Text

Exam Rept 50-302/OL-88-02 on 880601-02.Exam Results: Written & Operating Test Was Administered to One Candidate Who Passed
	ML20151Q757
Person / Time
Site:	Crystal River
Issue date:	07/27/1988
From:	Brockman K, Casto C; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20151Q742	List: ML20151Q739; ML20151Q757; RA88-006, Forwards Review & Comments on 880601 Senior Reactor Operator Exam;
References
	50-302-OL-88-02, 50-302-OL-88-2, NUDOCS 8808110278
	Download: ML20151Q757 (153)
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i ENCLOSURE 1 EXAMINATION REPORT 302/CL-88-02 Facility Licensee: Florida Power Corporation

,. Facility Name: Crystal River Nuclear Plant N

Facility Docket No.: 50-302 A written examination and an operating test were administered at Crystal River Nuclerr Plant near Crystal River, Florida.

Chief Examiner: mh ~2- M - T(

Date Signed CharTe~ - 1 to' Approved by: I _m Av I 7/A7[8s Oate/ Signed

'Kenhath E. Brockmag/' SectiogpChief Operator Licensing Section 2 Summary:

Examination on June 1-2, 1988.

A written and operating test was administered to one candidate, who passed.

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e REPORT DETAILS

1. Facility Employees Contacted:

L. C. Kelley, Manager Nuclear Operations Training J. Smith, Nuclear Operator Training Supervisor

2. Examiners:

C. Casto i

Chief Examiner

3. Examulation Review Meeting At the conclusion of the written exemination, the examiner provided J. Smith with a copy of the written examination and answer key for review.

The NRC Resolutions to facility coments are listed below,

a. SR0 Exam (1) Question 5.16 Disagree. The facility literature on this subject references both the Tave and the Fuel Temperature reductions. Learning objective #5 specifically addresses this concept. Additionally, the lesson material states that coastdown operations were performed during Cycle 5 at CR-3. No change to the answer key is required.

.(2) Question 5.17 Agree. The question will be modified to reflect the facility comment.

No change to the answer key is required.

(3) Question 6.03

! Disagree. The facility reference material describes the function of dummy bistables. The feature is available for use by the facility should they elect this method. No change to the answer key is required.

(4) Question 6.10 l Agree. The question will be modified for future use. For this I examination the answer key is modified to allow for actions associated with HPI system actuation.

(5) Question 7.09(a) l, Agree. The question has been modified to reflect the facility comment.

2 (6) Question 7.09(b)

Disagree. Although this information is contained within the body of a procedure, the knowledge required to answer the

-question represents-a basic understanding of the methodology associated with performing "RCP bumps." The question does not require specific steps / procedures to be recited. No change to the answer key is required.

(7) Question 7.10 Agree. This question was extracted from the Crystal River examination bank. The facility should ensure questions are maintained up to date via a quality assurance system. The answer key has been modified to reflect the facility comment.

(8) Question 7.13 Agree. The answer key has been modified to correct the typographical error.

(9) Question 7.21 Agree. The answer key has been modified in response to this comment.

(10) Question 7.22 Acknowledged. Question will be modified prior to transmission to the NRC main bank. No change to the answer key is required.

(11) Question 7.24 Disagree. The operator should be able to respond to this item based upon fundamental knowledge of how Rod Insertion Limits f change based upon specific plant conditions. NUREG 1122 Knowledges and Abilities Catalog states "knowledge of the ...

theoretical concepts as they apply to the CRDS: Rod Insertion Limits" and rates this as 4.3/4.7 for R0's and SR0's respectively.

The operator is expected to understand that Rod Insertion Limits may change if an RCP is secured or as core life progresses. No change to the answer key is required.

(12) Question 8.03 Disagree. The conditions as stated in the question do not warrant such a non-conservative action. There is no justification for defeating a complete trip system based upon a single failure. No change to the answer key is required.

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3 (13) Question 8.13 Acknowledged. No change to the answer key is required.

(14) Question 8.15 (a)

Agree. Due to incomplete initial conditions the question is deleted.

(15) Question 8.16 Agree. The table was inadvertently omitted. It was explained to the candidate at the start of the exam to inform the proctor should additional reference material be needed. The additional material would have been provided, if appropriate. The candidate made no such request and was able to adequately respond to the question. No change to the answer key is required.

(16) Question 8.17 Agree. Answer key modified to correct typographical error.

'4.- Summary There were no generic weaknesses noted during the oral examination.

t The cooperation _ given to the examiner and the effort to ensure an atmosphere in the control room conducive to oral examination was also noted and appreciated.

The licensee did not identify as proprietary any of the material provided

.to or reviewed by the examiners.

F .,

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.,,. NRC;0fficial Use Only h6b Nuclear Regulatory Commiscion Operator Licensing Examination 4

This document is removed from Official Use Only category on date of examination.

NRC Official Use Only

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U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: CRYSTAL PIVER REACTOR TYPE: PWR-B&W177 DATE ADMINISTERED: 88/06/01 EXAMINER: REGION II CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Use separate paper for the answers. Write answers on one side only.

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

% OF CATEGORY' % OF CANDIDATE'S CATEGORY VALUE TOTAL ' SCORE VALUE CATEGORY 29.50 24.74 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS 30.00 25.16 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION

'2l9.75 24.95- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 30.00 25.16 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 119.25 % Totals Final Grade All-work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

/

i NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS 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.

22. .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 anir 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 eheet, write "End of Category __" as appropriate, start each category on a ang page, write only an ang 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.

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

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

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

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

16. If parts of the examination are not c?. ear as to intent, ask questions of 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.

, 1 18.'When you-complete your examinution, you shall:

-a. Assemble your examination as follows:

(1) Exam questions on top.

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

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

b. Turn in your copy of the examination anc all pages used to answer the examination questions.

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

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

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5. THEO'GY-OF' NUCLEAR POWER PLANT OPERATIONS FLUIDSs_AHH PAGE 2 THERMODYNAMIGS LQUESTION 5.01 (1.00)

Which one of the following correctly describes the observed reactor response for the same small addition of reactivity, one positive and one negative?

a) The response will be faster for the. negative addition at all times in core life, b) The response will be faster for the negative addition at BOC but faster for the positive addition at EOC.

c) The response will be faster for the positive addition at all times in-core life.

d)- The response will be faster for the positive addition at BOC but faster for the negative addition at EOC.

e) The response will be the same for both the positive and negative addition.

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

5. THEORY OF NUCLEAR POWER PLANT OPERATJON. FLULDS. AND PAGE 3 THERMQDJNAMICS QUESTION 5.02 (1.00)

With the' reactor critical at 10 E-7 amps, rod withdrawal is used to increase power to 10 E-6 amps. Select the statement that correctly describes the position of the rods after the power is stablized at 10 E-6 amps,

a. The rod position will be higher than at 10 E-7 amps because more fuel must be exposed to the available neutrons to maintain the higher power level.

b. The rod position will be higher than at 10 E-7 amps to overcome the effects of the power defect.

c. The rod position will be the same because the outward rod motion needed to achieve a given startup rate equals the inward motion needed to reduce the startup rate to L zero,

d. The rod position will be lower than at 10 E-7 amps due to the increased delayed neutron population associated with the higher power level.

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

S. THEORY OF NUCLElVLF0HER PLANT OPERATIOL FLUIDS. AMD PAGE 4 THERMODYH&dIGH QUESTION 5.03 (1.00)

During a reactor.startup, power is being raised above the point of adding heat. Which one of the following statements if CORRECT?

(Assume a linear reactor power increase to approximately 3%)

a- . Since header pressure is 885 psig, Tave will not rise above the corresponding saturation temperature of 532 degrees Farenheit,

b. Since the OTSGs are low level limited and header pressure is being maintained at 885 psig, Tave will rise and the steam temperature will tend to follow Th.

c. With the header pressure being maintained at 885 psig, the OTSGs will remain at saturated conditions and no superheat will.be added.

d. Since the OTSGs are low level limited, the steam is superheated at aero power conditions and rises pro-portionally with power.

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(***** CATEGORY 05 CONTINUED ON NEXT PAGE **Kt4) i-

5. THEORY OF NUCLEAR POWER PLANT OPERATXON. F1UJJbt. AND PAGE 5 IHERMODYNAMICS-QUESTION 5.04 (1.00)

Refer to the attached Table 3: Cooldown Limits.

The purpose of the "fuel pin in compression" limit during a Steam Generator Tube Rupture event is to:

a. Limit pressure stress on the fuel pins to prevent cracking of the pellet.

b. Prevent weakening the clad due to stresses applied under EMERGENCY cooldown conditions.

c. Minimize the clad strain during cooldown to <1% plastic strees,

d. Prevent aire hydriding from weakening the cladding.

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(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

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Table 1: Adequate Subcooling Margin RCS PRESS MARGIN

> 1500 psig > 20*F

$ 1500 psig 2 50'F 3.11 IE t$ equate subcooling margin does HQI exist, THEN:

o Within 2 min, stop all RCPs, o CONCURRENTLY PERFORM AP-380, ES Actuation, beginning with Step 3.4, o Raise OTSG levels to 95% with EFW, o Start full HPI.

Table 2: Required OTSG Levels Condition Level Inadequate subcooling margin 95%

No RCPs 65%

and adequate subcooling margin RCPs Low Level and adequate subcooling margin Limits Table 3: Cooldown Limits Normal Emergency RCS 2 500*F s 100*F/hr

5 240*F/hr

RCS < 500'F S 100'F/hr

1 100 ' F/hr

Tube to Shell AT s 100

F AT S 150*F AT Fuel Pin in Compression Apply Do not apply

IE no RCPs are operating, THEN cooldown rate should be 1 50*F/hr.

EP-390 REV 05 PAoE 20 or 35 ScTL J

5 '. THEORY OF NUCLEAR POWER PLANT' OPERATION. FLUIDS. ARH PAGE 6 THERMODYNAHIGE QUESTION 5.05 (1.00)

-Which combination below describes how the three heat transfer regions in the 0TSG change as power INCREASES?

NUCLEATE BOILING FILM BOILING SUPERHEAT a, constant increases decreases

b. increases decreases constant

c. decreases constant increases

d. increases constant decreases

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

5 ~. THEORY OF NIJCLEAR POWER PLAtLT APERlLTJRN. FhDIDS. ANA PAGE 7 l THERMODYNAMlf3 l l

QUESTION 5.06 (1.00)

Which one of the following conditions would be the major concern when conducting a forced circulation cooldown with

-one OTSG dry and depressurized?

a. Pressurized thermal shock.

b. OTSG Tube-to-Shell differential temperature.

c. Excessive Subcooling Margin.

d. Excessive Delta Tc.

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

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5. - T11EORY OF NUCLEAR POWER PLMLT OPERATION. FLUTDS E PAGE 8 IHERdpDYNAMICS QUESTION 5.07' (1.00)

Which.one of the following is correct concerning differential control rod worth (DRW)?

a. It is a measure of reactivity due to rod position,

b. With a normal cosine flux shape, DRW reaches a maximum value at a rod index of less than 28%.

c, Rod Group Overlapping maintains a constant DRW.

d. Its units are delta K/K/%index.

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

5. THEORYLOF NUCLEAR-POWER PLANT OPERATION. FLUfDS.'AND PAGE 9

. THERMODYNAMICS-QUESTION 5.08 (1.50)

With the Unit operating at 100% power with all control systems in automatic, a Turbine Bypass Valve. fails full open. Indicate how~the following parameters will change relative to their initial values when plant conditions stabilize: (INCREASE, DECREASE, REMAIN THE SAME) a)' Tavg b) MWe c) Reactor power i

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(***** CATEGORY OS CONTINUED ON NEXT PAGE *****)

5. THEORY OF NUCLEAR POWER PLAEI_0PERATION. FLUIDS. 4HIl PAGE 10 THERMODYNAMICH'

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-QUESTION 5.09 ( .50)

In a suboritical reactor, reducing the boron concentration of the RCS will result in (a decrease /no change /an increase) in the subcritical multiplication level of the reactor.

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(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

S '. THEORY OF NUCLEAR POWER REANT OPERATION. FLUXDS. ARQ PAGE 11 THERMODYNAMIqS QUESTION 5.10 (1.00)

With regards to the Flux / Flow / Imbalance Trip functiori, state whether a Positive or Negative Flux Imbalance would allow a higher trip setpoint-(assuming other pertinent parameters are the same). Explain your answer.

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

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5: THEORY OF NUCLEAR __ POWER PLAliT OPERATION. FLUIDS. AND PAGE 12 THERMODYNAMICS QUESTION '5.11 (1.50)

State.three reasons why the initiation of Emergency Feedwater provides for an increased rate of heat transfer over the use'of Main Feedwater.

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(***** CATEGORY OS CONTINUED ON NEXT PAGE *****)

+ . 5l THEORY OF NUCLEAR POWER PLANT OPERA 710N..ELUIDS. AND PAGE 13 IEEllN10XIIMIGE i,

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! QUESTION 5.12 (1.00)

Explain'how the use of RCP "bumps" minimizes the effect of

. gas AND steam accumulation'within the RCS.

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(***** CATEGORY 05 CONTINUED ON NEXT PAGE '*****)

' )h.i THEORY OF 110 CLEAR POWER PLANT OPERATION. FLUIDS. MG PAGE 14 in THERMQD1R&MICS QUESTION 5.13 (1.00)

.Since fuel burnup is a direct. function of operation, why is

. the attached Core Excess Rea'ctivity Curve a non-linear function, particularly early in core life?

(***** CATEGORY 05 CONTI(UED ON NEXT PAGE *****)

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5. THEORY OF NUCLEAR POWER PLAtlT_QEEEEJON. FLUIDS E PAGE 15 THERMODYNAMICS QUESTION 5,14 (1.50)

If the OTSG low level limit were decreased, indicate whether reactor power would have to be HIGHER, LOWER or the SAME to achieve a TAVG of 579 3 degrees. Explain your answer.

(***** CATEGORY 05 C011TINUED ON 11 EXT PAGE *****)

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5. = THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AEH PAGE 16 TJ{ER!iODYNAMICS I'

QUESTION 5.15 (2.00)

Reactor power is 45% with loop feedwater flow demands at 45%, ICS is in AUTO, and no operator intervention occurs.

The "A" feedwater flow indication fails to a aero scale reading. State the response of each of the following to this condition:

a. ACTUAL feed.iater flow to the "A" OTSG (increase / decrease),

b. Tave (increase / decrease).

c. Load ratio circuit signal to BOTH OTSGs.

d. Turbine header pressure (increase / decrease).

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

5. THEOR,Y - OF NUCLEAR POWER ~ PLAT 1L QEERATION . FLUIDS. M PAGE 17 THERMODYNA11LCS QUESTION 5.16 (1.00)

Assume the reactor is operating at end of cycle conditions, and the operating cycle has been extended by "coastdown".

EXPLAIN how the power defect Nr the core is affected by operation in this state.

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *v***)

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5, THEORY OF NUCLEAR POWER PLANT OPERAIION.c FLUIDS, AND PAGE 18 THERMODYSAMICS l

l QUESTION 5.17 (2.00) l Assume that the plant has experienced a degraded electrical l power condition and that your are monitoring the plant's L cooldown on natural circulation. EXPLAIN why you agree or l disagree with the following statements:

a. A slow downward trend in indicated Tave is a good indication of well-established natural circulation flow.

b. A difference between wide-range Thot and wide-range Teold of ~65 deg. F. and slowly increasing indicates developing natural circulation flow.

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(***** CATEGORY 05 CONTINUED ON NELT PAGE *****)

-5; THEORY'0F NUCLEAR' POWER PLANT OPERATTON. FLUIDS. AND' 19 PAGE IEERMODYM&MICS QUESTION 5.18 (2.00)

For each of the following, choose the situation for which individual rod worth will be GREATER. Then EXPLAIN why, a.'Tave equal to 150 deg. F. or 500 deg. F, b.~Early in core life or late in core life.

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

-[L THEORY-OF NUCLEAR POWER PLANT OPERATION. FLUIDS c AND PAGE 20 THERMODXUAMICS-QUESTION 5.19 (2.00)

One OTSG is significantly more fouled on the secondary side than the other OTSG. Considering how the ICS would respond to this condition.(in full automatic mode), answer the following: (Consider only steady-state effects)

a. Are the steaming rates of the two steam generators the same or different? EXPLAIN,

b. Are the levels in the two steam generators different?

EXPLAIN.

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *e***)

5 '. THEORY OF NUCLEAR POWER P1 ANT OPlRAUGL_JLUIDS. AND PAGE 21.

THERMODYNAMICS, N

QUESTION 5.20 - ( 1. 00 ) '

The reactor la operating at 50% power when a fully withdrawn control rod drops into the core. Boron concentration is slightly reduced to return to 50% power, but the rod is not retrieved. EXPLAIN the effect this would have on the Shut-Down Margin.

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(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

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5. THEORY OF NUCLEAR POWER PLANT OPERATIOIL FLUIDS E PAGE 22 T11ERUDDDial1IEE QUESTION 5.21 (1.00)

Loss of all Feedwater (Main and Emergency) is more critical on a small break LOCA than on a large break LOCA. Why is thia true?

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(***t* CATEGORY 05 CONTINUED ON NEXT PAGE *****)

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5. THEORT OF - NUCLEAILp4ER PLMlT_fPERATION, FLlJIDS. AND PAGE 23 THERMODYNAMICS

}

QUESTION 5.22 (1.50) 1 Attached is a curve showing Keff vs. moderator-to-fuel ratio for 500 ppm Doron concentration. For the following, indicate where on the curve the applicable location would be located: (e.g. above and to the left) a) Overmoderated region b) Negative-MTC region c) Direction optimum point shifts as Boron concentration decreases i

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) I

1.6 OPTINUM YALUE K K 2

- - - - *- 6ff K ............... . . . . . . . . . . . . . . . ...............:.........................

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1.0 0.8 :

0.6 i 0.4 i i 0.2 1 2 3 4 5 T 7 8 ig 10 2

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~5. THRORY OF NUCLEAR POWER PLANT OPERAT101L FLUIDS. AtU). PAGE 24

. THERMODYNAMICS QUESTION 5.23 (1.00)

Given that CR-3 is operating at 2544 MWth, calculate the Average Linear Power Density. (177 fuel assemblies) Show all work,

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

.5. THEORY OF NUCLEAR POWER PLANT OPER&IlpN. FLUIDS. AND PAGE 25 THERMODYNAMICS QUESTION 5.24 (1.00)

An OTSG is receiving 4.68E+9 BTU /hr from the reactor. The following loop conditions exiet:

- Th is 600 deg. F.

- Tc is 555 deg. F.

If both reactor coolant pumps are operating in this loop, then how many lbm/hr must each deliver to the OTSG?

(Assume cp 1.3 and no heat addition for the RCPs) i i

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(***** END OF CATEGORY 05 *****)

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G. PLANT SYSTEMS DESIGN e CONTROL m AND INSTRuffEFTAT10N PAGE 26 QUESTION 6.01 (1.00)

Which one of the following will NOT cause the ICS to enter the TRACKING mode of operation?

a. Placing the Diamond-Control Station in Manual,

b. Placing BOTH Main Feedwater Valves in manual control.

c. Placing the Reactor Demand station in Manual.

d. Feedwater Cross Limits in effect.

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

6. PLANT SYSTEMS DESIGN, COMTROL. AND INSTRl]1iElLTAI10R PAGE 27 QUESTION 6.02 (1.00)

Which one of the statements below correctly describes the operation of the Low Load Control Valve (LLCV) and the Main Feedwater Block Valve (MBV) during power decrease from 100% to 15% ascuming both valves are in Automatic?

a) The MBV starts to close as Loop FW Demand drops below 80% and the LLCV starts to close when the MBV reaches the fully closed position.

b) The MBV starts to close as Loop FW Demand drops below 50% and the LLCV starts to close when the MBV reaches the 80% open position.

c) The MBV starts to close as Loop FH Demand drops below 45% and the LLCV starts to close when the MBV reaches the 50% open position.

d) The MBV starts to close as Loop FW Demand drops below 45% and the LLCV starts to close when the MBV reaches the fully closed position.

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(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

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8. PLANT SYSTEMS DES EN. CONTROL &ND TNSTRUMENTATION PAGE 28 QUESTION 6.03 (1.00)

Which one of the following is correct concerning Reactor Protection System operation with one "Dummy Bistable" installed?

a. The RPS is in a 2-out-of-3 Trip Logic

b. The affected channel is in the tripped state

c. The Dummy Bistable contacts are normally open and close upon a trip signal

d. If installed as a replacement for High Flux bistable, placing the channel in shutdown bypass would defeat the purpose of the dummy bistable l

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

PLANT SYSTEMS DESIG U ANTROL.AND INSTRUMENTAT E 29 G '. PAGE

.kUESTION 6.04 (1.00)

,Which one of the following purposes is correct for the Control Rod Drive mechanism Lead Screw?

a. Provides coupling between the rotor assembly and the control-rod.

b. Determinea the absolute position of the drive,

c. Prevents radial motion of the upper portion of the rotor.

d. Slows the rod during the last (12)' inches of travel to prevent damage to the torque tube.

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****) l

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E, PLANT SYSTEMS DESIGN, CONTROL. AND INSTRUMENTATION PAGE 30 QUESTION 6.05 (1.00)

Refer to Figurec 9,13-15 attached. For each flowpath

-depicted, choose the correct alignment listed below.

Figure 9 Figure 13 Figure 14 Figure 15 SF cooling with the DH system DHR with the SF pumps Initial fill of the SF system SF pumps / valves operability checks Recircing the FTC BWST Purification l

j (***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

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~ L ' PLANT SYSTEMS: DESIGN.-Cf#LTROL. AND INSTRUMEliTATIQH PAGE. 31 QUESTION 6.06 (1.50)

Indicate for each of the following whether they apply to an RPS Biotable or an RPS Contact Buffer?

1s ) Two ana16g inpute, with one input being a setpoint.

b) Must be manually reset via a toggle switch.

c) Energizes a relay if input senses a trip condition.

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

6. PLANT SYSTEMS DESIGN. CONTROL d ND INSTRUdRNTATION PAGE 32 QUESTION 6.07 (1.50)

-List the three chemical analyses performed by the PASS Jaystem for the liquified phase.

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

l

l=

i8. PLANT SYSTEMS DESIGN. CON'EAND INSTRUMERATIOt1 PAGE 33 QUESTION 6.08 (1.50)

Assume operation at 100% power all control systems in automatic. A failure of the selected Thot instrument occurs that results in a mid-scale reading. STATE the response of indicated Tavg (increase / decrease / remains the same) initially, Control rods (in/out/ remain the same),

feedwater flow (increases / decreases / remains the same).

(***** CATEGORY 06 CONTINUED ON HEXT PAGE *****)

1 L_ PLANT ' SYSTEMS DESIGN. C0tLTROL. At1D IMnIEll1EETATION PAGE 34 QUESTION 6.09 (1.50) ?

-Assuming full power operation with all control systems in automatic. The Diamond Control Station is~taken to manual.

For each of the given conditions listed below, indicate whether BOTH loops or EITHER loop in this condition will prevent feedwater from accepting Tavg control:

a. OTSG on low level limits.

b. OTSG BTU limited.

c. Feedwater Loop Master in Hand.

(+**** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

.l

8. -PLAtlT_ SYSTEMS 'DESLCWNND INSTRUMDLTATION PAGE 35 l QUESTION 6,10' (2.'00)

J Assume a valid automatic Low Pressure Injection initiation signal cccurs. Lict five actions / realignments of the Decay Heat System (including DH Sea Water) in response to thia signal.

(*+H t CATEGORY 06 CONTINUED ON NEXT PAGE *****)

W L PLAllT SYSTEMS DESIGN. CONTROLJND INSTRUliEl!LTATION PAGE 36 QUESTION 6.11 (1.00)

Indicate for each of the following situations whether the indicated breaker can be closed or if cross-tie blocking will prevent closure. Refer to the

. attached drawing showing the 4160ES Distribution.

a) Breakers 3207, 3208 and 3209 are closed. An attempt to close 3210 is

.made, b) Breakers 3205, 3208 and 3210 are closed. An_ attempt to close 3200 is made.

(*+++* CATEG0hY 06 CONT!NUED ON NEXT PAGE *****)

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8. PLAST SYSTEMS DESIGN. COXTJOL...lNDINSThUMEtLTATIOtl PAGE 37 QUESTION 6.12 (1.00).

For the operating conditions listed below, indicate what error signal would be the controlling input into the Megawatt Calibrating Integral, Assume that all other controle are in Automatic, with the unit at power.

a) SGRX in Manual b) Turbine not in ICS Auto a

f k

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

.c

m . . . - . . .

8. PLANT SYSTEMS DESIGN. CONTROL J 1D fHSTRUMERTATIOR PAGE 38 QUESTION 6.13 (1.50)

List-the 5 modifications made to the Reactor Protection System when the Shutdown Bypass switch is placed in the "Bypac," position.

t b

(***** *****)

CATEGORY 06 CONTINUED ON NEXT PAGE W

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

G. -PLANTJYSTEMS DESfGN. cot 1 TROL _JND THSIBHL4ENTATION PACE 39 m

0.UESTIOt1 6.14 ( .50)

State whict meaker is "Blocked" from closing with a normal electrical and SP-354B Monthly I'unctional Test of EDG in progress. , B r-n line with its outpat Srsaker closed) i l

(***** CATEGORY 06 CONTINUhD ON NEXT PAGE *****)

\

6._ PLANT ' SYSTEMS DESIGN , .. CONTROL JND fliS.TBUMEtLTATION PAGE 40

QUESTION 6.15 (2.00)

'For the. Absolute Position Indication instrumentation, answer

'the following:

La. What is the. source of indication? (0.5) b._ List five.(5) applications of the system output. (1.5)

Note: consider multiple uses of the same.

indication / interlock / control etc. as one application.

I-l l

(***** CATEGORY 06 CGNTINUED ON NEXT FAGE *****)

L 1

I

~- 6 . PLANT -SYSTEMS DESIGN JONTROL. ' AND IEETELEtLTATION PAGE 41-QUESTION 6 16 (1.00)

Assume a loss of offsite-power occurs coincident with a HPI actuation. Explain the feature of the HPI pump otart ,

selector switches which will prevent two HPI pumps from

), being loaded onto one diesel generator.

(***** CATEGORY 06 CONTINUED ON HEXT PAGE ***-**)

6. PLANT SYSTEMS _ DES ~L(11L CONTROL. AND INSTRUM,ERTMIGH PAGE 42 1 QUESTION 6.17 (2.00)

.For the Emergency Feedwater Control Valves EFV-55, EFV-56, EFV-57, and EFV-58 provide the following information:

1. EXPLAIN the motive force used to operate the valves.

(0.5)

2. What system provides the contrclling signal (s) for the val.ves? (0.5)

3. What is the basis for the "fill rate limiting signal for valve operation? (1.0)

(***** CATECORY 06 CONTINUED ON NEXT PAGE *****)

.fL -PLANT SYSIF49 DESIGN. CONTROL. AND INSTROMENTATlQH PAGE 43 QUESTION 6.18 (1.50)

While at 75% power, with all control systems in AUTO, the SGRX Master is placed in : LAND. Describe the effect on the ICS from increasing its output to 80% Discuss only the systems affected by the control manipulation and how the ICS compensates for the increased demand.

l l (***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

-- -m , + , - - - .,m_, _- %.._ ,__,_.,,_ p, .,

B-. PLANT SYSTEfiS-DESIGN. CONTROL J MD INSTRUtiENTATIOR PAGE 44 QUESTION 6.19 (1.00)

For-the Refueling Bridge EXPLAIN the significance of confirming the Z-Z' tape readings (both up and down) in all locations.

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

SA PLANT SYSTEMS DESIGU M L. AND'INSTRilMEHIb210H PAGE 45 I

QUESTION 6.20 (1.00) 1

-Assume the plant is being brought to cold shutdown by use of the Remote Shutdown Panel. The four transfer switchec have

-been switched to the RSP position. Answer the following:

1

a. Should a loss of power occur to any of the four transfer switches, EXPLAIN the effect on the control of the associated functions.

b. A Fuse Status Light is extinguished for a component, EXPLAIN the significance of this condition.

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

6i PLANT SYSTEMS DESIGN, CONTROLsAND.INSTRUMENTATIOR PAGE 46

' QUESTION 6.21 (1.50)

EXPLAIN how the Control Rod Relative Positicn Indication operates, such that it will NOT display the correct position of a dropped control rod.

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

6. PLANT SYSTEMS DESIGN. COMIROL. AND TNSTRUMENTATIQH PAGE 47 QUESTION- 6.22 (2.00)

Refer to Figure 18 attached and answer the following:

a. CR-3 is operating at full power. An EFIC-MSLI "A" signal is received. Would the MSIV relays "A" and "B" ENERGIZE or DEENERGIZE (choose one), AND would the valves CLOSE7 (yes/no).

b. Assume the MSIVs had closed due to an EFIC-MSLI signal which has cleared. Permission has been granted to reopen the MSIVs and the operator positions the Control Switches to the OPEN position. _The MSIVs do not open. EXPLAIN what interlock / action must be satisfied to complete this evolution.

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

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6. PLANT-SYSTEMS DESIGN, COPJROL , AND INSTR N 9H PAGE 48

' QUESTION 6.23 (1.00)

Briefly EXPLAIN how the ICS determines RCS flow for feedwater re-ratio and runbacks.

(***** END OF CATEGORY 06 *****)

7. , PROCEDURES '- NORMAL. ABNORMAL. EMERGERCY AEH PAGE 49 1AHlOLOGICAL__CONTRQL 1

I

-QUESTION 7.01 (1.00)

AP-380 Engineered Safeguards Actuation gives the operator guidance that "If-HPI throttle requirements are met, then open MVP recires, and throttle HPI flow as required". Which one of the following is NOT a limitation given by this procedure for controlling HPI flow?

a. HPI must be throttled to maintain subcooling margin

(<100 deg) when no RCPs are operating,

b. HPI must be throttled to maintain RCS PRESS and TEMP

< NDT limits.

c. HPI must be throttled to maintain HPI flow < (540) gpm/ pump.

-d. HPI must be throttled to mala.tain cooldown rates if subcooling margin DOES NOT exist.

l l

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

{

"f . PROCEDURES - NORMAL. ABNOhMRGENCY_ARD PAGE 50 BADIOLOGICAL COtLMOL QUESTION 7.02 (1.00) to the OSIM, which one of the following must be According used for r #r*oper tracking of "special valve line-ups"?

P a) Placing an entry in the operator's log.

b) Listing on the shift relief check list.

c) Placing an entry in the shift supervisor's log.

d) Making a temporary procedure change.

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(++*** CATEGORY 07 CONTINUED ON NEXT PAGE **4**)

l 1

L PROCEDURES - !10RMAL M AL. EMERGE M PAGE 51 BADIOLOGICAL_CMITRQL l

l QUESTION 7,03 (1.00)

Consider a situation where a Large LOCA has occurred, and you are operating the plant under AP-380, "Safeguards Actuation" and EP-290, "Inadequate Core Cooling". While performing a needed step in EP-290, you find you are unable to complete the action as called for in either the "ACTIONS" or the "DETAILS" column of the procedure, Which statement below correctly describes the appropriate action the operatur should take, assuming additional methods NOT LISTED in EP-290 could be utilized to complete the required action?

a. The operator at the controls should take the appropriate mitigating actions, and then inform the NSS or ANSS.

b. The operator at the controls should await direction from the NSS or ANSS, and if none is forthcoming, continue with tne procedure.

c. The operator at the controls should inform the NSS or ANSS of his alternative action for concurrence, prior to performance.

d. The operator should continue attempts to take the action as stated in the EP, while continuing on with the procedure.

(+**** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

7. PROCEDURES - NORMAL- ABNORMAL. EMERGENCY AND PAGE 52 RADIOLOGICAL CONIRQL QUESTION 7.04 (1.00)

Prior to reaching 200 deg F. RCS temperature during a heatup, a vacuum is drawn on the OTSGs. Which one of the following is the correct basis for this action?

a. there is a danger of oxygen pitting of the OTSG tubes during heatup; therefore all air must be removed from the OTSGs.

b. ensures that all nitrogen is removed form the OTSG prior to reaching 212 deg. F.

c. promotes early boiling of the OTSG water inventory; therefore, promotes _even heating of the OTSG shell.

d.' minimizes the possibility of water hammer in the OTSG.

P I

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

17 . PROCEDURES - NORMAL. Alt {pBMAL. EKERGENCX E'1 PAGE 53 RADIOLOGICAL COMROIs

' QUESTION 7.05 (1.00)

Which one of the following conditions is a procedural

, requirement for manually tripping the reactor?

a. Emergency feedwater actuates,

b. Subcooling margin drops below 50 deg. F. during power operation.

c. Shutdown margin is determined to be less than 1% dK/K.

d. Feedwater flow is lost.

l' 1

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l l (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

L t

_ ~ . . _ - , e,. ., y _-

7. PROCEDURES - NORMAL. AB M EMERGENCY AND' PAGE 54 RADIOLOGIRAL CQJLTROL QUESTION 7.06 (1.00)

In accordanco with AI-400 P0QAM, select the correct action that must be done in order to deviate from a procedure.

a. Immediately report it'to the SSOD and responsible section superintendent / supervisor,

b. Mak'e a note on the procedure and continue.

c. Void that procedure and restart with a new copy.

d. Immediately contact the Document Control Section.

l

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

r 7 '. PROCEDURES - NORMALS _ABEDRMAL. EMERGENCY AND PAGE 55 RADIOLOGICAL CONTRQL 1 QUESTION 7.07 (1.00)

Which one of the following is correct regarding the

opera tion of: the CRDMs?.

CRDMs should not be energized unless:

a. The TBVs are in auto.

b The CRDM heaters are off.

c. SW is in service to the CRDMs.

d.' Shroud fans are in operation.

l (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

L- _

L7 PROdEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 56 RADIOLOGICAT J l m QUESTION 7.08 (1.00)

While. touring the-Auxiliary Building you. notice a sign indicating that the dose rate in that area is 80 mrem /hr.

That area should be marked ac a..

a. Radiation Contro11cd Area

b. Contaminated Area

c. Radiation Area

d. High Radiation Area l

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

7. PROCEDURES - C BNORMAL. EMERGENCY MlIl PAGE 57

-RADIOLQGICAL CONTRQL l

QUESTION 7.09 (1.00) a) When performing an RCP "bump" in an effort'to restore Natural Circulation, why 10 OTSG Pressure reduced, prior to starting an RCP, so.that RCS Tsat is 40-60 degrees below Incore Temperatures?

b) What two methods / indications can be utilized by the operator to determine if RCS pressure is high enough to allow a RCP "bump"?

'n**** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

7. -

7. PROCEDURES ' NORMAL. ABNORKSL. EMEBGEMCY AND PAGE 58 HAD10L.QQICAL CONTROL

~ QUESTION 7.10 (1.00)

' List two Entry Conditions for AP-770 Emergency Diesel

' Generator Actutation.

t I

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l (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

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'7.

PROCEDURES - NORMAL. ABN N ERGENQX_ARD PAGE 59

.BADIOLOGICAL CQ1LTRQL i

QUESTION 7.11 (1.00)

List all the modee that require the Out of Service Log to be updated

-and maintained.

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

' 7 '. PROCEDURES - NORMAL'. A2NORfi4LEGENCY ' MD PAGE 60 RADIOLOGICAL CO M QUESTION 7.12 (1.00)

In accordance with OP-404 Decay Heat Removal System, the DH system will be isolated from the RCS if RCS pressure is

>_ nsi and/or RCS temperature ic > deg. F.

(fill-in the blanks) 4

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

p

I

7. PROCEDURES - ~ NORMAL dBNORMEJERGFJ1Cy AND PAGE' 61 MDlDLEd9Ak_GOREQL 1

~ QUESTION 7.13 (1.00) l l ,.According to~0P-210 Reactor Startup, under what two l . conditione must the reactor be manually tripped?

[.

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

- . L;_fgQCEDURES - NOF C BNORMAL. EtiERGENCY AND PAGE 62

~R&DJ EQGlGAL CONTROL

' QUESTION 7.14 (1.75)

'a)

Assuming reactor power is 35%, what are the 3 parameters, which if exceeded' require entry into AP-660, "Turbine Trip"? (.75) b) While performing the IMMEDIATE ACTIONS of AP-660, the Governor Valves

-fail to close and the generator output breaker fails to open. What-are the appropriate REMEDIAL ACTIONS 7 (1.0) o

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

I PROCEDURES - NORMAL. 4BRORMAL. EMERGENCY E PAGE 63 RADIOLOGICAL GONTROL QUESTION 7.15' (1.00)

~ List four areas which require authorization from the Nuclear Fire Protection Specialist on a Fire Work Permit.

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

~_-- -

7. PR0cEDURES - NORMAL m&BMORMALs_EMERGEEPY s AND PAGE 64 RAALOLOGIcAL colin 0L l-l QUESTION 7.16 (2.00) a) In accordance with AI-500, "Conduct of Operations", what are the 4 areas which if affected by a procedure, require that the procedure be

-done in a step-by-step manner? (1.0) b) What is meant by conducting a procedure in a "step-by-step" maaner?

(1.0)

(***** CATEGORY 07 CONTINUED ON NEXT PAGE **k**)

7-. ' PROCEDURES --NQBRAL. AB110PMAL JiEBGE*1CY AND -PAGE 65-RADIQLQGXGAL ColEBOL QUESTION 7.17 (1.00)

The RWP that you signed in on gives you a margin of 1,000 mrom. You've already received to date, for this quarter, 850 mrem. If during the course of your job you realize that you have received 5?O mrem, what actions (if any) are you required to take?

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

7 PROCEDURES - NORMAL. 4}3 NORM W ERGENCX_.AMIl PAGE 66 RADIOLQGIC L CAtiTROL QUESTION 7.18 ( 1 . 511)

Answer' the following questions regatJing fuel handling operations:

ai While handling new fuel assemblies utilizing _the overhead crane, why must the 1.5 ton auxiliary hook be utilized when loading into ROW 1 of the new fuel storage racks, vice the main hook?

b) What indication can be utilized to verify that the Fuel Transfer Carriage is located in its normal storage area againot the "hardctops" in the "A" Fuel Storage Pool?

.c) After a fu'l assembly has been lifted, as indicated by the "Grapple Tube Up" light, what must be checked to verify grapple position?

l l

(***** CATEGOPY 07 CONTINUED ON NEXT PAGE *****)

i L _ _ _

7. PROCEDUREG - MQRtfAL. E110HttAL. EMERGPNCX_AND PAGE 67 RADIOLOGICAL CONTROL QUESTION 7.19 (1.50)

Assume that the dain Condenser :s tiOT available. What are two bases for allowing an Emergency'Cooldewn Rs.te of 240 degrees / hour to a Thot of 500 degrees while performing EP-390, "Steam Generator Tube Rupture"?

4 J

I (***** CATEGORY 07 CCNTINUED ON NEXT PAGE *****)

I

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

'7. PROCEDUBES ' - NOTRE ABNORMAL ._EMERGENCLA/JD 3 PACE 68 RADIOLOGICAL CONTRQL QUESTION 7.20 (1.00)

When the vessel head is removed, DHV-3,4,&41 breakers are required to be placed in "Lock-Reset" and Blue Tagged to the SSOD. Why is this action done?

(***** CATEGORY 07 CONTINUED ON HEXT PACE *****)

a

7.. PROCEDURPS - NORMALJBl; ORE EMERGENCY AND PAGE 69 RADIOLOGICAL,_ CONTROL QUESTION 7.21 (1.50)

With the Incore thermocouples selected, the subcooling margin monitor indicatea < 0 deg. F. .What procedures should the-operator be in and what are the Immediate Actions 7 I

(***** CATEGORY 07 coNTItiU?D ON NEXT PAGE *****)

4

'a _.

7 . PROCEDUEES_- NORMAL. ABNOR!iAL EMERGENCY AND PAGE 70 RADIOLOGICAL CONTROL QUESTION 7.22 (1.00)

Refar to step 3.10 of AP-530 Natural Circulation attached. EXPLAIN two

-bases for BOTH closing the PORV A.ND starting an RCP/ loop after recovery of RCPs and OTSG heat removal.

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(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

3.0 FOLLOW-UP ACTIONS (CONT'D)

&_CTIONS DETAILS Note EFW should not be throttled unless Nat Circ is established in at least 1 OTSG or Nat Circ level setpoint reached.

3.9 Throttle EFW to maintain Select EFW control valves to RCS cooldown rate manual and control flow.

s maximum allowable.

See Table 3 for allowable RCS cooldown rates.

Note Subcooling margin should be closely observed af ter starting RCPs.

3.10 IE, at any time while o RCPs are available for performing.this procedure, operation when gli of the RCPs become available, following conditions exist:

&ED OTSG heat removal is available, o Adequate subcooling THEN close PORV, margin, E start 1 RCP/ loop,

, AEQ TO TO Step 3.25 o RCP start permissives in this procedure. are met.

LE RCPs are available, o RCS PRESS is above RCP

&ED OTSG heat removal is NPSH curve, observe SPDS EQI available, or see enclosure 2.

THEH start 1 RCP,

&ED GO TO Step 3.25 o RCP-1B operating is in this procedure. preferred for maximum PZR spray.

1 Close TBVs or ADVs to Limit RCS Cooldown.

2 Start desired RCPs.

3 Maintain RCS TEMP using TBVs or ADVs.

AP-530 REV OG PAGE 9 of 22 NC 8

y-

7. PROCEDURES - NORMAL. ABHODMAL. ESERGENCY_AND PAGE 71 RADIQLpGICAL CONTROL QUESTION 7.23 (2.00)

Refer to step.3.18 of AP-990 Shutdour. From Outside the Control Room.

a. EXPLAIN where AND by what technique the operator completes this step. (aasume instrument air is available) (1.0)

b. -What is the basis for the 1010 psi setpoint for the OTSG prescure? (1.0)

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

h g- - -

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(_

3.0 FOLLOW-UP ACTIONS (CONT'D)

ACTIONS DETAILS 3.17 Ensure EFW is operating and See Table 2 for required OTSG controlling OTSGs at proper levels.

level.

3.18 Maintain OTSG PRESS at

= 1010 psig using the ADVs.

IE instrument air is HgI available, THEN r.otify CNO to manually control ADVs locally.

3.19 Establish PZR level control 1. Ensure running MUP is using make-up from BWST. aligned from BWST and to MUV-31.

II MUPs are HQT operatir,.;,

IHKH notify available operator to start MUP-1C and its cooling water pumps.

2. Ensure MUP recircs are open:

i o MUV-53 o MUV-257.

I l

3.20 IE personnel are available, 1. Establish bleed path from IHEN establish bleed to AB Rad Waste Panel.

RCBT,

&HQ establish a letdown 2. Open:

flow path.

MUV-49, Letdown Isolation, MUV-40, Letdown Cooler Isolation, MUV-41, Letdown Cooler Isolation.

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l AP-990 REV PAGE 17 of 19 SOCR QQ

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7. PROCEDURES - NORNAL ABilORMAL c EMERGENCV AND c PAGE 72 RADIOLOGICAL CONTROL QUESTION 7.24 (1.00)

' State two reasons that the computer generated Rod Insertion Limits and alarms may have to be changed periodically in accordance with OP 204 Power Operations.

I (n**** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

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1

7. PROCEDURES - NORMAL. ABHO@ AL . EMERGENCY AJlll PAGE 73 RADIOLOGIGAL.00tiTROL U

-QUESTION 7.25 (1.50)

Describe THREE indications that are available to the operator that Natural Circulation flow exists following a loan of RCPo.

4

(***** END OF CATEGORY 07 *****)

8. ADMflifSTRATfVE PROCEDURES J J1DITIONS, AND LIMITATIONS PAGE 74

. QUESTION 8.01 (1.00)

Which one of the following is NOT a criteria for the bases of rod position limits in Tech Specs?

a. ECCS power peaking

b. Shutdown margin

c. Power-imbalance boundaries

d. Potential ejected rod worth

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

8. ADMINISTRATIVE PROCEDTJRES. CONDITIONS. AND LIMITATIONE PAGE 75 QUESTION 8.02 (1.00)

.While operating at 75% power, WSV-3, Isolation Valve to the BMA-6 Containment Gaseous Process Monitor, fails shut.

Attempts to open the valve prove unsuccessful and the valve is declared INOPERABLE, deactivated and left shut. Which action below correctly describes what must be done with the plant in accordance with the attached Technical Specifications?

a. No further actions are necessary.

b. You must be in Hot Standby 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after the failed valve was identified.

c. You must be in Hot Standby 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months after the failed valve was identified,

d. You must be in Hot Standby 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months after the failed valve was identified.

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

8. ADMfNISTRATIVEL PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 76 I QUESTION 8.03 (1.00)

While operating at 80% power with ALL RCPs in operation, one channel of the."A" RCP input into the RCPPM has been declared INOPERABLE. Its input to all 4 channels of the RPS Contact Monitors has been placed in the tripped condition.

Subsequent investigation for a generic problem reveals that one channel of the "C" RCPPM is also INOPERABLE, such that a trip of the "C" RCP would not-result in a trip input to the Contact Monitors. Which statement below correctly describes the action that should be taken in accordance with the attached Technical Specification?

a. Place the "C" Channel of RPS in BYPASS.

b. Place the "C" Channel of RCPPM in BYPASS.

c. Place ALL 4 Channels of RCPPM in BYPASS.

d. Initiate actions to shutdown the plant to Hot Standby within one hour,

c. De in Hot Standby within six hours.

(***** CATEGORY 08 CONTINUED ON NEXT PACE *****)

8. ADMfHISTRATIVE PROCEDURES. CONDITIONS. AND..LIMIX61LQLS PAGE 77 QUESTION 8.04 (1.00)

The power-imbalance envelope defin d in Tech Specs is based upon which one of the following.

a. assure that an acceptable power distribution is maintained for control rod misalignment analysis,

b. assure that the potential effects of control rod misalir:gment on steam line break accident analyses are minimized.

c. assure LCCA analysis bounds on maximum linear heat rate for maximum cladding temperature limits.

d. assure that the nuclear uncertainty factor in LOCA analyses will not exceed the Final Acceptance Criteria.

b

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

o s M 8 '. ADMfNISTRATIVE PROCEDUBES. CONDITIONS AND LIMITATIONS PAGE 78 QUESTION 8.05 (1.00)

Which one of the fo11 cuing is the correct emergency classification for: An actual or potential substantial

- degradation of the level of safety of the plant not expected to' threaten the public?

.a'~ Unusual Event

b. Alert

c. Site Area Emergency d General Emergency I

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

'8 , ADMINISTRATIVE PJ1QCEDURES. CONDITIONS. AND LXMITATIOllS PAGE 79 QUESTION 8.06 (1.50)

List three generic eveats/ conditions as described in CP-111 Documenting, Reporting, and Reviewing Nonconforming

. Operation Reports, that would warrent completing a NCOR.

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

1

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

- 8. ADMINISTRATIVE PROCEDURES e CONDITIO U ND LIMITATTO E PAGE 80 i-4 f

I

- . QUESTION- 6,07 (1.50) i~

j .What three conditio'ns must be met to allow the operator to l j~ leave a fuel handling bridge unattended? ,

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(***** LnTEGORY 08 CONTINUED ON NEXT PAGE *****) l t

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8. ADMINISTRATIVE PR()CEDU*tES. CONDITIONS. AND LIMITATIONS PAGE 81 s

QUSSTION 8.08 (1.50)

List three conditions / requirements, per OSIM, for removing a Decay Heat Train from service.

(* * **:* CATEGORY 08 CONTINUED ON NEXT PAGE ***** )

~ 8. ADMINISTRATIVE PROCEDURES. CONDITIONS J ND LIMITATIONS PAGE 82 QUESTION 8.90 (1.00)

What two officiala (by title) must approval the raising of a new fuel assembly with the new fuel elevator?

l

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

t

Q . ' ADMINISTRATIVE PROCEDURES. COFDITIONS. AND'LIMIIATLONE PAGE 83 QUESTION 8.10 (1.50)

List five of_the amergency teams (by title) that may be activiar,ed by the emergency coordinator.

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i

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *'****)

b_ ._ _

-- 8 . ADMINISTRATIVE PROCEDURES c CONDITIONS J ND LIMITAUONE PAGE- 84 QUESTION 8.11 (1.50)

List, in order of preference, the methods used to notify the State Warning Point, Tallahassee (SWPT).

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

8. ADMINISTRATIVE PROQED_UEEfL CONDITIO)MND LIMITATIOlin PAGE 85 QUESTION 8.12 (1.00)

What type of tag, i.e., Red, Blue, or White, would be used to administratively restrict the operation of an individual piece of equipment?

(***** CATEGORY 08 CONTINUED ON NEXT PAGE ****v) l

8'. 'ADMItHSIRATfVE PROCEDURE M NDITIONS.JAND LIMITATIQBH PAGE 86

. \.

QUESTION 6.13 -(1.00)

Which'stepo of the Emergency and Abnormal procedures must the operators be able to perform without having the procedures in hand?

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

8. ADMINISTRATIVE PROCEDURES. CQJiDITIONS. AND LIMITATiggd PAGE 87

-QUESTION 8.14 (1,co)

In accordance with CP-115 In-Plant Equipment Clearance and Switching Orders, can a clearance be authorized to work on a valve ceat which is isolated from a system by one valve if i

the ayatem is at 400 pai, 230 deg. F., and the pipe size le 1"? EXPLAIN.

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(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****) I

a

b ADMINISTRATIVE RROCEDURES. COMDITIONS. AND LItiLTATIONS PAGE 88 QUESTION 8.15 (1.00)

Referring to the attached TS Fig 3.4-3, "RCS Temp-Press Limits for Cooldown", answer the following questions

a) What indication is used for determining RCS temperature when in a Natural Circulation mode of operation?

b) Why does.the most limiting region of the reactor coolant system change from the the Closure Head region to the vessel beltline region after the first several years of operation?

1 I

l

(***** CATEGORY 08 CONTINUED ON NEXT PAGE +-****)

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.8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIdlIAILONS PAGE 89 QUESTION 8.16 (2.00)

While entering a recently completed refueling outage, it was determined that the leakage past CFV-1 (see attached drawing) was 1 5 gpm. After the refueling outage, during <

the plant startup, a leakage test on CFV-1 revealed that the leak rate was now 4.0 gpm. Using the attached TS 3.4.6.2, determine the appropriate action that should be taken.

Indicate what portions of the TS were utilized in making your decision.

Aesume that the plant is currently in Mode 3.

r

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

-8. -ADMINISTRATIVE PROCEDURES. CORDlyIONS. AND-LIMITATIONE PAGE 90 QUESTION 8.17 (1.00)

a. What' official (by title) must approve an individual exceeding the 1.25R/QTR limit?

b. What administrative limit would be enforced for an individual who exceeds the 1.25R/QTR limit?

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

.jL ADMINISTRATIVE PROCEDURES, CQNDITIONS. AND LIMITATIONS PAGE 91 QUESTION 8.18 (2.00)

Answer each of the following in accordance with the requirements of AI-401 "... Revisions to P0QAM Procedures"

1. When can interim changes (IC) be used?

2. What changes can be made by an IC?

3. Compare the type of review that is required fcr an IC with that required for a permanent revision.

4. How many ICs can be in effect on any one procedure?

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

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8. ADMTNISTRATTVE PROCEDUE CONDITIOE_AND_ LIMITATIONS PAGE 92 QUESTION 8.19 (1.00)

Explain what must be done to meet the requirements of TS 3.3.3.1 for Rad Monitor RM-AS, if the Control Complex Ventilation System is INOPERABLE while in MODE 6 with the reactor defueled.

(***** CATEGORY 08 CONTINUED ON NEXT PAGE ***+:*)

8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 93 QUESTION 8.20 (1.50)

It is determined that the block valve for the Pressuriztr PORV is INOPERABLE. If TS action statement 3.4.3.2(b' is applied and the solenoid valve for the PORV is deenergized with the PORV closed, does that now require application of TS action statement 3.4.3.2(a)? Explain your answer.

(***** CATEGORY 08 CONTINUED ON t1 EXT PAGE **++4)

8. ADMINISTRATfVE PROCEDURES, CONDITIONS. AND LIMITATIONS PAGE 94 QUESTI0ii 8.21 (1.50)

Referring to the attached TS 3.7.13.1, what is the basis for the limitation on the maximum curie content?

1

, (*:**** CATEGORY 08 CONTINUED ON NEXT PAGE **+**)

8. -hDMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 95 QUESTION 8.22 (1.50)

What is the basis for ensuring the Diesel Generators obtain a load of at least 3248 KW when performing the operability surveillance stated in paragraph 4 of TS 4.8.1.1.2 attached?

Ensu.e you are specific with regards to the situation that requires this diesel loading.

(***** CATEGORY 08 CONTINUED ON NEXT PAGE ****+)

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8. ADMfNTSTRATIVE PROCEDURES. CONDITIONS d ND LIMITATIONS. PAGE 96

' QUESTION 8.23 (1.00)

State the two minimum protective actions when a General Emergency is declared.

i

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

'8. ' ADMINISTRATIVE PROCEDilRES. CQNDITIONS. AND LIMITATIONS PAGE 97

~ QUESTION 8.24 (1.00)

EXPLAIN what must be done with a procedure that was started but will not be completed.

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

(************* END OF EXAMINATION ***************)

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e g 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVE!LLANCE REOUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Limiting Conditions for Operation and ACTION requirements shall be applicable during the OPERATIONAL M00ES or other conditions specified for each specification.

3.0.2 Adherer.ce to the requirements of the Limiting Condition for Oper-ation and/or associated ACTION within the specified time interval shall constitute compliance with the specification. In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, completion of the ACTION statement is not mquired.

3.0.3 When a Limiting Condition for Operation is not met, except as provided l in the associated ACTION requirements, within I hour action shall be initiated to place the unit in a MODE in which the Specification does not apply to placing it, as applicable, in:

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

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

3. At least COLD SHUT 00WN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

k Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to thes'e requirements are stated in the individual Specifications.

3.0.4 Entry into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the conditions of the Limiting Con-dition for Operation are met without reliance on provisions contained in the ACTION statements unless otherwise excepted. This provision shall not prevent passage through OPERATIONAL MODES as required to comply with ACTION statements.

l 3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable limiting Condition for Operation, provided: (1) its r.orresponding normal or emergency power source is OPERABLE; and (2) all of iti redundant system (s),

sybsystem(s), train (s), component (s) and device (s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1)'

and (2) are satisfied, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months action shall be initiated to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply by placing it as applicable in:

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

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

\ ; 3. At least COLD SHUT 00WN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

This Specification is not applicable in MODES 5 or 6.

CRYSTAL RIVER - UNIT 3 3/4 0-1 Amendment No. 40 s

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l l REACTOR CCCLANT SYSTIM 3/a.a.5 IEJCTOR CCCLINT SYSTI'd LEAKAGE LIAXAGE CETECTION SYSTIMS L:MIT!'lG CONDITICN "CR CPERAT:CN 3.4.5.1 The following Reac:cr C: clan: System leakage de:acti:n systems -

shall 'ec CPERABLI:

a. The containment a:meschere iccine racicactivity moni Oring system,

b. The contair. ment sumo level monitoring system, and

c. The containment a:mesonare gaseous radioactivity monitoring sys tam.

APPLICABILITY: MOCES 1, 2, 3 and 4 ACTICN:

With Only :wo of the acove r9cuired leakage detection systems CPERABLI, cceration may continue for up to 30 days :revided grio samoles are oc-tainec and analy:ed at leas: Once :er E? neurs wnen .ne recuirec gasecus and/:r iccine radicactivity meni cring system is incoeracle; o tnerwi se be in a. leas: MOT STANCBY wi Min One nex 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months anc in COLD 5'uTCCWN d

within -he 'cilowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RECUIREME'iTS 4.1.5.1 The leakage detac:icn systems shall be demonstra ad CPERABLE by: .

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3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR. PROTECTION SYSTEM INSTRUMENTATION

~

LIMITING CONDITION FOR OPEPATION l

3. 3.1.1 As a minimum, the Reactor Protection System instrumentation chanrels and bypasses nf Table 3.31 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.

APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each Reactor Protection System instrumentation channel shall be demonstrated OPERABLE by the performance of the CHAhMEL CHECK, CHANNEL CALIBRATION And CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-1. '

4.3.1.1.2 The total bypass functir,n shall be demonstrated OPEPABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation.

4.3.1.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 l months. Each test shall include at least one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the "To~ Wo. of Channels" column of Table 3.3-1.

I

!CRYSTALRIVER-UNIT 3 3/4 3-1 a

.. .. --- .. .-- -~~ ---

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6

< Technical Specificati,rNrmp.cnation (TSI)

Ts1 586-26 October 24, 1986 Technical Specification 3.3.3.1 This Technical Specification interpretation is to provide an alternative nethod for air flow sampling and ventilation when RMA-5 is not operable.

Technical Specification 3.3.3.1 states the following: '

'The radiation monitoring instrumentation channels shown on Table 3.3-6 shall be OPERABLE with their alara/ trip setpoints within the specific limits.'

Technical Specification Table 3.3-6 states that the Control Room Radiation Monitor (RM-AS) shall be OPERABLE in all modes.

The Control Complex Ventilation System is not required to be operable below Mode 4 by STS 3.7.7.1, the requirement for operability of RMA-5 by STS 3.3.3.1 in all modes suggest the need for this ventilation system to be operating in order to obtain air flow for taapling by RMA-5.

When the reactor vessel is defueled the requirements in STS 3.3.3.1 for monitoring control room activity may be met with a portable monitor located in the control roca, and that breathing air for control room operators could be supplied by Scott air packs also located in the control roca.

Approval:

K. R. Wilson, Manager l Site Nuclear Licensing I

g TABLE 3.3-4 RADIATION MONITORING INSTRUMENTATBON g MINIMUM g CilANNELS APPLICABLE ALARM / TRIP MEASlJREMENT -

, INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTSON -

E y 1. AREA MONITOR $

s.,

a. Fuel Storage Pool area

1. Criticality Monitor i

d 15 mr/hr 10-I-104 mr/hr 14

2. PROCESS MONITORS

a. Reactor Building -

id 1. Gaseous Activity-RC5 Leakage

't Detection I I,2,3,4 Not Applicable g 11. lodine Activity- 103 -10' cpm 15 RC5 Leakage Detection i 1,2p.4 Not Applicable 103 -106 cpm 15 r

b. Controf Room

i. lodine Activity-Ventilation .

g Systeen isolation /

,E Recirculation i All Modes 6 2 x background 101 -806 cpm 18

?o a With fuel in the storage pool or building a

.o b

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in j *i TABLE 3.3-6 (cont.)

RADIATION MONITORING INSTRUMENTATION I

s kH H MINIMUM w CHANNELS APPLICARLE i

ALAEN/ TRIP MEASUREMENT INSTRtNGENT OPERABLE MODES SETPOINT RANGE ACTION l 2. Process Monitors (Continued) .

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I U C. Condenser Vacuum Pump D Euhaust Monitor - Gaseous Activity Monitor (RM-A12) I g 1, 2, 3, 4 19 i

! d. Nuclear Services Closed cooling Mater Monitor - -

I (RM-L3) i All Modes 19 l 3I 4

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I R e. Decay Heat Closed i 2 Cooling Mater Monitors l 3 (RM-L5 and RM-L6) 1 All Modes 19 .

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3 4

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TABLE 3.3 4 (Condnued) ,

TABLE NOTATION ACTION 14 - With the number of channels OPERABLE less than required by the Mirdmum Chanr.als OPERABLE requirement, orm area surveys of the monitored area with portable monitoring umentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 13 - With the number of channels dPERABLE less than required by ttw Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1 1

ACTION 18 - With the number of channels OPERABLE less than required by the Minimurn Channels OPERABLE requirement, within I hour initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

ACTION 19 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, plant operation may continue provided grab saa:ples are collected and analyzed for gross activity

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

LLO fgr noble gas principal gamma emitters shall be 5x10' C1/cc. LLO for liquid samples shall be 1x10-6 Ci/ml .

CRYSTAL RIVER - UNIT 3 3/4 3-24 Asandment l'o. 44.69 b

t l REACTOR C'OOLANT SYSTEM POWER OPERATED RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.3.2 The power operated relief valve (PORV) and its assochtted block valve sh311 be OPERABLE.

APPLICABILITY: MODES 1,2, and 3.

ACTION:

a. With the PORV inoperable, within I hour either restore the PORY to OPERABLE status or closc the associated block valve and remove power from the block valve; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ,

b. With the block valve inoperable, within I hour either restore the block valve to OPERABLE status or close the block valve and remove power from the block valve or close the PORY and remove power from the associated 91enold valve; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. The provisions of Specification 3,0.4 are not applicable.

SURVEILLANCE REQUIREMEN7S 4.4.3.2.1 in addition to the requirements of Specifications 4.0.5, the PORY shall be demonstrated OPERABLE at least once per 18 months by performance of a CHANNEL CALIBRATION.

l 4.4.3.2.2 The block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel.

CRYSTAL RIVER - UNIT 3 J/4 4-4a Amendments Nos. 5), H, 7), 77

PLANT SYSTEMS 3/4.7'.13 RADIOACTIVE WASTE SYSTEMS - F WASTE GAS DECAY TANKS LIMITING CONDITION FOR OPERATION -

3.7.13.1 The quantity of radioactivity contained in each Waste Gas Decay Tank shall be limited to less than or equal to 39000 curies (considered as Ee 133) . .

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactivity in any wasta Gas Decay Tank exceeding the above limit, immediately suspend all additions of radioactive material to that tank, and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within its limit.

b. The provisions of SpecifTeations 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIRZMENTS 4.7.13.1 The quantity of radioactive material contained in each Waste Gas Decay Tank shall be determined to be within the limit at least once per 7 days whenever radioactive materials are being added to the tank, and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during primary l

coolant system degassing operations. l CRYSTAL RIVER - UNIT 3 3/4 7-48 Amendment No. 69 t

h ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4 At least once per 18 nonths, by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months when the battery is subjected to a battery service test.

5. At least or.ce per f.0 months, by verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to a' perfomance discharge test. This performance discharge test shall be perfomed subsequent to the satisfactory completion of the required battery service test.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE.

a. At least once per 31 days on a STAGGERED TEST BASIS by:

1. Verifying the fuel level in the day fuel tank,

2. Verifying the fuel level in the fuel storage tank,

~. Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank, 4 Verifying the diesel starts from ambient condition and can accelerated to at least 900 rpm,

5. Verifying the generator is synchronized, loaded to greater than or equal to 1500 kw, and operates for greater than or equal to 60 minutes, and

6. Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.

b. At least once each 92 days by verifying that a sample of diesel fuel from the fuel storage tank is within the acceptable limits specified in Table 1 of ASTM D975-68 when checked for viscosity, water and sediment.

c. At least once per 184 days in lieu of surveillance 4.8.1.1.2.a.4 by verifying the diesel starts from ambient condition and accelerates to at least 900 rpm in less than or equal to 10 seconds,

d. At least once per 18 months, by:

1. Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recornendations for this class of standby service, CRYSTAL RIVER - UNIT 3 3/4 S-4 Amendment No, $, /J, 7) 96

gLECTRIC M POWER SYSTEM 5 SURVEILLANCE REQUIREMgNTS (Continued) s 2. Verifying the generator capability to reject a load of 1515 kw without tripping.

- 3. Simulating a loss of offsite power in conjunction with Reactor Building high pressure and Reactor Building high-high pressure tests signals, and; a) Verifying de-energization of the emergency buses and load shedding from the emergency busses, b) Verifying that the 4160 v. emergency bus tie breakers open, c) Verifying the diesel starts from ambient condition on the auto-start signal, energizes the emergency busses with permanently connected loads, energizes the auto-connected emergency loads through the load sequencer, and operates for 15 minutes while its generator is loaded with the emergency loads.

- 4. Verifying the diesel generator operates for at least 60 minutes. 1 During the first 5 minutes but no greater than 6 minutes of this test the diesel generator shall be loaded to greater than or equal to 3248 kw but less than 3300 kw and during the remaining time of this 60 minute test, the diesel generator shall be loaded to greater than or equal to 2750 kw but less than 3000 kw,

- 5. Verifying that the auto-connected loads to each diesel generator for the worst case diesel generator operating condition do not exceed 3248 I kw, and l

6. Verifying that the automatic load sequence timers are OPERABLE with each load sequence time interval within t 104.

This test shall be performed in MODg 3

The specified 18 month frequency say be waived for Cycle VI startup

- These revised requirenents shall become effective upon approval i of the licensee's final test report and supporting documentation i and shall apply only until the end of Cycle VII.

CRYSTAL RIVER - UNIT 3 3/4 8-5 Amendment No. 6,U ,H , 104 i

i

,_ f} d') G /

o 5.. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 98 THERM 0DYNAlilCfS ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II ANSWER 5.01 (1.00) c REFERENCE CR ROT 1-6, obj 8, 9 K/A (3.0/3.0) 2003K107 ...(KA'S) .

AtlSWER 5.02 (1.00)

C.

REFERENCE CR 3 ROT 1-13, 13-2 (3.4/3.7) 001000K549 .

.(KA'S)

ANSWER 5.03 (1.00) b REFERENCE CH3 ROT 3-7 pp. 3 and Fig 2 (3.8/4.0) 035010K109 .(KA'S)

ANSWER 5.04 (1.00) d.

REFERENCE CR ROT 5-20 obj 3. (3.0/3.8) 000038K007 .(KA'S)

ANSWER 5.05 (1.00) d.

REFERENCE CR ROT 4-32 obj 2 component HTX (2.2/2.4) 000000G000 (KA'S)

L i THEORY OF NUCLEAR POWER PLANT OP2EATJ.ON. FLUIDS. AND PAGE 99 THERMODYNAMTCH ANSWERS -- CRYSTAL RIVER -88/06/01-i(EGION II ANSWER 5.06 (1.00) b.

REFERENCE CR ROT 3-3 obj 12 (4.5/4.7) 000040K304 .. (KA'S)

ANSWER 5.07 (1.00) d.

REFERENCE CR ROT 1-7 (2.8/3.1) 192005K105 . (KA'S)

ANSWER 5.08 (1.50) a) Decrease (+.5 ea) b) Decrease c) Increase REFERENCE OP-0C-TA-NT pp 7/8; LO lb CR ROT 3-3, obj 2 (3.6/3.9) 041020A202 . (KA'S)

ANSWER 5.09 ( .50) an increace REFERENCE CR ROT 1-12 obj 1 EQB (2.8/3.2) 004000K507 ..(KA'S)

a 5.. THEORY _0F NUCLEAR PCWER PLAllT CPERATfolL FLUIDS E PAGE 100 THERMODYMAMICS ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II ANSWER 5.10 (1.00)

Negative (+.5) Due to colder water nearer bottom of the core (Higher allowable Kw/ft) (+.5)

REFERENCE OP-0C-SPS-IC-RPS pp 12, LO lb (3.1/3.3)

CR ROT 4-12 ANSWER 5.11 (1.50)

1. the ini".iation of EFW lowerc the naturation precsure of the OTSG, and therefore the saturation temperature.

2. the EFW is sprayed directly on the OTSG tubes high in the ateam generator, therefore, increac3ng the effective area for heat transfer.

3. the EFW is ecsentially at ambient temperature, ao compared to main feedwater which han been heated.

(0.5 ea)

REFERENCE CR ROT 4-15 obj 5, para. 1.3 061000K501 .

(KA'S)

ANSWER 5.12 (1.00)

(The intent of their use is to restore natural circulation)

In doing this, gasec in the RCS should be mixed with RCS liquid to eliminate cac pockets. [0.5]

Bumping the RCPc condennes the steam bubble by cooling it (and starting reflux boiling). [0.5]

PEFERENCE Oconee Op-OC-SPS-PTR-AM-2 obj 1.f. 4.0/4.4 CR ROT 5-25 obj 3 p. 7 AP 53C 00074K311 . (KA'S)

5.. THEORY OF NUCLEAR POWEJLELART_DPERATION. FLUIDS dED PAGE 101 THERMOAVNAMICS ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II ANSWER 5.13 (1.00)

The addition of Eurnable Poison Bods slowa the decreaes, especially early in core life. (+1.0)

REFERENCE OP-0C-SPS-RT-RBC pp 12; LO it.1 (2.5/2.7)

CR ROT 1-11 obj 4 p. 11-9 1 mR 5.14 (1.50)

Lower (+ 5) due to the heat transfer area decreasing, the Delta T across the OTSG must increace to achieve the same power. (+1.0) (Q:uA DeltaT)

REFERENCE CR ROT 2-5, obj 10/11 K/A (3.8/4.0) 035010K109 .

.(KA'S)

ANSWER 5.15 (2.00)

a. increase

b. decrease

c. Hill attempt to control Tc by increasing demand to the "B" OTSG and decreasind the demand to the "A" OTSG.

d decrease REFEREllCE CR ROT 4-14 obj 7 pp 82,83. (3.0/3.3) 059000A211 (KA'S)

ANSWER 5.16 (1.00)

The extra reactivity required for coactdown operation corec moctly from a reduction in fuel temperature with a cmall ancunt coming from a reduced moderator temperature.

REFERENCE CR ROT-1-13 obj 5 pp 13-9 (2.9/3.1) 001000K530 . (KA'S)

5.. THEORY OF NUCLEAR POWER PLANT OPERATIO!J, FLufDS._ABH PAGE 102 IllEEMODX1L91LCS ANSWERS -- CR'.'STAL RIVER -88/06/01-REGION II ANSWER 5.17 (2.00)

a. Dicagree Tave is a calculated indication and one parameter decreasing will cause Tave to decrease giving a false indication. (Agree if candidate states other indicatione are used in conjunction with Tave.)

b. Disagree Natural Circulation is indicated by Th stabliaing then tends to decrease. Tc tends to track OTSG saturation temperature. (i.e. decreasec). dT will decreate as decay heat load decreasec REFERENCE CR ROT 3-3 obj 2,3,5 para. 3.0 (3.7/4.2) 000056K101 ..(KA'S)

ANSWER 5.18 (2.00) 600 deg. F. As the temperature of the coolant increaseo the neutronc are traveling further and further. This increases the likelihood that a neutron will reach a control rod.

Late in c"re li fe . As the core ages, boron cor. centration of the RCS in reduced. This reducen the neutron competition and maka*, the rods worth more.

(0.50 for each condition, 0.50 for each explanation)

REFERENCE CR ROT 1-7 EQB obj 15 '2.2/2.8) 001010K504 (KA'S) l u.. m

5.- THEORX__filLlllJCLEAll_P_QHILR PLANT OREH82 ION FkUIDS. AND PAGE 103 THERMODYM& MICE ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II ANSWER 5.19 (2.00)

a. The steaming rates of the two OTSGs will be the same.(0.5)

Using Q:mc(Th-Tc) and assuming an equal Th and primary flow rate for each generator and that the load ratio circuit is maintaining the dTc at 0, then Q will be equal for the two (0.5)

OTSGs. With equal heat input, the steaming rates will be equal.

b. Levels in the two generators will NOT be equal. (0.5) Using Q-UA(Tave-Tsat), it can be seen that if the heat inputs and dTs are equal, then any decrease in the heat transfer capability (U) must be offset by an increase in "A" level.(0.5)

REFERENCE CR ROT 4-14 obj 4 (2.2/2.9) 035010K502 .(KA'S)

ANSWER 5.20 (1.00)

Shut-Down Margin would be reduced by the amount of reactivity removed by the baron.

REFERENCE CR ROT 1-9 obj 10 (3.1/3.9) (EQB) 000003K107 .(KA'S)

ANSWER 5.21 (1.00)

In a small break LOCA core heat is not being removed sufficiently by the break and little RCS flow is being delivered due to elevated RCS pressure. In this case then OTSG cooling is needed in order to rer;ve the remainder of the heat to provent core damage. (For a large break LOCA, sufficient heat removal is being done by the break and ECCS flows, therefore, OTSG cooling is not necessary).

REFERENCE l CR ROT 3-4 obj 1 EQB (4.6/4.7) 000054K305 ..(KA'S)

Sv . THEORV OF NUCLEAR PCWER PL&M7 OPERATIQde FLUIDS _. AND PAGE 104 THERM M E ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II l

l ANSWER 5.22 (1.50) l l

a) Right of the optimum point (+.5 ea) l b) Left of the optimum point c) Above and to the right REFERENCE CR ROT 1-8, obj 10; CR ROT 1-9, obj 4 K/A (2.9/2.9) 192004K107 .(KA'S)

ANSWER 5.23 (1.J0)

ALPD = Total Thermal Power / Active fuel length of all assb.

= 2.544E+6 KW/(12 ft/ rod)(208 rods /assb.)(177 assb.)

= 5.76 KW/ft.

REFERENCE CR ROT 2-9 obj 3, (3.1/3.5) 015020K505 ..(KA'S)

ANSWER 5.24 (1.00)

Q = mcp dT m: 4.68E+9 1.3

45 m = 80,000,000 lbm/hr for two pumps == 40,000,000 lbm/hr/ pump

, REFERENCE l CR ROT 2-4 obj 3 (3.3/3.9) 003000K501 .(KA'S)

'6. PLANT SYSTEMS DESIGN. Cot 3 TROL. AND METJWliF.JLTAT10Ji PAGE 105 ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II ANSWER 6.01 (1.00) b REFERENCE OP-0C-SPS-IC-ICS pp 23/24; LO 1h (3.2/3.2)

CR ROT 4-14 obj 2.d. pp 11 ANSWBR 6.02 (1.00) d REFERENCE CR NAO 96, obj 6 K/A (2.4/2.6)

ANSWER 6.03 (1.00) a.

REFERENCE Oconee OP-0C-SPS-IC-RPS pp 23 1.g 3.1/3.5 CR ROT 4-12 pp 48 012000K603 .(KA'S)

ANSWER 6.04 (1.00) a.

REFERENCE CR ROT 4-27 obj 1. para. 1.4 ANSWER 6.05 (1.00) l Figure 9 BWST purification Figure 13 DHR with the SF pumps l Figure 14 Recircing the FTC Figure 15 SF pumpa/ valves operability checks i

l

EJ PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATIOR PAGE 106 ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II REFERENCE 4 CR ROT 4-29 Obj 7-14 (2.4/2.4/2.5/2.7) 1 033000K102 033000K104 . .(KA'S)

ANSWER 6.06 (1.50) a) Bistable (+.5 ea) b) Buffer c) Buffer REFERENCE OP-0C-SPS-IC-RPS pp 19-23; LO if, 3a, 3b (2.8/3.3)

CR ROT 4-12 ANSWER 6.07 (1.50)

The concentration of boron, pH, and chloride (0.5 ea.)

REFERENCE ROT 4-23 OBJ 4 p. 21 (3.3/3.6) l 029000K102 ..(KA'S) l ANSWER 6.08 (1.50)

I Tavg decreases l Control rods withdraw Feedwater flow decreases (cross-limits)

REFFRENCE CR ROT-4-14 obj 7 EQB I

l l

ANSWER 6.09 (1.50)

Both Either Both REFERENCE CR ROT 4-14 obj 4 EQB

'6.. PLANT SYSTEMS DESIGN. CONTROL. AND INSTJ1Ht1 FAT 12LOH PAGE 107 ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II ANSWER- 6.10 (2.00)

The BWST.is aligned to the DH pump suction header The valve in each LPI line opens DH pumps start DH (0.50 Seaea)

Water 9g Pump ec f [s start REFERENCE ~

Gd (bfhg CR 4-2 obj 7 para. 4.4 (3.2/3.5) 005000K402 ..(KA'S)

ANSWER 6.11 (1.00) a) Cross tie blocking in effect (+.5 ea) b) Breaker will close REFERENCE CR ROT 4-3, obj 5,6 K/A (2.8/3.1)

ANSWER 6.12 (1.00) a) Input / Output across SG/RX (+.5 ea) b) Header Pressure error REFEREhCE CR ROT 4-14, obj 3 K/A (2.7/2.9)

ANSWER 6.13 (1.50)

Bypasses Low Pressure Trip (+.3 ea)

Variable Low Pressure Trip RCPPM >1 hi/lo amps Flux /dflux/ flow trip Inserts 1720 psig Low Pressure Trip setpoint REFERENCE OP-0C-SPS-IC-RPS pp 16; LO le (3.3/3.6)

CR ROT 4-12 fig 5

l

' - * *S . ' PLANT SYSTEMS DESIGN. CONTROL ._AND_lNSTRUME)1TATION PAGE 108 ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II l

i ANSWER -6.14 ( .50)

(3209) A EGDG output breaker REFERENCE CR ROT 4-3 obj 6 EQB ~

ANSWER 6.15 (2.00)

a. There are 45 reed switches strapped to the motor tube,

b. 1. Position indication in the contol room

2. Individual rod position indication is used to determine group average position.

3. Asymmetric Rod

4. Group In and Out limits

5. Provides input to the sequence enable

6. auto inhibit and out inhibit circuits

7. Bleed and feed permits (5 at 0.3 ea)

REFERENCE CR ROT 4-28 obj 4 (3.5/3.8)

ANSWER 6.16 (1.00)

The start selector switch prevents a selected pump from tripping on an undervoltage condition and ensures that the

-non-selected pump does trip when an undervoltage condition exists on the 4160 ES bus. (1.0)

-or-When a pump is selected, a contact in series with the contact that is closed by the undervoltage relay is opened.

This prevents the trip signal from reaching the breaker tripping device. Conversely, when a pump is not selected, the contact is closed and the pump breaker will be tripped if an undervoltage condition occurs on the bus. (1.0)

REFERENCE CR 4-1 p. 90 obj chap. 2-2a. (4.3/4.4) 006000K405 ..(KA'S) .

C 6.. PLANT SYSTEMS DESIGN. CORTROL~. AND UlEIRU11ENTATION PAGE 109 ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II ANSWER 6.17 (2.00)

1. The valves are modulating solenoid valves that utilize an increasing DC current opposing spring pressure to modulate the valve (0.5)

2. EFIC (0.5)

3. This is done to minimize overcooling of the reactor coolant system when EFW is initiated.(1.0)

REFERENCE CR ROT 4-15 obj.6 (2.7/2.7)

ANSWER 6.18 (1.50)

Feed flow and reactor power will increase due to the increased demand.(+ 5)

This will cause OTSG pressure to rise above the turbine header pressure setpoint (+.5). The Turbine Control Valves will open to ;iestore the header pressure to setpoint, accounting for the extra 5% heat generation (+ 5)

REFERENCE CR ROT 4-14, obj 4, 5, 8 K/A (2.9/3.3)

ANSWER 6.19 (1.00)

The Z-Z tape reading is very important in assuring the fuel assembly or rod is fully withdrawn into the outer mast (up reading) or fully seated in a rack, basket, or core grid (down readings).

REFERENCE CR ROT 4-26 obj 14 para. 2.1.2 034000K601 ...(KA'S)

ANSWER 6.20 (1.00)

a. The functions controlled by the transfer switches will be transferred back to the Non-RSP mode automatically.

b. This indicates that control power has been lost to the component. (The fuse status lights monitor control circuits which do not have an automatic fuse switch out l when going to the RSP mode.)

t l

t

l

6.'-PLANT SYSTEMS DESIGN. CONTROL _ARD s INSTRUU,ENTATION PAGE 110 ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II REFERENCE CR ROT 4-16 obj 2, 3. para. 4.3.4,4.3.5

' ANSWER 6.21 (1.50)

A pulse stepping motor is connected in parallel to the (A, C and BB) phases supplying each mechanism. (0,5) As the phases are energized to cause rod motion, the stepping motor turns also. (0.5) The motor drives a potentiometer, which then produces a variable output corresponding to rod position.

The system only reflects rod position as a function of field rotation. (0.5)

REFERENCE CR ROT 4-28 objS (3.5/3.8) 001000K401 ...(KA'S)

ANSWER 6.22 (2.00)

a. ENERGIZE, NO (0.5 ea.)

b. The Test, Normal, Reset Switch must be placed in the reset position. (1.0)

REFERENCE CR NA0 83 obj 3, ROT 4-5 obj 2, (3.3/3.40 039000K408 ..(KA'S)

-ANSWER 6.23 (1.00)

The ICS calculates a flow eignal based upon the RCP breaker status.

REFERENCE CR ROT-4-9 obj 2 EQB

o47.. PROCEDURES - NORMAL. ADNORMAL. EMERGENCY AND PAGE 111

-RADIOLOGICAL CONTR01 ANSWERS'-- CRYSTAL RIVER- -88/06/01-REGION II ANSWER' 7.01 (1.00) d.

REFERENCE CR AP 380 p. 20 (4.1/4.3). (4.0/4.4) 000074G007 000074K311' ..(KA'S)

ANSWER- 7.02 (1.00) d)

REFERENCE CR OSIM V-2 (3.6/3.7)

ANSWER 7.03 (1.00) e REFERENCE CR ROT 5-14, LO 5 R/A (4.0/4.1)

ANSWER 7.04 (1.00)

-C.

REFERENCE CR OP-202, pp. 25 (2.7/2.8) 035010K113 ...(KA'S) i ANSWER 7.05 (1.00) d.

REFERENCE CR, OP-204 p. 8 (2.6/2.8) 056000G001 ..(KA'S)

- /.* PROCEDURES - NORMAL. h EMERGENCY AND PAGE 112 FADIOLQQJCAL-CONTROL ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II ANSWER 7.06 (1.00) a.

REFERENCE CR ROT 5-39 obj 7, EQB

' ANSWER 7.07 (1.00) c.

REFERENCE CR ROT 5-3 obj 3 EQB ANSWER 7.08 (1.00) c.

REFERENCE oCR ROT 5-43 obj 1 EQB ANSWER 7.09 (1.00) a) So that the OTSG will provide a good heat sink (+.5 ea) b) SPDS or RCP NPSH curve with plant wide range pressure indication REFERENCE CR ROT 3-5, pp 23; AP-530; ROT 5-25, LO 4 K/A (4.0/4.4)

ANSWER 7.10 (1.00)

Annunciator Alarms associated with 4160V ES bus E b d S M !'

9'/6C"" 5 NF-under/ degraded voltage.

Engineered Safeguards lights for EDG are bluo.

pg / ,p e ) < <, .4d "

,,p7,p,77 REFERENCE CR ROT 5-19 objs 1, 2, and 3 EQB

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

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

4 ,,, . . . . - . , - - -

.7. . PROCEDURES - kJDRt!AL . ABNORM AL . EMERGENC'(_BliQ PAGE 113 BADIDLDQl. GAL CONTBQL ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II ANSWER 7.11 (1.00)

Modes 1-4 REFERENCE CR ROT 5-38 obj 7. EQB ANSWER 7.12 (1.00) 284 psi and 300 deg. F.

REFERENCE CR ANO-86 obj 7 EQB ANSWER 7.13 (1.00) 2 MSIVS go closed PZR > 30s" t 70 " ,q REFERENCE CR ROT-5-2 obj 3 EQB ANSWER 7.14 (1.75) a) 1) > 50 degrees delta T between condensera (+.25 ea)

2) > 8 Degrees delta T tetween highest / lowest hot gas temperatures

3) > 10" Hg absolute condenser vacuum b) Close MSIVc (+.5 ea)

Notify Load Dispatcher REFERENCE CR ROT 5-29, LO 1 & 3; AP-660 K/A (2.8/2.9), (2.9/3.2) 045000G014 045000G015 ...(KA'S)

'7.* PROCEDURES - NORMAL c ABNORMAL. RMERGRHCX_AHIl PAGE 114-RADiptoaIcAL cortTAQL ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II

' ANSWER- 7.15 (1.00)

-1) Cable' Spreading Room (+ 25 ea for any 4)

-2) ES Switchgear Room

3) Station Battery Rooms

4) CRD Equipment Rocms

5) Control Center REFERENCE CR ROT.5-40, CP-118 LO 1; CP-118, pp 2 K/A (3.7/4.1)

ANSWER 7.16 (2.00) a) 1) Nuclear Fuel (+.25 ea)

2) Primary Coolant Pressure Boundary

3) Containment Integrity

4) ES_ Systems b) As each step is performed, the performer must sign / initial the step (1.0)

REFERENCE AI-500, pp 42; CR ROT 5-38, LO 13 K/A (4.1/3.9)

ANSWER 7.17 (1.00) leave the area and notify HP's REFERENCE CR ROT 5-43 obj 7 EQB ANSWER 7.18 (1.50) a) The Main hook will not reach ROW 1 (+.5 ea) b) POOL CARRIAGE OVERTRAVEL light

, c) "Z-Z" Tape full-up position must be checked REFERENCE CR FP-302, pp 5; FP-601, pp 5, 8; K/A (2.7/2.9)

"/ .

PROCEDURES - NORMAL . ABNORMAL EMERGENCY AND PAGE 115 RADIOLOG1CALEllLTROL ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II ANSWER 7.19 (1.50)

1) Minimize the release of radiation to the environment (+ 75 ea any 2)

2) Minimize level increase in the affected OTSG (Carryover)

3) Minimine depletion of non-recoverable BWST water REFERENCE B & W Technical Bases Document, CH III-E, pp 28/29 CR-ROT 5-20, LO 4; K/A (4.2/4.5)

ANSWER 7.20 (1.00)

To prevent isolation of DH system due to spurious ACI actuation (284 psi)

REFERENCE CR ANO -86 obj 7. EQB ANSWER 7.21 (1.50)

EP-290 Inadequate Core Cooling (0.75)

Ensure Full HPI flow (0.25 ca.)

If LPI is delivering flow, then maintain max LPI flow.

Ensure OTSGs are at SB% on the operating range.

REFERENCE CR ROT 5-19 obj 2 EQB ANSWER 7.22 (1.00)

PORV 1. allows for better inventory control

2. allows for better cooldown control RCP 1. provides better mixing of the coolant

2. provides elevated heat transfer to the OTSGs REFERENCE CR ROT-5-25 obj 3 (4.4/4.7) 000056K302 .(KA'S)

'7.' PROCEDURES - NORIE ABRORMAWERGENCY ARD. PAGE 116 RADIQLOGICAL_..CONTR01 ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II ANSWER 7.23 (2.00)

a. To obtain 1010 OTSG pressure will require the operator at

'the Remote Shutdown Station (0.5) to'take the valves to hand and manually lower OTSG pressure (0.5).

b. Allows a margin in pressure to allow the MSIVs to reseat and still minimises the cooldown of the primary plant. (1,0)

REFERENCE CR ROT 5.31 p. 4 AP 990 obj 3.

ANSWER 7.24 (1.00)

Effects of core life Configuration of the RCPs REFERENCE CR OP 204 p. 17 (4.3/4.7) 001000K504 ..(KA'S)

ANSWER 7.25 (1.50)

Tc approximately equal to Tsat of OTSG Th,Tc, and incores lower when OTSG pressur is lowered.

Tc coupled with Tsat for the OTSGs DT (incores - Tc_ develops and stablilizes any 3/4 for 0.5 ea.

REFERENCE OR ROT 5-25 obj 4

'8.. ADMINISTRATIVE PROCEDI)RES. CONDITIQNS..AND LIMITATIONS PAGE 117 ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II V.

ANSWER 8.01 (1.00)

.c.

REFERENCE i l

t CR Tech Specs 3/4.1.3 2.6/3.8 f 002006K006 ...(KA's)

I ANSWER 8.02 (1.00) l C

REFERENCE CR-ROT-5-1, LO 1/pp 24; CR TS 3.4.6.1, 3.0.3 K/A (3.3/4.1) 103000G005 .(KA'S)

ANSWER 8.03 (1.6-b REFERENCE TS 3.3.1.1, note (b); CR ROT-5-1 LO 1 K/A (3.4/4.3) 012000G005 ..(KA'S)

ANSWER 8.04 (1.00)

C.

REFERENCE CR Tech Spec bases 3.2.1. 2.6/3.8 002006K006 .(KA'S) i f ANSWER 8.05 (1.00) b.

REFERENCE CR ROT-5-51 obj 2 EQB

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

=8. ADMINISTRATTVE PROCEDURES. CONDI TIONS ._MD_ L LliITATIONS PAGE 118

ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II ANSWCR 8.06 (1.50) 1.'A condition adverse to quality of CR-3 operations, 2 .' Reportable (condition),

3 Non-routine event.

BEFERENCE UR ROT-5-40 CP-111 obj 1.0 ANSWER 8.07 (1.50)

1. grapple disengaged

2. grapple full-up

3. equipment de-energized REFERENCE CR ROT-4-26 obj 0 (2.8/3.3)

ANSWER 8.08 (1.50)

No more than one DHT shall be removed from service at any one time.

The requirements for voluntarily entering a degraded mode por CP-115 have been met.

The refueling transfer canal is flooded -or- at least one OTSG is available to remove decay heat via forced / natural circulation (only one required).

(0.5 ea.)

t REFERENCE CR ROT 5-38 obj 10 EQB (3.3/3.4) 005000G013 ...(KA'S)

ANSWER 8.09 (1.00)

Refueling Supervisor Reactor Specialist REFERENCE CR ROT 4-26 obj 6 EQB (2.3/2.9) 034000G001 . .(KA'S1

'8.

ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 119 ANSWEia --' CRYSTAL RIVER -88/06/01-REGION II ANSWER 8.10 (1.50)

Emergency Medical Team Radiation Emergency Team Plant Fire Brigade Environmental Survey Team Sampling Team Emergency Repair Team Dose Aesessment Team any 5 at 0.3 ea.

REFERENCE CR ROT 5-51 obj 1 EQB ANSWER 8.11 (1.50)

SHRDTS, NAWAS, COMM (0.33 ea. -0.25 for each swap required to place in proper order)

REFERENCE CR ROT 5-47 obj 17 EQB ANSWER 8.12 (1.00)

Blue REFERENCE CR ROT 5-40 CP 115 obj 7.0 ANSWER 8.13 (1.00)

Immediate and Remedial REFERENCE CR ROT 5-39 obj 5 EQB ANSWER 8.14 (1.00)

Yes - as long as the PRC approves it or the MOC (0.5 ea)

8.*

ADMTHISTRATIVE PROCEDURES,.CONDITIO W ID LItiITATIONS. PAGE 120

. ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II REFERENCE CH ROT-5-40 obj 5 EQB

/

o. s ANSWER 8.15 (4--00 ) '

g C c_.

a) DHR System Return to the 'Tieuvi,vr Vessel (t.5) b)

REFERENCE Due to the effects of neutron irradiation (+.5) W]

CR TS 3.4.9.1, B3.4.9.1; K/A (3.6/4.1) 002000G005 ...(KA'S)

ANSWER 8.16 (2.00)

TS 3.4.6.2, Table 3.4-2, note a.3 applies, therefore the actions in TS 3.4.6.2.b must be fol owed. (+1.0) Be in 4 d_ d7#

Cold Shutdown in 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . (+1.0) ogif Ge4h (c) f5 apphka udlei 4 ka pc ac&(O REFERENCE skub7 cptr.s p)d e ')"cp7 g. cpg, g TS 3.4.6.2; CR ROT-5-1 LO 1 M"' k 6(flbNnTu usD)ncre m3+ac4neJ}

K/A (3.5/4.2) 000000G005 ...(KA'S)

ANSWER 8.17 (1.00) c< 4j;7fd

a. The Plant Manager BN30- d

b. 2250 mrem not to exceed 5(N-18)

REFERENCE CR ROT 5-43 obj 5 EQB

'- ' 8_. A ADMINISTR&TIVE PROCEDQRES. CONDI N ND LIMITATl0RE' PAGE 121 ANSWERS -- CRYSTAL RIVER' -88/06/01-REGION II ANSWER 8.18 (2.00)

1. When time prevents implementation by other procedure change methods.

2. They may be used for the addition and deletion of steps not normally addressed in the procedure for a specific period of time, or event.

3. IC's must be reviewed and approved by the same review and approval cycle as required for new and permenanent revisions. Handwritten IC's may be used.

4. One (0.5 ea)

REFERENCE CR ROT-5 39 obj 2 ANSWER 8.19 (1.00)

The requirements may be met with a portable monitor in the

. control room (+1.0)

REFERENCE TS Interpretation 86-26; CR-ROT-5-1 K/A(3.1/3.0) 073000G005 ...(KA'S)

ANSWER 8.20 (1.50)

No (+.5) The intent of fulfilling either action statement satisfies the TS (1.0).

REFERENCE TS Interpretation 86-13; CR ROT-5-1, LO 1 010000G005 ...(KA'S)

'8.*' ADMINISTRATIVE PROCEDURES. CONDITIONS. AND'LIMITAT ONS PAGE 122 ANSWERS -- CRYSTAL RIVER -88/06/01-REGION II

' ANSWER 8.21 (1.50)

If the curie content was as the maximum and a total release of ALL Tanks" contents were to occur (+.75), then the total exposure (whole bony) to an individual at the nearest exclusion area boundary would not exceed 0.5 rem.(+.75)

REFERENCE CR TS B3/4.7.13.1; CR ROT-5-1 LO 1 K/A (1.9/2.9) 071000G006 .(KA'S)

ANSWER 8.22 (1.50)

This is the assumed load for the first several minutes of the worst case diesel generator loading condition, (+0.5) a Loss of Offsite Power concurrent with an ESF actuation due to a Large Break LOCA, and a failure of the opr.aite train diesel to actuate (+1.0)

REFERENCE TS B3/4.8; CR ROT-5-1 LO 1 K/A (2.7/3.9) 064050G006 ..(KA'S)

ANSWER 8.23 (1.00)

Evacuate to the two mile radius all sectors.

Shelter to the five mile radius affected sectors.

REFERENCE.

CR ROT-5-51 obj 7.

ANSWER 8.24 (1.00) tiark VOID and provide a brief note on the cover sheet of the procedure / data sheets to indicate the reason (s) for voiding.

REFERENCE CR ROT 5-39 obj 6 EQB

ML20151Q757

Text

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