: CEACS,NS-9,pp(KA'S) . 3 and 5, Rev. 5.

001090k404 001000K403 ... oso

ANSWER 6.02 (1.50) 1.

high neatron flux power pre-trip [+0.3] - cannot be disabled [+0.2] (.bs a cr > aot a.y befo-1.ote p t- < d 2.

high rate of change neutron flux pre-trip [+0.3] -[disabledso-adit sdy below 10-4% power g a p,, a y, ,y,, 3.

thermal margin / low pressure pre-trip [+0.3], disabled below 10-4% power [+0.2] a+'*M L c be %ue4Ly b,/p.u eu,, 2.is fo# ' REFERENCE CEACS, NS-9, p(.15,)Rev. 5; 8 Ph US~ / fI 1 / ) 1.

Maine Yankee: 001000K403 ... KA'S 001000K402 ' ANSWER 6.03 (3.00) a.

Reactor power is the higher [+0.5] of: the associated nuclear T-cold is used for compensation

+0.5.;.p(ower safety channel [+0.5], OR the power de auctioneered high) RCS delta-T

+0.5 (Auctioneered high) . - L 1.

periodic reset is necessary to raise the setpoint [+0.5] 2.

none [+0.5] REFERENCE 1.

Maine Yankee: RPS, NS-12, Section 2.1.1, pp. 9 through 14, Rev. 5.

' 012000A101 012000K402 ...(XA'S) i , .. _.,,,,- --.--------.---.--..--_---.n-.--- --,-..----,.,-,..,-.~~..,.--- -- -.-. - -., , -. -., - -.

'

. . 6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 26 - , ANSWERS -- MAINE YANKEE-88/02/09-GRUEL, R.

ANSWER 6.04 (3.25) control lever to "no fuel" position.y moving]the injection Engine can be immediately shutdown b a.

[+0.75 no,m s<snm M sJ.u utn croar) m e su,r,+ t o.r..., <- p.s a., y s a a.-s s b.

Overspeed is minimized by starting the governor booster pumps [+0.5] and b on its bus [y starting the diesel with some electrical loads +0.5]. c.

On an autostart, both P-29A and P-29C breakers shut {+0.3]. The circuit is designed such that if the "A" service water , , ' p(ump breaker (P-29A) shuts, the "C" service water breaker P-29C) will automatically trip back open [+0.3]. If the "A" i service water pump breaker (P-29A) fails to shut, then the "C" service water pump breaker (P-29C) will NOT trip open 1:+0.4]. The logic is designed to minimize diesel loading [+0.5; . REFERENCE 1.

Maine Yankee: Diesel Generators, AS-12, pp. 53, 56, and 57, Rev. 3.

064000G007 064000G009 064000K401 ...(KA'S) ! ANSWER 6.05 (1.75) a.

The EFCVs are installed to isolate the SGs and protect the RCS against rapid cooldown following a major downstream steam line rupture.

[+0.75] b.

During cooldown, a vacuum can be maintained on the upper portion of the valves' internals which holds the valve up preventing valve flutter and allowing steam firw at very low pressures and flow rates [+0.75]. The system allows

,

an additional means of decay heat removal [+0.25]. , ggfERENCE 1.

Maine Yankee: Main & Reheat Steam System, PGS-2, pp. 3, 9, and 10, Rev. 5.

039000G004 ...(KA'S) . ,.-. - , .,. ,, -, -, - , . - _, - -. -.. - -., -.., - -. - ,,,., -

' ' . . ~ - 6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 27 ANSWERS -- MAINE YANKEE-88/02/09-GRUEL, R.

, ANSWER 6.06 (2.50) a.

1.

when PCC heat exchanger outlet temperature > 85 degrees F 2.

when SCC heat exchanger outlet temperature > 89 degrees F [+0.25] each .r b.

Radiation monitors RM-3401 and RM-1701 cause closure of the respective systems' surge tank vent valve [+. (and yiggt' -*of the gland leakoff tank overflow to the PAB sump).

a e-m.

.c o.5 psig) 0.25] SIAS (on containment press > 5 psig) [+[+0.25] e.

SIAS (on contain.nent presi > 5 psig]or b.

Pzrpress<1585psig) [+0.25 CSAS(oncontainmentpress>20psig)andSIAS) [+0.5] RAS on RWST level < 100,000 gallons [+0.5] n containment press > 5 psig) [+0.25 rip (on SIAS and SG press < 400 psig) ][+0.5] CIS HFW ' c.

none [+0.5] REFERENCE 1.

Maine Yankee ECCS, MS-5; Rev. 5, p. 36 (SIAS), p. 48 (CSAS),

p.43(CIS). ,, MaineYankee:Containmen$ Spray,NS-7,Rev.3,p.25(RAS)'. 2. ' .- E Maine Yankee: Main Feedwaher, PGS-12, Rev. 4, p. 65 (MFW Trip). , 013000K101 ...(KA'S) I ( o ! ... ...,,,. ~. -. _ _ -, - - - -. - - - _ _. - _.. . . _ _,. . - - _ - - -. ~... -. - . ' ' . . 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 30 - RADIOLOGICAL CONTROL ' ' ANSWERS -- MAINE YANKEE-88/02/09-GRUEL, R. ANSWER. 7.01 (1.50) 1. to ensure uniform heat transfer in the steam generator [+0.75] 2. to ensure the loop remains subcooled [+0.75] REFERENCE 1. Maine Yankee: Procedure No. 1-10-5, Section 2, p. 1 of 5, Rev. 7. 002000K409 ...(KA'S) . ANSWER 7.02 (1.50) a. by increasing the seal injection flow as seal leakage ficw increases [+0. 5] b. RCP seals may not receive adequate lubrication [+0.5] which could result in seal stage wear and damage [+0.5] REFERENCE 1. Maine Yankee: Procedure No. 1-10-7, Section 6.5, p. 7 of 16, Rev. 23. 003000A201 003000A401 ...(KA'S) ANSWER 7.03 (1.00)to eliminate a means of pressurizing the RCS at low temperature [+1.0] -REFERENCE .. k Maine Yankee Procedure No. 1-11-6, Section 3.0, pp. 1 and 4 of 32, Rev. 22, 2. Maine Yankee: TS 3.4. 004020A103 ...(KA'S) . - - - - - - - -, -, - - - -,, - -. -,. - -,, -,,.. - - - - - - - - - _ ,,,, -, -, -,,, -. - - - -.. - - - - --., - - -, - -, - - -, - - , - . . ' . . '7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 31 RADIOLOGICAL CONTROL ' ANSWERS -- MAINE YANKEE-88/02/09-GRUEL, R. ANSWER. 7.04 (1.50) 1. SIAS [+0.5] [+0. 5] [+0.5] 2. PORV actuation 3. RPS trip REFERENCE 1. Maine Yankee Procedure No. 1-22-2, Section 5.3, p. 5 of 10, Rev. 7.062000A208...(KA'S) ANSWER 7.05 (1.50) a. at 3.5 in Hg or less [+0.5] b. To prevent harmful vibrating stress levels [+0.5] which could lead to turbine damage (cracking of blades or disc attachment areas) [+0.5]. REFERENCE l 1. Maine Yankee: Operations Memo 9-D-11. , ' 045000G001 ...(KA'S) l ANSWER 7.06 (1.26) a. the valve Lst be tagged shut [+0.5] j l b. hydrogen [+0.5] concentration exceeding 4% [+0.25] ,, i l RErERENCE - E Maine Yankee: AOP2-30,Section2.0(d),p.1,Rev.12. l 2. Maine Yankee: AOP 2-17, Section 1.0, p. 1, Rev. 8. 103000K406 ...(KA'S) . I l . , ' - . . , 7. PROCEDURES - NORMAL. ABNORMAL EMERGENCY AND PAGE 32 RADIOLOGICAL CONTROL ' ' ANSWERS - MAINE YANKEE / / -88 02 09-GRUEL, R. ANSWER, 7.07 (2.00) a. 1. trip the reactor and turbine (+0.51 2. trip the RCPs (within 45 seconds) [+0. 5] b. an operator must be dispatched to remove power from the PORVs [+0.5] c. SGs may be fed from the fire system [+0.5] REFERENCE 1. Maine Yankee A0P 2-28, Steps 5.1 and 5.2, Rev. 12. 2. Maine Yankee: A0P 2-90-1, Step 5.3, Rev. 5. 3. Maine Yankee: AOP 2-90-8, Section 1.0, Rev. 5. 000065EA20 039000G013 194001K116 ...(KA'S) i r - h 4 e i v , -

,----w

- - - - - - - - -v: -, -- - - --- .,, - - -~ ~ - - - - - - - - - - - - - - - - - ' ' . . 7. PROCEDURES - NORMAL. ABNORMAL. ENERGENCY AND PAGE 33RADIOLOGICAL CONTRDL ANSWERS -- MAINE YANKEE-88/02/09-GRUEL, R.ANSWER 7.08 (4.50)RCP Trip Criteria 1:+0.3] [+0.3] a. 1. 2. SIAS Initiation Criteria 3. SI Throttling Criteria [+0.3] 4. EFW Supply Switchover Criteria [+0.3] 5. Minimum FW Flow for Decay Heat Removal [+0.3] Manually [+ trip]CEDMGen.setoutputbreakers(MG-1A, b. 1. MG-1B) 0.4 , 2. Manually OPEN and reclose 480V supply breakers to BUS 9 and BUS 12 [+0.4] 3. (Go to FR-S.1 and) ensure turbine trip [+0.4] 4. Ensure minimum FW flow for decay heat removal [+0.4] 5. (Ensure reactor is subcritical and) initiate emergency boration [+0.4] c. Send an operator to locally close the valves [4.5]. They are located in the EFW pump room and equipment hatch area [+0.5]. REFERENCE 1. Maine Yankee: E-0; Step 2, Step 11, Rev. 1; Foldout Page, Rev. 3. l 2. Mair.e Yankee: FR-S.1, Steps 1-6, Rev. O. 000007G011 000029G010 000069G006 ...(KA'S) \\AhSWER 7.09 (1.50) J '= , h To prevent overpressurization of the CEDM duct work (if three fans were running). [+0.75] b. To cool the stagnant upper head fluid (so that loss of subcoolingmargindoesnotoccur.) [+0.75] i REFERENCE , ...(KA'S), Step 5 Caution Basis, key. 2. ES-0.2 1. Maine Yankee: l 000007G007 _ _ _ _. _ .. _ _ _ _, - _ _ ' .. .7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 34 RADIOLOGICAL CONTROL ' ' ANSWERS -- MAINE YANKEE-88/02/09-GRUEL, R. ANSWER. 7.10 (3.25) a. If it is the ONLY RCP available to provide pressurizer spray. [+0.5] b. 1. RCS target pressure is set to (the equilibrium pressure of rup]tured SG to) minimize / eliminate RCS leakage [+0.75. 2. RCS target temperature is set to maintain required subcooling margin at the RCS target pressure [+0.75]. c. 1. ES-3.1 [+0. 5] 2. When a more rapid cooldown and depressurization is required. [+0.75) REFERENCE 1. Maine Yankee: E-3, Step 3 Caution, Steps 17-20, Step 42 Basis, Rev. 2. 000009EA20 000009G012 003000G001 ...(KA'S) ANSWER 7.11 (2.00) a, the boric acid storage tank [4.5] ^ b. the boric acid transfer pump [+0.5] c. through an idle charging pump through the HPSI lines (by [ l operating BA-N-36 or 37 and opening HSI-M-40, 41, 42 and 43) [+1.0] j. REFERENCE - E Maine Yankee: Procedure No. 10-1 Appendix D, Sections 1.0 and 5.0, p. 27 of 65, Rev. 11. 000024G010 ...(KA'S) l . . .- . 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 35RADIOLOGICAL CONTROL ' ' ANSWERS -- MAINE YANKEE-88/02/09-Gk'JEL, R. ANSWER, 7.12 (1.50) a. Alternate alignment is possible using a "plumb-bob" suspended from the hoist box. [+0.75] b. The major disadvantage is higher personnel exposure. [+0.75] REFERENCE , 1. Maine Yankee: Procedure No. 13-6A, p. 1, Rev. 4. 034000G009 03400G3592 ...(KA'S) ANSWER 7.13 (2.00) a. 1 layer = 1 HVL I/lo = 2**x < x = In 25/in 2 = 4.64 Therefore 5 layers are required [+1.0] (Full credit given for any correct method.) b. Yes[+0.5]. The resultant radiation level results in a dose rate (125 mres) in excess of 100 mrea in 5 days [+0.5]. REFERENCE , l l 1. Maine Yankee: Protection Manual, Section 1.0, p. 1-1 and l Section 3.4.1, p. 3-2. l 19401K104 ...(KA'S) , y . . b a i l ._ _ . _. _, _ _ _ _ _ _ __ _ _ _._ _,.__ _,,_ _ ____ ~ _ _ . _ _ _ _ _ _ _.. _. -. _ _, - _ _ _. _. _ _ _ _ _ _ _ _... _, _ _ _. . - -. . . -- - - -.. .. ... ... ' .. , ' 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 36 i . ANSWERS -- KAINE YANKEE-88/02/09-GRUEL, R. , ANSWER 8.01 (2.00) RCS T44g [+0.25] increases to 210 degrees F [+0.25] a. Te-e. b. control rod withdrawal [+0.5] (Neutron flux log range channel instrumentation {^0.25}'#' c. indicates) greater than 10**-4% rated power -[e0.25] /t p+0.5] d. They differ because of the change (decrease) in boron concentration necessary to counteract a Tavg change (increase)of at least 490' degrees F (500 degrees F - 129-degrees F) [+0.5]. S98 180 REFERENCE 1. Maine Yankee: Technical Specifications, pp. I and 2 of definitions. 001000G005 001000K529 001010A101 015000G005 ...(KA'S) , l* a h . < - - -. _ _ . -. . . . - _ ' . . . 8. AMINISTRATIVE PROCED'JRES, CONDITIONS, AND LIMITATIONS PAGE 37 . ANSWERS -- MAINE YANKEE-88/02/09-GRUEL, R. . I ANSWER 8.02 (4.50) a. R0 [+0.5] per Tech Spec Figure 5.2-2. (Maine Yankee Procedure 1-26-4, Section 4.2.12, states that the SOS shall possess an SR0 license.) b. 1. review and initial the Crew Document Review Book 2. review and initial the Shift Information Book c r 3. review and initial the Yellow Tag Book 4. review and initial the Night Order Book ! 5. review the Operations Turnover with the off-going PSS 6. review the Control Room Log over the past 24 hours-or-back to his last working shift , 7. discuss reasons for annunciator alanns, abnormal system line-ups, status of safety related systems, equipment tagged , 8. review initial conditions and precautions of procedures l in progress, which he may be involved with l Any five (5) [+0.3] each, +15 maximum. c. No[+0.5]. TheCR0leftthecontrols{46r5dntwor,ccasionsO.cJ l [2^. 5].'.- l t l d. Only when an SOS (+0.5] and STA [+0.5] remain in the Coritrol , j Room. REFERENCE /* .,\\ < 1. Maine Yankee: Technical Specification, Figure 5.2-12. . - ' , E Meine Yankee Procedure 1-26-3, Section 3.1.3, Rev. 6. 3. Maine Yankee: Procedure 1-26-5, Section 4.1, Rev. 1. 194001A103 ...(KA'S) tl {, . - - -, .,,, 2-----.---r- , .-,-v-,v.-w---..--- e . . - - - - -.. -... - - * - - - - . .- . - 8. ADMINISTRATIVE PROCEDURES CONDITIONS _'10 LIMITATIONS F?5E 38 ANSWERS -- MAINE YANKEE-88/02/09-GRUEL, R. , ANSWER 8.03 (2.00) a. Direct alignment checks of the affected system [+1.0] (using approved plant procedures). b. the procedure [+0.5] c. (immediately) return to the Control Room [+0.5] REFERENCE , 1. Maine Yankee OP Memo 9-L-20, Rev. 4. 2. Maine Yankee Procedures 1-300-10, Rev. O. 3. Maine Yankee Procedures 1-200-10, Section5.6(d),p.4of38, Rev. 2. 194001A102 194001K101 194001K116 ...(KA'S) ANSWER 8.04 (3.00) a. 1. when the component or equipment is Safety Class [+0.75] l ' 2. when the independent verification results ia. a i significant amount of radiation exposure (as determined j by the PSS/ SOS) [+0. 75] l Awhitetagcanbeclearedbytwoauthorizedindividuals;]the ! b. l supervisor or "coworker" of the "tagger' [+0.5 for either and the PSS/ SOS [+0.5]. ' ' c. acnthly [+0.5] j. REFERENCE - E Maine Yankee: Procedure 0-14-1, Sections 5.1.15, 5.6.4, 5.9.1, Rev. O. 194001K102 194001K103 ...(KA'S) . ., - -. - - - -.,.,. , - - - - - - ,., - - - -- -- - . . ' 8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 39_. ANSWERS -- MAINE YANKEE-88/02/09-GRUEL, R. , ANSWER 8.05 (1.00) 1. Plant Manager (or designated alternate) Gt.o] 2. Radiological Controls Section Head (or designated alternate) [f% iA A * l*N n N.e, j A o .w, P wo el/.~.a er su,,,,t;# N.5] c:che. REFERENCE 1. Maine Yankee: OPS memo 9-L-13, Rev. 2. 103000G001 ...(KA'S) . ANSWER 8.06 (3.00) a. The valve must be reopened [+0.25] within one hour [+0.5]. b. LPSI p] ump P-128 must be tested [+0.5] within two hours [+0.25jor s. j pq p x..t, p y g,w 4g,gcutQ c. Immediate action (+0.5] must be taken to restore at least one pump to operable status [+0.25]. d. No action is required [+0.75]. REFERE'Cr n i 1. Maine Yankee: Technical Specifications, 3.6.C.1, Exception and 3.6.C.2, Remedial Action 1, p. 3.6-2. Amend 97; 3.8.E, Remedial Action d, p. 3.8-2, Amend 88; 3.10.A.3, p. 3.10-1, Amend 68. 001050A204 006000G005 006000K419 061000A204 ...(KA'S) ,. . . O I . _ .: . 8. ADNINISTRATIVE PROCEDURES, CONDITIONS. AND LIMITATIONS PAGE 40 - ANSWERS -- MAINE YANKEE-88/02/09-GRUEL, R. ANSWER 8.07 (3.00) 3psig[+0.5]. Maintains peak accident pressure below 55 [+0.5] and (permits a positive containment pressure which)psig a. allows for successful operation of the continuous leakage monitoring system [+0.5]. b. 112 degrees F [+0.5] 1. shift HXs k "= "i n ' E t H ' 2. add HXs . 3. add SW pumps 4. add PCC pump (vs.a7 %, imw mw.u.po Q 5. reduce power Any four (4) [+0.25] each, +1.0 maximum. REFERENCE 1. Maine Yankee: Technical Specifications, 3.11.C p. 3.11-2, Rev. 89 and p. 3.11-6, Rev. 80. 2. Maine Yankee: Operations Memo 9-B-3, Rev. O. 022000A101 022000A102 022000G010 ...(KA'S) ANSWER 8.08 (2.50) o&IBl$feps a. when it is within 4 steps of its upper electrical limit [@5] b. True [+0.5] c. Operation ma;, continue provided: satisfied [+0.5] gin requirements are demonstrated as /* the shutdown mar 1. without including the reactivity - associated with the inoperable CEA [+0.25] within 2 hours i , [+0.25]. i 2. only one CEA is inoperable [+0.5]. REFERENCE l 1. Maine Yankee Technical Specifications 3.10; Sections A.2, A.5, B.2; pp. 3.10 - 1,2; Rev. 68 98. 001000G005 001000K401 KA'S) ... _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ __. ' ' . . 8. ADMINISTRATIVE PROCEDURES. CON 0!TIONS. AND LIMITATIONS PAGE 41 - ANSWERS -- MAINE YANKEE-88/02/09-GRUEL,R. , ANSWER 8.09 (4.00) a. the on-duty PSS [+0.4] b. plant manager assistant plant manager operation department manager technical support department manager [+0.3] each a c. declaring and categorizing the emergency condition notifing offsite authorities advising offsite authorities with respect to protection actions coordinating emergency operation of Maine Yankee and governmental agencies [+0.4] each d. Maine State Police [+0.4] within 15 minutes of declaration ofan emergency (or within 30 minutes of discovery that an EAM EM-has been reached) [+0.4]. REFERENCE1. Maine Yankee: Esegency Plan, Volume II, Section 5.1, pp. 5.1 ' and 5.2; Section 3.2, pp. 5.5 and 5.6; Section 6.2, p. 6.7; Volume 1, 2.50.l Section 4.0. 194001A116 ...(KAS) J' . h n -. _ _ _. _ _ ._, _ _ _, . _ -.. - _ ,.. _, ... _ _ _. _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ - _ _ . .. . . - . ........................................................................... EQUATION SHEET. ............................................................................ . . Where mi = m2 (density)g(velocity)i(ana)) =(density)2(velocity)2(a;'a)2 ............................................................................ KE=*{2 where V = specific g 3 = PE +KE +P Y22 PE = mgh PE + KE +P V 2 l g volume P = Pressure ............................................................................ Q = mc (T-Tin) Q = UA (T-Tstm) Q = m(h -h ) p out ave i 2 . < ...................................................................,........ P=P10(SUR)(t) P = P e /T SUR = 26.06 T = (B-p)t t o o T p ............................................................................ CR (1.Keff1) = CR (I~Eeff2) CR = S/(1-K,f f) delta K = (K,ff-1) i (1-K,ff3) (1-K,ff)x100% SDM = M = (1-Keff2) eff K ............................................................................ I = A e.(decay constant)x(t) decay constant = In (2) = 0.693 A O 1/21/2 t............................................................................ Water Parameters Miscellaneous Conversions l 1 gallon = 8.345 lbs 1 Curie = 3.7 x 10 dps l 1 gallon = 3.78 liters 1 kg a 2.21 lbs 1 ft3 = 7.48 gallons I hp = 2.54 x 10 Btu /hr , l 6 Tensity =62.4lbg/ft 1 MW = 3.41 x 10 Btu /hr Density = 1 gn/cm 1 Btu = 778 ft-lbf Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 i l Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters 2 1 Ata = 14.7 psia = 29.9 in Hg g = 32.174 ft-lbm/lbf-sec ' ............................................................................ - - - - _ _. _. _ _. _ _ _ _ ..__ ._,__. _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -____ _____ ... . . . .tm0 RcvicW J crm: SfhWP7rinac 2.1. l. 2 . acylce n 3'/W cmt 4hdlP7 rncnacD n WI//Ad . f f I { , , -) . $_ =. _. _ _ . .- _ .. _. ~. _ _ . _ ..... _ ._. _. . _ ____. _ _ _ _ _ . _ _ _ __ __. , _ i._._ _ -, _. - .._. ._ .._ _ __. 4__ .. ,_. . __,.._=_.4._.. __ ___. ... _ _ _.. _. _. _ _ .__ . _ __ _._. ... . . _... ... _ ._ =___.o._. . ,. _ _ - ..,_4- __4 ___ - - . ._ -- _ 4.._. ~_ ..- _._ - . ,. _.. o--A; . o ...a.... . -... _.. _ _...... - _ _... _ _.. _ -... _. _. _. _ _. - -.. _._ - .___ _ ___ __........ - . - -.. _ __._._n4..._.__..__ . _. _.__ - ._ .. . - __ -i. * _t._ - ___. - :- _--- __.._i___. _ _ _,. ._, _,_.... -' _. .__.4.....i.....__. __, - r.._4.._-- -- + - = a_ 4 __. -- .. _. _ _ . , . -4 _ j.._ __. ,.-_4 _ _a __._..._.4"...._"u..__.... ._. a... -\\ ~=. _\\. _ __ _... _.. _ __ _-_.. _, ,__t , y -. . _ . .__.a.____.. .a... .... _ g . ____._._.._._x_._.m.x..__ .. _. _.... .4 __ . - -.... _. _. _. _. _ o o . __ _ _ -- . ..... _. - - . -- - . c.o _ H - - 4 __4 - a.. _ g _ __ y am .... a.. i _.. g.__. _ _ _ -. _.. _.. _ _ _... _.. _... o g ,.,..g...9..___.-...4..... . _...., _ _ _ _ . g. gg y .. _ t_. __ g _ n_ Cr _ _... _... . _ . - . _ - _ _.. _ _. _ _ _ ... . _ _. - . _. a _._. o ... . _ _ s __ _ . _ _. y r a . _ _.. _. _. _ _ .. _ _.. _ _ . gg __ _..... ). ........ @ _. . .1. s. ...,. ;..._....._.. y , mo ._ _ . _,. _..... _ , ... _ _. _ _ _. _ _ _ _ H _.. .. _. _ _ _ _- _.__,_, _ __..._ _ _ _.. . . - __ _-a. _ _, _ _ _ _. _. . . .. _. ._ - _, - _, _,. _.. _. _ _ s .. .. _ _. _ _. -.. . c- . _ _. _.... _ _.___..._.4........_,._._._. -........... ..... _. _ _..... _ _ _.. . _ _ _. _ _. _ _ g cc . _ _ _. _._.... - ...,. _ _ .) . ___ ._ __ w . . . . o sW . _. _ _,. _ _ _ _ _ _ _ _ _,. _... _. y ..._.._..._4.__._. __ _.. _ _. _ _ _... _.. c .. u - .__ __m ..._i... _- . - H . ._. + - _. .. _. ..,._.s..-..-s. a _ _.. v. =._.t. _._......... - - 4._a..... _.. _ _, _ _ _ _-- a. _ _ - s . , . ... . .._ _.... _. . . ...... .. .s. _ g - _.. . _ .. .. . . .. ......, _... _... _,.... _. .,... _,. _ ..... _ -.. _ _.,........ _ .._ H (n>z . . _ _ . _. __ .,._.i._ _. m _. _ _ _. __ _._. ___. _3 ._- .. _. _ . ._. _ o . _4._..#.._.___.s._.._._ . . _. , __.... y .. _ _ _. _. o ....m._. _.___. __m... _ . , .. o - r _ _ _-.. t _. _ . _. _ _.. _ _. _-r .-. _. ... O ..o. .. H .... .. .... .._......sb._.._ ..,._ _ _..,... _ . _ ..,.L._.___ .... _. _ _ . L., .. _ _.. . _. - - . .... L. 4.____ _ _. ~. z__,. .. _._ .. c:t_._._._. _ _._ _ - - _ _ , _ _ . u__. . _. _. _. _. _ _ _ _. _ s....___._. .4.._. .... . - , . . _. ...T*.... _.. g'**~ """1 . 4.a. . .., _ " " _ . *~ ( . t . -., ...,..,.._.a.- . .,.....,._ _.. -.. _. . , ... . . ___- . _ .. _ _ _. .. _ _. . ___ , --. .__ ___...a__ . , .__ _.4__ =4_._ ,- _ _ ._ - _ t___2._=... __ - _.- m. . ,.. . ....... .- - . ... __.. _ _.. _. . _ _, _ _., _.. _.. . _ _m._. . ..._.._4 ._ - - . _ _ _ _ _ _. -.. _,. .,.__ _. _. _ _m. _ - . _ ,. a. . . . _ -. _. _ _. _ - -- - _ . _ e . . _ _ - .....,._ _ _ _.- - -. _A. : :-.. _. . ._...i.. ....,._.. _ ... _ _. .. - _.,.. _, _ - _. _ _ _.. _.. _ _. _. _., _. _. _ __.__.. _.. _- .._. . _, _ .. _ _ _. __ ,... .s_._4__,.._.__.__,. ... =. _. ___ _ ___.. ., _.. - ._._.. . ,. . _ _ .. . t. -. .=t._ e _._ .. _ . _ _. , _. _ .. -, _.. a... _,.... _..... .$_......... g _.. . . _. _. ._ . =- . -. . ..._.__..a__ .. ... .-_ ._ , .,-_t___ .. _a , _ , ... . .y .... .... .... _... ... _. , _......__._.. -. _... . __.. . - .. _ _ _. _.., _ _... _ _... _. _ -._.:2 __ _. __.. _. _ _... _. _...... . _ .__.... . _.. . . _... _ . _ _ _. _ _.. _... _ _._ ___ ._. _ _ ._ _ _d._. . ,. _,. .,..... . ...,. _ _. . _ _.. f_..p.. _.....::4:._..:4._..._.. 4 _..,.. t , ...g., ._. - ___I _.. _.... .. . .. _. . ... . ._ _. .. l _.... . , .. O I . . l t1 N. -. ? ? l (J 930 83d OH8 W1'l30 %IO*0T 01) Y . . , f l - _ - - - _ _ _ . - _. .- - .. _ _ _ _ _ _ _ - . i . s.. s. . . . . - .v a. . _, , . . - . I f . FUEL TEMPERATURE DEFECT VS POWER ~ I CONDITIONS: CORE 10 .I p. . __ e ],d. }i ...l . :1 ,. . -2.0 p ..12 th...r:.. .. . d. p11.i.- d._.p... . _ L. ,J . .. i3 '1 2 :::. t: 4 . -> y:use T . -{ _... 7#. {,n. t.-- g-et-:fh. [-h, q 11 ,7 zartu 1: &, - n ==s1: .h2r_ .: u - -q. 4: nL. n: :_:s_I11 .. [,__. p.. : 2 si-a M _ _ t ..ts :!r+- r-2 .,tr 1s,r 11. t#_,_ ... l 'i._....t. g: _1.8 _ _., h_. 1 :::.. ..3 - til2 u g 13 } y.... t - . .3.... - -,...4-- - gm ggM 4yh2- -7n,-+',] -._,... . ..... . ::, ; tq-r i,.1 tp : 1-11 :.: s tipt - - - se - a s.1. .rv srp gn1 v1 ..: ,. x ,1t._na~. g q;y _u _ y' # *p syn:' * --" ''' b. "* I I - q"; ' gn.a. _' n.. i:. g'g ;ij7 m,L ^ - m -q-1 6 - 4m_,,t q. . - ys,=. ;n.,;;.:1Md --t ji-j },qu-j. 1_gr w:q,,.- #,,n g . h. LI i -- - i q:.iE In,., j n. E ! p :; nu 7,l: it :.., t1j: t rr -~4 , qe,-- t::- art::. .: trri - eir - = . - ,..= :a u. .]2 rc. =.mcr _.2:2 o g4a::=::: :::l;e{3; i5 Mr- ' -* w m ===:-.2 m :r .. uug. H. - a .. 1. e.. _ @;p1 p: 3: Pu .e a- _3 7 -- - t-tr*I- ]u_. d.ba:4, -,,; ..r r - -1 :.-_, - - . _. % 5, g-l,s.1_ . y_ _ u,.,3=r. .2. r,{ a . y p 1,,. . i3 2: -= +-+n m..- ~. . _ _ =d tt . t..T..i = =r - - . - -. , ---. - - + -- +e - . . t:la+. ::- i--.n. ;__ . -1 .=: .-2g ndT,1~.- t. _3 t,lt12) n_.3 ^r.t.;- u. . n. a.;-I,.Sg. J. :. - m h r a Q1_ - .. ... _ a Qa efg-. -.m.,e s . 1~1;- 1-. r i: 31.. ' . %np-sr2:. %;p.. ip n-3p g _3.g_q. ~ 1_ m t,9 m1 24,1 n u t] ;be r in1 -JE gm. j ;,),,.u xuy; 4,, r,.rr , 3,, . I:.... __.. ._ _ .. 1,,a. 3...e. t 1,m- + t_u_.r -. f - nI _J - F .. m._.,F_1._77. _._t . .:2-qy__ ____. - j g _:f p._._" -x_ ntx r ..20:t :. JA .z .-- [d- 21 :_r _ J 4]# at:.1 r'~~t*r_t:{S li- t:r :r- -2 z'.N . " nc J ^x" i - U' l' p*u,;l7j3is.-P-11. t-4 1-x --"~~~# ^ m ""' T "' ~" ' ' -0.8- . h_ 1 - --. rt- - - ^ 1 g.qr :..n - - - 4, .c . _. l... 1. ==:. + H - _ 8 :t_.,2.y'l .. ... ..2: -7,. . ..., - _.c t.h.r2:j::,, ji. . :: r: i s. i i .:- .,w-n1n p::-:r:.- . ,- e1. i.... p!,.a.gi., y i .. ... .r~ ..gg_:vl_-3;, } ... y. .4.. - e _,n:_ a 1: r> , a-. n , 1- .,., m.. lya-- - . 1. a,-n ., . a _0.6 38'. . M,,; p'g 'g j - '#C, {. 1 '"5 ": F=3'#.=..' r-~~~~ j,1'1.f;f..I.tssjF: :" ' i.1~r -=.r:~ra .. -t. W. .g i! j . 3, ~ p_= = r r:r - at _. f=-m .p,g_,3 - Br.u- ,q-e:== - jT ll1gi g;a,..., g j. ,- ..tj:- - g g sc.1 soc. r . -.}.:a-m u - _ .. .. '- - i - - 4 R.. :., n.u: t, - s - , ,_ .- 4- ~+ -r . ,0 4 - 1: . t s'-' p g*- I ' s".- sul{IpI pi ! 'i si u - e.j-Ir n.I . ui r" - y81 j !: " -: f n! ptj s: - l ' 'u ! u }' ' L ' ' ' { y 't vag !2 t m41 i + 115 32 1:4=s 2. = _ n irl p'n4..n m .r m;g i! 3.. 1.g220 b,ut11. q i - -el ... - i , -- _g.2- =~3r.2 2= E .:.:. . I @.... I':.' .. 1x _;; - ~ F.::4m'.J =2*j'1 g;,._...,.,; ..4, .rlj=,I r _ . . '3' :. P. :.:: ., " - r t' - 2l _ ... rc . , _2 4..f- -- 2 n .. . ya4- - ..2a_t . . M3--.2,;p ...pt4_=:.&a 7.n.i:=m= uryr pag1: x =~ .. r n r.. u. L 1.;x:1 nt n.0.0- . t..s:. u 1- . . 10 30 50 70 90 100 A rv ' POWER W % _.W - r- . \\_ , j i . _ _ _ -______ _ _ _ _ ___ . . . i I j . . . J - .. v - . . . i MTC/ITC VS. POWER CONDITIONS: CORE 10, RRO, EO XE, NORMBLIZED TO MERSURED VALUES .--- i: __ 1.0 .__ _ ..4- - .- - - ---~~- - - , --- -_-- --- - -._ ____- - - - - -._ .mu . mei ....m,.mi- _ ,. -.. _ _,,4._ .-.. ..-m ..mM-u.- ._- -. >-.._m. >.._a. ,. ._.4 .. .-- m.._,_ _ ,. a_.-...s. >-.. _. .e- . . . _ .. ..--i-.mm. 4m.mimmumes, w-.-.-. _ . =.i .-_.. .M.-' '~ ~ ~ ~ ~ L._ %_y ..-....__ __._ ___-- .____ _ ._. _ - ._- _____. ,--__..,_ ._-_..__-- - .-.. - - - g _: .- &- m-; .- -.- me, ar l- - - .--- .--- -_ -- v c) -- -- m_~--_ -._- .___- , __ - .--.._ ---_. .-_.-- 0.0-_._ -_- - _ .._ ._ .-_ _ -._ __ _ ._ _ ___ .. , ____ -... ____ __.___. ._ _ .-.._. g ._________-_ ._. _ ____ _ . -,-,___y. g- . ,,- -.___ _-__- ,- g _ I E, Bac _- . ..--,_, .-- -__.__-_ ._ _ _ _. ._-.___ . _ ____ ,: _ - -. ~~ff --- .._ .___.-__. .__r:2 Q- __. _ _ .-. - -7- .--- o - . _.._ __- ._-._ __ ._.. __ Q, - __ .- -_-. i y - -_. - .- ---. .--.- --.- - m-1. 0 -- _ _.. - ... _.._ .__ - n u ~~-~~- --,. ,__ ____ .- . ____ - . __..- . ._. ___.. __ _ gg . . Q _'~~~ ~ nm,tre __.. - E T ._ .9 =:-,---__[ :Z- ,-- [ y _ . .- -- -__ . --. -< Ha _ _:-,- __.,_ ,, -- _. y __ ._-__ .-- . .---_,,,. ,---, yj. a. ._ -- - ._ .._-- .-. g - .._- <--___ . --__ - _ ._-- ._..-__- y , - ._ s .)__.-__ - .--___..__- _ ,---, - .. ,-_, _,=,,,'. -_- ._- - g . ....-,. .,.,-~_,,,'. . . , . ' [ -2.0 - .__ . Im, tre [ _ - -- .__ ' ~- - -. "__:,-- _ - ---w-c._ - o - 1---- - .-- - -- - -- - - _-. _-... _ ._ , = . - . .. .__. - -_. .._._. - ..- ___ .____. ._. _ ._ _- -___ . ._. . _. . . _ -

.-

- - .--- _- - - . .-.--__-- , - O ._,.__. --. - _ - - g _ .-_-- _- - _--. -

._-

_-. .-. y H , _3.0_ ._.-...._.-- . . Y , s , ,_-,_ __- __-_-_. ___. .__- J ' . . _..., . ..- -. N ' _ - .. a _ .- _ _.--._ ._. ._ _ __ _ ._. __ __ _ . g ._.._ - -____..-.- - -.__.- ._ .-. . _ -. __- g . p _ ._ _ . _._ _ __ _ _ -._ .--_-_- _ ._.- -__. _ _. __.._- ._ _ __. - _ __- ._.. -- - __- -.. - .-.. .- ... - -- . _. _._-_-.. , , -4.0- , , . , " 10 30 50 70 90 100 b POWER (%) F-E - . I \\, . . me mim 36 om (7/e/M rieuc 2. 2.1. 3 /' mlon er,3h M ~ om 4 NIM mmco ar'W Au. , , n . ) . . 'q..... <- .,. .... -_ = j. y. ., _ _ _ , ... . _ .__ , ' -[( ...___.____ __ PJ i E P .sp - .. ...__yp - / , . ..,..__/ ..f ',. ; j l __ ..._.}. . _ .. _ . .. _ ., i . 7.i r > i . < , ,st . , , j . . __ .___ ,T....".'.'.'.. , ,- 7,.. 4..... , . , ;.. . .,. ., . T ""~~' { . q. ,, .. .,_ _ . .__ - ...-7 , , .. .,... .. . 7 9..._ .... . . ,..._ . . ..<__ _____ - . , . _ j..}. ....._ . .,. . .<._q . H.- ..-..- - ,. i-- ' ^ - -- -- .-... -.- !.i .. . p .. g _ g3 .j .7. }, .... j < q.L.. . . . . j _ ._.. . q _..3.,,. g - ., , . xa - . , 4, i ,,, .w Da 2 " 'T *-'--_-1,.f" '. . - -- r i i;. O a i H ,--E.i .p. __ . t- , ,. w d .. ... . i. l , .. ga .. . ... , .i.. . , - __ __7.. , Q..d _1. . y - y. .. .... ...... . ... .....__ . .. , . ..3.. . . . g , oN - ,, , - -- - j, , i O Ey % ,,r. H - i .il,__ yi. .J.. g ._ . . . . .. . .. .< ..... gm i ,_ .. .. 7..._ .+ g ... . .. . _-__. .% ,. _p '.j - - - , , .q..+1 1.4..i.' p:+. - y (n.. . .. j j.< q..,/ { p ..j i.H--H:. ---H 1/-H H.- F l c-- c ,. ) n 3.{... ._ . .L. . }f t.t.. -l .f, l ;4 7>' ' ' , y , H O. -_..- . . j.. .'.q. . ._... , _-- H O , . . . J,- o "i.'. ' T. J q. E ' r._ i 4, . .. ' ' m . , , I .__ q .I'.... q. - -... . . , NH .L ., .< . .. J .[. . . H... . - o-i c . . i.1' _ g t- - i, ,i i i-r - ga i , n :z: ' t "1 b1 . . . . i , w . '-" a is , i _~~- -k .,h'~ a o . o _ i+i, 2- , ._ 1_ . _ _ l.i i , d ._ . .. . , . .' . .. . . . ._ . . .- -j. . a e , ._ .... _ ,____ ,,j. . . . ,, ,, <- <- _ . , ~~--T .H. H '.- - i i i ii , ~ e i . i _ . i '. w _ i I i ' <-___ ... i 4 ,i . . .. __ ___ ,___ .__ _ .___ . . , , . . _ . ., , ,7, _.__ . . .; . ., , _ ........ ,, . . . .. i -._ sr.. *. . . . 4 in . -[ _ j ,i l- .\\.. . < ,.. ... .<... . < QL.g,. . ., .. , -O . . . . . i i tO. O. O. O. O. O. m C m (N r) e . i L .4 (.l 930 83d OH8 91'130 % 10'0) DII/01W . .) . , . . . _ _ _ _ _ _ _ - _ - _ _ _ - _ - -. _ _ _ _ _ _ - - _ _ - _ - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ ) > . ,. . v _ . - . t p: . MODERATOR TEMPERATURE DEFECT VS. POWER CONDITIONSi CORE 10, ARD, EO XE RND SM, NORMALIZED TO MEASURED VALUES-1.2 y^ _ - - .- _ -1.0 - -, --"-- --=-0.9- -0.8- -- - o - -_ - - - ' I-0.7- - --. ..: - - - , .- . . gg tr _ _ _ = - j " -" c-0.6-- m.., .. pg t- - [.. m - = ,, . g _-0.5- ' " -.p.g ~- --~ ~ ~ --- '- - o - ,; _ _ . - - --- - - pk " ~ ~"-~ 0.4 - p:H -- "i"' --,- "-j+ - --- --- -- g p " -- " -- - -- ~~~ " - ._ - __ . grc a s -._ s __ _ e-c - ..- ._7 , -0.3- - - -i---- j- - - . . l- --- , s- - . ,_, , --- ~ tr-0.2- ~- o _ - ._ _ .-- _E .. 3. =' _ p ,, - - = - 3:. _---0.1 n _ _ 3 = - -, g --- ..j ., ~..Jhhh_ " - ' ]] j [ ~- ' - !2$ "' ' ' ' ~ _ ] ' - - ii E 5 l KC ' -- ur - --- - r - - :X - = - - -= - ~ - 0.0= p - -- . -.- -- :: - - -5- ~-- ~ - 1: -:m._ ~ T=' _: = m ~ L = -- . .. .. - m oc -- T ' ' " . u a 0.1- ,3 - t; +=+- -.: + s: c:- .._=.- 2:- _ w : .:: - ' qy _ - - = 0.2- [ - z- - f ~ ~ : --: - ---, -gg~ 0.3 - f ()- :- 1: , . 10 30 50 70 90 100 " h>~ POWER (Z) . N .L ' N , i - - ., s . p . MODERATOR TEMPERATURE DEFECT VS. BURNUP CONDITIONS: CORE 10, ARD, HZP TO HFP RT EO XE AND SM, NORMALI2ED TO MERSURED VALUES-1.2 - [ . 1 g , , . _ j.j . . . , . ,. ,. j. f. -[ , ! _j, j _ 3l . J .l _ + - -y-1.0 - - tf q. . -0.9-I ' ' ' t. j - J }... j; - o - ; l - . " ';I.jj t-0.8- . < _ t .1 I-0.7-F' l -I J- ... ! rg= - tr _ r, - 1. --1: . , a- -0.6 3.i g i g- -, . j ,! E ' I d-0.s ! ' ' rs-e . . o . c. , . -0 * 4 - E i if $ ' - N - i; - .7- .l - t.1 _, s - . ' . y ,; I-0.3 ..- .lI i l . . - a ~.-- . ' -l rr-0.2-+ . - o _ j-M - , ' r i - - -0.1 - . . -' g t.. , ,, b , ,, $ + 0.0 - 3-x - - l-a.J 0.1 [ ' - . I-a_ { _ , 0.2- ,.! , ' ' , 0.3 , . ,1 3 5 7 9 11 13 15 N" BURNUP (KMWD/MTU) e ru b -\\ , . . . ...- .. . . , ' egne gylgu % gyng #1997 fleug 2.2.2.3 ' -_ myto a et l'k.htygg 4h4n psyvya er W to m I ..- , r i n . . g . . . \\ . l s ___. , , . __ ._..__ __.. ..___ . ___.. . ._ .___ .___..___ s_ _ f. a. . _ _ ___. __ __.___ ..___ .___ y y. ._ .._.g _ __ _ ... _ _...___..___ ____ , f. , -_ _ .. .___ __..___ _ -___. .___ 7.. ____ __ __.._ _ ____ ___ __ __ = ,_ . -._ _ .. _ ___ ._.,t _ .. -i- - - --_- y , f i i_ _ ._..._ .. .. ... .._. .___ __._ g,, - __ __ .___ ._. , g _ , ' c i . _.__ ..__._ . _i7 . . g , . _ . __.. . __-_ . y f . . .. . _.. _ .._ ._._ ___ ..___ t !',1 . ,l ,Q - t- - -- H - ! ' -f-N-Hy ~-. - - - --. , , .O .....p..p ..._ [i. ' ''' l _.p ' ___ =.. , . _., y . . , ,a .p , _. - ...__ ____ ...__ . __ __ w - ____ , g5 ____.. 4.. .t..p , u , __ .. _.. ____ ._ __ . .___ .y a , ___ ____ __... _ ._ gg . w i ' .iiI. i - . .... . .._ .. . .. _ _ .._._._ ._ - .. I g ? ! L L3 W i * -- i. .r-' (r i g, e. g _f. .-__- -. - Q: C . .. .-- ' !.. .l l *. .-.. ' = ' ' -.-y~j4 4- "-) -> y CI*. yp .H.7 -.< .. J. H .. . _ .. .. - _.. ._ . ... ... ..l_- ' 1_ ..:_ c _- ___ _ ___ .. . .. _ .. _. __ . .H t- . ..,__ .___ ...__ , , > ] I '. i a e . -[_;_ '; _ __ _ + - - _- m _ _ .. __ _ L W H _ __ 4.Q. p.__- p 4__j l H' - $ _ _. .. . . .. , W C i +H .t p.4 ,2. ..g _ _. __.._ - _. _ __ .._ _ _. - _.. _. 4 a.___ a_ .p. . eO ' t u ._ . - ._- _ -- ' !. , ,_o _L. ...J.J __ __ _ . _- ._ ___ _...... . . i a s . - i ____ _.' * ' __ . ' _, . _, ' c +. i . i I . _ _ . p , _ ._, _ _. ._ _. , , - --r r -' '- , .r-- -t-(- __ - i = i - -1 r 1 -'-- + .., . , _ a i . y.1.y - ._+ .y .__. .:. _ ... ..:_ .__- .___ .. _._ ___ .___ ___ _ _..____ ... ... -.._.. .< '. . ., .. . .. T ] s , ....,. . . . 4. ._. _. .... .** _. - ... , __ -_. 4 . _ m l 8 . u ., _p. ;.,. _l ___..___..__ _ ___...___ _._ _._ - . . - -o . , . . 1AM NQ M N M '** la I i 4 ' (OHW U1130 %) H180M - . . .. . . . I . L > - _ _ _. _. _ _ _, _ _ -. _ _ _ _. _. _ _ _., _,., _, _ _ _, ____.__,__,,____m_____ . . ... .. _. o , . P8MC CCVIEO _h;.; c Af g _ 7 /f 4 /,3,, rig ggg p,3, g g NEYlECEO EYb ATE (.#/d///b PREPARED BY MM 3 I % ! i t i % i N iW . f 7 e I 'S T I. . N -.J-.H.i -=, ' . ,H Q g.w - i.+- .O - N o g -=o p - I I @ @ ""Y" "' o ==e +-, -.. g h hh . hI hI k h N 4 I T I N . . . I I I I I I I I ., M I - .I I I .I , cd Z , I I ] I ! I 2 % ! l l . I . .. ... 1q ' ' ' ' ' t M CO r i i r 1 I ! i i b i i , I .I l ! . . I I I I I. I I I I I - I I II I I I . I . M I I I I T l: .i ! l'1 I Y gI. f p.g I . I i' .. 'I i1 1. 'I I ! 1 T I T T II !! I 1 ' ! I ' I I 1 I ! I , gg 'I I I i r M h kI ! . i1k k I i h5I 1 I ! , ! l' r i , 1 I I E' M, l f' 1 h ! I f () . . 8" l I I .1 I 1 i . N D'd g I . '1 I MQ I I II ( ~ t I1. I f I [ ] 1 . V f I k I i. T1 I.'I i ! i C I I .. I .1. 1' I 1 . . '$ "* I I i 1 I1! L 1 I I g I I . I i. I Ir ! 1 : I Q I I I R II 1 7 i: I I w"g g Y :1 I I 1' C,I I l' I .1 ? Ih g ,. b T 'l' T 1 EI i 1 1 I I I L E l' I I* , 1 1 L 1 ' &H _ l IE M 1 1:. L q ? L 1 i L I . . T L : T I I I L Tf L E I y I l 1 W X g L 1 R I I i I 1. M !1 M F I % g T 11 IL ! 1 1 l LI Y ' I 1 I .. v L. 1 I I L : . h I r TI TI I ! I I I T I I . nq O I . I . . I . Y I1 ! ! 1 I ! I i 1 1 1 I L I 1: M V I I I I T I i I I I \\ f 11' I U %Z . . . . Y i' T ! 1 . . '" ( I I I I I 7 y I - 3 g! 'g g I g I h . %T T '. 1 l' % 1 % . I g s 1 s I I I gg Y I . L L 't 1 L M MA \\'< 'i I $ I i " M , i i s w s T sr . L 1. t T ', % Tk s . i L M o __ . m,L,. L i i v s T Z ss L L'L % i L L . . -L 0 $ T3M , vm m - .. tu, , Lu i w iM8 I I I M I a I I 11 ! I f 1 _ , , . w W T M NO l i I e i . . ..... . ( OHW tii~DO % ) H180M , , . , e , --- - - ., -- - .., - - -- .--. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ ______ ___________ _- _ _ _ _ ... _ _- - . . . s. . PORC REVIEW )b DATC Ih MM7 F10URC 2. 3. l.5 . RCYlCWED BY MM DATE NhElI7 PREPARED BYWban.A I / ,.. w .) . .-oo - = , " "'"' .t.- 4 44.y, .p -,- .<-. . I I I ] - Iip.,,, ... -- d.4 a.4 4..+.4 .. . ~ - ..,.- . , ' ., .o . . . .. .. . , m .,.t.,. 4.,.,- . -,,, <. + . ..,.en..t & * i i a..,.4,. 44 .l-,.. 4.a.4 .. 4.g . . . - 1 . --- . a. 6 , 4., . , c . .. .1. 6;H., 4a..,, -- < . ... .. . . .g .. .... . . <!'.,-I- .. 4 _ - < - '. 4- ,.."***)~..;. +,. W".,.,H-t-U,.34..+4- - - - g. . c , . .o -. ...i.,. p 4.,. .,t***+-***-**.<. o.+.4. <.,-+.e + - .+-+ ._. ,. w +4 - -t.4 . -- -..r.3...+ . e .t.' .6 g,,,. , - .+ -. .;4.+.H.m TZ~ 4' lL 5.1.l~ 'k.+.+ {, " -l*2' i 'll l ', 1 +.~ . ,, Cd .. .itiili.!:ti..i t i k, !~ '*+03.a.4.j-..i.tttr 1.E i ,. ,. --+-- y ,a2a.a...iti-o . ,.,. . , . ..,.t.. .- e.+., -,e-+-+.+.. . . Q,, "A g . - -. - a ' - , - m - .+.e-9 - I ' *7 '~I- . -+,-+ 4 4-t' .. , i. '- - 1-~ t= -~ -'- - ,,. . -,..t " - .p.t +-*..+- '--t-d-e - .-1-t* . c o o . : tt.ta..4.t-+-1-d tJt :htri M;., k..e. g9 M 'EN.II i F >o %W $qN - .T.,.,r 4., .. ., 4z, pc,'cr;- :*I T.2 r'.;.y. . :..r.d-t-.r:- -. . - ce a m. .,. . cg O . . M .,,,,i. a,a, .... v n, . a...,. < .==,.... - . , oa o e i . t, . . ca . 2 2..,..- ...,..,. . _.a..p... g.. .4. a... . . .. e ce . . . .. .... ... . m ,. .ow . p. 2z ,S .; . L.. <, ..,1r;. -. .,.. .. ,. _.,..... ... % Oo o,. . .. ,_ .,2 .. --T. ".... ... o - - , . - - + . _- . . .u.. .. 1....T: ..... .t... <. .3 o .. r J . . .... i n .< < - . + (/) It... , ..,.., .. .:. . . , w . . Q,.l1. - , .. . eN .... <,,... ... , . . xO em~ T...y , . ~T f.3< _. .4.. +a. ' - - . - 7.-- .- -.--1.,,". < t, .,,t e o< 2o , e ,,.9...,. .v v .,.,.t. . .,1,t...- . - 4.. + {. . .4 4, q,, . l. .. " < D_ Q <C.,+ , . ~ , +. . .. ,.,.,.T,.~< . .- . z . . . ,...! 7... T- .. . ,_.. . cd 2 ga o ... . ..j. t,.4. + e.== , + , +,4... 4.,+.. . _ - l O O, nN ,.... ..... ..4.4 L 4 . . . . *T" . 7 g..., -, - .. <... .4-5 - .. T. '4'*3 ~ - -- o Cr. .aee , .4. 6,., ,.. g < i ._., p, o .. .o O,e d .M < D . ., 15, .,. J w -.,.g..<.,,.. .<.4.,,- .,.. ,. .. . . s. -.,..b.._,.. .e .., , I". <., . . .,.. ,- .'<---4**,. -' T. 4,_.< - .,.4.i< -. . .e ,. .4' .. O .. % - n a . . - . g m C3 t-' -*.,I*- + + - +y .'.. - pP".-p 44- . ~ "$.' ' ..,.4.<.."Q"" r! '.4.a . .. . o a o ._ - . ". p i _, f l J J.... i.,.. J 4. . .<.. 1T.".. 4 '. 't" ~ 4.<-.4.;.2 4 A .o w' ... . . _. _ ... .~ - ..4...m . e . ... n . .. .. ......... .o.. . ,.. T I.. , .- n,W g, p. . f' .. 3 p<. . . . <.o. . <. i e . . , .. .,.. ... O g . , 1$. T". . 4,.'I",....,i.<Z.,, .,. . o, N y . 4.... p ). .. .. ...._ .. - . ., , . - . . . . .. ,.,. , .... . NI i. . r hg . d. m, i - - -. . .,. 3 W.- <-. qm'rt'. i. E. .. . .. ( q . r - ri.,. ,, . .. . . .- .. . t.....,, .. <. ,,.. , ,._ .,.... - ,. .... ., ... . .- p ... . . . . 4.. .< , k'. . ...<.- T.<, 4..,44 _ d. .. . ,.... J..L., . . .< . p...'.4., ... .<... . l..... . < '""- O g g.g 1.< ..7. . - <,. . . . . - , , . ..- .< .. .< .. . < oO W +-- .i - - .. ]7.7 -..1. 'I'.' .- . - . . < - . < 1-. .. ). . . .< I - {NA g .j.. -- -< - - ' - .-d '. ai.Tl. "'. ."<CD W -+ . . p , -o .... . . ..... .. ... . O. O. O. C O O. O 'e n d 'd O i ! i i I . .) - (OH8 Y.l.T30 %) H186M - . % _ _ . . . . ' J- ' - V .. _ .g(I . . . r.,1 - el t- ! . SH BEIIAVIOR DURING POWER INCREASE VS. INITIAL WORTH , . [! CONDITIONS: INSTANTANEOUS POWER INCREASE TO 100% POWER FROM CIVEN SM WORTH I-5 - _ g..m.d ._p._.1 .-..-H- - 4mi. .gp.sp..,,,,.... _u mn.-_ _>==lbd 4>.e.1>==.. 4m.> <.-s-..< w a 4kmp-.,w ag4>g. ..mmi = * pi.--l'. <*'-.>d ..-s - 4.=4 m . -. w r. '-..4 .m_ s-.,-e>.4 4p-.m'-_ - g-d..m.m.Nums>" .w - -mmg..-r. -w . ,e - . --.. --- ._----.-.m-w>,.M.. .w .mw.w.<.-q,s . ____ - -._ __ . __--_. .._.-. _ .__._ __.. .._.. ._.. .._.. m4.mmm-w g-N.mhwr ._i <=.--i.mma gi.mm4m . u-.mm. .a.m . ,,n.,. -- . . __ -.. _- _ _ -_-__ .-.___ __.. 4 w d .*um 4.e>. -uma>m.. .>g>w .m. . .w - ..-.p.a>..g, .w ._, pp.g qg ,4,, eas.g,a,.4,. ww,,, , .__ _ - -_.. _- - - ..-._ .--- __.,._ .. - --~ n O, - --- ..- -- -.. _--. --- .- . - .-- g - - ..,_-.- . .__._. .- .._._ ._. _ .. . . _._.. . p , ._..._.. - - _ ._-.. ._-.. . _.._ . ._>_-.._.,_. .._.. .. ___ . .-. ---.-.- - --.- .- - - . .. .-----.- _.-- - -_ - --.- ..- n p r -- - -- - -- -- -- -- --- < E-3 ~~~"~~~" ~~~ ' ~~~~ ~ ~~~ ~~~ ~~~~ ~~~ " x" g ._..-- -_._ ... ..._.. ___. --._ , , , .__- -_- _- ____- __._ . _-__ . ___ - __.. ._ _-_.... -- . - .- - _-. g _ _ . .__ ..-_.. , .

..

-_ --- . - ---.. --.. .-_ . _.. --.. . g .-._.. .- . _ ._- .._ - . -.. ._.. _ ._.. .n s .. O ~ ~ '~'- - -~~~' ~ -~ - '--- - -- - -~- ---~~ - - ~g 5 . 1.2 Zfe -- - - -- - ---g - .-.. -__.. - -. - -_- ,. , _ . 1.0 4 - - - - --- ---W-2- - 0.8 .._-...___- - --.. ____. ___-.. .-. -. __-_ - . _ ._- .-_.____- ,o I , ,, - - c.6 --. -- 2: ,; ..._-._ ._ _ --..__ _ - __. ._. , .r '. 0.2 _ j ~~ ~~ ~~~~~' T~ .'~~ ~ ~ __.. .._...._ __ _ 0.0 -. . -__-. _ -- ---- - --- -.- - - --. --- ' Q - .___ ..--..-.___ . x--- e-1_ m.,- ~ [ 1__,;g-q .__ . :~~ ~~"~~~ ~~' f ~~ _ _-_...- .-.__. .__ . - > n> , _ a __- - ___.:_;-- - -.:_-a --- - n __.-- -__..--.- _ _ __.. _>_. -..-.- -- ... _ - ..___. ._ _ ..__ - - --- - -a _ $ - __ _ _ .-.. __.. _..-.. _- , -~'~~~".3-p -.--_-. - __-- - . .--..--.. .-- _ -y ,. r~ ~ ~~~~ ~ ~~ ~ "~~" ~~ 'I ', , ~~~ ~'~~~" Ou m. . Cl53 1C O 150 20:0 2 ',0 300 350 4 (10 45G Sd0 itu , . - D no T ir1E (It00RS I - l \\~ e - _ _ _ ___ . _ _ _ _ _ __. _ i-. W i . s + d'. -- . - .' ' ' REGULRTING GROUP INTEGRAL HORTH HITH OVERLRP CONDITIONS: CORE 10, HZP . , s.0 -- - l f,n , ct _,a j g 4.0 - f j __ m BOC NERSURED O g/ ~ - r: ::: ::::_ _____ f g - goc m 7co_ x ____ l _. _ _ ____ f 2 "a-c c 3.0= E UJ H CZTyr ,~ g ._3 _f_ _ . .< 9 < ___ - _. w g ___- , y ~. a _ - _ __py_.,___ __. % g __. g_ p. _ a - . Q C___,/ " 2.0= y j_7____ , e g _. g d o . j----t z F / I r ,,, - -/ ___ s a- -- [f " ~# 1.0-- g ~ 3 R f 'f . .a &t~ ] > ' ' f-i / F -. , R - ur' uj/ ~~ u ___..__ ' = 0.0 9"l ,100 200 300 400 500 600 700 N . enar 1 same s aume Sn,s > . . . . . . . . . . . . . . . O W 3W 150 180 SD 150 180 50 1G3 15 0 ISO f ~_ 5 *WImr 2 omotr 4 . . . . . . . . . . . ( SD 100 150 ISO 50 100 150 ~80 STEPS WITHDRAWN . . me mimM cm R-&rl neue _2.6o 2 mioa erb.m bt~em Joklt? m m a etCwLL / i i . r . , \\ r. -g - 9_ = =*: . .#_ ..-._.i ... . -. ._ 6g .. - .a. . _... ...,.r , , _=j+ : -. -- g .::::* F ,.- . .. e.. ,... +. +. s u,.+. u .,.r ~_ .m. , Q t=r::r:;*:* - -,.,,,=.,,c.,a,+..:::- , ~~~ - .: I - 4~ % ,~,.;;,,. , .** _ g.%,,~ % "-. ::: .* y + .. im . @ ,. . .% . ..... $"g . e ' "4+.**. ... i _u C L u. i. fi~:: ":iLu. ~._._ + .Q .,_,- ,._ _.w - _ . _ _, - .. ,., --t.; :: >+=*+~. .. a u_-* E~~~*. '_.. ___;, -E.,,,,,.+W~ ._ t c3 -" -~~~::-. ., . ,., .~~* %.- _- _ . + + +...,_e. . ego.++. _ _ "q "**"* i .".*::":*::*_ . - , ' T4 _.. - . -- u_ w u _ - - - - - _ - x - - g..::= _ _ . . - - =.-_. ~.~::: -_. _..@ ._ __ 4. b .a, . . , M, _ _, k2 ** -. _. . _ _.. -.. _..._. . _ _. _.. . _. _. . _ =_ ". _'. .. _. .gp; _:% m.. - s cc % __ _M +- - t= - ::- . a. ._ .- - _ Q o Z -- v . '.; z-N - M, a c - J % .. =. _ --.m . _... __ %._. .. ._ _.. .- - ,. _ _ _ - _ @ Cd C a n-- - . ,a Cd -gg;:::. p r o - ,. C.D ,,,,_ yW ._.. . m --.. .. -h.~r. B _ _Q T., . H '"-~ .. - j g - CD -. _ _ _ g i _&.- -+ Z. / ,, Cr . O-h -. E @A Q _- -' _ .. - ' - _-- i LO .. - W . W - H l ct c.n.,. _ m s . - _ Q (A - - N , 3.- _ %- = - .-._ I O . - a m m - Cdgg - w ___. _ , . - _g e ... ...g, - t g. _i-. c -._- -3 *::~.:.::- , l ,, _,, _ -(._":"._. ._ - ., = _ . - . O - E _,,, _ _ =_ . _.. ,. " - ' _ " '" _Q g .. -% + ,,,,,,,, ( '--- .. -@ .- . _ q w,'ae.+ ..... . ,91 ,... "_ - - - , . Q . g..+ pe. ... . ., _, M - _. . ' . g .a. % '**--h ~~ ~*" -- -- .~~* _ .'[~~ . _. [. i ,O . , , , . . . , ,, i. 4. , , . i , i , I m + M N e-* Q CD CD N LD m + M N M Q l e e e e o e e e e e e e s e e e a M M M .-e m Q Q Q Q Q Q Q Q Q Q l g ) . - (OH8 W1130 %) HIMOM r i l __ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ ... P0ftclicy!Of O __ trrft dM/f'7 fla.Ht. 2 S I. 2. FOt!!)G gy bb ytTC 4N7 pg?NICD BT %3^ * * t h- ... - ,I I ' IBW (PPM PER % DELTR RHO) - - o .) 8 e 8 - s. - - . I i i I i . e ~~ - r+ n .. _ -. 1, -n _ ,,__. ...v- _- . - g , .,.. ,,,,_,,, t , . .. -. ..,4- ,...J . - +"-'d *-+;- , 4, . ".. w. 4..#:a , - e .. ... - a a..a ....-+. -,. . a.-..a .o .~ 4.6 .....a. n .4 , ...... - . _p.p m . ,,,..a g, 4,;p .... .... ,7 , .. - .- __- _- - .c.. +.- ; I '---.a -- -,. - . -....a ,,., a ,, ..a., 4 +. . .,. - - 4 9., w . ., a. . .. -- .,., ,. ;g 3 :.-L._. .1. ' g o...f._.....rm..-.f j.-L-- i.'L.T'1-2 t-::-t'7.:0: $:;..T . i, . L. n .-W '#.it.- ,...e.- . .; -.. . -- --..;1 7 {{.t::.: .g-:-' f.-I.5v. ~',W1 -* 2. c.' ':2 r' '*7p2 - * " 4- ' g c"; 'T . ;:p-..,34 ._ m g; . : 4:.2. ,y: ~ -,.. gt:.:.:.;p-.g%,_ ,.e . ..,.,,,;;; ::2 ;;;.g;;. _.,_.;. f.yy_y g-..ea 4 4.w ,..4.;.,y ,., t_, 2 ~. .. .. - - .. , ,g.;,-.,egj _-4g ~., 7,', + 9-. y g,. ..%_ . -. .;,g .-t I I- - + _,6,441+,6 :,,,,; ;-13 *. * - j +.+a-+. +-;..... ,,, .: ,,,, m t p . _ _ -: - [ ,e , T -.=..- . .h. 4 4 4 . _.. 4-l 4v.4 44 - 44 ; 4-.. E 7. ' g,. I _= . 47:.., -,.- 4 6 4 q. c Ti,.w. i 4+...g 4a.. 4 -.5 o gg;;..p .s., .. -,... 3..-+. .,,h. g . -4.. . - . g .y .4.+,~.*..~.+-+4-4-- . 42,f,.g: g 4.1;.g q.,,_,,_ *g,i;,g:e; .,. %;, - _ ,,,,, .. _..;..-. +.-. 3 _..-. _,, cE, o h.n.ri.h: x:.:r1]I5E t.. 4 "I L _1:12: ::$*~ TFli$?:'HIF-m - ...... . t. -,- _., :. - _ _ . .: 2. 4,i.. .F~ -T- __ 4 +.q.,..a =_ 1::-- .l1= .. - -- 4 - + + 4 : _:. .,4i - CD . "") 2 ~ ~ "t*E-II.'.*T-Y7'k.i: I.2*ti~ ,1 : 37.b -i:2.. .. .TT: 3 "Y H + + + " ~(d cc L._.22-12:. TY: h 7":;h..d...71r2 :: 5TT\\tT : 5T zE31. =- N >o m,,.1:r.3- :.:t- :..u.=* r e. -2' . 3 L. x =3 .t.=....2t-. =-1 ...r.J.:.. 2.:'. O c, ) .- -. x, - - * .- ' -*. y .e .:. :.=....,r ~ .. =-. . .... , 1..; ... .r..tr g tr it.~.r :. 3.3.l n:..:1 : W. ... . cQ. L r : W'"-* ]z. g .. .. r-1: Jn J.t 7lT_f };.1:g}.u.}.:.r*,[.4 :fd 1. : u -TJ. at F31-N 71t .. s} w - - - :. -..1 '.,-.:ti t.j.;;;.T T-. W.m...::= , r 'o - =2 W == - .nr- . g 11,q.t. t. :. t..t.i., f r-": :: }:- '}.t Hp.". T.1.t. -:- '-0- -"-, :77+4.ff, g-1, 3p - - . g . . , ,, .. - ... . .. .. , ..:- .-. , ., . .- .l. . : . c-) .,.. . .. <. ... .. =t;a cc . Q .:.,1:. -.; s.tr.:t. . .. 1 .1 * L --) . u c. r.:.t; 2: .:b.r.d: d.. ..,Tk. - -+ 2-.. -- ,,I.T '.. EX.. %. ".4.. I. t. cQ .. J [ ': W.. J 3.1 ,O .J.' 1.1t. ....s , -. - . -. .. ' ' O 7.3.. 4J 7.T2:.?ar.TJ1 L.*.*" :.1.?g!q. t:I. : = :.: -" - -.r.n :-: ' 7%%:c.:.T..u.,:, cc , .: y . J. 7*.- .u: .T ~% ~ .2 .!: . . . **2: ;;' 0.*O ~ . ... . 7. a .2Ty ":..t tJ.. * T-$}7 2":!!T. :T3.II* T CD Jtt !*. . .,

4--

r:::ts.... :. N-4 :::~ t.T..* :n..t..1,* 7 ; ::.3 !"; 21:. -- r 3.,. a. . -- ,,......3 .T g . . .. ..,..Fi: ... I't.M.1 t *+ : 4 4- --"[ '. - [ t* d .,2 '~ ] ' * -- .J1 L. . 1.. A..'.m1 t. 'e. Lr, r, s *.-+. m ! .l.:h. -*l:-. . .,. 3........ - . .. ....., . n::2: t474.:'::::- :.r.* ? ' l; -*r-a.:7 '* *t.:- J :1--g..' . -- I."d 7.' ;.,,M'.y., -: ;. f*.1 - ht:T - Ed-T- . h" +.r-.-4- . .*z r.:. r,: v.1 :"7*.7 - - 3- ..-.,.3 r..g,.. _ n...:1.TL.42..a; _3. . .- -,. . u..:.... .u. _ . .T.-..1... %... .a...s..... J:T ,. . . a 6- . . . .... . ..i.l.*:.3f.iY.-.g ~.2-I.idII-d5i.}E T['.%Ed."'.I.I..I._TY.[.I 3.. 5#5?T.-M k ' I . ' . . . .:' ;..~.{:1. - - * " y 4+m. . - . g. . .. -, ,.. _f: . i; ** Tt .., a . ... TNT'.T - '.'.TTT:-:T: Tr ... - - ?!t:-M T.' . ]j' T. 1M .T j ,u tt'gT .. , . -fi t . ,. . ... . 1, I1 >d. m l dM *p* . $1.1d I.d. -, d** lI. r.J .l-.'l * '' "> EA . '. t* :7?-.u p ..g . j;;1. -,.t....L. t.... 1:. u ?g3. %:J.y- .JJ . .u.:.).5 E.1".:.:. '-?,. . 21 :- - - =.-m.= :.-... ., . ... '- .. . . 1 ; 111 ' . . .. .. T. i,a.w .. T.T -"T ~ . 1 ' t', tT1 P 4i ~ Tir,. t .. O , , . , , . > i O. C. U3 e. N. O. CD. b W"4 9". 9'4 .l o a i i i i ) (Wdd 83d OH8 U1130 %IO*0)'H180M N0808 . . .- _. _ ,.. _. _ _. _, _ _. _,, ,,. _ _. _ _ _ _ _ _ _ _ , _ _ ,.. .. _ _. .. _ _ _ _ _ _ _ - . .- _ ._. _ L. {!x. ~ - .a . . O , . - . i f . BORON DEFECT VS. BORON CONCENTRHTION CONDITIONS: CORE.19, 576 OEG F. MODERATOR TEMPERATURE _ _, ., < . ._ . . , - , , , _. ' ' lie!: T~er r;tz p :I$[ M;; 3Eg ip*1 }TF +4y %g ig:- $'T;- Q $+ .j+r p-19ses 2: =t= q.: t:rt T rz 2,$ Isg gg gg iss Frit =pa r,* zi-y qq p: -q_ , 4.;h.,,4 1:w,.7 .,, g gocr_17 _. .__.re --% *W -+ t ... .. p. q.,,d. 1.,7::: -er.: --+t 4 tty ;[: .E $. Q.. __ . .. . , stw- ._ - ... . _. r-m - , -iW i: t Ti$ TI*r +F-i-e-- 3;il xtmi-FR itW. E$ trii di 35 Eni- ::iti W Ws i 355 +i4+ +5+4M44 y 4 Fr 4 rt t y't3 1:4U-ITFE~ f _r,EEE * H-Ai+ 6-I:R tirr m .t-1,- - y . a=E x=w =:= IEs is:::==n: as gii w* p:.: igii 5g 90g;,1; ~2' m ^I w ~'+[..,;2 ,j.l g. Ejji5 '. ~ ~j;j TEli -rtFjTj '..EM +! : -'"" < . - - MF YIU Nh; i* tN * i J' lg - a- -12tilt +1-If r-P i - t-'" Mi1;::ICE --c'4 ++~-+ ' ' - H > e*- H te% , .+,1+ -, 1,,- ==w,- -,,. - =-e=. w,w... me.v w - =., v,+ ua.d -11 - - - .g .. . - e ,,,. . m. , -- - , . -. - .. s , .. ycp M..- $.;jt 1;ttp $$:lg ;pl:g,. i,..; g , O - e,+ _ -. g.- ..~ - ' , -14:- +i4^ e-xt:--- - - .^ch t- .. =ite :nr :.. 2:= 22. = ris M=- 2EE 4:2: EiEE Ef i ST* P ',!! <:J.P y. - . r;=E Ias 23i1 i= coc EE S$iE IEE GF i:::: ii3EE ${E I.!;l%&: l T5_,, - - ' ' _ g _, s w m Wee @ f.* WM.p a m. h wm sgg . . t e-i-M =rdi i E E!E EnE i:tr '~+ n.. .i tFdiiEi! :br I I ix;E 3r-;V - "- . I N h . , .; $@~[;iEEE Itt?-.; i._ :% 1. 4(- @Ef.-jj'-Idi i:;t;t2 :u ' ?' ll. :5 h.- WIi~ 5E :jiE. :en-,-Wi $1.[,!..is " - <- ir rg;i2%I:- x=Tii 9 - - - -r - -2 .. g;tmi-4;= ,---%E rt= xc2 Ije se + s= 2:*2-Q- p .< fI. . ., ., - . - -. -- - -- --- - El3 ---!!!! 1Eb'.i !35lE EEiI ,.4 iti:$ lltp: 3.!i4 44.*is' ;i sip.i,iisi g ,iNr i3}3 - * * * Pt. _. - -e-I- iiil!L4! IEEi Siis EiEE We EliIE :i'EI J RE itist EEliE $EidiliE Blig.;p iP d.f - - - - - . O - - 900 1000 1100 3200 1'500 1100 1500 1600 1700 1800 -* 100 200 300 400' 500 600 700 800 BORON CONCENTRATION (PPM) ~ iq- . _ ___ _-__ - ______ _______ _. _ _ _ , fl77AkWMMY A.. . ,. " 'SECTICW 5.o , 5.01 The ase of Keff as a given piece of information decreases the operationalor!entation of this question. This question should not be added to the NRC's Maine Yankee esam bank unless modified to reflect installed instrumentation ! capellities. s ! a. Using the equation supplied on the Equation Sheet (delta K = (Keff -1)) l the answer to ints question is: delta K .95 - 1 l -.05 . -5% delta K i j Is is recognized that this equation provides only an approximation for l reactivity that increases in accuracy as Keff approaches 1, but the t inclusion of this equation on the Equation Sheet must be taken into account when grading the question, b. Using the equation supplied on the Equation Sheet (delta K - (Keff - 1)) the answer to this question 15: K 1 - 60/110 (1-0.95) - 0.973 ,delta K .973 - 1 .C27 l - -2,7% delta K Again it is recognized that use of this equation provides only anapproximation whose accuracy increases as the reactor approaches criticality. Use of this equation is justified both operationally when J conducting a reactor startup and by its inclusion on the Equation Sheet. i 5.02 No technical problem exists with this question, however the use of watts and . megawatts as an indication of power level decreases the operational l orientation of this question and can create confusion, this question should not be added to the NRC's Maine Yankee exam bank unless modified to reflect I installed instrumentation. ' 5.03 No coment r t i 5.04 No comment i i ( 5.05 No coment 5.06 No comment ,' , 2826t , ! -- - . .. . . -. ,._-_.__ _ _. - ___ - - - _ - _ - - _ - _ _ _ -. - - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _, _ _ _ - _ _ _ _ _ _ _ _ _ ___ _ _ .' .e i '.5.07 Answering this question requires reading multiple T.O.B. curves accurately. The answer key should reflect a range of acceptable answers based on a reasonable expectation of accuracy when reading these curves. . i 5.08 a. No consent b. The answer to this question depends on how the candidate judges "!N!TIAL." An increase in steam flow will also cause an increase in i power, it is difficult to predict the "Initial" effect on fuel center line temperature. Elther INCREASE or DECREASE should be accepted depending on the brief justification.c. No Cor 'nt d. No Comment , 5.09 a. Other indications exist which can be used to verify natural circulation j flow. See Procedure ES 0.1 step 12 attached. 5.10 No comment5.11 No comment 5.12 Answer could be slightly different due to our 100% power Tc now being allowed to be 552'F vice 550'F as is assumed in the answer key. See T.0.8 figure attached. ! ' l , l rl l , , l 2826t - - - - _ -. - -m.._ _ .' .. Section 6.0 . 6.01 a. No comment b. This auestion involves memorization of facts which are not required by our learning objectives, not included in the KSA catalog and not important to the operation of the facility. The question should be deleted. 6.02 No comment 6.03 No comment 6.04 a. A second available method to perform an emergency shutdown of the Emergency Diesel Generator is: 1. Depress the engine stop pushbuttons (s: ops motor driven fuel pump). 2. Operate the emergency fuel cutoff valve (shuts off fuel to the engine driven fuel pump). Reference Lesson R0-L-5.4 page 16 (Reactor Operator Lesson plan on EDG's) - attached. Either answer should be accepted. c. The question states that service water pumps (A and C) are powered from bus 5. These pumps cre powered from bus 7 which is powered from bus 5. This question should be modified prior to being added to the NRC Maine Yankee exam bank, i 6.05 No comment 6.06 b. The gland leadoff tank overflow is maintained disabled to flow continuously to the PAB sump and therefore should not be included in the answer. r Reference: Procedures 1-15-1 (step 4.11.3) attached. l 1-15-2 (step 4.10.4) attached. l , l 2826t l ,. _. _ _ _ _. - -. - _ _ _ _ _ _ . _ _ _, _ _ _ . ' .. . . c. This question is extremely open ended. Answer will be affected by plant condition (cold shutdown or at- power). Answer could include actions of AOP's, Technical Specifications,Emergency Plan and many others.Grading of this question should not be limited to the responses listed in the answer key.Full credit should be given where correct responses are provided. 6.07 No comment 6.08 No comment b. Valve number (LD-S-14) should not be required. Full credit should be given for reference to letdown system relief to the VCT. 6.09 No comment 6.10 a. The first listed answer is incorrect since all three HPSI pumps must be valved in locally. P-14S may be valved in as either an "A" or "B" train HPSI pump, b. No comment 6.11 No comment 6.12 No comment l' 2826t _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ __ ______ .. . . 'Section 7.0 General Comment - This exam section contains many questions / answers that require memorization of normal operating procedures beyond the level required by our learning objectives and beyond the examination construction guidance contained in NUREG - 1021, ES-402. Paragraph A.3 - Category 7 - Procedures: Normal, Abnormal Emergency and Radiological Control, clearly indicates that complete knowledge and understanding of the symptoms, automatic actions and immediate action steps specified by off normal or emergency procedures is within the scope of this section. This paragraph goes on to state that the candidate should be able to describe generally the objectives and methods used in the normal, off norrt,a1 and emergency operating procedures. Although Haine Yankee feels that the high number of questions / answers not conforming to this guidance generally invalidates this excn. section, the following comments are provided. 7.01 1. General comment applies 2. KSA reference supplied does not match requested knowledge. 3. Other acceptable answers: - to maintain the pressure within the bounds of the HPT curve (step 3.1). - to ensure no backflow from the stea;n generator to the loop (step 5.3). , 7.02 No comment l l l 7.03 No comment 7.04 1. General comment applies Other inadvertant plant responses are possible and "cou?d" occur. In ! order to receive full credit on this question per the answer key the l candidate must memorize the discussion section of this (and thus every) normal operating procedure. , ' 7.05 a. 1. General comment applies Memorization of Operations Memos (especially setpoints in Operations Memos) is not ano should not be considered required. 2826t - .. __ . .. l l 7.06 No comment . 7.07 a. The question indicates there are only two (2) initial actions which must be taken after a loss of control air. AOP 2-28 - Loss of Control Air lists eight (8) initial actions. Any two (2) of these eight (8) should be accepted for full credit. AOP-2-28, Section 5.0 attached. ' b. No comment c. General comment applies 7.08 a. General comment applies - memorization of the fold-out pages in the E0P's is not required by Maine Yankee and does not meet the criteria of ES-402 with respect to examination scope of E0Ps. b. Your question specifically refers to answering the question with regards to E-0. The answer key requires responses from FR-S.I. The correct answer should be that listed in #1 and #2 of the answer key plus transition to FR-S.I. c. No comment 7.09 No comment 7.10 a. General comment applies - memorization of caution statements is not required by Maine Yankee and does not meet the criteria of ES-402 with respect to examination scope of E0P's, b. No comment c. No comment 7.11 No comment 7.12 General comment applies This is a good example of choosing an extremely obscure and very infrequently used procedure and asking detailed (and also open ended) queftlons. This question should be deleted from the exam as being clearly beyond the required scope. 7.13 This question requires knowledge which is not within the job responsibilities of an SR0 at Maine Yankee. This suestion should be deleted from the exam. ' 2826t _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ .' . 'Section 8.0 General Comment - when referring to operating conditions with respect to Maine , Yankee Technical Specifications, the use of condition nami: (i.e., cold shutdown, { transthermal, etc.) is generally used vice condition numbers. Questions in this exam referring to Technical Specification operating conditions should be modified to reflect this fact prior to being entered into NRC's Maine Yankee exam bank. 8.01 a. The answer key indicates that "RCS Tavg" is necessary for half credit. This is an unreasonable assignment since in fact we use Th when less than 210'F. The answer "RCS temp" should be accepted for half credit. c. The answer key indicates that "Neutron flux log range channel instrumentation" is required for half credit. This is an unreasonable assignment since this instrumentation is the only means available for power indication in the range of 10-'% power, 10-'% power shc.uld be acceptable for full credit. d) The lead in clearly specifies that this question is to be answered regarding the DEFINITIONS section of the Maine Yankee Technical Specifications. This question makes the statement thd cold shutdown Boron concentration (DEFINITION) differs from the hot shutdown Boron , concentration (DEFINITION). In fact the DEFINITIONS are exactly the same. Full credit should be given if the candidate responds accordingly. l The explanation in the answer key should read "of at least 290*F (500 degress F-210 degrees F). 8.02 a. The examiner seems to be attempting to trick the candidate into stating l "SR0" which is in fact the way the plant is operated, by using "per Maine Technical Specifications." Since we are required by Technical , l Specifications to adhere to our plant procedures, "SR0" is an acceptablel answer. l b. No comentc. The answer requires the candidate to state that the CR0 left the l controls "on two occasions" for one-third credit. This is an i unreasonable assignment due to the subjective nature of the requirements to "justify your answer." r , d. No comment 8.03 a. The question indicates potential sabotage and the candidate may respond accordingly by contacting security and initiating an investigation which should be accepted for full credit. (Reference is in Safeguarded Security procedures.) b. No comment c. No comment 2826t _ .. _ . .__,.8.04 No comment .8.05 1. The reference (OP Hemo 9-L-13) has been deleted. 2. Only one person may now allow a loop entry at power - the Plant Manager Reference OP-1-200-10 Section 11 and Section 11.3 (attached). "Plant Manager" should be accepted for full credit. 8.06 Genersi - this question requires memorization of actions to be taken beyond the one-hour time frame normally considered within the scope of Section 8 examining procedures. a. No comment b. 1. General comment applies 2. Another acceptable action would be to valve in P-61s as an "A" train LPSI pump and test run. In all cases the requirements of Tech. Spec. 3.0 will apply and may be mentioned. 8.07 General comment - this question requires memorization of details and numbers contained in Administrative procedures. This practice is not in conformance with the guidance provided in ES-402 Section A.4 - Category 8 - Administrative Procedures, Conditions, and Limitations, which states that the l candidate is not expected to memorize the exact details, numbers andsurveillance requirements contained therein. [ ' The answer for question 8.07a shou'.d be granted full credit if the basis is correct. The answer for question 8.07b should be granted full credit if four (4) valid ' actions are listed. b. Other acceptable actions should be: l - Verify satisfactory PCC flow to recirc fan coolers. - Increase PCC flow to recirc fan coolers. T l 8.08 a. Since the UEL is 181 steps, an answer of greater than 177 steps should l be accepted for full credit. b. No comment c. No comment i 2826t .. _-. - ~ -_ _ .m._.. .. . . . ,8.09 a. No coment , b. Question is incorrectly worded. . Anyone qualified to be an Emergency Coordinator is authorized to act as Emergency Coordinator upon their arrival on site. These personnel are designated on the Emergency Plan Roster by name and not title. c. No comment d.- The answer "Maine State Police within 15 minutes" should be accepted for full credit. Once an EAL (see typo in answer key) is reached, we are required to declare the appropriate event within 15 minutes. The fact that the event has already been classified can be inferred from the question. )* 2826t . -. -. .. - . -. - ._ - --. -_ __._ . -. - . . _..,... .... . ~ ~ Proco Noo ES-0.1 Procedure Title: - Rev. No. Rev. 2 .. 25-0.1 Page 13 of 18 - REACTOR TRIP RESPONSE ' - -. ... .... STEP._.. ACTION /E/PECTED RESPONSE RESPONSE NOT OBTAINED ,_ , . .- .. -. .. . NOTE ,_ RCP-1 or RCP-2 provide Pzr. spray. . - - -.. - -. - Check RCP Status - AT LEAST Try to start one RCP: ONE RUNNING a. Establish conditions for starting an RCP per ATTACHMENT A. /3/}lA)/A] l ~ ' '/ b. Start one RCP. IF an RCP CAN L) S gg NOT be started, THEN verify ' I natural circulation flow: y g,Np o Core region subcooling greater th,an 12*F. . o SG pressures constant or decreasing. l l o WR T-HOTS constant or . l decreasing. o Core region Temp. l constant or decreasing. , o HR T-COLDS at saturation Temp. for SG pressure. (Use HPT Curve or Steam , Tables) )* IF nataral rifculation flow H5T verified, THEN increase domping steam from SGs. . d .M % / e e e n. ...,, -- - - -., - - . -,. - - - - - -,w ,, - -, - -~ ,m. . . . . .s,.a, . .. . , , . . .. . . . .. ...... . . . . . - - - e ,3 POT.C REVIEW %/J) DATE _f/Jg//g FIGURE 12,2 i PJ REVIEWCD BY }WMd DATE_glg.q(g5 PREPARCD BY__"T pb /f\\ ghj .. I d -- Q . " i F ~'i. . ~ ,," i i I i i ! I W A . 1 . . . ...8 , '1, . , i: - i i i ii L. v [I , it. . "-"" 7 h ~ s iI e I i i . I i I I 4' ' 1' _ ii a _ L I L ld__ , 'I ig TI l a ' a i I ! , '. I T U ( '~ f i 'i _ h I* * * j f]_ ! , , .. .". . ,' i O .A >' ' ' I ' t '- x - n;f - - CD -*-**-=. , , ., ,, , .i 1 , ' -vi i i+ , j4:- o _qi , - ', ' i 7-,s. <p' X % , , , - ct. _ _.p i ,,, 2_27T. o f._. _ o_ i ,- _ ., c.s ,,, . - g 1 i > > _ _ _. _ u c3 -.-4. - O. -Ag -- C-p 4, ,,,, - -b-4-- ,,t--+ -t f-Q ,, ,i j h , - _h--- w r- - . i > z l' l. _u _.3 - C c . ,, r ' e!, __..jsO .i$. e , I r - > " l' l ' -'~"y.- r T*"*~r b O Id , , Z - H H . - o '; ' . O l ', ', '} %' ,,, '_ii.~~~~ ~ H ( ' O ' ' ' N,1 c.o r- -+t- , 1. , , , , , ,, -, m 1 i i , w - I ' _s ., _ .. ,, .M,)l, -f @ ., ., , r <+-aM *- - ,., c 3 ._ z'..r v-C C oy ! !d L.iD..i 4+ -M W y H li i t. - +4-h ' ~;' x , ' ' . -5 4' H i . l i : ' - i o_ l , ' ' ' o i 4--\\- ', '; -F-i A-44-- ,a , l iil E ' d,,\\ 4ll. ' , l b i + s o. . . ] j ' . . ' m 4.. ,. l i Nb. [ CO , ii i"' ' ' ' * -'- ' ' ' 'i M s: : ' ' O ! ' - ' %l l l 'v ?.4-- J. _ _ + < ' , i -- , i i . , , i ic -.J.1 L._ i ' ' > > i i i _. , !; >isL , a ,: ,. +r - M, it-+* A- -.{ L4- ' ' qi i > i . __ 4l ,T M.p ! r . > > > ._4 - -- l u* 1 _ + ;- -- - ' i I - tp, .. -- L , i 4. m..__ l t _ .., a .6 _'%._-- jA.4.L.-. 4 by-. -.h * ** g -t?'" ' i e , c>;j_ > i , "-]. - .-p 3-y -' N ' -.. - , 9.- , , ) i.. , , . , . t-w - =b . 1, [ i i_ I I , =-d g,,.,i _ p. .. ..H .. }. 4.. , g. g. _ i; , 1 2 __t . .._.__._ __._ . g 1 ., . ' _ .1,';, i-4+-4 .l_; -. _ , , -- - ..t-. v4.. , , o . 4. t . ! I ' ., _ __ .a-A. ,9 4.i.q. k' -. M r . * . . . . ! .b.-++ --- '- h . -{-- - t% * g. 'r .<. _._.q., .._L_ _..._. . ..py-J. -- . w. . 1-e , , l l ' , , ,, - --9 - - - it 'i- . i, i 9" 4 4.L4_.g.- _. 4.,.L_.-. 4-4 4.. 4...<---.< 4-4-4 , ! M.i . 4 _._ , ,, C , C. C. C. C. O. C. O. O. O. C. C. O O O O O ^O O O O - CD CO N CD Wr") N (.D W to W to W W IA r ( (J 630) 38DIW83dW31 S08 . e.. e -- m m - -- - ~ ~ ~ HY-T-68-84, Rev. 1 . ELO OUTLINE OF INSTRUCTION INSTRUCTOR ACTIVITY REFERENCE B. Engine shutdowns Use Haine Yankee valve location Surveillance book to illustrate operating 3.1.4 1. Unload DG and trip DG output breaker requirement location a. CR or excitation panel 2. Depress engine stop pushbuttons - a. Two buttons 3. Governor cutomatically reduce speed to idle 4. Idles for 11.5 minute cooldown DG-102-7 a. If auto start signal o Engine will restart T o Hili not manual restart Q d $ 5. Automatically to "no fuel" gQ a. Engine secured 6. Emergency shutdown a. Place injector control lever in no fuel positton , b. Shut emergency F.O. shutoff valve and push both stop buttons . 2158t - LESSON RO-L-5.4 PAGE 62 0F 64 . . - - . . /,(CMy Q Proc. No. 1-15-1. Rev. No. - Q Page 3 of 31 O^ - . 4.11 The PCC system is being chemically treated with potassium chromate and the following precautions must be followed. 4.11.1 Report all leakage, spills, or drainings of the PCC system to Chemistry. 4.11.2 Any water vented or drhined from the system must be directed to and processed by the waste disposal system or directed to a suitable container. 4.11.3 Chromates are toxic. Avoid contact and wipe up all spills immediately. 4.11.4 Maintain collection tank overflow aligned to PAB sump (solenoid tripped). 4.11.5 Floor drains in pump pit area are directed to the PAB sump. Floor drains in the Heat Exchanger area are directed to the Turbine Hall Sump. If the shell side of any HX must be drained, these drains must be directed to the pump pit area or to a suitable container. VerifyonlyPCCisalignedtoP-14Soilcoolersifitisan.."A"humporonly 4.12 SCC is aligned if it is a "B" pump. It is possible to cross connect the PCC and SCC systems through misvalving. 4.13 Whenever a PCC pump is placed in standby, after maintenance has been done, it shall be tested for a minimum of 15 minutes. This will ensure all interlocks are cleared and the pump is reliable. 4.14 Many valves in this system are required to be aligned as per ECCS, CIS, and containment integrity procedures. Before changing a valve's position ensure the valves intended function is not defeated. When returning these valves to service, fill out proper documentation as required (re; the white tag system and portions of surveillance procedures). 4.15 If the PCC surge tank level begins to change, a leak may have developed in the system.. The rate of change in the sight glass is approximately 18 gals / inch. Refer to AOP 2-25. NOTE: If the reclaiming filter plugs up, water will be lost due to overflow to the sump. 4.16 PCC must be supplied to every operating RCP. Normal PCC D/P is 5.5 to 7.0 psid. 4.17 In order to prevent any possibility of freezing or non-condensible accumulation in the PCC lines supplying cooling to DG-1A, a positive flow must be maintained in these lines. Normally a bypass around the OG-1A cooler does this. If.for any reason this cooler is isolated, the )ypass valves located on the inlet and outlet PCC lines in the diesel generator room must be opened after the jumper connection located at the valves is in place. 4.18 Operation of valves designated by an asterisk (*) may result in a breach of Containment Integrity. Refer to Procedure 1-12-5, Technical Specification 4.11 and Technical Specification definition of Containment Integrity. 1599r -. - _ _ _ _ _. __ _ - - _ ~.. ,. _ _ _ . , ._ _.... __. _ ._ pt$\\9N ' - Proco No. 1-15-2 . _ _ _ _ _ _ _ _ _... M< Rev. No. ,, _._ __ &p _ Page 2.of 3.7 . _.. _. . . - .. = _... 4.0 PRECAUTIONS 4.1 Maintain the pH between 7.0 - 8.5. 4.2 Main'tain the potassium chromate concentration between 700 and 1200 ppm; . 4.3 The design component cooling flow through the RHR heat exchanger is 4000 gpm with a maximum limit of 5000 ppm. MCB annunciator alarms at 4800 gpm. 4.4 Verify the radiation actuated trip coil at the surge tank is energized and operative in the open position. The trip valve at the reclaiming tank overflow will be left in the tripped position. 4.5 The full 16ad amperage is 46.2 amps. 4.6 Maintain the proper pump oil levels. 4.7 The' permissible starts per hour for SCC pump motor's are'.: , ,, 4.7.1 M6 tor at ambient temperature - 5 consecutive starts. ' 4.7.2 Hotor at fu?l load temperature - 4 starts with motor running between starts and 3 starts with motor shut down between starts. b 4.7.3 Motor at rated total temperature - 2 consecutive starts. 4.8 Component Cooling Heat Exchanger limitations: Service Water CC Water pressure - 75 psig 150 psig flow - 10,000 gpm 6500 gpm temp. - 150'F 200*F 4.9 If exces3tve pump gland leakage is noted, a Discrepancy Report should be filled out. 4.10 The SCC system is now being chemically treated with potassium chromate and tne following precautions must be followed: f . 4.10.1 Report all leakage, spills or draining of the SCC system to a Chemistry Supervisor and the Hazardous Haste Coordinator. , , 4.10.2 Any water vented or drained from'the system mus't be it'rected to and processed by the Haste Disposal Evaporator or directed to a suitable container. Duratek cannot process chromated water. 4.10.3 Chromatesaretoxicandanyspillsshouldbbwipedupimmediately. ' ' 4.10.4 Maintain collection tank overflow aligned to PAB sump (solenoid tripped). t . en e - - -.. . - ' . ., . .. . , f( '! (Yi hb Proc. No. AOP 2-28 Rev. No. o -- - Page 3 of 4 . 5.0 INITIAL ACTION. 5.1 Trip *the reactor and turbine. 5.2 Trip the reactor coolant pumps within 45 seconds and initiate Procedure E0P E-0, Emergency Shutdown from Power or Safety Injection. 5.3 Stop all of the main feed pumps and the heater drain pumps. 5.4 Olspatch an operator to lower level PAB to take manual control of seal water supply regulating bypass valves and charging header supply isolation valve (CH-A-32 or CH-A-33 depending on operating charging pump). This will provide seal water flow control to RCP's. R 5.5 Start and stop an auxiliary or emergency feed pump (steam ' driven preferred) to maintain steam generator level: as necessary until an operator can be dispatched to the Emergency Feedpump Room to manually control feed flow to S/G's using valves EFH-103, 203 and 303, EFH Flow Control Bypasses. (CRS-2) 5.6 Shut the letdown isolation valve, LD-N-2 5.7 RCP seal water supply may be sufficient to maintain pressurizer level. Additional makeup may be acquired by taking a suction from the RHST with a charging pump and discharging through the fill header bypass valva. (CH-85) 5.8 RCS temperature control is accomplished by using atmospheric dump valve l (MS-A-162) l l 6.0 SUBSE0 VENT ACTION . ! 6.1 Reference Emergency Plan Section 2.50.0 to determine Emergency Action Levels. 6.2 In secondary plant perform the following: , l l 6.2.1 Open the condensate pump seal water bypass valve. (SSL-84) 6.2.2 Open the exhaust hood spraf valve bypasses. (CD-49, CD-45) 6.2.3 Shut the normal condenser makeup isolation valve. (CD-92 ) l l 6.2.4 Open the manual bypass for SCC to the H coolers, turbine oil coolers i . and EHC coolers. (SCC-230, SCC-261, SCC-319) 6.2.5 Assume manual control of SCC heat exchanger outlet / bypass controller. (SCC-T-23) ' i I .1146r . _-. . - - - _ _ . - - - -. ~..,. . -., . '.. s . . . . . . . S , h gh proc. No. 1-200-10 / d Rev. No. ' ' 0+h \\ Page 35 of 113 l . . ( 10.12.3 All procedure changes will be independently reviewed in I accordance with Procedure 1-200-9. , 11.0 RADIOLOGICAL CONTROLS AND INDUSTRIAL SAFETY i 11.1 The use of proper radiological practicas and procedures is the i responsibility of all members of the plant staff. All personnel must be continuously alert to the radiological aspects of the work / evolution they are involved in and take appropriate actions to preclude industrial accidents. 11.2 The PSS/ SOS are responsible for frequently inspecting their job sites and areas of responsibility in the plant to ensure that appropriate and effective radiological and safety procedures and controls are being utilized and that deficiencies are identified and repoyted to l appropriate supervision. - , , i [ 11.3 Loop entries are defined as any entry within the "blological shield" ( as specified by the HP Section Head. Loop entries may be conducted [ only with approval of th:, Plant Manager. The PSS is responsible for ( controlling each of the operator entries to ressain within the man-ren . [ budget specified in the Radiation Work Permit. ! 11.4.The PSS is responsible for monitoring the exposure of each operator and to insure that job assignments are being made with due ! consideration for ALARA principles. ' - 11.5 Whenever an RMS process monitor becomes inoperable and Tech Specs require that a grab sample be taken, the following shall be performed.11.5.1 DR issued. . 11.5.2 Log entry made that includes: . o Time out of service. o Time Chemistry is notified of grab sampling requirement. J' ' [ o Entry into remedial action, if appilcable. 11.5.3 If the sample is required to be taken once per 24 hours, inform . .i Chemistry to get a sample once per 24 hours until further notice. , 11.5.4 Enter on shift turnover and keep it on the turnover until the monitor 1r, back in service. ' 11.6 When the monitor becomes operational again, log it back in service in the Control Room Los and notify Chemistry that samples are no longer required. .1810e.. 877Wdsinw7 b s O MAINE YANKEE FACILITY COMMENTS / RESOLUTIONS . These comments were prepared in accordance with ES-201-1, Enclosure 3. Facility comments without a concise recommendation were not addressed. Paragraph 2 of ES-201-1, Enclosure 3 states that the facility coments will be submitted to the NRC by the highest level of corporate management for plant operations, e.g., the Vice President for Nuclear Operations. The facility comments were in fact submitted by the Operations Training Section Head. 5.01 The approximation AK = K-1 was accepted for full credit. 5.08b "Increase" was accepted for full credit as long as appropriate justification was provided. 5.09 Additional indications of natural circulation noted in ES-0.1 were accepted for full credit. 5.12 New Tc allowance was accepted for full credit. 6.01b K/A reference was corrected. Question was not deleted (SR0 K/A of 2.8). , 6.04a Alternate EDG shutdown method was accepted for full credit. Facility comment reference to R0-L-5.4, page 16 should be page 62. 6.04c Requested change was incorporated into question for exam bank use. 6.06b Response regarding gland leakoff tank overflow was not required for full credit. Facility comment reference to procedure 1-15-1, step 4.11.3 should be step 4.11.4. 6.60c Any correct answers were accepted for credit. 6.08b Valve number was not required for full credit. 6.10a Alignment to either ESF train was accepted for credit. 7.01 2. The noted K/A (operation of loop isolation valves) yas used as it provided the closest reference to the conditions under which an isolated loop is maintained. 3. The additional answers were not accepted. The first is applicable only if the loop is pressurized: it does not define why it is overpressurized. The second answer is precluded by the question structure which implies no loop leakage. 1 r). s 7.07a No changes were made. The ordering of steps and the time associated with the second step implies that only the first two steps are of , immediate concern. 7.08b No change was made. The facility comment is based purely on semantics. The operator was asked to state the'inmediate action steps for a given situation. 7.13 No change was made. Knowledge of shielding uses and radiation level requiremen:s for radiation areas are ALARA concerns and are supported by ES-402 and the referenced K/A. . 8.01a Use of "temperature" instead of "Tavg" was accepted for credit. 8.01c Reference to neutron flux log range channel instrumentation was not required for full credit. 8.01d The noted temperatures were corrected. No other changes were made. The facility comment is based purely on semantics as the conditions are different; the question did not ask if they are different, but why they are different. 8.02a No change was made. The facility comment implies that the correct minimum license requirement is either an R0 or SR0 license. Technical specifications state the minimum requirement. ' 8.02c Stating that the CR0 left the controls was accepted for full credit. 8.03a No change was made. Se:urity and other valid concerns were allcued. 8.05 Plant manager was accepted for full credit. Reference to the Radiological Controls Section Head was allowed. 8.06b Lining up swing pump was accepted for full credit. 8.07b Alternatives to "add PCC pump" were accepted for credit. 8.08a 177 steps was accepted for full credit. 8.09b No changes were made. No supporting information was provided so designations in the Emergenc," Plan were used. F 8.09d No chan es were made. Information within parenthesis is not required for ful credit. l .- - - _ _ - _ ___- - _ _.. _, .- }}

v t e Inspection Report - Maine Yankee - 1988002
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \| 25 \|
1988 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 7(0) 8(0) 9(0) 10(0) 11(0) 12(0) 13(0) 14(0) 15(0) 16(0) 17(0) 18(0) 19(0) 22(0) 23(0) 24(0) 80(0) 99(0) Security 200(0) Operator Exams Emergency Planning Other

IR 05000309/1988002

Text

Navigation menu

Search