ML20215N178
| ML20215N178 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/10/1986 |
| From: | Bill Dean, Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20215N169 | List: |
| References | |
| 50-280-OL-86-01, 50-280-OL-86-1, NUDOCS 8611040402 | |
| Download: ML20215N178 (175) | |
Text
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. 4 ENCLOSURE 1 EXAMINATION REPORT 280/0L-86-01 Facility Licensee: Virginia Electric and Power Company P. O. Box 26666 Richmond, VA 23261 Facility Name: Surry Nuclear Plant Facility Docket No.: 50-280, 50-281 Written, oral, .and simulator examinations were administered at Surry Nuclear Plant near Surry Virg ni . ,
Chief Examiner:(_ [ 8(t/ _ ' "
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/0 C[f6 Wi liam~M Dean Date Signed Approved by: ./ d((( , //l-(oc M/086 John F. Munro, Acting Section Chief jaw Date Signed Summary:
Examinations on July 21-30, 1986 Simulator examinations were administered to 18 candidates,14 of whom passed; Oral examinations were administered to 18 candidates; 17 of whom passed. 18 candidates were administered written examinations; 10 of whom passed.
Based on the results described above, 4 of 8 R0s passed and 6 of 10 SR0s passed.
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0611040402 PDR 861020ADUCK PDR 05000200 V
REPORT DETAILS
- 1. Facility Employees Contacted:
- Dave Christian, Supervisor of Operations
- Bob Saunders, Station Manager
- Harold McCallum, Nuclear Training Supervisor
- Bill Marshall, Nuclear Training Instructor
- Larry Gardner, Simulator Supervisor
- Attended Exit Meeting
- 2. Examiners:
- Bill Dean Dave Nelson.
Clyde Shiraki
- Chief Examiner
- 3. Examination Review Meetina At the conclusion of the written examinations, the examiners provided Surry's training staff with a copy of the written examination and answer key for review. The comments made by the facility reviewers are included as Enclosure 3 to this report, and the NRC Resolutions to these comments are listed below.
- a. R0 Exam
! (1) Question 1.12 (5.12): Question asked for basis behind 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> as
- the period required to establish recire, not reason for establish-ing recirc. Second part of answer key is just a reiteration of part a. Answer key modified to require only the first part of answer key.
(2) Question 1.15(5.15): Based on supporting documentation in AP-39, will accept 50% as additional setpoint for pressurizer level, and will accept "RCS pressure >2000 psig to , ensure sufficient subcooling" as a correct answer. SG 1evels at NOL are equivalent
! to 33% at 0% power.
(3) Question 2.07(b) (6.08(b)): Will change answer key based on recent mesifications (not reflected in system descriptions) to delete "(xhaunt fans trip" and add "TV-IA-101A/B close and
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- 05 opens". Tech Specs should be modified to reflect current plant status.
I (4) Question 2.09: Test modified to reflect correct question value.
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(5) Question 2.14: Based on supporting information in a separate lesson plan, will add recommended answer as an additional correct answer. Lesson plan referenced in original answer should be modified to fully reflect all causes of a stub bus breaker trip.
(6) Question 2.20(b) (6.20(b)): Based on the possibility of interpreting the question as stated by the facility, recommended answer will also be accepted.
(7) Question 3.01: Question was based on a generic Westinghouse Plant's P-4 permissive, which does not totally apply at Surry.
Answers "a" or "b" will be accepted.
(8) Question 3.03 (6.04): Agree with facility comment. Wording of question should be " gain in" vice " output from" to elicit the desired response. "b and "c" will both be accepted.
(9) Question 3.07 (6.06): Agree with facility comment. Question deleted.
(10) Question 4.05 (7.05): Agree with facility comment. Most recent revision of this procedure results in question not having a correct response. Question deleted.
(11) Question 4.10 (7.09): Based on additional reference material provided, will accept "RCS barated to hot, xenon free conditions and being maintained at Hot Shutdown" as an additional correct answer, as long as Superintendent of Operations permission is also included.
(12) Question 4.11 (7.10): Question is not worded to expressly elicit the substeps in Step 9 of EP 1.00. The actions in Steps 10 and 12
. of EP 1.00 will be accepted as additional correct answers.
(13) Question 4.14(c) (7.13(c)): Based on the limits given in the referenced OP, answer key will be changed to reflect 25 cc/kg l vice 5. Contradiction in documents should be corrected by the facility.
(14) Question 4.15: Agree with facility comment. Vent-vent RM monitor will also be accepted.
(15) Question 4.17: The only place this action is referenced is in the facility lesson plan. There are no operating procedures or admin precautions that support the recommended additional answer. No change to answer key.
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(16) Questf on 4.18: There is a specific sequence required, to ensure the reactor is not tripped before the turbine, preventing excessive cooldown. Though the P-4 contacts will pick up if the RX trip breakers are opened tripping the turbine, AP-20 is very specific on tripping the turbine first. No change to the answer key. ,
(17) Question 4.22 (7.22): Agree with facility comment. Answer key will be modified to not require the part of the original answer after verifying all rods on the bottom.
- b. SRO Exam (1) Question 5.02: Based on recent change to TS, answer key changed to "b".
(2) Question 7.03: Step 26 of EP 1.00 (which is after checking for SI termination) reminds operators to notify STA and ensure CSF status trees are monitored. This is after SI termination criteria are checked, hence "b" is correct answer. No change to answer key.
(3) Question 7.07(b): Answer key based on earlier revision of EP 1.00. Will modify key to list "no" as the correct answer.
(4) Question 7.19: The HP-12 forms supplied by the facility list an extension level not included in the material provided the NRC (extension to 2.25 Rem /Qtr by Vice President Nuclear Operations).
The plant staff is still required to sign the approval sheet for the 2250 and 2750 R/Qtr. extensions. Answer key will be modified to include the 2250 R/Qtr limit as an acceptable answer.
(5) Question 7.24: Agree with comment that providing data in choice (4) could cause confusion regarding its applicability to the other choices provided. Will eliminate the last two required responses from the answer key.
(6) Question 8.08: Agree with facility comment that a surveillance on an operable RHR pump does not meet the exemption requirements of TS 3.10.6. Though core alterations are in progress, removal of
{ the RHR pump from service is not for that purpose. Will change j answer key to not allow maintenance.
, (7) Question 8.13: Agree with facility comment based on current shift staffing that has the third Reactor Operator filling the Radwaste
- Coordinator position. Will delete this part of the answer key.
, 4. Exit Meeting l At the conclusion of the site visit, the examiners met with representatives j of the plant staff to discuss the results of the examination.
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4 There were generic weaknesses noted during the oral and simulator examina-tions. The areas of below normal performance were in knowledge of breaker interlocks and faults causing breaker trips and a' tendency for senior operators to set aside emergency operating procedures when several malfunctions were in progress and try to deal with the individual malfunctions vice use the procedures as a framework to accomplish these actions.
The cooperation given to the examiners, particularly the assistance of Larry Gardner, was also noted and appreciated.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the examiners.
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- 5. THEORY OF NUCLEAR DOUER PLANT OPERATION, c'LUIDS. AND PACE 2 QUESTION 5.01 (1.001 Which state ent below . :orrect if the power range i n s t r u m e n t :, have been adjusted to 1 0 0 ". based o c eclculated c r l o r : 't, a t r i c ?
- a. If +'te feedwater terperature used in the c a l o r i m e t r :. c ifalculation uc- higher than actual feeducter tempereturer actual power will be loss than indicated power.
- b. r* the reactor coolant punp heat input used in the colorimetric calculation is omitted, +ctual r; o w e r will be less thar indicated power.
- c. If the stean flow used in the c a l o r i m e t r :. c calculation was lower than actual steem # low, cctual pouet iill be less than :ndicated Power.
- d. If the steam pressure used in the calartmetric calcul at ion is lower then ectual ntecn precsure. actual power will be loss than :.ndicated power.
nUESTILN 5.0: (i..ei The effect, of rod 'm ..
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canputing which of t r .- ouins core pe-fstm: nce neaturementc?
J. N u c l P ..v r i t tla ;,,y h a +. <: h a r . r i e l factor
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- y S. THEORY OF N U C'_ E A R POWER OLANT QPERATION, FLUIDS, AND PAGE 3 luftMODYNA"ICS QUESTION 'a . 0 5 (1.50)
An estinated critical boron concentration of 975 ppm was calculated using the inf or nation on the cttached data sheet cn the reactor reached c crttical condition at 153 steps on Bank 9 with Tave of 547 degrees. How would the Den? O rod position dfrer if the conditions used in this calcula*.un were d i f' f o r e n t as given be ow' Assume no '30 on changes and conside* each conditior, separately.
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- 3) ower level at shutdown was 7% equilibrium b) Time sir ce shutdown was 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> c) horuje RCS temperature was 5 3 :' degree: ;
GUESTION 5.06 (1.50)
- Indirite whether tho folloutng L .1 INCREASE, DECREASE or have 5n Ir;ECT
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i a) T h r o ' '. l e shut on " ie punp disch>rg" l
b) Increase the Wmpercture of the uction ide flii: d c) ' '
.,cre3se the pre,5 urn of th, HZ b l a n i.L e t on the suction sido :Upply tank
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GUESTION 5.07 (1 50)
For 9 , c: h of +$e followinq s' e t. i ,
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- reactivity chenge due to contt'cl rod i n ... e ':en.
Note' .h une 100'. moaer. Gank n 4+ 220 step 2 OCL.
- a. An erca of h: :h relative flu: vs, low relative flun.
- b. U ] ,' of the coro rs.
- t ri d l e c e the core.
- c. Rod il (ins "di vs. rod #2 in wttod bec,ide rod 11.
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- 5. THEORY OF NUCLEAR POWER oLANT OPERATION, FLUIDS, AND PAGE 4 DUESTION 5.00 (1.50)
Assuming a s y m re ntrical (ideal) axial flu, shape, match the CONDITION in Color,n A to the LOCATION that it would occur i n Column B, COLUMN A COLUMN E'
- c. MINIMUM Crltical Heat Flu 1. 00TTOM
- 2. 9etween BOTT"M 1 MIDDLE
- b. MAXIMUM Ac+vcl Heat Flu: 3, MIDDLE 4 Lotween MIDDLE ! TOP
Attachea 11. a curve showing the :. a d e r a t o r to fuel r ] t :. o >;. Meff with the o p
- 1 ri u m point identified. This it the point when the Moderator Temperature coeffici.ent would be just zero. if we were to add boron how vo:d the optinum point s'. l f t on th15 eve v e >
GUESTION S.10 ( 2.00)
'ist 6. h e four f a c t o r ,. ' h :: t cause the Doppler o ower D3 efficient to change over r. o r e li fe cnd indicated uScther each of tH se fcctors mmF. 'he 00ppler power n U F *' i C l e n t MUF CP L E S C, N [ C A T I '[ .
QUESTION S."' (1.00i lho roictor is ape r 4'- nj 3' ' 007. power ' ~tth 4 11 rods ut, near EOL w i t' e c,' ' i ! b r l u r, Xonon ec dit: tat wheri power it
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND oAGE 5 O '.l E S T IO N 5.13 (1.00)
Given that a battery capacity is 1650 ampere-hours, EXPLAIN the term
' ampere-hour'.
QUESTION 5.14 (2.00)
- a. During natural circulation, E:: Plain how it is possible to forn a bubble in the reactor vessel head when indications show that the RCS is subcooled?
- b. How will pressurizer level respond, (INCREASER 0ECREASEr or REMAIN THE SAME) if the backup heaters ere energized with a bubble in the reactor vessel head? Assume normal Pressuriner level and briefly EXPLAIN your enswer.
QUESTION 5.15 (3.001 List three parameters which the. operator can try and maintain which will hel t support thu naturel circulation process. Include the applicable setpoints and briefly state how maintaining these parameters helps ensure natural circu!rtion.
UUESTION 5.16 (1,00)
What characteristic share should a inverse n.u l t i p l i c a t io n plot (1/M plot) have during fuel loading when the fuel is loaded so that the distchee between the detector and the fuel steadily decreases? A sketch is sufficient te antwer thic question.
QUESTION 5.17 (2.50)
What are the purposes of each of the +' a l l o u i n g reactor thernal limits?
If a spec: #ic nccident or condition amplies, state this in your answer.
a) Reactor Safety L i vi i t s b) Enthalpy R: :e Hot Channel Factor /Fn(Delta H))
c) Nuclear F l v :- Hot Channel Factor (Fq(2))
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- 5. THEORY OF NUCLEAR FCWER PLANT OPERATION, FLUIDS, AND PAGE 6 QUESTION 5.18 (2.00)
Unit I has just restarted fellowing a refueling outage while Unit 2 is near EOL. Answer the following regarding the differences in plant response between the two units (explain your answers);
c) At a steady power level of 10EE(-8) amps during a startup, equal reactivity additions are made (approximately 100 pcm). Which Unit w:11 neve the LOWER tteady state startup rate?
b) At 50% power, a control rod (100 pcm) drops. Assuming NO PUNBACK or OPERATOR ACTION, which Unit will have the HIGHER steady state Tavs?
QUESTION 5.19 (1.50)
Sketch the K( ) height correction factor curve used in the heat flut hot channel factor calculation and explain the basis behind any changes in the curve's deviation from 1.0.
QUESTION 5.20 (2.00)
The Core Cooling Monitor has determined the following readings result in the most conservative margin to saturction:
N/R pressure PT-456 = 2235 psis Incore Thermocouple (T/C) = 630 deg.c
- 3. Calculate the margin to saturation.
- b. Assume the T/C refererice junction bon temperature indication has failed low (zero) and actual box temperature is 170 deg.F. Explain the effect of this failure on the resultant margin to saturation. Addrecs both subcooled and superheated conditions.
Note: Mointor assumes 160 des.F reference temperature upon failure, answer without regard to part 3. above.
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- 6. PLANT' SYSTEMS DES'IGN, CONTROL, AND INSTRUMENTATION PAGE 7 GUESTION 6.01 (1.00)
What set of signals below are sent to the Reactor Protection System to I r . indicate a Turbine Trip?
I' a. Stop valves closed & Auto Stop Dil pressure low
- b. Stop valves-closed & EHC pressure low
- c. . Governor valves closed & Auto Stop Oil-pressure-low F d .- Governor valves. closed & EHC pressure low 00ESTION 6'.02- (1.00)
Which valve listed below is used to throttle auxiliary spray flow?
a.- FCV-122 .(Charging FCV)
- b. . PCV-453A-(Spray valve from Loop A)
- c. PCV-455B (Spray. valve from Loop C)
- d. HCV-311.(Auxiliary Spray Valve)
- e. You cannot, throttle auxiliary spray 00ESTION 6 03 (1.00) t Which of the following describes the purpo'se of the J-tubes which have been r ecerit ly insts11ed on the'S/G feed rings?
- a. Provide even flow d'istribution.of feedwater around the downcomer.
- b. Prevent the introduction of debris in the feedring from classing i the path to the'S/G.
c .- Allow extra. pre-heating of feeduater by recirculation flow before the feed enters the downcomer region of the S/G.
- d. Prevent-water hammer due to steam condensation in the feed ring if a loss of feed were.to occurr then reinitiated..
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(***** CATEGORY 06 CONTINUED ON NEXT PAGE :xxx**)
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- 6. PLANT SYSTEMS DESIGN, C0t: TROL. AND INSTRUMENTATION PAGE 8 GUESTION 6.04 (1.00)
Which of the folicwing will result in a higher output fron the Variable Gain Unit of the Red Control Syster?
2 A 'DWER powe" level senser' by N1-44
- b. A LOWER pcwer level sensed by Turbine Impulse Pressure
- c. A HIGHER power mismatch error signal
- d. A LOWEP power nasrrtch error signa;
- e. A PIGHER (Tref-Tavg) error signal GUESTION 6.05 (1.00)
Which one of the following malfiinctions could cau2e one o t' the v e r' temperaturo 41 t e T trip bittcbles tc trip'
- 3. Controlling 'urbine inpulse pressure channel a i l i n g low.
- b. Power range N43 lower detector +c :ng ;ow.
- c. Reactor coolan+ flaw detector " ailing low,
- d. Controllir:3 pr as;ur : re- level channel #siling low.
QUE3T10N 6.06 ( 1 s Inp;ain why the 1r . aheddin a - _ure .ssociated with a degraded or undervol;cge co- .ition is de'eeted after an Energency 3160 UAC Bus is sclated frr- .he Reserve Stat:cn Transformer and the c esel output breater e acec.
QUESTION 6.07 (*.50)
Deseribe how the " i _: S Steam Lirn -low SI input var.es and the par neter on which thir program it b e s e <_ ,
(.***.** CATEGDRY 06 CONTINUES ON NEXT c' A G E s te ry )
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P 6'. PLANT SYSTEMS DESIGNr CONTROL, AND INSTRUMENTATION PAGE. 9 OUESTION 6.08 (1.50) j Indica.te what automatic actions, if any, occur when high l'evel alarms are ;
received on the followins process radiation monitors. ,
a) RM-GW-102(Plant Vent Gaseous Activity) ,
b) RM-RMS-162(Manipulator Crane Area Monitor) l QUESTION 6 09 (1.00)
What is the-Main design purpose of. the flow restricting nor:le in the !
Mein Steam Lines?
QUESTION 6.10 (2.50) '
Describe the sequence of events that occur once a valid RMT swapover signal. f is initiated. Inc.lude any applicable time delays or interlocks and the indications on the control board of swapover status, j QUESTION 6.11 (1.00)
List 2 reasons for providing a void volume in a new fuel rod. l OUESTION 6.12 (1.00) !
Aside Prom a loose printed circo.it board card, list 4' distinct causes of an 'URCENT FAILURE' in the Power Cabinets of the ~ Rod Control Systen. !
l I
00ESTION 6.-13 (2.00) :
List eight different.paraneters which are capable of being monitored j on the Remote Monitoring Panels (PNL-REM and ASC-RMP). j i
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With the pressurl:er -level control selector switch in position III/IIr an instrument failure causes toe following plant events in sequence (Assume no operator actions taken):
- 1. Charging # low reduces to minimum
- 2. Pressuriner level decreases i 3. Letdown secures and heaters deenergine
- 4. Level increases until high '.evel trip Which instrunent failed (Il or III) and in what direction did it fail?
QUESTION 6.15 (1.50) f a) What are the 4 sources of water available for the Spent Fuel oool?(1.0) l i b) What design feature of the spent fuel racks ensures criticality does
} not occur in the Spent Fuel Pool? (0,5) i 1
j QUESTION 6.16 (1.50)
Describe what causes a *Hard Subble' in the pressuriner during normal plant operations and how this affects the reactor on plant transients.
GUESTION 6 17 (2.00)
Consider the following situation: UNIT 1 is.at 5% and each of the loop i
temperatures are equivalent. (ie. each S/G is receiving the'came heat
- input) The level in 'A' S/G is several inches higher than 'S' and 'C' I
S/Gs. causing these two S/Gs to steam off more quickly resulting in their levels lowering. Discuss how the feedwater controls should be operated to restore all S/G 1evels (magnitude. direction. parameters observed, what feed flow is compared to) -to correct levels.
QUESTION 6.18 (3.00)
All reactor controls are.In automatic with Bank 0 rods at 210 steps and reactor power at 7 0 ?. . The output of the Auctioneered Tave circuit fails low. Describe the effect this would have on all the plant control systems supplied with this signal until a stable cendition is reached or a" reactor trip occurs. ( a s~s u m e no operator action) 2 (W**** CATEGORY 06 CCN'iINUED ON NEXT PAGE *****)
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i I -0UESTION 6.19 (1'.50) l l a)--While at power with no rod motion in progress, an IRPI deviates-15 steps from its bank average. What annunciator will actuate? ( 0.5).
l- b) .If rod motion were in progress in the above situation, would this
- annunciator _ alarm? E:: plain your answer. (1.0) t QUESTION- 6.20 '(3.00)
,a. After a valid SI. initiation signal has been generat'ed which HHSI pumps should be operatins? (assume all pumps' power supply from normal source) (l'.0)
! 'b. State at.least-two bases for " locking-out' HHSI pump (s) during'an SI l initiation. signal. (2.0) i i.
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(***r* END OF CATEGORY 06 *****)
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- 7. FROCEDURE3 -NORM AL, ABNORMAL, EMERGENCY AND PAGE 12
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GUESTION 7.01 (1.00)
On a' loss of condenser vacuum where vacuum is greater than 20' Hg and decreasins, which of the following is NOT an immediate action?
- a. Place an additional set of air ejectors in operation.
- b. Start a Hogger,
- c. Start an additional Circ Pump.
- d. Reduce turbine load.
- e. Start an additional condensate pump, if available.
l QUESTION 7.02 (1.00) which of the following reasons correctly describes the basis for allowing RCP restert in E0P-FR-C.1 ' Response to Inadequate Core Cooling'.
i 3 Helps tc min the SI' flow to protect reactor vessel from cold water..
I b. Once subcooling is established, restarting the RCPs helps to collapse voids that may have formed in the reactor vessel head.
- c. Allows restoration of ;ZR pressure control using normal sprays.
- d. Provides for cooling of the core when secondary depressurization does not alleviate inadequate core cooling.
QUESTION 7.03 (1.00)
Which of the follouing statementc describes the correct usage of the Critical Safety Function (CSC) Status Trees while performing E0P-E-0
' Reactor Trip or Safety Injection *?
- b. Awareness of Red Path Criteria is required at all times, but the CSF Status Trees are nonitored only cfter it is determined that SI can NOT be terminated,
- c. Monitoring of the CSF Status Trees connences as soon as the immediate action steps are completed.
- d. CSF Status Trees.are required to be monitored as soon es the procedure is entered and a valid SI is determined to have occurred.
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- CATEGORY 07 CONTINUED ON NEXT PAGE *****)
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QUESTIr4 7.04 (1.00)
Which statement below describes the AFW flow requirenentz following a reactor trip without an SI? (ie. your in EP 1.01, ' Reactor Trip Recovery')
- a. Throttle flow if it exceeds 536 spm.
- b. Throttle flow if a S/C level exceedt 91 level
- c. Throttle flow only if one or more Main Feed Pumps are running
- d. Throttle Flow only i# ell S/Gs 9% level
- e. Throttle flow only if all S/G 9% level and flow exceeds 536 3pm OUESTION 7.05 (* v0) p __ '
Which of the follo'.ng stat,ements w s_ uing cooldown durin3 a S/G Tube Rupture (EP-4.00' is correct?
- a. Coo'_own :. s commenced pr:or to isolating the ruptured S/C.
- b. Br ate the RCS to Cold Shutdown conditions prior to cocidown.
I c. .coldown rate is limited to 100 deg/hr.
I d. RCS depressurization i t, performed concurrent with the ecoldown.
QUESTION 7.06 (1.50)
Answer the #cllowing questions regardir3 E0P usage TRUE or FALSE:
a) If e Function Rettoration Procedure (FRP) is entered due to an ORANGE l Critical Safety Function (CEF) condition, and a HIGHER priority ORANGE l condition is encountered. the original FRP must be complated prior to proceeding to the newly identified CRP.
b) Unless specified. c task need not be fully completed before proceeding to a subsequent step as long as that task is progressir g s atisf actorily c) If a procedure transition occurs, any task s still in progrect from the procedure which was in effect need not be completed.
(***** CATEGOR 07 CONTINUED ON NEXT PAGE *****)
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- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 14
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I ' QUESTION 7.07 (1.50) i i
Indicate whether each of the following violates a Cri.tical Safety Function (CSF) Red Path or not (assume for the EP-1 series):
, a) Core Exit T/Cs 725 degrees F, no RCPs running and RVLIS full range 65%
! b) 'A S/G=40%. 9'S/G=35%, 7 S/G=25%, AFW Flow =300 spm c)
~
PZR level =10%, RCS subcooling=40 degrees F !
QUESTION 7.08 (1.50)
Complete the following statement by filling in tha blanks with the apptropriate numbers.
During a pressurized thermal shock condition, if PCS temperature decrease has exceeded _______ degrees in any _______ minute period, then a _______ hour temperature soak must be performed.
GUESTION 7.09 (1.00)
What are the_two' criteriar as stated in OP-1.1, " Unit Startup Operations",
that allow reactivity to be changed WITHOUT the shutdown banks fully
.withdraun?
QUESTION 7.10 (1.50)
On a reactor trip / safety injection, while performing the imnediate action steps of EP-1.00, you note that containment pressure has exceeded 23 psia.
What are your actions / verifications (there are three)?
GUESTION 7.11 (2.00) !
List the immediate action substeps that are required to complete the step to verify that the AC Buses are energi. zed in EP-1.00. !
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'7. PROCEDURES - NORMAL, ASNORMAL,' EMERGENCY AND PAGE 15'
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GUESTION 7.12 (2,00)-
Answer'the followina questions regarding a 'Non-Recoveable Loss of Air *r AP-40, on Unit 11 a) What are the three conditions that require the - RCPs- to be secured due to the loss of Component Cooling?
b) Aside from the RCPs, what 5 different pumps (there may be more than one of a particular pump, eg. 3 charging pumps) are secured as part of the immediate actions?
GU'ESTION 7.13 (1.50)
Fill in the blanks to correctly complete the statements regardin3 limits and precautions associrted_with the RCS and RHRS.
a)~ The maximum temperature differential allowed between the pressuriner and the spray flow is _____ degrees F.
b) The maximum - cooldown rate allowable while using the RHRS is _____deg/hr c) 'The reactor must not,begin producing' reactor power until the H2 concentration is at least _____ cc/kg.
GUESTION 7.14 (1.50)
AP-16, ' Excessive Primary Leakage', identifies numerous methods by which RCS leakage may be determined. List 5 radiation monitor alarms which
, could be symptoms of RCS leakage. (Monitors that check for the same problem like several effluent-line monitors count as one)
I OUESTION 7.15 ( .75)
Besides required notifications, what are the immediate operator actions if you are on shift in the control room and the refueling supervisor in the
~
containment reports they dropped a spent fuel element in containmentr and that they noted a cloud trail in the water?
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. QUESTION _ 7.16 (1.00) 1-l Suberiticality and Core Cooling are the two' highest priority CSF Status j Trees to monitor during accident conditions. List the remaining 4 CSF ,
i Status Trees in DECREASING order of priority.
I i
j . 0UESTION 7.17 (1.00)
List'two different ?onditions when an Inverse Count Rate Ratio Star. tup is i required.
, GUESTION 7.10 (1.00) . l
[ Ificontrol room evacuation was required due to a fire a.d you were unable i j to trip the reactor before you left (assume the plant is still operating at' j
- '50% power), _ what are the required inmediate actions before reporting to '
the Auxiliary Shutdown Panel?
f
, QUESTION 7 19 fl.00) 1 ,
l List the three levels of 3dministrative exposure limits that can be l 4
approved beyond the 750 mr/qtr and the level of the plant staff that ,
} provides the authorization. '
GUESTION 7.20 ( .75)
{ t What constitutes a Class II reactor trip?
t l
GUESTION 7.21' (1.50) <
{ Ouring a small break LOCA.(SSLOCA), it is required to trip the RCP.if the l trip criteria are met. If forced flow throvsh the core. promotes cooling, j why.are the RCPs tripped.
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i OUESTION 7.22 - b fC)
Describe the basic r.ethod by which the plant is shutdcun free 2% power to I hot shutdown. Include in your discussion the mode - of rod control utilized and any indications that you are required to observe to ensure that the shutdown is progressing correctly.
QUESTION 7.23 (1.00)
Euplain why EP-1.029, " Natural Circulation Cooldown with 'J o i d in t' Uessel' has you encure PZR l e< >e l is no 3reattr than 307. prior to initiating the cooldown and place the o ur level control in manual.
QUESTION 7.24 e [* h Place the following sources for reactor cavity makeup into the correct order of priority (from high to low) for a " Loss of Refueling Cavity Level' es stated in AP-22;
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- END Or CATEGORY 07 xxrer)
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j-i S. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 2 l
5 QUESTION 9 ~01 (1.00) l Accordins to Technical Specificationse which of the following is NOT Part
- of the Accident' Monitoring Instrumentation?
! c. Containment Hydrogen Monitor
- d. Auxiliary Feedwater Flow Rate GUESTION P.02 (1.00)
Which of the followins require activation of both the TSC and OSC?
J
- a. Either an unusual event, alert, site aree emergency or seneral emersency, d .
b._ Only an alert, site area emersency, or general e m e r s e n c y'.
. Only a site area emergency or general emersency.
j d. Only a seneral emergency.
OUESTION 8.03 (1.00) i Which of.the followins correctly' describes the con'bination of 1NOPERABLE j PZR PORVs and Block Valves that would require shutdown of the plant from j Mode 1 conditions. Assume that if a block valve or-PORV is inoperable, the appliccble block valve is closed and deenergiced.
- a. 2 PORVs
! b. 2 Slock Valves
! e. Mode i ops are allowed .io matter which valves are INOPERASLE t
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____________________________________________.______________ j QUESTION 8.04 (1.00)-
If durins a reactor plant cooldown using the~RHR system, the Safety l Injection-System is automatically actuated. Since the normal EP SI i
' termination criteria do not applyr which of the followins would be the l SI termination criterie in this~ condition?
a '. No - cr iteria e::is ts , terminate SI immediately,
greater than 10 degrees. t
than 50 destees with 11S/G WR level > 65%. !
'd. Initiatins condition cleared. l i
GUESTION 8.05 (1.00) -
Which of the following can be completed AFTER the Shift Supervisor has assumed the watch?-
-a. Review and initial the Shift Order Book
- b. Read and initial Required Reading
- c. Complete and sian Minimum-Equipment List l d.- Review the Balence of Plant Checklist I
OUESTION 8.06 (2.50)
' Define containment integrity per Surry Tech Specs by completing the seven l requirements In'the' format provided below. Be brief. Surveillance l requirements and numerical values are not_ required.
Containment integrity shall exist when;
- a. All non-automatic containment isolation valvent e::cep t those required !
for intermittent operation are! (1) '
They may be~ opened intermittently for operational activities provided that they are: (2) ,
- b. (3) [
c.. (4) !
- d. (5) ;
- e. All automatic containment isolation valves are: _ (6) l i
- f. (7) l l
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****) i
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E. PROCEDURE
S, CONDITIONS, AND LIMITATI0HS PAGE 4 GUESTION 8.07 (2.50).
Incicate whether the following reactor. trips are taken credit for in safety analysis or not. For any that are taken credit for, -indicate the type'of' accident it is designed to protect aSainst.
a) Power Range High Flux, Low Setpoint b) Over Power Delta T c) Lo-Lo S/G Water Level 00ESTION'. 8.08 (1.50)
Using~ the attached Technical-Specifications, answer the question stated in the situation presented below*
UNIT 2-is being refueled (> 23 f t above Rx Vessel Flange), loop C is isolated for maintenance and RCPs A and B are out of service for breaker repa' irs. -'A" -RHR pump and its Heat ~ Exchanger are being used to circulate t'eactor- coolant, with 1H-EDG INOPERABLE for routine maintenance. A request to take the "B' RHR Pump out of service for about 30 minutes to do an surveillance on the pump motor is sade by the electrical supervisor. Can this surveillance be performed? Suppport your answer by referring to the applicable Tech Spec (s).
QUESTION -8.09 (2.50)
Use the attached Technical-Specifications to determine the correct response to the questions below re3arding Nuclear Instrumentation.
a) What is the MAXIMUM % of each NI th'at can be out of service at any time without requiring action to reduce the plant operating mode?
Assume you are in Mode 1 at 75% power.
b) You are at the minimum t of operable Power Range NIs, when an IC tech requests permission to put an operable PR NI in test for a channel funetional test. Can this be done? Refer to applicable TS in answer.
.00ESTION 8.10 (- .50)
According to emergency plan implementing procedure, EPIP 5.03, ducir!g a site emergencyi personnel within the protected area and uneccounted for shall be determined within _____ minutes of the declaration of the emergency.
(***** CATECORY 08 CONTINUED ON NEXT PAGE *****)
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- 8. ADMINISTRATIVE PROCEDURESr CONDITIONS 7 AND LIMITATIONS ;' A G E 5 GUESTION 8.11 (1.50) a) During a non-emergency situaticn a temporary change to an operating procedure, which does not change the intent of 'he p .' o c e d u r e must ,
be authorized by when?
b) What forms are temporary changes and permanent changes to proceduree dccumented on?
GUESTION 3.12 (1.50)
- List three 2dmin
- .strative prm'm'+ ions that *ust be met to ente: : Locked Hign Radieticr Arec (; 1r/hr).
QUESTION S.13 _ [/*f0)
Aside +' r a c. the R eactar Operatora, list the normal .: h i # t manning for plant operators, ircluding number of operatorsr et ctsted in ADM-29.1.
Q U E S T lo t! 0.1G '1.00)
What is the required complement, by de? art ent and nud er , of the rire Brigade?
OUES' ION O 15 /1.50)
List the support e q u i p -- e n t in :s 3.16, 'Emer3ency o awer System'r required
'ar e Dier.el Gener ator tc be censidered operable (there are 6 different i cri+eria that must be net).
GUESTIDM 8.16 (1.50; Wh a t- three individuals, by title / qualification, ma, fill the pos: tion c#
Emergency Communicetor' l GUEST 10N 8.17 1.00)
List four hard copy cotrees of inft.r atlan tha' ar e eferred to when per f or mitia e o c c '. tr:p review, follou n; e untlenned reactor trip.
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- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND :_IMIT A TIC NS DAGE 6 DUESTION 8.18 (2.00) a) Why doesn't the Technical Specification for the Overpressure Miti 3ation Syste.,. iequire overpressure protection from the PORVs if the reactor vessel head is unbolted?
b) Explain why the TS for the OPMS requiae that.Pressuriner level be no higher than 33% narrev range-when Tevg 350 degreet and the reactor vessel head is bolted, QUESTION 8.19 (1.50)
- 2. While perforn:.ng a step in a Periodic Test the operator finds a step he can't perforr. due to the plant status. What actions should the operator tDe to d o c u r. e n t this inability to perform a step?
- b. Due to plant conditions (e.g. mode in which system not required) the perfarnance of a Periodic lest can not be completed. How does the operstor docunent non performance of.the procedures GUESTION S.20 (1.25)
Describe the technical specification lim i t a tipru on critfical operations with a positive moderator coefficient. (do no t, addres s e/c e p t i o n s for '
low power physics testing)
QUESTION 0.21 (i.00)
What actions should a n e r.t e r of the general population inside the EPZ ta9e if the Eerly Warning Syster siren were to eetuete?
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k3 88004 UNITED STATES 4f, Io,, NUCLEAR REGULATORY COMMISSION f, o ,_
REGION il 0 .g 101 MARIETTA STREET, N.W., SUITE 2900 4 ATLANTA, GEORGIA 30323 o,
s,
...../
, . . . , v o s/t L/C le ef t 1Litsmy ( 4e t nor t.
out)/(Ener;y in)
- 2 o 6 cg s o V,t
- 1/2 at
[ = mc KE = 1/2 mv a=(Vf - t,)/t A = AN A=Ae' 3
PE = m9n Vf = V, + at w = e/t a = an2/t1/2 = 0.693/t1/2 y , , .p A= nD 2 1/2'N
- M / M N 4 [(t1/2)
- IID I) aE = 931 am *
= m = V,yAo -I.x Q.= mah I*Iec Q = mCpat 6 = UAa T I
- I,e~"*
Pwr = Wfah I = I, 10'*/D L TVL = 1.3/u P = P 10 sur(t) HVL = -0.693/u P = Po e*/
SUR = 26.06/T SCR = 5/(1 - K,ff)
CR, = 5/(1 - K,ff,)
SUR = 26a/t* + (s - o)T CRj (1 - K,ff j) = CR2 II ~ "eff 2)
T = (t*/o) + [(s - oY Io] M = 1/(I - Keff) = CR j/CR, T = s/(o - 8) M = (1 - K,ffo)/(I - Keffj)
T = (s - o)/(Io) SDM = ( - K,ff)/K,ff a = (K ,ff-1)/K ,ff = AK,ff/K,ff t= = 10 seconds I = 0.1 seconds-o = [(1*/(T K,ff)] + [s,ff /(1 + IT)]
Idjj=1d P = (zov)/(3 x 1010) I jd; 2 ,2 gd 222 2
z = oN R/hr = (0.5 CE)/d (meters)
R/hr = 6 CE/d2 (f,,g) ,
Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lem. I curie = 3.7 x 1010 dps I gal . = 3.78 liters I kg = 2.21 lbm 1 ft* = 7.48 gal I hp = 2.54 x 103 Btu /hr .
Density = 62.4 1 /ft3 1 av = 3.41 x 105 Stu/hr Density = 1 gm/c lin = 2.54 cm Heat of vaporization = 970 Btu /lem 'F = 9/5'C + 32 Heat of fusion = 144 Btu /lbm . 'C = 5/9 (*F-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 77B ft-lbf I ft. H O2
= 0.4335 lbf/in.
e = 2.71g g _- ,
- Volume, ft'/lb D.thelpy. Siv/lb Enteopy. Sty /lb a F Water tysp Ste.m Water (vop Steam
","* Water Evap Steam a, 6 4, 4
, . . a. 8 ,
-0.02 1075.5 3075.5 0.0000 2.1873 2.1873 at f at 0.08859 0.01602 3305 3305 3.00 1073.8 1076.8 0.006) 2.1706 2.1767 35 l 35 0.09991 0.01602 2948 2948 40 2446 8.03 1071.0 1079.0 0.0162 2.1432 2.1594 .
40 0.12163 0 01602 2446 45 2037.8 13.04 1068.1 1081.7 0 0262 2.1164 2.1426 45 0.14744 0.01602 2037.7 18.05 1065.3 1083.4 0.0361 2.0901 2.1262 to 90 0.17795 0.01602 1704.8 1704.8 28.06 1059.7 1087.7 0.0M5 2.0391 2.0946 60 ,
40 0.2561 0.01603 1207.6 1207.6 38.05 1054.0 1092.1 0.0745 1.9900 2.0645 70 70 0.3629 0.01605 868.3 868.4 i
48.04 1048.4 1096 4 0.0932 1.9426 2.0359 80 80 0.5068 0.01607 633.3 633.3 i
468.1 58.02 1042.7 1100A 0.1115 1A970 2.0086 to 90 0 6981 0 41610 468.1 68.00 1037.1 1105.1 0.1295 1A530 1.9825 300 100 0.9492 0.01613 350.4 350.4 77.98 1031.4 1109.3 0.1472 1A105 1.9577 110 110 1.2750 0.01617 265.4 265.4 87.97 1025.6 1113.6 0.1646 1.7693 1.9339 130 120 1A927 0A1620 203.25 203.26 97.96 1019.8 1117A 0.1817 1.7295 1.9112 130 130 2.2230 041625 157.32 157.33 123.00 107.95 1014.0 1122.0 0.1985 1A910 1A895 140 140 2A892 0.01629 122.98 150 97.07 117.95 2006.2 1126.1 0.2150 1.6536 1A686 150 3.718 0.01634 97.05 77.29 127.96 1002.2 1130.2 0.2313 1.6174 1A487 150 140 4.741 0.01640 77.27 137.97 996.2 1134.2 0.2473 1.5822 1A295 170 170 5.993 0.01645 62.04 62.06 148.00 990.2 1138.2 0.2631 1.5480 1A111 130 180 7.511 0.01651 50.21 50.22 158.04 984.1 1142.1 0.2787 1.514S 1.7934 130 890 9.340 OA1657 40.94 40.96 i
33.64 168.09 977.9 1146.0 0.2940 1.4824 1.7764 30 300 11.526 0.01664 33.62 210 27.82 178.15 971.6 1149.7 0.3091 1.4509 1.7600 210 14.123 0.01671 27A0 180.17 970.3 1150.5 0.3121 1.4447 1.7568 212 212 14.696 OE1672 26.78 26.80 188.23 965.2 1153.4 0.3241 1.4201 1.7442 230 220 17.186 0.01678 23.13 23.15 198.33 958.7 1157.1 0.3388 1.3902 1.7290 230 230 20.779 0.01685 19.364 19.381 '
208.45 952.1 1160.6 0.3533 1.3609 1.7142 240 240 24.968 0.01693 16.304 16.321 218.59 945.4 1164.0 0.3677 1.3323 1.7000 250 250 29A25 0.01701 13.802 13.819 228.76 938.6 1167.4 0.3819 1.3043 1.6862 350 260 35.427 0.01709 11.745 11.762 238.95 931.7 1170.6 0.3960 1.2769 1.6729 270 270 41.856 0.01718 10.042 10.060 f
249.17 924.6 1173A 0.4098 1.2501 1.6599 330 300 49.200 0.01726 8.627 8.644 259.4 917.4 1176.8 0.4236 1.2238 1.6473 250 390 57.550 0.01736 7.443 7.460 269.7 910.0 1179.7 0.4372 1.1979 1.6351 300 300 57.005 0.01745 6.448 6.466 280.0 902.5 1182.5 0.4506 1.1726 1.6232 310 f 310 77.67 0.01755 5.609 5.626 290.4 894A 1185.2 0.4640 1.1477 1.6116 320 320 89.64 0.01766 4A96 4.914 311.3 878.8 1190.1 0.4902 1.0990 1.5892 340 840 117.99 0.01787 3.770 3.738 332.3 862.1 1194.4 0.5161 1.0517 1.5678 360 360 153.01 0.01811 2.939 2.957 353.6 844.5 1198.0 0.5416 1A057 1.5473 330 3a0 195.73 0.01836 2.317 2.335 l
375.1 825.9 1201.0 0.5667 0.9607 1.5274 400 400 247.26 0.01864 1.8444 1A630 420 1.4997 396.9 806.2 1203.1 0.5915 0.9165 1.5080 420 30S.78 0.01894 1.4808 440 1.2169 419.0 785.4 1204.4 0.6161 0.8729 1.4890 440 381.54 0.01926 1.1976 460 l
0.9942 441.5 763.2 1204.8 0.6405 0.8299 1.4704 460 466.9 0.0196 0.9746 480 0.8172 464.5 739.6 1204.1 0.6648 0.7871 1.4516 j 480 566.2 0.0200 0.7972 487.9 714.3 1202.2 0.6890 0.7443 1.4333 500 500 680.9 0.0204 0.6545 0.6749 l
0.5386 0.55 % 512.0 687.0 1199.0 0.7133 0.7013 1.4146 520 520 812.5 0.0209 0.6577 1.3954 540 0.4437 0.4651 536.8 657.5 1194.3 0.7378 j $40 962.8 0.0215 0.6132 1.3757 560 0.0221 0.3651 0.3871 562.4 625.3 1187.7 0.7625 SCO 1133,4 1.3550 580 i
0.2994 0.3222 589.1 589.9 1179.0 0.7876 0.5673 580 1326.2 0.0228 0.2438 0.2675 617.1 550.6 1167.7 0.8134 0.5195 1.3333 8J00 400 1543.2 0.0236 0.46S9 1.3092 Sao 0.1962 0.2208 646.9 506.3 1153.2 0.8403 820 1786.9 0.0247 0.4134 1.2821 640 0.1543 0.1802 679.1 4 54.6 1133.7 0.8666 640 2059 9 0.0260 0.3502 1.2458 660 i
0 0277 0.1166 0.1443 714.9 392.1 1107.0 02995 660 2365.7 0.9365 0.2720 1.2086 680 0.0304 0.0808 0.1112 758 5 310.1 1068.5 640 2708 6 0.0386 0.0752 822.4 172.7 9952 0.9901 0.1490 1.1390 700 700 3094.3 0 0366 0 1.0612 705.5 0 0.0508 906.0 0 906.0 1.0612 705.5 3203 2 0.0508 TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (TEMPERATURE)
A.3
W8ome. fi'ht, intWy I'iv/tt intro;p Stubb o F Eg. P tw/te Evep Storm W:te' 6 teem P '
Pro s 1s rap Evap Steam E ster Lver 6 teem m eter Water O he ** *e *e c *'s
- r *6 *s
- h 33024 0.00 1076.5 1075.5 0 2 1872 2.1872 8 1021.3 SAme6 0.0886 32.018 0.01602 3302A 0.01602 2945.5 2945 5 3 03 10738 1076 8 0 0061 2.1705 2.1766 3A3 1022.3 8.10 0.10 35.023 13.50 1025.7 4!.453 0 0160? 2004.7 20047 13 50 1067.9 1081 4 0 0271 2.1140 2.1411 0.15 c.15 0 0422 2.07?8 2.1160 2122 1028.3 920 0.20 53.160 0 01603 1526 3 1526 3 21 22 1063 5 1084 7 M 484 001604 1039 7 10393 32.54 1057.1 1089 7 0 0641 2.016S 2.0809 32.54 10320 e.30 0.40 0.0799 1.9762 2.0562 40.9/ 1034.7 c.40 c.40 72.869 0.01606 792.0 792.1 40 92 1052.4 1093.3 79.586 0 01607 641.5 641.5 47.62 1048 6 10963 0 0925 1.9446 2.0370 4742 1036.9 c.5 I 9.5 5124 1038.7 0.6 85718 0 01609 540 0 640.1 53 25 1045 5 1093 7 0.1028 1.9186 2.0215 9.6 04 *... .ar8966 2.00B3 -58.66. 1049 3 4
' O.7 .* 19009' ' D OIY>10 ' 465.93' .
- 466 94 - 56 40 104L7 el1008- . 03 .
94.38 0.01611 411.67 411.69 62.39 1040.3 1102.6 0 1117 1.8775 1.9970 62.39 1041.7 OA et 0 1264 14606 1.9870 66.24 1042.9 0.9 0.9 98.24 0.01612 368 41 36843 66.24 1038.1 1104.3 1A 10134 0.01614 333.59 333.60 69.73 1036.1 1105.8 0.1326 1A455 1.9781 -$933 1044.1 1A 2.0 126.07 0.01623 173.74 173.76 94.03 1022.1 1116.2 0.1750 1.7450 1.9200 94&3 10512 2A 109.42 1013.2 1122.6 0.2039 11854 12864 10941 1056.7 3A 3.0 14147 0.01630 118.71 118 73 4.0 4.0 152.96 0.01636 90 63 90 64 120.92 1006 4 1127.3 0.2199 1.6428 13626 120.93 1060.2 73.53 130 20 1000.9 1131.1 0.2349 1.6094 13443 130.18 1063.1 EA 8.0 162 24 0.01641 73.515 61.98 138 03 996.2 1134.2 0 2474 1.5820 12294 138Al 1065.4' 6A 6.0 170 05 001645 61.967 7A 0.01649 53 634 53.65 144.83 992.1 1136 9 0.2581 1.5587 12168 144.81 1067.4 i FA 176 84 0 2676 1.5384 1A060 15334 1069.2 E.0 S.0 182.86 0.01653 47.328 47J5 150.87 988.5 1139.3 91.,
18P.27 0 01656 42.385 42.40 156.30 985.1 1141.4 0.2760 1.5234 1.7964 15628 1070.8 9.0 161.23 10723 30 10 193.21 0.01659 38.404 38 42 161.26 982.1 1143.3 0 2836 1.5043 1.7879 26.83 183.17 970.3 1150.5 0.3121 1.4447 1.7568 180.12 1077.6 14.696 14.696 212.00 0.01672 26.782 0.01673 26.274 26.29 181.21 969.7 1150.9 0.3137 1.4415 1.7552 181.16 1077.9 15 15 213.03 l
i 20 227.96 0.01683 20.070 20 087 196 27 9631 1156.3 0.3358 1.3962 1.7320 19621 1082.0 to 30 250.34 0 01701 13.7266 13 744 218.9 945.2 1164.1 0.36S2 1.3313 1.6995 218 3 1087.9 30 236.1 933.6 1169.8 0.3921 1.2844 1.6765 236 0 1092.1 40 40 267.25 0 01715 10 4794 10 497 8 514 250.2 923 9 1174.1 0 4112 1.2474 J.6585 250.1 1095.3 50 50 261.02 0.01727 8 4967 60 292.71 0.01738 7.1562 7.174 262.2 915 4 1177.6 0.4273 1.2167 1.6440 262.0 1098.0 60 70 302.93 0.01748 6.1875 6205 272.7 907A 1180.6 04411 1.1905 1.6316 272.5 1103.2 70 to 312.04 0.01757 5 4536 5 471 232.1 900.9 1183.1 0.4534 1.1675 1.6208 281.9 1102.1 80 90 320.28 0 01766 4.8777 4.895 293.7 894.6 1185.3 0 4643 1.1470 1.6113 293.4 1103.7 90 100 327A2 0 01774 4.4133 4.431 258.5 888.6 1187.2 0.4743 1.1284 1.6027 298.2 1105.2 100 341.27 0.01789 3 7097 3 728 312.6 877A 1193 4 0 4919 1.0960 1.5879 312.2 1107.6 120 120 324 5 1109.6 140 240 353 04 0 01803 3.2010 3 219 325.0 868.0 1193 0 0.5071 1.0681 1.5752 363 55 0 01815 21155 2A34 336.1 859.0 1195.1 0.5205 1.0435 1.5641 335.5 1111.2 160 160 345.6 1112.5 180 180 373 08 0 01827 2.5129 2.531 346.2 850 7 1196 9 05328 1.0215 1.5543 200 35180 0 01839 2.26S9 2.287 355.5 842.8 11983 0.5438 1.0016 1.5454 3542 1113.7 300 250 40097 0 01865 1.8245 1.8432 3761 825 0 1201.1 0.5679 0 9585 1.5264 3753 1115.8 250 300 417 35 0 01859 1.5233 1.5427 394 0 8089 12029 0.5682 09223 1.5105 392.9 1117.2 300 7942 1234 0 0 6055 0 8929 1.4968 408 6 11IB !
l 1.3255 409.B 350 350 41173 0 01913 1.3064 424.2 7634 1204 6 0 6217 0 8630 1.4647 422.7 111E 7 400 400 444 60 0 0193 1.14162 1.1610 450 4t6 28 00195 1.01224 1.0318 437.3 767.5 1204.8 06360 0.8378 1.4738 4351 1118.9 450 t
449 5 755.1 1204 7 06493 0 814S 1.4639 447.7 11188 500 500 Af 7 01 00193 093787 0 9276 0 8412 460.9 743.3 1204 3 0 6611 0.7936 1.4547 45E.9 1118 6 550 S53 47694 00199 0 82183 469.5 1116.2 600 400 485 to 00201 074962 07693 4713 732.0 12037 0.6723 07738 1.4461 06556 491.6 710 2 1201 8 0692R 07377 1.4304 468.9 1116 9 700 703 .503 08 00205 063505 833 51a 21 0 0209 054809 05690 509.8 6896 1199 4 07II1 0 7051 1.4163 506 7 1115.2 000
[
900 13295 0 0212 0 4796S 05009 526 7 669 7 1196 4 0 7279 0 6753 1.4032 523 2 1113.0 900 542.6 (50 4 1192.9 07434 06476 13910 53';6 1110 4 1003 1000 544.5 B 00216 042435 0 4460 1100 1100 $1E 2c' ~ 0 0220 0.376f.3 0 4005 557.5 631.5 11891 0 757S 0.6216 1.3794 553 1 1107.5 0 0223 034013 0.3625 571.9 613 0 1184 8 0 7714 0.5969 1.36S3 556 9 1104.3 1200 3200 1903 l s67.19 E77 42 0 0227 030722 0.3299 585 6 544.6 1180 2 01843 05733 1.3577 580.1 1100 9 1300
$76 5 1175 3 07966 0 5507 1.3474 592.9 1097.1 1400 14C0 557 07 0 0231 0 27871 03018 598 B 0.8335 05253 1.3373 6052 1093.1 1500 1500 596 20 0 0235 025372 027/2 611 3 550 4 11701 l
672 1 466 2 1133 3 0 BCM 04256 1.2881 662 6 IO*S 6 2000 2000 635 BS 0 02"1 0 16766 01853 l
3f10 1093 3 C 9139 03206 12345 716 5 1032.9 2500 2503 EEd 1I O 02c.( 010209 01307 731 7 216 4 1070 3 09723 01691 1.1619 7622 973.1 3003 3003 69533 0 0343 0 050/3 00850 831 E O050t 936 0 0 9360 10512 0 10612 8759 875 9 37081 32962 70147 00%B O TABLE A.3 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (PRESSURE)
A.4
9mpettis's. F Abs'pesst 300 400 900 000 700 000 900 1000 1100 1200 1300 1400 1500 p) 100 2 0')
e 0 0161' 392 5 452.3 511.9 571.5 631.1 6907 3 6 68 00 1150 2 11957 1241.8 1288 6 3336 1 1984 5 (101.74) s 01295 2 0509 2.llL2 21722 2.2237 8.2708 2.3144
, 00161 76 14 90 24 102 24 114.?! 126 15 138 08 150 01 361 94 173 86 185 78 197.70 20D 62 221.53 231 45 6 6 68 01 11&& 6 1144 8 1241.3 1788 2 1335 9 1384 3 1433 6 1863 7 1534 7 1586 7 1639 6 1693 3 17480 18015 (162.24)s 01795 1.8716 1.9369 1.9943 2.0460 2.0932 2.3369 21776 2 2159 22521 2.28 % 2.3194 2.350) 2.3813 2Alc1 e 00161 3884 44 93 53 03 57.04 6303 69 00 74 98 80 94 86 91 92 87 98 84 104 80 110 76 116 72 30 6 68 02 1146 6 11937 1240 6 1787.8 1335 5 1384 0 14334 1483 5 1534 6 1586 6 1639 5 1693.3 1747.9 1034 (19. 21) s 01295 1.7926 1.8593 1.9173 1.9692 2 0166 2.0603 2.1011 2 1334 2 1757 2.2101 2 2430 22744 2.3D46 2.3337 e 0 0161 0 0166 29 89) 33 963 37.985 41.9 % 45.978 49 % 4 53 946 57.926 61 905 65882 6985B 73 833 77.8')7 36 6 68 04 168 09 !!92 5 1239 9 1287.3 1335 2 13838 1433 2 1483 4 1534 5 15805 16394 16932 1747A 1833 4 (213 03) s 0 1295 0.2940 1.8134 1.8720 1.9242 1.9717 2.0155 2.0 % 3 22946 2.1309 2.1653 2.1982 22297 2.2599 2.2890 o 0 0161. 0 0166 22.356 25 428 28 457 31.466 34 465 37.458 40 447 43 435 46 420. 49 405 52388 55.370 98.352 90 6 68 05 16811 1191.4 1239.2 1286 9 1334.9 1383 5 1432 9 1483 2 1534.3 1586.3 1639.3 1693.1 1787A 18033 (227.96) s 01295 0.2940 1.7405 1A397 13921 13397 1.9836 2.0244 20628 2A991 2.1336 2.1665 2.1973 22282 22572 e 0.0161 0 0166 11 036 12 624 14.165 15 685 17.195 18 699 20 199 21 697 23 194 24 689 26 183 27.676 29.168 40 6 68 10 168 15 1186 6 1236.4 1285 0 1333 6 1982.5 1432.1 1482.5 1533.7 1585 8 16368 1992 7 1747.5 1803 0 (267.25) e 0.1295 0 2940 1.6992 1.7608 1A143 1A624 1.9065 1.9476 13860 2.0224 2.0569 2.0899 2.1224 2.1516 2.1837 e 0.0161 0 0156 7.257 8354 9.400 10 425 11.43S 12.446 13.450 14 452 15.452 16.450 17A48 18 445 19441 60 6 68 15 16520 1181 6 1233 5 1283 2 1332.3 1381.5 1431.3 1481.8 1533 2 1555.3 1638 4 1692.4 1547.1 1802 S
.i (292.71) s 0.1295 0.2939 1.6492 1.7134 1.7681 IA168 1A612 13024 13410 1.9774 2.0120 2.0450 2.0765 2.1068 1.1359 e 0.0161 0 0166 0 0175 6 218 7.018 7.794 8.560 9.319 10 075 10.829 11 581 12.331 13.081 31.829 14.577 30 6 68 21 168 24 269 74 1230 5 1281 3 1330.9 13805 1430.5 1481.1 1532 6 1584.9 1638 0 1692.0 1746.8 1802.5 (312.04) s 0.1295 0.2939 0.4371 1.6790 1.7349 1.7842 1A289 18702 1.9089 1.9454 1.9800 2.0131 2.0646 2.0750 2.1041 o 0 0161 0.0166 0 0!?5 4 935 5 588 6 216 6.833 7.443 8 050 8655 9258 9360 10 460 11.060 llA59 100 m 68 2E 168 29 269 77 1227.4 1279.3 1329.6 1379 5 1429 7 14604 1532.0 1564 4 1637.6 1691.6 1746.5 1802.2 (327.82) s 0.1295 0 2939 04371 11516 1.706S 1.7586 1.8036 13451 12839 1.9205 1.9552 1.9883 2A199 2.0502 2.0794
, 0 0161 0 0166 0 0175 4 0786 4.6341 5.1637 5 6831 6 1929 6 7006 7.2060 7.7096 5 2119 8.7130 9.2134 9.7130 120 h 68 31 168 33 269 81 1224.1 1277.4 1328.1 1378 4 1428.8 1479 8 1531.4 1583 9 1637.1 1691J 17462 1802.0 (341.27) s 0.1295 0 2939 0 4371 1.6286 1A872 1.7376 1.7829 3 2246 13635 13001 13349 13680 19996 2.0300 2&592 e 00161 0 0166 0 0175 3 4651 3 9526 4 4119 4 2585 5.2995 5.7364 61709 6.6036 7A349 7A652 7A946 83233 340 6 68 37 168 38 26S85 1220 8 1775 3 1326 8 1377.4 1428 0 1479.1 1530 8 1583 4 1636 7 1990.9 1745.9 1801.7
, (353 04) s 0 1295 0 2939 04370 1.6035 1.6686 1.7196 1.7652 13071 1A461 1.8828 1.9176 1.950S 13825 2.0129 2.0421 e 0 0161 0 0166 0 0175 3 0060 3 4413 3 8480 4.2420 4 6295 5.0132 5.3945 5.7741 6 1522 6.5293 '4 9055 7.2811 160 6 68 42 16342 269 89 1217.4 1273 3 1325 4 1376 4 1427.2 1478 4 1530.3 1582.9 1636.3 1990.5 1745.6 1801.4
('63 55) s 0.1274 0 2938 0 4370 1.5906 1.6522 1.7039 1.7499 1.7919 1A310 1A678 13027 13359 13676 - 1.9980 2A273 e 0 0161 0 0166 0 0174 26474 3 0433 3 4093 3.7621 4.1064 4.4505 4.7907 5.1289 5 4657 5 2014 6.1363 6 4704 ISO > 68 47 16647 2649/ 1213 8 1271 2 1324 0 1375 3 1426 3 1477.7 1529 7 1582.4 1635 9 1640 2 17453 1801.2 (373 081 C 1294 0.2638 04370 15743 1.6376 1.6900 17362 1.7784 1Al?6 1.8345 1.8894 1.9227 1 9545 1.9649 2.0142 l
! e 0 01(1 0 0166 0 0174 2 3598 2.7247 3.0583 3 3783 3 6915 4 0008 4 3077 4.6128 4.9165 521@ 5.5209 5A219 l 200 e 68 52 168 51 269 96 12101 12690 13221 1374.3 14255 1477.0 15291 1581.9 1635 4 1689 8 1745 0 1800 9
! (35L60) s 01294 02935 0 4359 1.5593 1.6242 1.677G 1.7239 1.7663 1.8057 1 6426 1.8776 1.9109 1.9427 1.9732 2D025 o OC161 0 0166 0 0174 0 0!$6 2.1504 24662 2 6872 2 9410 3 1909 3 4382 3 6837 3 9278 4 1709 4 4131 4 6546 250 e 66 66 166 63 270 05 3/5 10 1263 5 1319 0 1371.6 1423 4 1475 3 1527.6 1580 6 1634 4 1683 9 1744 2 1800.2 (400 97) s C 1294 02937 0 4355 0.5 % 7 1.5951 1.6502 1.6976 1.7405 1.7601 1.8173 1.8524 1Ad58 1.9177 13482 1.9776 e 00161 0 01(5 0 3174 00186 1.7666 2.0044 2.2263 2.4407 2 6509 2 6585 3 0643 3.2688 3 4721 3 6746 3 8764 300 A 66 79 1 % 74 270 14 375.15 1237 7 1315 2 1368 9 1421.3 1473 6 1526.2 1579 4 1633 3 1688 0 1743 4 1799.6 (417.35) s 01294 02937 0 4317 C5%5 1.5703 1.6274 1.6758 1.7192 1.7591 3.7964 12317 13652 18972 1.9278 1.9572 e 0 0161 0 0165 0 0174 0 0186 1.4913 1.7028 IS970 2 0332 2.2652 2 4445 2.6219 2.7980 2.9730 3.1471 332C5 350 m 68 92 16$85 270 74 3?5 21 1251 5 13114 13662 1419 2 1871 6 1524 7 1578 2 1632.3 1667.1 17426 1798 9 (43173; e 0 1293 0 29)$ 0 43G7 0 56',4 1.5483 1.6077 1.6571 1.7009 1.7411 1.7787 1.8141 1.8477 12793 1.9s05 1.9400 e
e 0 0161 0 0166 0 0174 0 0162 12841 14763 16493 1 8151 1 9759 21334 2 2901 2 4450 2.5957 2.7515 2 9037 400 e (9 05 166 47 210 33 375?? 1245 1 1307.4 13t3 4 1417 0 14701 1523 3 1576 9 1631.2 16362 17419 1793 2 (444 to) s 5 1293 0293h 043t5 0 %G3 1.5782 1 5901 I6400 16850 17255 1.7632 1.7958 1.832b 18647 16955 19250 e 0 0161 0 0160 0 0174 0 0186 0 9919 1.1584 13037 1.4397 1.570E 1 6992 1 8756 1 9507 2 0746 2 1977 2.3200 500 > (9 32 1 % 14 270 51 375 38 1231 2 17991 1357 7 le12 7 145! 6 1520 3 1574 4 16291 1634 4 1740 3 1796.9 14L7 01) s 6 179.' L Wst OAM4 0ttEO 149?! 15595 1 P23 165/8 1 M90 17371 17730 1 80f9 14393 16702 119)3 TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE)
A.5
At s perst 1e m pe rstee, t sb/se la (ut. temp) 100 200 800 4D3 600 6w 7Da em 300 loco llto 12x lyio 3439 g$on e 00161 0 0168 00174 0 018t, C7b44 0 94 N6 10726 11992 1.3000 14093 15160 I6711 17252 18784 3.93%
600 6 69 58 169 42 270 70 37549 1215 9 1290 3 1351 8 1406 3 1463 0 1517 4 1571 9 1677 0 1682 6 1738 8 1795 6 (48620) s 0.1292 0.2933 0 4362 0 % 57 14590 1.5379 15844 163b1 16769 1 71 % 17517 3.7859 33184 1A494 137s2 e 00161 0 0166 0 0174 0 0186 0 0704 0 7928 0 9072 1.0102 1.1078 1 2023 12948 l.3858 1.4757 1 % 47 16530 700 6 6904 169 65 270 89 375 61 487 93 1281 0 1345 6 1403 7 1459 4 1514 4 1%94 1624 8 1660 7 17372 1794 3 (503Ce)s 01291 02932 0 4300 0 5655 0 6f6 1 5090 3.%t3 16154 1.6560 16970 17335 1767b 1 8009 18318 18617 e 0 0161 0 0166 0 0174 0 0186 0 0704 0 6774 0 7879 0 8759 0 9631 1 0470 1 1289 12093 1.28?5 13669 1.4446 300 6 70 11 169 BB 271 07 375 73 ADAP 1271 1 1339 2 13991 1455 8 1511 4 1%69 16?? 7 16769 17b 0 1792 9 (5182.) n 0.1290 02930 0 4358 0 5652 0682t 14E69 35484 1.% 50 16413 16507 1.7175 17522 1.7651 3 8164 1 8464 e 0 0161 001% 0 0174 0 01E6 0C?a4 0 % 69 0 0E 56 0 7713 0 8504 0 9262 0 99M 1 0720 1 1430 12131 1.2625 900 6 70 37 17010 273.26 37524 487.83 1260 6 13327 1394 4 1452 2 1506 5 15644 1620 6 16771 17343 1791 6 (531.95) s 01290 0 2929 04357 05649 06681 1.4659 1.5311 1.5822 16263 1.6%2 1.7033 I.7382 1.7713 3 6028 13329 e 0.0161 0 0166 0.0174 0 0186 0 0204 0 5137 06080 0 6875 0.7603 0 8295 0 8966 0 9672 1.0266 1.0901 1.1529 3000 6 70 63 170 33 271.44 375 96 487.79 1249.3 3325 9 1389.6 1448 5 15044 1561.9 1618 4 1675 3 1732 5 1790.3 (544.58) s 0.1269 0.2928 0 43 % 05647 04876 1.4457 1.5149 1.5677 3.6126 16530 1.6905 1.7256 3.7549 1.7905 1A207 e 00161 0 01 % 0 0174 0 0385 0 0203 04531 05440 0 6188 06865 07505 08121 0 8723 0 9313 0 9894 1.0468 1100 & 70 90 170.56 271A3 376 08 467.75 12373 1318 8 1384 7 1844 7 15024 1559 4 1616 3 1673.5 1731 0 !?t9 0 (5%28)s 0 1269 0.2927 0.4353 0 5644 0 6872 1.4259 1.4996 1. % 42 1 6000 1.6410 1.6787 1.7143 1.7475 1.7793 12097 e 0 0161 0 0166 0.0174 0 0185 0 0203 0 4016 0 4905 0 5615 0 6250 0 6845 07418 C 7974 0 8519 0.9055 0 95S4
, 3200 4 71.16 170.78 271.52 37620 487.72 1224 2 1311.5 1379 7 1440 9 1449 4 1%69 1614 2 1671.6 1729 4 1787.6
( (567.19) s 0.1288 0.2926 0.4351 0.5642 06868 1.4061 1.4851 1.5415 1.5883 1.6298 16679 1.7035 1.7371 1.7691 1.7996 e 001(I 0 0166 00174 0 0385 0 0203 0.3176 0 4059 04712 05282 05809 06311 06793 0 7272 0 7737 0 8195 1400 6 71 68 171 24 272.19 376 44 487 65 1194.1 !?961 1369 3 1833 2 1493 2 1551 8 1609 9 16680 1776 3 17850 (587.07) s 0.1287 0.2923 0.4348 0.5636 0 6859 1.3652 1.4575 1.5182 1. % 70 1.60M 1.uS4 1.6845 1.7185 1.7508 1.7815 i e 0.0161 0 0166 0.0173 0 0185 0 0202 0 023E O3415 0 4032 04555 0.5031 0 5482 0 5915 0 6736 0 6748 0.7153 72 21 171 69 272.57 376 69 487 60 6lf 77 1279 4 135E 5 1425.2 14E6 9 1546 6 16M 6 1664 3 1723 2 17E2.3 1600 4 (6G4 67) s 01266 0 2921 0 4344 0 % 31 0 6Eb1 OE129 14312 1 4969 1.5478 1.5916 1 6312 16678 1.7022 1.7344 1.7657 e 0 0160 0 0165 0 0173 0.0185 0 0202 0 0235 02906 03500 0.3988 0 4426 04836 05229 05604 0 5980 0 6?43 1800 a 72.73 172.15 272.95 376 93 487.% 615 % 1261.1 1347.2 1417.1 1480 6 1541.1 1601.2 1%07 1720.1 1779 7 (621/32) s 0.1284 02918 0.4341 0 5626 0.68'3 0 8109 1.4054 1.4768 1.5302 1.5753 1.6156 1.6528 16876 1.7204 1.7516 e 0 0160 0.0165 0.0173 0 0184 0 0201 0 0233 0.2488 0.3072 0.3534 0.3942 0 4320 0 4680 0.5027 0 5365 0.5695 2000 6 73 26 172 60 273 32 377.19 487.53 614 48 1240.9 1353 4 1408 7 1447.1 15362 1596 9 1657.0 1717.0 1777.1 (635 80) s 01263 0.2916 0 4337 0 5621 0 6834 0.8091 1.3794 1.4578 1.5138 1.5603 1.6014 1.6391 1.6743 1.7075 1.7369 e 0 0160 0.0165 0.0173 0 0184 0.0200 0 0230 0 1681 0 2293 02712 0.3068 0.3390 0 3692 0.3980 0 4259 0 4529 2500 4 74.57 173 74 274.27 377.82 487.50 612.08 1176 7 1303 4 1386 7 1457.5 1522.9 1585 9 1647A 17092 1770 4 (668.11) s 0.1280 0 2910 0 4329 0.5609 0 6815 0 8048 1.3076 1.4129 1.47 % 1.5269 1.5703 1.6094 1.6456 1.6796 1.7116 e 0 0160 0 0165 0 0172 0 0183 0 0200 0 0228 0 0982 0 1755 0.2361 02484 0.2770 0 3033 0.3282 0.3522 0.3753 3000 A 75 83 17t GB 275.22 378 47 487.52 610 06 1060 5 1267.0 1363.2 1440.2 1503.4 1574.8 1635 5 1701 4 1761.8 (69!'.33) s 0.1277 0 29J 0 4320 0 % 97 0 6796 0 8009 1.1966 1.3692 1.4429 1.4976 1.5434 1.5641 1.621/ 1.0561 1.6688 e 0 0160 0 0165 0.0172 0 0163 0 0199 0 0227 0 0335 0 1588 0 1987 0.2301 0 2576 0 2827 0.306% 03291 0.3510 3200 6 76 4 1753 275 6 3787 487.5 609 4 800 8 1250 9 1353 4 1433.1 1503 8 1570 3 1634A 1698 3 1761.2 (705 081 a 01276 0 2902 0 4317 05592 0 6762 0.7994 0 9708 1.3515 1.4300 1.4866 1.5335 1.5/49 14126 1.6477 1.6806 e 0 0160 0 0164 00172 0 ole 3 0 0199 0 0225 0 0307 0 1364 01764 0 2066 0 2326 0 2563 0 2784 0 2995 0.319?.
3500 m 77.2 176 0 276.2 3791 487.6 606 4 779 4 1224 6 1338 2 1422 2 1495 5 1%33 16292 1693 6 1757.2 s 0.1274 0.2899 0 4312 0 % 85 0 6777 0 7973 0 9508 1.3242 1.4112 1.4709 1.5194 1.% 18 1.6002 1.6353 1.6691 e 0 0159 0 0164 0 0172 0 0182 0.0198 0 0223 0 0287 0 1052 0 1463 0.1752 01994 02210 0.2411 0 2601 02783 4000 & 7&5 177.2 277.1 379 8 487.7 6065 763 0 1174.3 1311 6 1403 6 1481.3 1552.2 1619 8 1665.7 1750.6 a 01271 02993 0.4304 0 % 73 0 6760 0 7940 0 9343 1.2754 1J807 1.4461 1.4976 1.5417 1.5812 1.6177 1.6516 e 00159 0 0164 0 0171 0 0181 0 0196 0 0219 0 0268 0 0591 0 1038 0 1312 0 1529 0 1718 0 16*3 0 2050 0.2203 5000 a 81 1 179 5 2791 381.2 488 1 604 6 7460 1042 9 1252.9 1364 6 1452 1 15291 1600 9 1670 0 1727.4 s C.1965 0?$61 0 4267 0.5550 0 6726 0 7880 0 9153 1.1593 1.3207 1.4001 1.4582 1.5061 1.5481 1.5E 63 1.6216
- 00159 0 0163 0 0170 C 0100 0 0195 0 0216 002% 0 0397 0 0757 0.1020 0 1221 0.1391 0 1!44 01684 01817 60C0 4 E3 7 181 7 281.0 3b27 AME 602 9 7361 9%1 1968 8 1323 6 1422 3 1505 9 IM20 Rte ? 17247 s 01258 02670 0 4271 0 % 26 06093 0 7826 0 9026 1 0176 1.2615 1.35 N 1.4229 14745 1.5194 1.% 93 1%ol i
l o 001L8 0 0101 0 0170 0 OLES 00193 00?!3 0 024E O 0334 0 0573 0 0316 01004 0 1960 0129E D1424 0.1542 7000 4 862 IP4 4 223 0 384 2 489 3 601 7 729 3 901 0 1124 9 12F 1 7 1392 2 14M 6 1%31 1635 6 17111 s 0!?52 0 2Et9 0 42 % 05507 0GO O 7.77 0E970 10350 1 20 % 1.21e1 1 1904 144.0 14935 15P5 1 573!
TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE) (CONTINUED)
A.(
--. . . . - . a .. L s,.'.'., +. a.
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38 9 20 2. , gy y FIGURE A.5 MOLLIER ENTHALPY-ENTROPY DIAGRAM A.7
e e PROPEHTIES OF WATER Density e (Ibsfft')
PSIA Temp Saturated 2400 2500 8000 2300 Liquid 1000 2000 2100 2200
(* F) 62.909 62.93 62.951 63.056 62.637 62.646 62.867 62.888 32 62.414 62.846 62.87 62A9 62.55 62.75 62.774 62.798 62.822 60 62.38 62.446 62.465 62.559 62.185 62.371 62.390 62.409 62.427 100 61.989 60.587 60.606 60.702 80.314 60.511 60.53 60.549 60.568 200 60.118 67.859 67.882 67A98 57.537 67.767 67.79 67A13 67A36 300 67.310 64.342 64.373 64.529 63.903 64.218 64.249 64.28 64.311 400 63.651 63.925 63.95 64.11 63.475 63.79 63.825 63.86 63.89 410 63.248 63.50 63.53 63A9 63.025 63.36 - 63.40 63.425 63.46 420 62.79B 63.09 63.265 62.95 62.99 63.02 63.065 430 62.356 62.675 62.925 62.51 62.64 62.56 62.275 62.125 62.42 62.45 62.475 440 61.921 62.175 62.21 62.41 61.66 62.025 62.065 62.10 62.14 450 ' 51.546 61.725 61.76 61.96 61.56 61.61 61.64 61.68
! 460 61.020 61.175 61.50
- - 61.175 61.22 61.25 61.30 60.505 60.70 51.1 51.14 470 60.76 60.825 $1.035 60.20 60.62 60.66 60.7 60.74 480 50.00 60.35 60 575 60.175 60.22 60.265 60.31 4DG 49.505 49.685 60.13 49.714 49.762 49.81 49.858 60.098 48.943 49.097 49.618 49.666 600 49.203 49.254 49.305 49.56 48.51 49.05 49.101 49.152 610 48.31 48.735 49.01 48.46 48.515 48.57 48.625 48.68 620 47.85 47.91 48.155 48.45 47.86 47.919 47.978 48.037 48.096 630 47.17 47.29 47.56 47A9 47.296 47.362 47.428 47.494 640 46.51 47.23 47.27 46.726 46.794 46 862 46.93 45.87 46.59 46.658 650 46.142 46.216 46.29 46.66 45.92 45.994 46.068 660 45.25 45.54 45.62 46.02 i
45.22 45.30 45.38 45.46 670 44.64 44.844 44.93 45.36 44.50 44.585 44.672 44.75B 680 4366 44.11 44.205 44.68 43.73 43 825 43.92 44.015 590 43.10 43.33 43.434 43.956 42.913 43.017 43.122 43.226 600 42.321 42.432 42.55 43.14 41.96 42.08 42.196 42.314 610 41.49 41.483 41.616 42.283 40.950 41.083 41.217 41.35 620 40.552 41.44 630 39.53 40.388 640 3B491 39.26 65n 37.31 38.000 660 36.01 36.52 670 34.48 34.698 683 32.744 ,
32.144 690 30.516 TABLE A.6 PROPERTIES OF WATER, DENSITY
' A.B
1 F (ou 9 >'
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i
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1 I
. e 1-OP-1C APPENDIX A
'Page 1 of'10 a
1.0 Procedure' FEB 2 81986 Estimated Rod Bank Position After Shutdown or Trip NOTE: Equilibrium condition is defined to be: No change in power of greater than 5% during the previous 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
1.1 Previous Equilibrium Critical Conditions 1.1.1 Date: /6db [
1.1.2 Time: 3 00 1.1.3 Power Level Prior to Rampdown or Trip /OO %
1.1.4 Core Burnup: 70N MWD /MTU 1.1.5 Control Rod Worth at Previous Conditions:
1.1.5.1 Bank C c2 ol[ steps 1.1.5.2 Bank D S2I8 steps 1.1.5.3 Total Inserted Worth (Curve Pages 23 through 27) = (-) /EO pcm 1.1.6 Boron Concentration at Previous Critical Conditions 1.1.6.1 Previous Boron Concentration ppm 1.1.6.1.1 Date and Time of Boron Sample: /T M [5 2/M
, .1.1.7 Xenon Worth at Previous Critical Conditions 1.1.7.1 Xenon Worth (Curve Page 30) = (-)M M pcm f Power Defect at Previous Critical Conditions
( 1.1.8
, 1.1.8.1 Power Level from step 1.1.3 = /0 0 %
NOTE: Use boron concentration from 1.1.6.1.
1.1.8.2 Power Defect (Curve Page 29) =
(-) /f 0O pcm i
l, i
l-OP-AC APPENDIX A l
Page 2 or 10
'IALS - --
1.0 FEB 2 81986 Procedure [ continued]
1.1 Previous Equilibrium Critical Conditions (continued]
1.1.9 Briefly describe shutdown maneuver: (example:
"150MWe ramp from 97% starting at 0137, trip at 27%".)
Es T&t? FiloM (CO YO hug To con eF three tiscre. aus 2r
\
f.
.1 1
1-OP-lC APPL.NDIX A Page 3 of 10 f1ALS ---
FEB 2 81986 1.0 Procedure [ continued]
1.2 Projected Startup Conditions 1.2.1 Projected Date of criticality: /$ juk N 1.2.2 Projected Time of criticality: 2A @O 1.2.3 Desired Rod Height for Criticality 1.2.3.1 Bank C dd steps 1.2.3.2 Bank D /' E steps 1.2.3.3 Total Inserted Worth Curve Pages 23 through 27 = (-) MN pcm 1.2.4 HZP Boron Coefficient (Curve Page 21 HZP) =
(-) /O. lY pcm/ ppm 1.2.5 Xenon Worth at criticality 1.2.5.1 Time af ter shutdown (5.2.2 - 5.1.2) =
c2 hrs.
1.2.5.2 Average power for Xenon (Appendix B) =
/00 x 1.2.5.3 Did a rampdown of power occur before shhtdown?
1.2.5.4 If 1.2.5.3 is yes, proceed to Appendix C.
1.2.5.5 Xenon Worth (Curve Page 32, 33, 34 or Appendix C) = (-) bkO pcm t
l
. . 1-OP-lc APPEhD1X A Page 4 of 10 IALS .s gg,g 2 8 9 86 1.0 Procedure (continued}
1.2 Projected Startup Conditions [ continued]
1.2.6 Temperature Defect 1.2.6.1 Proj ected Temperature at Criticality =
f 'F 1.2.6.2 Temperature Defect (Curve Page 28) =
(1) pcm 1
NOTE: If the projected temperature is greater than 547'F, the temperature defect is negative. If the proj ected temperature is less than~ 547'F, the temperature defect is positive.
t 1
i
\
. . 1-OP-lc APPENblX A Page 5 of 10 1ALS .s FEB 2 8 WB6 1.0 Procedure (continued]
1.3 Reactivity Balance 1.3.1 Change in rod ~ worth from previous critical conditions to estimated critical conditions
(-) /20 - (-) A y 0
. /2o pcm 1.1.5.3 5.2.3.3 1.3.2 Change in xenon worth from previous critical conditions to estimated critical conditions
(-) UDO - (-) N WO = ~ YOO pcm 1.1.7.1 1.2.5.1 1.3.3 Change in defects from previous critical conditions to estimated critical conditions
(-) / NO - (-) O = -80 pcm
.. 1.1.8.2 1.2.6.2 I 1.3.4 Total change in reactivity from previous critical conditions to estimated critical conditions
/70 . . y o; . _,gog , _ n ec ,,,
l 1.3.1 1.3.2 1.3.3
! 1.3.5 Equivalent change in boron concentration "l *7 N s -JOI4 . I3 C pga
. 1.3.4 1.2.4 3 1.3.6 Zero- over critical boron concentration
+ 17 I = 997 ppm 1.1.6.1 1.3.5 NOTE: Step 1.3.6 represents the critical boron concentration at the i
specified date and time, RCS aterage temperature, and rod position.
(
i
< l
. ./
REACTOR OPERATION
- 8. Coeffecients and Control (continued)
POINT OF OPTIMdM MODERATION l
l Kg s
NMfm l
l l
l
_ m .. . -- - - . . . - . .
[
TS FIGURE 3.12-8 l7E 6-16-81 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE SURRY POWER STATION 75 q: ._-l. .9 ; - ; _ .; _: .- j : .! ,j,...,
l --.-~T - - Ti~" TI"#4:~-!E-f~ Mil i. ~~~"I' '~ 4'~=i ~d IMI~Fp:3' ~ i 1.0 . . . _ . . . - -
-I
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- =-f=i:=;
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.q .:
p =y -p:=- ! _.; _ s. . _.y:+ . ;=;_ .. i .. _. i. .\: - \
-J'= -!\
l :E = __ .::E$ri . .p- . p . _i:FC= E =hE ' :-- :..:n!0=
l 0.8 .i
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Amendment Nos. 70 & 70 i
- f. .
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TS 3.0-1 2-9-81 3.0 LIMITING CONDITIONS FOR OPERATION 3.0.1 In the event a Limiting Condition for Operation and/or associated modified requirements cannot be satisfied because of circumstances in excess of those addressed in the specification, the unit shall be placed in at least hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> unless corrective measures are completed that permit operation under the permissible action statements for the specified time interval as measured from initial discovery or until the reactor is placed in a condition in which the specification is not applicable. Exceptions to these requirements shall be stated in the individual specifications.
70 3.0.2 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered operable for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding nor-I mal or emergency power source is operable; and (2) all of its redundant I
l system (s), subsystem (s), train (s), component (s) and device (s) are operable, l
or likewis'e satisfy the requirements of this specification. Unless both l i
conditions (1) and (2) are satisfied, the unit shall be placed in at !
r least hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least cold shutdown within the i following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. This specification is not applicable in cold shutdown !
I i
or refueling shutdown conditions.
i i
i 1 Basis I
a ;
3.0.1 This specification delineates the action to be taken for circumstances not directly provided for in the action statements and whose occurrence would 62endment Nos. 64 & 64
'f TS 3.1-2 9-29-81
- b. If an unscheduled loss of one or more reactor coolant pumps occurs while operating below 10% rated power (P-7) and results in less than two pumps in service, the affected plant shall be shutdown and the reactor made suberitical by inserting all control banks into the core. The shutdown rods may remain withdrawn.
- c. When the average reactor coolant loop temperature is greater than 350'F, the following conditions shall be met:
- 1. At least two reactor coolant loops shall be operable.
- 2. At least one reactor coolant loop shall be in operation,
- d. When the average reactor coolant loop temperature is less than or equal to 350*F, the following conditions shall be met:
- 1. A minimum of two non-isolated loops, consisting of any
. combination of reactor coolant loops or residual heat removal loops, shall be operable, except as specified in Specification 3.10.A.6.
- 2. At least one reactor coolant loop or one residual heat removal loop shall be in operation, except as specified in Specification 3.10.A.6.
Amendment Nos. 72 & 73
- *- -- - TS 3.7-1 9-29-81 3.7 INSTRUMENTATION SYSTEMS Operational Safety Instrumentation Applicability:
Applies to reactor and safety features instrumentation systems.
Objectives:
To provide for automatic initiation of the Engineered Safety Features in the event that principal process variable limits are exceeded, and to delineate 82 the conditions of the plant instrumentation and safety circuits necessary to ensure reactor safety.
Specification:
A. For on-line testag or in the event of a sub-system instrumentation channel 82 failure, plant operation at rated power shall be permitted to continue in accordance with TS Tables 3.7-1 through 3.7-3.
B. In the event the number of channels of a particular sub-system in service falls below the limits gisen in the coluna entitled Minimum Operable 82 Channels, or Minimum Degree of Redundancy cannot be achieved, operation shall be limited according to the requirement shown in Column 4 of TS tables 3.7-1 through 3.7-3.
l Amendment Nos. 72 & 73
. o TS 3.7-2 6-19-84 C. In the event of sub-system instrumentation channel failure permitted by Specification 3.7-B. Tables 3.7-1 through 3.7-3 need not be observed during the short period of time and operable sub-system channel are tested where the failed channel must be blocked to prevent unnecessary reactor trip.
4 D. The Engineered Safety Features initiation instrumentation setting limits shall be as stated in TS Table 3.7-4 I
E. The radioactive liquid and gaseous effluent monitoring instrumentation channels shown in Table 3.7-5(a) and Table 3.7-5(b) shall be operable with their alarm / trip setpoints set to ensure that the limits of Specifications 3.11.A.1 and 3.11.B.1 are not exceeded. The alarm trip setpointa of these channels shall be determined and adjusted in accordance with the Offsite Dose Calculation Manual (CDQf).
1.
With a radioactive liquid or gaseous affluent monitoring instrumentation channel alars/ trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid or gaseous effluents monitored by
! the affected channel and declare the channel inoperable or change
{ the setpoint so it is acceptably conservative.
2.
With less than the minimum number of radioactive liquid or gaseous effluent monitoring instrumentation channels operable, take the
action shown in Table 3.7-5(a) or Table 3.7-5(b). Eaert best efforts to return the instruments to operable status within 30
- days and. if, unsuccessful, explain in the next Sealannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner. .
Amendment No. 97 and No. %
TABLE 3.7-1 REACTOR TRIP INSTRUMENT OPERATING CONDITIONS 1 2 3 4 OPERATOR ACTION IF CONDITIONS OF DEGREE COLUMN 1 OR 2 MIN. OF EXCEPT AS CONDI-OPERABLE REDUN- PERMISSIBLE BYPASS TIONED BY COLUMN 3 FUNCTIONAL UNIT CNANNELS DANCY CONDITIONS CANNOT BE MET
- 1. Manual 1 -- Maintain hot shutdown
- 2. Nuclear Flux Power Range 3 2 Low trip setting when 2 Maintain hot of 4 power channels greater shutdown than 10% of full power
- 3. Nuclear Flux Intermediate 1 -- 2 of 4 power channels greater Maintain hot Range than 10% full power shutdown
- 4. Nuclear Flux Source Range 1
-- 1 of 2 intermediate range Maintain hot 10 channels greater than 10 shutdown amps
- 5. Overtemperature AT 2 1 Maintain hot shutdown
- 6. Overpower AT 2 1 Maintain hot shutdown g-u 3 of 4 nuclear power channels i El 7. Low Pressurizer Pressure 2 1 Maintain hot
! !+ and 2 of 2 turbine load shutdown ,g n channels less than 10% of 4 un y rated power yy 00 %J e
e- -
- 8. Ni Pressurizer Pressure 2 1 Same as Item 7 above Maintain hot shutdown "k
1
TS 3.10-1 5-12-81 3.10 REFUELING Applicability Applies to operating limitations during refueling operations.
Objective To assure that no accident could occur during refueling operations that would affect public health and safety.
Specification A. During refueling operations the following conditions are satisfied:
- 1. The equipment door and at least one door in the personnel air lock shall be properly closed. For those systems which provide a direct path from containment atmosphere to the outside atmosphere, all automatic containment isolation valves in the unit shall be operable or at least one valve shall be closed in each line penetrating the
, containment.
- 2. The Containment Vent and the Purge System and the area and airborne radiation monitors which initiate isolation of this system, shall be tested and verified to be operable immediately prior to refueling i
operations.
j Amendments No. 67 & 67
. . TS 3.10-2 5-12-81
- 3. At least one source range neutron detector shall be in service at all times when the reactor vessel head is unbolted. Whenever core geometry or coolant chemistry is being changed, suberitical neutron flux shall be continuously monitored by at least two source range neutron detectors, each with continuous visual indi-cation in the Main Control Room and one with audible indication within the containment. During core fuel loading phases, there shall be a minimum neutron count rate detectable on two operating source range neutron detectors with the exception of initial core loading, at which time a minimum neutron count rate need be established only when there are eight (8) or more fuel assemblies loaded into the reactor vessel.
,,. 4. Manipulator crane area radiation levels and airborne activity levels within the containment and airborne activity levels in the ventilation exhaust duct shall be continuously monitored during refueling. A manipulator crane high radiation alarm or high airborne activity level alarm within the containment will automatically stop the purge venti-lation fans and automatically close the containment purge isolation valves. ,
- 5. Fuel pit bridge area radiation levels and ventilation vent exhaust airborne activity levels shall be continuously monitored during .
refueling. The fuel building exhaust will be continuously bypassed through the iodine filter bank during refueling procedures, prior to discharge through the ventilation vent.
l Amendments No. 67 & 67
?
. o TS 3.10-3 5-12-81
- 6. At least one residual heat removal pump and heat exchanger shall be operable to circulate reactor coolant. The residual heat removal loop may be removed from operation for up to 1 bour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of core alterations or reactor vessel surveil-lance inspections.
- 7. Two residual heat removal pumps and heat exchangers shall be operable to circulate reactor coolant when the water level above the top of 75 the reactor pressure vessel flange is less than 23 feet.
1 i
- 8. At least 23 feet of water shall be maintained over the top of the reactor pressure' vessel flange during movement of fuel assemblies.
- 9. When the reactor vessel head is unbolted, a minimum boron concen-tration of 2,000 ppa shall be maintained in any filled portion of the Reactor Coolant System and shall be checked by sampling at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- 10. Direct communication bwtween the Main Control Room and the refueling 75
. cavity manipulator crane shall be available whenever changes in core geometry are taking place.
i 11. No movement of irradiated fuel in the reactor core shall be accomplished 75 until the reactor has been subcritical for a period of at least 107 hours0.00124 days <br />0.0297 hours <br />1.76918e-4 weeks <br />4.07135e-5 months <br />.
l Amendments No. 67 & 67
e 4 6k9-84
- 12. A spent fuel cask or heavy loads exceeding 110 percent of the weight of.a fuel assembly (not including fuel handling tool) shall not be
, moved over spent fuel, and only one spent fuel assembly will be handled at one. time over the reactor or the spent fue5 pit.
- 12. A spent fuel cask shall not be moved into the Fuel Building unless the Cask Impact Pads are in place on the bottom of the spent fuel pool.
14 Two trains of the control and relay room emergency ventilation system shall be operable. With one train inoperable for any reason, demonstrate the other train is operable by performing the test in Specification 4.20.A.1. With both trains inoperable comply with Specification 3.10.3.
- 15. Containment purge shall be filtered through the high efficiency par 'eulate air filters and charcoal absorbers.
- 3. If any one of the specified limiting conditions for refueling is not met, refueling of the reactor shall cease, work shall be initiated c: ::rrect the conditions so that the specified limit is met, and no operations which increase the reactivity of the core shall be made.
C. After initial fuel loading and after each core refueling operation and prior to reactor operation at greater than 75 'of rated power, the
- i . .
movable incere detector system shall be utilized to verify' proper pcwer distribution.
- 3. The recuire=ents of 3.0.1 are not applicable.
m en = ent .a. n m .c.=5
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATIONr FLUIDSr AND ' AGE 19 ANSWERS -- SURRY 182 -96/07/21-9EANr W M ANSWER 5.01 (1.00) b REFERENCE NUS, Vol 4r pp 2.2-4 Surry 1-PT-35 015/0005 K5.04(2.6/3.1)
ANSWER 5.02 (l'.00)
,-b REFERENCE Farley TS 3/4.2 Sorry ND-06.3-LP-3 pp 3.10f 73 3.81 l
l 001/000; K5.46(2.3/3.6)
ANSWER ',03 (1.00) d g[g (h Rr ERENCE manprehensive Nuclear Training Operitions (CNTO)r pp 4-16/27 _
001/000; K5.13(3.7/4.0)
ANSWER 5.04 (1.00) d.
REFERENCE 002/000; A1.09(3.7/3.8) & A1.13(3.c/2.0)
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATIONr FLUIDSr AND PAGE 20 ANSWERS -- SURRY 1&2 -96/07/21-DEANr W M ANSWER 5.05 (1.50) i a) Lower critical rod position (+.5 es) l b) Higher critical rod position c) Lower critical rod pcsition REFERENCE SURRY OP-1C 001/010; A4.03(3.5/3.9)
ANSWER 5.06 (1.50) a) Increase (+.5 ec) b) Decreaae c) Increase REFERENCE Surry ND-83-LP-Br pp S.17 Appendi:, A: Centrifugal :unps NPSH (3 4/3.6)
ANSWER 5.07 (7 50)
- a. High relative flus - causes a y eater reac.tivity change due to CRW being proportional to f l u i- tip/ flus evs. therefore, the higher the relctive flu: the greater the change. (0.333 for area /0.5 for Exp.)
- b. larger effect for the middle - due to absorption of neutrons which have 3 high pro' e ability af causing fission. Whereas control rods at the edge l abcorp neutront which have a high probability of leakage.
1
- c. t1 has higher worth. When inserted il depresses the flu > 3round itselfr this increases the flu > in other regionce when 12 is inse:ted the flut has been depressed therefore its worth is lower (then its worth in an
~unrodded core).
REFERENCE North Anna ~' s O P - pp. 6.13 6.1:r6.19 Obj. E SURRY ND-86.2-LP-6 K/A 001-000-K5.02 (T.o'3.4)
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- 5. THEORY-OF NUCLEAR POWER PLANT OPERATION, FLUIDS,'AND PAGE 21 ANSWERS -- SURRY 1&2 -86/07/21-DEAN, 9M ANSWER 5.08 (1.50) s.~5 (0.5 ea.)
- b. 3 (4 with explanation)
-001/0003-K5.46(2.3/3.6) l ANSWER 5.09 ( .50)
Optimum point would move down and to the left (+.5)
REFERENCE SON /WBN License Cert Trns, " Reactivity Coefficients' Surry ND 86.2-LP-2, .pp 8.12/12 004/0001 K5.15 (3.3/3.5)_
ANSWER 5.10 (2.00)
.1) Pu-240 buildup--More Negative (+.5 ea)
- 2) Accumulation of Fission Product Sases--More Negative
- 3) Fuel Densif.ication--More Negative
- 4) Clad Creep.--Less Negative REFERENCE TPT Requal Lesson Plan, Cycle I, 1985
- Core Life Changes", pp 16 CNTO, ' Reactor Core Contro1*, pp 2-44/45 Surry, NO-86.2-LP-1 & LP-10 001/0007 K5.49(3.4/3.7) l I
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDSr AND PAGE 22 ANSWERS -- SURRY 1 P.2 -06/07/21-DEAN, uM ANSWER 5.11 (1.00) '
Ove to the greater decrease in the temperature of the coolant exiting the core relative to the decrease of the inlet coolant. (+.5) note positive reactivity will be added in the upper core regions, resulting in a more positve (less negative) AFD (+.5)
REFERENCE Westinghcuse Nuclear Training Operations, Ch 9 Surry NO-86.2-LP-8, pp 8.14/15 001/000; K5.29 (3.7/3.9)
ANSWER 5.12 fi 0) ~~
- 1. Minimum tina necessary to cause boric acid in the vessel / core region to cpproach the solubility limit - ~ (f l4) g r. ._,,u,_ u_, __ . _ _ _
REFERENCE North Anna NCPODP-95.2 Surry ND-91-LP pp 23 K/A 000-011-EK3.13 ( 3 . '3 / 4 . 2 )
ANSWER 5.13 (1.00)
The ability to deliver a certain nurber of amperes for a specific number of hours before the cell voltage drops to a specific n i n i n.u m value.
?EFERENCE North Anna: N C R O D t' CO.3 Sec. I S u r r y . N D - 9 0 . 3 -- L ;' . 6 pp 6.5/6 063/000; 91.01(2.5/3.3)
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- 2. Subcooling is Msed on core e::it T/Cs or hot les RTD readin3s. During nature; circulation the mess of netel in the head can retain hest and keep local temperatures above saturation. The temperature indicators would not reflect this locs1 caturated condition. (1.0)
- b. Pressurizer level decressas because the pressurizer pressure increase will compress the vessel void and force water out of the pressurizer.
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REFERENCE G.P. Heat Tr a r, s f e r and rp pp 3 5 5_3:5 e EPE-074; EA2.05(3.4/4.2) & EA2.07(4.1/4.7) sNSWE.n c.la a 7ma s . 0 n, ) go% PH pp39) [M 3 4MWf
- 1) Pressurizer Level at 22%V(&.4 paraneterr +,1 setpoint) which is an indication core is covered (+.5 for description)
- 2) RCS subcooling /= 50 degrees, subcooled water implies no voids 3s cr level in at least 1 3G .. / = '7%. ensurec heat sink maintained l aQ g,c;3 prt1Nft > E000pt:3 4e enivrt so ##Ufn+ twhc.sekl9 REFERENCI SURRY ND-86.3-LP-a r pp a.G/C l EPE-015; EK1.01(4.4/4.6) & EK3.07(c.1/4.2) i l
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t ANSWER 5.16 (1.00)
(
Concave down REFERENCE NUS Vol 3r CH 12 015/000; :5.05(4 :/4.0) 1 I
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- 3) Maintain D r48 R s 1.3 and core e:: t enthalpy saturated (+1.0) b) Prevent bulk boiling (+ 5) during normal operations (+.25) c) Ensure fuel clad temperature 2200 degrees (+.5) during a LOCA (+ 25)
REFERENCE Surry ND 86.3-LP-3, pp 3.12 001/000; K5.46(2.3/3.6)
ANSWER 5.18 (2.00) a) Unit 1 (+.5) due to a higher Beta coefficient at 90L (+.5) b) Unit 2 (+ 5) due to MTC being more negativer so Tavs will decrease less to add sana + reactivity (+.5)
REFERENCE Sorry ND 36.2-LP-2 and 86.1-LP-9 001/000; MS.49(2.9/3.4) and K5.10(3.9/4.1)
ANSWER 5.1? '1.50)
-see attachedcurveh.h
- 1) first deviation 13 to account #ct the fact that the upper core region is uncovered first and refilled last on s LOCA. (+.5) 1
- 2) the ser ond deviation is due to the resistance ancountered in refilling the core following a small break LOCA. (+.5)
REFERENCE SON TS 3/4.2.2 and SON FSAR CH 15 SURRY TS 3.12 001/000) K5.46 (2.3/3.6)
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. THERMODYNAMICS
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ANSWERS -- SURRY 1&2 -86/07/21-DEAN, W M- i
}
ANSWER 5.20 (2.00) :
a..~.ThotL=.630 des -
Tsat.0 2235 psig ~
= 653~ (+/- 1) [1.03- i subcooling = 23 deg.F (+/- 1) !
l
- b. For subcoolsd' conditions'the reading would. indicate 10 deg. (0.25) more ;
-subcooling than actually~ exist (0 25).
1 For superheated conditions the reading would indicate 10 des. (0.25) less sup.erheat then.actually-exist (0.25).
REFERENCE -
North Anna' Core.Coolins Monitor Obj. 2. r Surry ND-93.4-LP-2 i K/A Camp T/C (3.'0/3.1) I' 002-000-A1'.04 (3.9/4~.1) [
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- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION C' AGE 26 ANSWERS -- SURRY la2 -96/07/21-DFAN, WM ANSWER 6.01 (1.00) a REFERENCE SONP Systen Descrip. 'EPS'r pp 10 & RPS Mechanical Logic Orewing Surry ND-93.3-LP-10, pp 10.15 012/000; 6 . 0 3 (3.1/3.5)
ANSWER 6.02 (1.00) 3 REFERENCE Surry NO-88.1-LP-3, pp 3.13 010/000; A4.01(3.7/3.5)
ANSWER 6.03 (1.00) d REFERENCE Sorry ND-98.1-LP-4 pp 4.11 059/000: M1.03(3.1/3.3)
ANSWER 6.04 (1.00) b er O REFERENCE Sorry NO 03.3-LP-3, pp 3.8 001/000; K4.08(3 2/?.4)
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- 6. PLANT SYSTEMS DESIGNr CONTROLr AND INSTRUMENTATION OAGE 27 ANSWERS -- SURRY 182 -96/07/21-DEANr W M ANSWER 6.05 (1 00) b.
REFERENCE North Anna NCRODP 93.10
- Surry'ND-93.3-LP-14,. pp 14.7/9 012/000; '( 4 . 0 2 ( 3 . 9 / 4 . 2 )
ANSWER 6.06 (1.00' Prevents voltage dror during the diesel-load sequence '+.5) fran ecusing cubsequent .oad shedding (+.5) neseting the loading of the diesel.
REFERENCE g fkk - --
NCRODP 90.4, _0C' Surry ND-90 eLP-7 064/000* .4.10 (3.5/4.0)
ANSWER -6.07 (1.50) 38% setpoint from 0-20% (+.5) Turbine Power (+.25) and l i n e a r '. y from 30-108Z 2s Turbine Power goes from 20-100% (+.75)
REFERENCE NCRODP 91.1r 'ESF-SI or ECCS' Surry NO-91-LP-3, pp 3.9 013/000; U1.01 (4.2/c.4)
ANSWER 6.08 (1.50)
. a) Stops discharge f r o it containment vacuum system and waste decay tanks (Shuts RCV-CW-160, 260 101) (+.75) b) Trips Unit l's purge supply -
fans, shuts purse air -
butter #1y vcives(MOV-VS-100Ar B, C, D) (+.75) f
- .r e g g g y p' r # 'W yV -74 **ieft)/6 (l036 [(40Y$uspx>ar 40 Out%'@
TPT SD68 ' Radiation Monitoring and orotection System', pp 34/3J Surry TS Table 3.7-5 atrJWQ
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i 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 28 ANSWERS -- SURRY 1&2 -86/07/21-DEAN, W M EPE-059. & 060; EA2.05(3.6/3.9) & (3.7/4.2) i .
ANSWER 6.09 (1.00)
TO limit'the rate of S/G blowdown during a main steam line break (+1.0)
, REF$RENCE i Svery ND-89.1-LP-2, pp 2.4/5 t EPE-040iEK3.01(4.2/4.5)
I i ANSWER 6.10 (2.50)
'1) LHSI discharge to-CHG Pump suction (MOV B63A, B) start to open while LHSI recire valves (MOV 885A, B, C, D) start to close (+.75)
, A white status light illuminates (+.25)
- 2) 2 minutes later, HHSI normal suctions (LCV 115B, D) close and the LHSI suctions from CNTMT sump (MOV 860A, B) open. (+.75).
An' amber status light illuminates (+.25).
- 3) When MOV 860Ar B are fully open, LHSI pump normal suctions close (+.5)
REFERENCE Surry.ND-91-LP-3, pp 3.21/23 006/020i A3.04(4.2/4.3)
ANSWER 6.11 (1.00)
- l. 1)- Accopiodate release of f.p.. gases (+.5 es for any two)
- 2) Differential thermal expansion between clad and fuel pellet
- 3) Fuel density changes during burnuP
! REFERENCE l Surry ND 88.1-LP-2, .pp 2.23 4
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ANSWERS -- SURRY 1&2 -86/07/21-DEAN, W M j ANSWER 6.12 (1.00) 1). Phase Failure (+.25 ea)
- 2) Regulation Failure
) 3) Logic Error
- 4) Multiple::ing Error
! REFERENCE i Sorry ND-93.3-Lo-3, pp 3.22 001/050; K4.01(3.4/3.8)
ANSWER 6.13 (2.00) i
') S/G Pressure (+.25 ea) l 2) WR Tc (Loops A/B)
- 3) SR counts
) 4) % reactor power
! 5) WR S/G Levels
, 6) WR Th (Loops A/B) j' 7) Pt level j 8)~ P:t Pressure REFERENCE Sorry ND-93.4-LD-6 pp 6.5 EPE-068; EM2.01(3.9/4.0)
ANSWER 6.14 (1.00)
Level III Channel (+.5) failed high (+.5)
REFERENCE Westinghouse PWR Systems Manual " Primary System Control'r PP 12-14 TPT SD9 'PZR and Pressure Relief', pp 38-40, 57; DWG 5610-T-D-15 Surry ND-93.3-LP-7 011/000; A2.10(3.4/3.6)
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- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 30 j ANSWERS -- SURRY 1&2 -86/07/21-DEAN, W M l
ANSWER 6.15 (1.50) i j a) PG System (+.2.5 ea)
! CVCS Blender Soron Recovery Tanks Fire Main l b) -The center-to-center distance ensures ! .95 Keff for spent fuel, (even if unbo ated water is used) (+.5)
REFERENCE TPT SD41 " Spent Fuel Pool Cooling, Purification and Ventilation', pp 4-6 Sorry ND-92.5-LP-6, pp 6.5/8 l 033/000; K4.05(3.1/3.3) l
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ANSWER 6.16 (1.50)
Gases, particularly Hydrogen from the VCT (and some f.p. gases) come out of solution as they are sprayed into the PZR. (+1.0) this creates larger t
pressure oscillations during transients (+.5)
I REFERENCE Surry ND-88.1-LP-3, pp 3.27 010/000; PWG-7(3 4/3.9) j ANSWER 6.17 (2.00)
Open ALL 3 feedwater bypass control valves a small increment (+1.0) observe level behavior and readjust only if levels aren't changins as
' ^ * -
anticipated (+.5) -
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ofsept frend recoestG , .t/C {eveh SJ Srn FM/t*r*154tt O 0 REFERENCE Sorry ND-88.1-LP-5, pp 5.16 035/010; A2.04(3.6/3.8)
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- 6. PLANT SYSTEMS' DESIGN, CONTROLr AND INSTRUMENTATION PAGE 3'1 ANSWERS -- SURRY 1&2 -86/07/21-DEAN, WM ANSWER 6.18 (3.00)
- 1) Rod control- Due to Tavg< Tref, rods will withdraw until a rod stop is reached (+1.0)
- 2) Pzt level control- Low Tavs will cause P:t level control system to shutdown on FCV-122 until l'evel is 22% (+1.0)
- 3) Steam Dumps- Tavs <Trefr so that even if armed in the Tavs moder.no dump actuation would occur (+1.0)
REFERENCE Surry ND-90.3-LP-2 016/000; K3.01(3.4/3.6)r K3.02(3.4/3.5) & K3.03(3.0/3.1)
ANSWER 6.19 (1.50) a) COMPUTER PRINTOUT ROD CONTROL SYSTEM (+.5) b) No (+.5) Due to induced electrical.noiser the setpoint is increased (to +/- 37 step.s) (+.5)
REFERENCE Surry ND-93.3-LP-3, pp 3.32/33 014/000; K4.06(3.4/3.7)
ANSWER 6.20 (3.00)
.a. The two pumps not in Pull to Lock (1.0)
- b. 1. LHSI.can only deliver enough flow to provide sufficient suction pressure to two~HHSI pumps. (1.0)
- 2. (for NA)The pumps are 900hp each this action limits loadin.g on the EDG to within specifications. (1.0)
- 2. (For Sorry)To conserve R4ST water dtring the injection phase (1.0)
REFERENCE North Anna: NCRODP 71,1 Surry ND-91-LP-2r pp 2.14/16 006/000; K4.05(4.2/4.4)
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ANSWERS -- SURRY la2 -86/07/21-DEAN, W M ANSWER 7.01 (1.00) e l REFERENCE McG, AP/2/A/5500/23, p. 2
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Surry AP-14e pp 3 EPE-051; *WG-11(3.7/3.7)
ANSWER 7.02 (1.00) d REFERENCE Westinghouse background info for TPT EOPs, "RCP Trip / Restart', pp 49/50 000/074; EK3.07(4.0/4.~4)
ANSWER 7.03 (1.00) b REFERENCE Westingh.ouse guidelines for usage of E-0 PWG-11' Performing Immediate Actions (4.3/4.4)
ANSWER 7.04 (1.00) b REFERENCE
( Sorry EP-1.01 i .
EPE-024; PWG-7(3.5/4.4).
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ANSWERS -- SURRY 1&2 -86/07/21-DEAN, W M ANSWER .05 (1.00) b REFE'~ dNCE Sur. y EP-4.00
'r'E-038; Ek3.06(4 2/4.5)
ANSWER 7.06 (1.50) i a) (+.5 ee)
False b) True c) False REFERENCE Westinghouse User's Guide for EOPsr pp 5-12 PWG-22(4.3/4.3)
ANSWER 7.07 (1.50) a) No (+.5 es) b) m Mo c) No REFERENCE Surry EP-1 Foldout Page PWG-10(4 1/4.5)
ANSWER 7.08 (1.50)
- a. 100 (0.5)
- b. 60 (0.5)
- c. 1 (0.5)
! REFERENCE I
Catr EP/1/A/5000/2Dir pp. 16 Sorry FRP-P.1, pp12
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ANSWERS -- SURRY 1&2 -86/07/21-DEAN, WM EPE-069;PWG-7(3.4/3.9)
ANSWER 7 09 (1.00) 1). Require permission of the Operations Superintendent (+.5 ea)
AND RCS is borated to the Cold Shutdown condition 2)koA AU 6ersted k 5t-ket,ke+ renddreet i gep q a t ga REFERENCE +
Surry OP-1.1, pp 6 PWG-7(3.5/4.0)
ANSWER v*4o
' - (1.50) og 3
- 1) Verify MSTV closure ( .+. .5 ea) '/) OkMI Cl JfM - goJJT /4 f -(J p.>ap3 rvoney E
' -) Jerify Phase 3 isolation
. c ,peu; gg7 ),va l 4 M /W
- 3) -StoP RCPs in 2 1inutes REFERENCE Surry E0P-1.007 step 9/ctt . d C k U k C ,4 g ,, , g R S SyJ W g gy pgttt!
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-ANSWER 7.11 (2.00)
~1 ) Verify at least H or J buses energized (+.5.ee)
~2) Verify SS Auto Swap-over
- 3) Unaffected unit. supplied by RSS
- 4) Verify load mted using attachment to procedure REFERENCE Sorry EP-1.00, step 3 EPE-007; PWG-11(4.4/4.5) s
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- 7. PROCEDURES - NORMALr ASNORMAL, EMERGENCY AND PAGE 35 RADIOLOGICAL CONTROL ANSWERS -- SURRY 1&2 -86/07/21-DEAN, W M ANSWER 7.12 (2.00) a) High Bearing Temp Alarm (+.25 ea response)
High Stator Windin3 Temp 2 minutes elapsed b) Containment Vacuun Pumps Main Feed Pumps HP FW Drain Pumps Chilled CC Pumps Cire Water Pumps REFERENCE Surry AP-40, pp 3 EPE_065; OWC-11(3.9/3.9)
ANSWER 7.13 (1.50) a) 320 '+.5 ea) b) 50 C) 27 REFcRcNCc Sbtry PL ? '. pp 36, 39, 53,* 08/ 3 b k W" /
002/020; PWG-7(3.7/4.3) and 005/000; PWC-7(3.5/3.0)
ANSWER '.14 (1.50)
- 1) CNTM Air Particulrte Monitor (Any 5 1' o r +.3 ee)
- 2) CNIM Radioactive Gas Monit.or
- 3) Componer.L Cooling L_ quid Monitor
- 4) Condenser Air Ejector Cas Monitor
- 5) S/G E:l o w d o u r Monitor
- 6) i.u:e Rutiding Area Monitors
- 4) t/cotOnf RM REFERENCE TPT 040P 1008.2, pp 2 Sorry AP-16, p ,e 3 000/020; EA1.06(3.3/3.6)
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ANSWERS "-'SURRY 1&2 -96/07/21-DEAN, WM ANSWER -7. 15 ( .75)
- 1) Halt operations, evacuate and secure area (+.25 ea) 2)_ Check closed the containment purge valves
- 3) . Request initiation of EPIP-1.01 REFERENCE TPT ONOP 16000.2, pp 2/3
'Surry AP-41, pp 2 034/000; PWG-11(2.0/4.1)
ANSWER 7.'16
. (1.00) 1)- Heat sink (+.15 for CSF, +.1 for correct order)
- 2) . Integrity
.3) Containment-
~PWG-22(4.3/4.3.).
ANSWER 7.17 (1.00)
- 1) Following refueling (+.5 ea)~
2). TIf'a. change in critical conditions of > 500 pcm since last criticality has occurred REFERENCE Sorry OP-1C and OP-50.2.1 001/010; K5 16(2.9/3.5)
ANSWER 7.18 (1.00)
Trip the Turbine EEFORE locally. tripping the reactor by opening the ex trip or MG set breakers (+1,0) i
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~~~~R55i5E55fCKE C5siE5E------~~~---~~---~~~~~~-
! ANSWERS -- SURRY 1&2 -86/07/21-DEAN, W M REFERENCE Surry AP-20, pp 5 EPE-068;PWG-11(4.5/4.5)
ANSWER 7.17 (1.00) 1.25 R/qtr-Health Physic; (+.33 e a ) 4r W 3 1.75 R/qtr-Station ManagementA L.2 M M vp guchst PJ 2.75 R/qtr-Corporate Managemeiit REFERENCE Sorry HP Manual, HP-1.2, pp 5 PWG-15(3.4/3.9)
ANSWER 7.20 ( .75)
Cause not clearly understood (+.25) or safety related/important equipnent operated I ri an abnormal or degraded manner (+.5)
REFERENCE Sorry ADM 14, pp 2 NA ADM 19.18, pp 1 PWC-10: Recognizing abnormal indications (c.1/4.5)
ANSWER 7.21 (1.50)
To prevent excessive depletion of RCS i.nventory (+.75) such that the PCP trip occurs at a point where the break would completely uncover the core (+.75)
REFERENCE Westinghouse background i n f' o o r E0Ps. 'RCP Trip / Restart' 000/00?: EK3.23(4.2/4.2)
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ANSWERS -- SURRY 1&2 ~B6/07/21-DEAN, WM ANSWER 7.22 ClD)
- Insert control rods in the MANUAL node w while naintaining Tave as n e c e s s a r y (+.f)En s u r e Tavs is not decreasing when the IR is below the POAH
(+.25) ensure Audio count rate meter is on and a SR recorder is selected and the High Flux at Shutdown in in block (+.5) Trip the reactory ensure all rods on the botton % i l
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REFERENCE.
Surry OP-3.1 i 001/0501 PWG-12(3.7/3.7) f ANSWER 7.23 (1.00)
This ensures adequate space exists in the PZEr since the potential for void fornetion in the upper heed region exicts, and allows increases in the PZR level to accomodate this growth.
REFERENCE Westinghouse Guidelines for ES-0.3r 'NC Cooldown w/ Voids and RVLIS' FWG-7(3.5/4 0) l C,s)
ANSWER 7.24 - ..
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( .25 for each switch needed to put in correct order)
REFERENCE Gorry AP-22 and ND-92.5-Lo-7, pp 7.10 EPE-036; PWG-7(3.3/3.C) l l
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~ ANSWERS -- SURRY 132 -86/07/21-DEAN, W M ANSWER 0.01 (****)
ANSWER 8.02 (1.50)
- 1) Dose Rate Meter is required to be on/ monitored continuously (+.5 ea for any 3)
- 2) Use of buddy system is required (two people in constant contact or communication)
- 3) Two people must sign for dey issue
- 4) The entrance is guarded while area is occupied (can be locked if egress is iot hindered)
REFERENCE Surry HP Manual 2-12, pp 3/4
, PWC-15(Radeon) (3.4/3.9)
ANSWER 9.03 (2.00) a) If the head is unbolted, a RCS pressure of s 100 psis is sufficient to i provide the relieving capccity of a PORV (+1.0) b) Gives sufficient time for an operator (appro: 10 minutes) to rerpond
, in case a nelfunction resulting.in mc: charging flow from one Che pump. (+1.0) l REFERENCE t Surry ND-93.3-LP-6, pp S.9/11 010/000; PWG-5(2.9/4.1)
ANSWER B.0a (1.50)
- a. record this on the critique sheet and initiate procedure deviation (+.5)
- b. Submit PT critique sheet (+.51 a ri d complete the Scheduling Data Sheet noting reason for non-completion (+.5, REFER [NCE North Anna Adtin 11.2 p 10 Surry ADM-99 pp 13 PWG-1(Operator Responsibi;ity during Tests / Maintenance) (3.5/3.9)
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C REFERENCE Surry TS 3.7.21 016/0007 PWG-5(2.7/3.5)
ANSWER 8.02 (1.00)
(b)
REFERENCE EPIS 3.02 anc 3.03.
PWG-36' E ;1an (2 9/a.7) i l
At!SWER R.03 (1.00) e ANSWER 9.04 (1.00) b REFERENCE Surry Stm ri : . n g Drder I4 PWG-7(3.5/4 )
ANSWER 8.01 (1.00) l b REFERENCE l Sorry ADM 29-1, pp 24 l PWG-23(2.8/3._)
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(1) lock.ed closed and under administrative control (4.5)
(2) under cdmin control and ceceble. of bein: closed i m m e d i e t e l v, (+.5)
(3) Olind flanges installed where required (+.25)
(4) Access hatch is properly closed / sealed (+.25)
(5) One door in air lock is closed / sealed (+.25)
(6) Operable or locked closed under admin control (+.5)
(7) Uncontolled CNTMT leak age TS is satisfied (+.25)
Svery TS 1 0.4/1.0.5 r_PE-069; PWC-5(3.3/4.0)
Rc J-cR=_Nr= m_
VG, TS, p 3/4 6-11 VG, ROLP, 97.
ANSWER S.07 (2.50) a) Yes (+.5) o over e"cursion #ran low pouer (+.5) b) No / +.5) e) Yes (+.5) Los cf Heat Sink [f.I)
RECERENCE Surrv 'S 2.3 012/000' PWC-5(3.2/4.0) l l
t ANSWEP 3.00 '1.50)
Mri>tenance c e rft b e perforned (+.5) TS 3.10.6 :pp2ies (+1.0)
RECE9ENCE l
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IR-2
- c. r, - .+
b) Yos (+,5) TG 3.7.C applies (+.5)
ANSWER E 1^ t .50) 30 (+.5)
REFERENCE S u r r y E c'E T 5.03, pp i PWG-36 (2.0/4,7)
ANSWER 8,11 (1,50) c) Shift Superviser cod c licensed SRO (+1.0) b) renp! oracedure Deviation (+.25 ma)
C'e r m : Request to Change Procedure
- .c_ c. r_ o c_.ey iscue l 4) The entrance is guarded while area i s, occupied (can be locked if 93reus is not hindered) p e_ r c R c N C e-Surry HP Manual 2-12, pp 3/a PWC-15(Radeon) (3,4/3.9) i L
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(17) _
Turbine Building (2) (+,25 ea)
Avniliery Buildiig ( 1.' _
Service E' u i l d i n- a (1)
Condensate Polish:ng Building /2)
Outside (1)
Appendi:, C' (1)
REFERENCE Surry ADM-29.1, pp 11 PWG-23(2.8/3.5) i ANSWER 3.14 (1.00)
I l 3 operat:ans (includes .he r>cene leader) and 2 securit> (+1.0)
RECE;:ENCE l
l Sorry ADM-29.2, pp id PWG-19(3.4/4.2) l ANSWER 9.15 ': .50)
- 1) Suffic:ent cariccity in d:i tenk (290 gel),
'+.25 es) 2' o r' - s ' t e supply (35,00n gal)
- 3) 2 0:ernble ruel floupethe
- 4) EDO D :, t t e r y oper4 510
- 5) EDG Charger o p e r -2 b l e
ps_. .
- -r ,
burry la a . ., 6 064/050; PWC-5(3.1/0,1) l l
- 8800, UNITED STATES
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'3 . ADMINISTRATI'/E PROCEDURESr CONDITIONS, AND LIMITATIONS c' AGE 11 ANSWERS -- SURRY 122 -96/07/21-DEAN, W M ANSWER S.16 (1.50)
Control R o o :a Operator (+.5 ea) ,
Instructor with c NRC license / certification Treinee dA8/#A'7 J
6%. Irttm
- a. E c. r r- o. r Nu- or Surry E'r 5.9 PWC-36 (2.9/3.7)
ANSWER B.17 (1,00)
- 1) S e c;v e n c e of events reco*dar (+.25 es for any 4)
- 2) P-250 olarm Typewritar
- 3) Strip Cherts
- 4) Loqs
- 5) Completed Pre.:edures
- .wi c e r/w R. r N-umr
m Surry ADM-14, A t t. c c h n e n t E' oWG-2G(2.9/3.5)
ANSWER 6.1E (2.00) a) If the head is undo 1*,cdr a RC3 pressure of 100 psig is sufficient to c" ovide the relieving cepacitt o# ' PORV (+1.0)
- 0) Gives suffic;2n* time t' o r cr 2;.erator (appro: 10 minutes) to respond in c a t.e c c.lfunction r o ': v ' t I n g in na charging flow fenn one Chs p u r. p . (+1.0) o, c .r .-r o, r.. e.s v ..r
- 3. . p p y ug o3,3.
3-6, ?p 6.9/11 010f000; PWG-5(0.0/4.1 1
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- 8. ADMINISTRATIJE PROCEDURES, CONDITIONSr AND LIMITATIONS PAGE 1.2 ANSWERS -- SURRY 122 -86/07/21-DEAN, W M ANSWER 8.19 (1.50)
- a. record this on the critique sheet and initiate procedure deviation (+.5)
- b. Submit PT critique sheet (*.5) and conplete the Scheduling Data Sheet noting reason for non-completion (+.5)
REFERENCE North Anna Admin 11,2 p 10 Surry ADM-89, pp 13 DWG-1(Operator Responsibility during Tests / Maintenance) (3.5/3.9)
ANSWER 8.20 (1.25)
- 1) ' 3 pcm/deg at less than 50% (+.5)
- 2) linear decrease from 3 to O p e n, / d e g as power goes f r o n. 50-100% (+.75)
REFERENCE Sorry TS 3.1.1E 001/050; PWG-5(2.9/4.3)
ANSWER 8.21 (1.00)
Turn on radios or TV sets to the Emergency Droadcast System (+1.0)
REFERENCE Sorry EP, pp 4.42 PWG-36(2.9/4.7)
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1 U. S. NUCLEAR REGULATORY CCMMISSION REACTOR OPERATOR LICENSE EXAMINATION ACILITY: SUPRY 1&2 REACTOR TYPE: PWR-WEC3 DATE ADMINISTERED: 06/07/21 EXAMINER: DEAN, 9M APPLICANT
- _--_----_--___-----______
INSTRUCTIONS 10 APPLICANT:
Use separate paper for the answers. Write answers on one side only.
Staple question sheet on top o' the enswer sheets. Doints for each question are indicated in parentheses nr+er the question. The passing .
3rcde requ2res at leest. 70*. in e c c L, category and a finc1 grade of et least 30%. Enamination , apers will be pick ed i,, s:
- > (6) hours aftur the eaamination starts.
., ,c CATEGORY
- Or APPLICANT'S CATEGORY VALUE "0TAL SCORE VALUE CATEGORY gg y--- -- -- ----_------ -------- --_---__--------------------____---
- 1. ORINCIPLES 0~ NUCLEA: c'0WER PLANT OPERATION, THERMODYNAMICS, I 4 EAT iRANSFEP AND rLUID FLOW 31.o--
cf'qn
~ ~
-_-------__ -------- 2. PLANT DESIGN INCLUDING SAFETY
! AND EMERGENCY SYSTEMS I 29 0
~)
- f*,
- 3. INSTRUMENTS AND CONTROLS y --- ------ --_------- --_-____
l
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7' a. PROCEDURES - NORMAL 7 A E:MO RM A L r EMERGENCY AND RADIOLOGICAL CONTROL i lit OO ~
_ r 100.00 TOTALS FINAL GRADE _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _:.
All work done on th:s e n a c. i n a t :. a n is ny own. I have neither given no* received eld.
APRLICANT'S SIGN ^'JRE
- - -- . .m. _ . _ _ _ _ _
thz pa%, UNITED STATES
~94 ~ NUCLEAR RECULATORY COMMISSION s % #o&
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- 1. PRINCIPLES OF NUCLEAR :0WER ;'LANT OPERATIONP C' A G E 2
~~~~;sisF557sEREC57 PEET~iEEssFis K65 FEUIDFECE OUESTION 1.0; (1.001 Which of the following statc tot- concerning *.he i's e of water as the
'i: O d e ' ; t O Is Correet9
- 3. W a t *3 r h3d a UICU scat +2"'ng cross-sectionP a LOW 3bsorption c r e s t - c e c t i o r. . end a LeR9E energy decrement p e '. ecilicion,
- b. Water has a '_ C W 3C5ttering cross-section, 2 UICH absorption cress-Eectiont 7: n d C LARGE energy decrenent per cellision.
- c. Water has a HICH scattering Cro3S-seChionf a :_0 N Ibsorption cruEr -sec t1 Drt ? and E SMALL en9rgy decrenent per Coll.Slon.
- d. Water has a LOW scattering cross-section, a HIGH absorption cros section, and c S M A '_ : energy decrement per collision.
I OUESTION 1.02 (1.00)
- odo WO.
Which of the followin: c" .
,em (we attached .emce) ~ reoresenting Xenon cencentrat:on 2s corr- _ 'or the c ven tower hister")9
)
QUESTION 1.03 (1.00) l A r e a c *,o r has Seen operating t #i ..' l l :owar for three nonths when a nanual reactor trip cceuru. All svstent ere operctional and the steam dumps are tuediately c, laced in the tean presso'e control mode. Ten minutes after the reacter trip. ell RCR t are tripped. Twenty ninetet -#ter the recctcr t r i.a , Lcop 1 0"P is iogged s momentertly. Which set of traces (2 - d) on figure i 174 moct c1csely represents the previoucly described events' OUESTION 1.04 (1.50)
An estimated critical boron concentrat ion of 075 cm n was cal:viated ,r usinq ~
the in#ornetion o r. the etteched date cheet and the reactor reached s critical condition 3t 153 steps on Bank D with Tavg of 547 degrees. How j
would the Bank D od position di#for lf the conditions uset in this calculation we"e different as given below? Assume no boron changes and f consider each condition ,epErately, a) tower level at shutdown was 75% equilibrium bi Time since shutdown wen 15 h o u r t:
c) Averaae RCS t e m r. e r a t u r e was 532 decrees - P
- CATEGOO 01 CONTINUED ON NEXT PAGE tror)
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! 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATIONr PAGE 3
~~~~55E55667U555CEI~5E5T~TRd55EER~5U6'ELU5D'E[6U QUESTION 1.05 (1.00)
A Centrifugal Pump is started up with its discharge valve open. How would the following parameters differ (INCREASER DECREASE or R_EMAIN THE SAME) if the pump was started with its discharge valve chut?
a) Motor current b) Discharge pressure Z TC OUESTTON 1.06 -
_ T-For each of the #ollowing sets of conditions EXPLAIN which one would result in the g r e z:t e s t reactivity change due tc control rod insertion.
Note
- Assume 100% powerr 3ank D at 220 steps? SQL.
- a. An crea of high relctive flu > vs. low relative flux.
- b. Edge of the core vs. middle of the core.
- c. Rod 11 (inserted) vs. rod 12 inserted beside rod fl.
QUESTION 1.07 ( .50)
Attached is a curve showing the moderator to fuel ratio vs. deff with the optimum point identif ied. This is the point when the Moderator T ert pe r atur e coef ficier t would be just.nero. If we were to add boron how would the optimum peint-shift on this curve?
QUESTION 1.08 (2.00)
List the four factors that cause the Ocppler Power Coefficient to change over core life and indicated whether each of these factors make the Doppler Power Coeff:cient MORE or LESS NEGATIVE.
QUESTION 1.09 (2.00)
Aside from heat generation rate and bulk fluid temperaturer list 8 factors which would cffect c'eak Centerline Temperature of a fuel pellet. (These factors consist of des:gn and naterisi propertiew as well as some factors which may becone an effect es the core ages.) Do NOT discuss changes to these # actors over core life.
( * * * * :t CATEGORY 01 CONTINUED ON NEXT RAGE *****)
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- 1. PRINCIPLES OF NUCLEAR POWER DLANT OPERATIONr PACE 4
~~~~ tress 507sEsiCs? sEEF TEsssFEE Eso FLui5 FE5s I
l QUESTION 1.10 (1.50)
- Describe the effect the production of ou-239 has on Beta effective and why this change. occurs?
QUESTION 1.11 (1.00)
The reector is operating at 100% power with all rods oute near EOL with i equilibrium Xe on conditions when power is to be reduced to 50%. The operator observes that AFD is within its band and decides to lower power by borating, leaving rods in the ARO position. Actuel Tavs follows programmed Tav3 Describe the change that will occur in AFD and why it occurst prior i to changes in Xenon having e noticeable effect.
QUESTION
+kt 1.12 (7 /*0 0)
List y reasotig why 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> was established as the time period in which swapover from cold les recirculation to hot les recirculetion should occur.
QUESTION 1.13 ( 1.00)
Civen that a battery capacity is ;650 ampere-hours. EX? LAIN the term
- a nip e r e-h o u r ' .
l QUESTION 1.14 (2.50)
)
- How does each of the following parameter thenges a f' f e c t the DNBR (INCREASE, DECREASE or REMAIN TPE SAhE)' B' 'Cly explain your answers and
[
DON'T consider the transient effects.
f a) D"essurizer Temperature INCREASES 5 degrees (1.0) b )- Mass flow rate in the core INCREASES 10% (1.5) 00ESTION 2.15 (0.00)
Lict three parameters which +he operator can try and maintain uhich will help support the netural cireviction process. Include the rpplicable setpoints and briefly state how maintalging these parameters nelps ensure natural circulation.
?o*** CA'IGORY 01 CONTINUED ON NEX' 04GE m **)
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT GPERATION, PAGE 5-
--- isEEs557sEsiEE- REEi TEss5 FEE Es5 FE5i5 FE5E QUESTION 1.16 (1.00)
What characteristic shape should a inverse multiplication plot (1/M plot) have during fuel loading when the fuel is loaded so that the distance between the detector and the fuel steadily decreases? A sketch is sufficient to answer this question.
QUESTION 1.17 (1.50) a) What is meant by 'k excess? (0.5) b) Name 4 core t r a ns i e n t s / c ha rise s which create reactivity changes that
'k excess' helps to negate?
00ESTION 1.16 (2.00)
Unit 1 has just restarted following a refueling outage while Unit 2 is near EOL. Answer the following regarding the differences in plant response between the two units (explain your answers)*
a) At a steady power level of 10EE(-8) amps during a startup, equal reactivity additions are nade (approximately 100 pcm). Which Unit will have the LOWER steady state startup rate?
b) At 50%' power, a control rod (100 pcm) drops. Assuming NO RUNBACK or OPERATOR ACTIONr which Unit will have the HIGHER steady state Tavg?
GUESTION 1.19 (1.00)
Place'the #cllowing descriptions of the gradations of 2 phase flow in a reactor coolant channel into order from least to nost severe.
- 1) Slug low-
- 2) Annular Flow
- 3) Bubbly Flow
- 4) Mist Flow
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 6
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~~~~YUEkkUbE5d5565 ~5EdT IE5UEF55~d U~FLUEU~EL50 k
-QUESTION 1.20 (1.00)
The pressuriner 'A' PORV partial ~1y opens to a throttling position during operations at 85% power. Assuming Guench Tank pressure is 20 psia and saturation conditions in the pressuriner correspond to 2240 psia, what L is the quality of the steam on the downstream side of the PORV? Show all calculations.
QUESTION 1.21 (1.50)
The reactor is producing 100% rated thermal power at a core delta T of 60 degrees and a mass flow rate of 100%, when a blackout occurs. Natural
! circulation is established and the core delta T goes to 35 de3rees F.
If decay heat is 3%, what is*the core mass. flow rate in %?
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(***** END OF CATEGORY 01 *****)
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- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 7 GUESTION 2.01 (1.00)
Which valve listed below is used to throttl.e auxiliary spray t' low?
- a. FCV-122 (Charging FCV)
- b. PCV-455A (Spray valve # rom Loop A)
- c. P C V-45 5E: (Spray valve from Loop C)
- d. HCV-311 (Avuiliary Spray Valve)
- e. You cannot throttle auxiliary spray GUESTION 2.02 (1.00)
Which of the following. describes the purpose of the J-tubes which have been recently installed on the S/G feed rings?
- a. Provide even- flow distribution of feedwater around the downcomer,
- b. Prevent.the introduction of debris in the feedring from clogging the path to the S/G.
- c. Allow entra pre-heating of feedwater by recirculation flow before the feed enters the downcomer region of the S/G.
- d. Prevent water hammer due to steam condensation in the feed ring if a loss of feed were to occurr then reinitiated.
QUESTION 2.03 (1.00)
Which statenent below regarding reactor breaker shunt trip coils is right?
- a. They do NOT receive e trip signal when e manuel reactor trip is actuated.
- b. They can NOT be trip tested separately from the undervaltage coils
- c. They cre DEENERGIZED to trip.
- d. Receive auto trip signal throV3h the auto shunt trip coil circuit.
(r***8 CATEGORY 02 CONTINUED ON NEXT PAGE *****)
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, 2. PLA'NT. DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS oAGE O l
! GUESTION 2.04 (1.00)
Wh'ich of the following describes the' basic flowpath through the Hydrogen {
i Recombiners?
! a. Mining chamberr_ pre heater, recombination region
- b. . Mining chember, recombination region, heater section
- c. Pre heater, recombination cesion, mining chamber ;
j d. Pre heater, mining chamber, reconbination region
.. Pre heaterr mining chamber, heater section 4
GUESTION 2.05 (1.00)
- . Which of the following describes the correct effect of an SI initiation of the operation of the Component Cooling Pumps?
, a. The pumps will start as soon as its bus is energized.
- b. The pumps will start 60 seconds after the SI and can be manually started if needed before .that time.
c.- The pumps will receive a start inhibit signal for 60 seconds and then must be manually started. j
- d. The pumps will auto start after 60 seconds and are locked out from manual start ent:1 that time.
-GUESTION' 2.06. (2.00)
(_ For the following components, indicate whether they ~eceive an GPENr CLOSE l or NO SIGNAL upon a Manual SI initiation:
a) Control Room Supply and Exhaust Ducts b) SI Ar:cumulatcr Discharge Valves L c) Main Steam Isolation Valve:
d) RWST tc LHSI Pump Suction .ves e) Seal Water Return Isolatic 31ve f) Component Cooling Water Isc tion Valve from RHR
- 3) Component Cooling Water Isc . ion Valve from Letdown Hxer '
h) Steam Supply Valves to Turt ae Driven Feed Pump (x**** CATEGORY 02 CONTINUED ON NEXT PAGE xxxxx)
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- 2. PLANT DESIGN INCLUDING SA;ETY AND EMERGENCY SYSTEMS PAGE 9 GUESTION 2.07 (1.50)
Indicate what automatic actions, if any, occur when high level alarns are received on the following process radiation nonitors' a) RM-GW-102(Plant Vent Gaseous Activity) b) RM-RMS-162(Menipulator Crene Area Monitor)
QUESTION 2.05 (1.50)
- a. Which component (s) of the Control Rod Drive Mechanism act as the pres-sure boundary between the RCS and the Containment atmosphere? (0.5)
- 6. Enplain why the stationary coils for the CROM are supplied with TWO DC voltages. (1,0)
QUESTION 2.09. 43 00)
Indicate what happens to the Rod Control System (rods inr rods cut, no change) and E:R IEF L Y explain uhy the change will or will not occur for the following conditions. Rods are in auto snless otherwise specified.
- c. Reactor power is 1 7"' whcn the controlling turbine first stage impulse pressure transmitter falls high.
- b. Reactor power is 1007. and loop 1 That fails high.
- c. Auctioneered high nuclear power is 50%r Rod Control is in manual.
Instrument test;ng i: in progress on the turbine power input to rod control which has turbine power at 100%.
All indicetions have been stcble for the last hour.
The 9ank Selector switch is then placed in AUTO.
QUESTION 2.10 ( .50)
What is the source of power for the automatic field flash of the energency diesel generntors?
(***** CFT _ GORY 02 CONTINUED ON NEXT c' A G E ****x1
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- 2 .. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY _ SYSTEMS PAGE 10 QUESTION 2.1'1 (l'.00) j What is.the Main design purpose of the flow restricting no :le in the l
Mcin Stean Lines?
i GUESTION 2.12 (2.50)
I Describe _the sequence of events that occur once a valid RMT swapover. signal 4
is initiated. Include any ' applicable time delays or interlocks and the indications on the control board of swapover status.
QUESTION 2.13 (1.00:
~
Fill-in the blanks to correctly complete the following statement regarding i the recirculation systems:
l The ______ recirculation pumps can be stopped by placin3 their initiation, but the control switch to LOCKOUT reci.reviation. pumps with cana NOT
______be stopped until ______is______.
l 4 GUESTION 2.14 ( .50) 4 i The 4160 MV Stub E:Uses supplied from the H and J buses will deenergine
?
when what condition occurs?
- QUESTION 2.15 (1.00) a) Why will a loss of vital bus 1-I not require a reactor trip, while 4
a loss of any of the other three will?
b) Which two vital buses use a Sola Transformer _to supply them 120 VAC? !
4 i GUESTION 2.16 (1.50) ,
i
! List the 5 sources of water to the AFW system in order of preference.
I <
(***** CATEGORY 02 CONTINUED ON NEXT PAGE"*****) !
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- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 11 QUESTION 2.17 (1.50)
Describe what causes 3 'Hard Bubble" in the pressurizer during normal 1
plant operations and how this affects the reactor on plant transients.
QUESTION 2.18 (2.00)
Consider the following situation: UNIT 1 is at 5% and each of the loop temperatures are equivalent. (ie. each S/G is receiving the same heat input) The level in 'A' S/G is several inches higher than 'B' andC' S/Gs, causing these two E/Gs to steam off more quickly resulting in their levels lowering. Discuss how the feedwater controls should be operated to restore all S/G levels (magnituder direction, parameters observed, what feed flow'is compared to) to correct levels.
QUESTION 2.19. (2.00) l List 5 parameters associated with the RCPs which are monitored after starting a RCP cs stated in OP-5.2 'RCP Operation'. Provide the required minimum values.which must exist, if applicable.
I QUESTION 2.20 (3.00)
- a. After a valid SI initiation signal has been generated which 9HSI pumps shoulc be operating? (assume all pumps' power supply from normal source) (1.0)
QUESTION 2.21 (1.50)
Describer in order, the actions that are required to locally reset the AFW overspeed trip-throttle valve. (1.0).
l QUESTION 2.22 (1.00)
. Describe the operation of the Emergency Diesel motor driven and attached p fuel pumps. Include in your discussion flow paths and ranges of operation.
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! (***** END OF CATEGORY 02 *****)
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' 00ESTION 3.01 (1.00)
Which of the following is NOT.a function of the P-4 permissive (trip and bypass breakers oPen)?
! a. Allows bypassing of steam dump cooldown interlock.
i
- b. Allows operator block of SI signal.
- c. Causes feedwater i solation- if low Tavs is also present.
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- d. Causes a turbine trip.
i
- -QUESTION 3.02 (1.00)
What set of_ signals below are sent to the Reactor Protection System to
, indicate a Turbine Trip?
- a. Stop valves closed & Auto Stop Gil pressure.1ow
- b. Stop valves closed & EHC Pressure low 4
- c. Governor valves closed a auto Stop Oil _ pressure low f d. Governor valves closed & EHC pressure low 1
i DUESTION 3.03 (1.00)
Which of the following will result in a higher output from the Variable Gain Unit of the Rod Control System?
a.' A LOWER power level se'nsed by NI-44
- b. A LOWEF. Power level sensed by Turbine Impulse Pressure .
- c. A HIGHER power mismatch erro.r sianal
- d. A LOWER power _ mismatch error signal l
- e. A HIGHER ( T r e f-T 'a v s ) error signal I
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- 3. INSTRUMENTS AND CONTROLS PAGE 13 DUESTION 3.04 (1.00)
Which one of the following malfunctions could cause one of the over tempercture delte T trip bistables tc trip?
- a. Controlling turbine impulse pressure channel " ailing low.
- t. Power range N43 lower detector failing low,
- c. Peactor coolant flow detector failing low.
- d. Controlling pressuriner level channel failing low.
QUESTION 3.05 (1.00)
Indicate whether the following siti.iations would cause the steam dunp system to ARM ONLY, ARM E ACTUATE or HAVE NO EFFECT:
a) PT-447 (1st stage impulse pressure for load reject ~ signal) fails LOW, Mode Control in Tavs moder Tref '
Tave by 6 des C.
b) Turbine Tripsy Mode Control in Tavs moder Loop 4 Tavs fails HIGHr the Steam Dump Control Select switch is HELD in the " Bypass' pocition QUESlION 3.06 (1.50)
Using the attached drawing of +he CVCS system, indicate whether the following velves receive an OPEN, MODULATED or CLOSED signal for the given makeup mode selector switch positions, c) 114A in AUTO b) 1138 in DILUTE l
c) 1140 in ALT DILUTE d) 1148 in BORATE f e) 113A in MANUAL l DUESTION 3.07 (1.00)
Explain why the load shedd' 3 feature associated with a degraded or undervoltage c o n d i t i o r- .c de r eetec efter en Emergency 4160 VAC Bus is isolated fron the r >erve Station transformer and the diesel output breeker closec
( v :r * * :* CATEGORY 03 CONTINUE 0 ON NEXT RAGE * * :r * * )
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- 3. INSTRUMENTS AND CONTROLS PAGE 14 GUESTION 3.08 .(1.50)
Describe how the High Steam Line Flow SI input varies and the par' meter o rt which this program is based.
QUESTION 3.09 (1.25)
Fill in.the blanks below in the statement regarding Nuclear Instrumentation requirements for critical operations
- The minimum number of operable Power Range instruments to proceed to critical operations is _____. It is required that _____ Intermediate Range channel.(s) be operable unless _____ of _____ Power Range channels indicate (s) S _____% full power.
. QUESTION 3.10 (2.00)
, List all the signals that automatically reposition / shut the following valves associated with the CVCS. (Assume control switches in remote / auto) a) Orifice Isolation Valves (HCV-1200A, 9, C) b) Letdown Trip Valve (TV-1204) c) Letdown High Temperature Divert Valve (TCV-1143)
GUESTION 3.11 (1.00)
Describe all the conditions that must.be met fer RMT (Recite Mode Transfer) eutomatic swapover to the recire mode following an SI. Include any. logics or setpoints.
QUESTION 3.12 ( .50)
What is~the input that is used to generate the level program-signal for the S/G 1evel control system?
QUESTION 3.13 (1.00)
What are the two conditions which will cause the Turbine Driven Auniliary Feed Pump to Auto Start? Include appropriate coincidences.
(****< CATEGORY 03 CONTINUED ON NEXT PAGE xx***)
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Whatsare the two inputs id.to the Overpressure Mitisation. System and how
. what.-two alarms are associated with them? (setpoints not required)
QUESTION '3.15 (1.50)
~
List the 6 outputs of-the Auctioneered High-Tavs control circuit.
QUESTION 3.16 (1.00)
. Aside<from a loose printed cir'cuit board card,. list 4 distinct causes of an " URGENT FAILURE' in the Power Cabinets of the Rod Control System.
QUESTION 3.17 (1.00)
~ ~
What are the 2-inputs into the Rod Insertion ~ Limit (RIL) circuitry?
GUESTION 3.18 (2.50)
' List'!the 3 blocks associ'ated with SI actuation signals. . Include when and how these blocks can.be-initiated and any~ required coincidences /setpoints.
-QUESTION 3.19 (2. 00)-
List ~eight different parameters which are capable of beins monitored on the Remote Monitoring Panels (PNL-REM and ASC-RMP).
LGUESTION 3.20 (1.00)
The. controls on the Emergency Generator Isolation Control Panel (ICP) are essentially the same as those found on the Emersency. Generator Control Panel (CP), except for 4 important ~ controls. List these four significantly different switches found on.the EDG ICP and not on the EDG CP. (Note' some of-these switches perform a similar function)
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
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.0UESTION 3.21 (1.25)
The Detector Current Comparator r.eceives input fromuall 4 upper and lower
- ' pous- range detectors. . How.are these inputs compared, what is the alarm.
i s~troint and when is this circuitry in operation?
l ' QUESTION 3.22~ (1.00) i With the pressurizer level control selector switch in position III/II, .
j- an instrument failure causes the following plant events in sequence
.(Assume no. operator actions taken)*
~
- 1. Char 3ing flow reduces to minimum' !
j 2. Pressurizer level- decreases
- 3. Letdown secures and heaters deenergize
- 4. Level increases.until high level trip p
-Which instronent failed (II or III) and in what direction did it fail? !
i OUESTION 3.23 (1.50) i .
l a). While at power with no rod motion in progress, an.IRPI deviates 15 steps i from its bank averase. What annunciator will actuate? (0.5) b) If rod motion were in progress in the above situation, would this-j annunciator alarm? Explain your answer. (1.0)
} OUESTION 3.24 (1.50) ,
1 Describe the operation of the 4160 VAC Emergency Bus Degraded Voltase [
l Protection System. Include in your discussion coincidences, setpoints and. ;
f any time delays that apply.
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(***** END OF CATEGORY 03 *****)
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- a. PROCEDURES - NORMALr.ABNORMALr EMERGENCY AND PAGE 17
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GUESTION 4.01 (1.00)
_On a . loss of condenser vacuum where vacuun -is greater than 20' Hg and
-decreasing, which of the following is NOT an immediate action?
a, Place an additional set of air ejectors in operation.
- b. ' Start a Hosser,
- c. Start an additional Cire Pump,
- d. Reduce turbine load.
- e. Start an additional condensate pump, if available.
i OUESTION 4.02 (1.00)
If a ' Rod Control Urgent Failure
- alarm occurs due to a failure in the logic cabinet, the Tave/ Tref mismatch is immediately. maintained by which of the following?
4
- e. controlling turbine load.
- b. tak ins manual control of individual control rod banks.
I c. taking manual control of individual control rod 3roups.
- d. bor.ation and dilution of the reactor coolant system.
QUESTION 4.03 (1.00)
Which of the following reasons correctly describes the basis for allowing RCP 'r e s t a r t . i rt E0P-FR-C.1 ' Response to Inadequate Core Cooling'.
)
- a. Helps to m i:: the SI flow to protect reactor vessel fran cold water.
- b. Once subcooling is established, restartins the RCFs helps to i collepse voids that may have formed in the reactor vessel head.
- c. Allows restoration of PZR pressure control usins normal sprays.
- d. Provides for cooling of the core when secondary depressurination does not alleviate inadequate core coolins.
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(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
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- 4. PROCEDURES - NORMAL, A9 NORMAL, EMERGENCY AND PAGE 18
~~~~E5656LUGEC5[~CU5TRUE~~~~~~~~~~~~~~~~~~~~~~~~
GUESTION 4.04 (1.00)
Which statenent below describes the AFW flow requirements following a reactor trip without an SI? (ie. your in EP 1.017 ' Reactor Trip Recovery')
- 3. Throttle flow if it exceeds 536 3pm.
b '. Throttle flow if a S/G level exceeds 9% level
- c. Throttle flow only-2f one or more Main Feed Pumps are running
- d. Throttle flow only if all S/Gs 9% level
- e. Throttle flow only if all S/G 9% level and flow exceeds 536 sem QUESTION 4.05 (1.00i Which of the f ollowing sta+ amer. ;s corTeerning cooldown during a S/G Tube Rupture (EP-4.00) is corr eto
- a. Cooldown is c .nmenced prior to isolating the ruptured S/G.
- b. Dorate the r S to Cold Shutdown conditions prior to cooldown.
- c. Cooldown r ce is limited to 100 deg/hr.
- d. RCS deptr,surination it performed concurrent with the cooldown.
QUESTION 4.06 ( .50)
TRUE or FALSE:
If on an SI, a containment spray pump CANNOT be started, the ' Response Not Obtained' step requires verification that its associated Chemicci Addition Tank MOVs (MOV-CS-( )03 A R C or 9 & 0) be closed.
QUESTION 4.07 (1.50)
Answer the following question- regarding E0P usage TRUE or FALSE:
a) If a Function R e s t o r :i t 2 c n Procedure (FRP) is entered due to en ORANGE Critical Safety C unctton (CSr) condition, and a HIG9ER priority ORANCE condition is encountered, the original TRD must be completed prior to proceeding to the newly identified FRP.
b) Unless specified, c tad need not be fully completed before_ proceeding to a subsequent step '-
long as that task is Progressing satisfactorily c) If a procedure transition occurs, any te@ s still in progress fran the procedure which was in effect need not be completed.
(it m CATEGORY 04 CONTINtJEO ON NEYT PAGE ** m )
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- 4. -PROCEDURES - NORMALr ABNORMAL, EMERGENCY AND PAGE 19
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QUESTION 4.08 - ( 1. 5 0 )
Complete the following' statement by filling in the blanks with the apptropriste numbers.
During a pressurized thermal shock condition, if RCS temperature decrease hasLexceeded period, then a _______ hour _______ degrees soak temperature in anymust
_______ minute be_ performed.
QUESTION 4.09 (1.00)
List the whole body administrative limits per calender quarter that can be achieved (a) without any additional approval and (b)- with the highest level _of approval.
'GUESTION 4.-10 (1.00)
What are the two criteria, as stated in OP-1.1, ' Unit Startup Operations",
that allow reactivity to be changec WITHOUT the shutdown banks "ully withdrawn?
GUESTION 4.11 (1.50)
On a reactor trip / safety injection, while performing the imnediate action steps of EP-1.00. you note that containment. pressure has e::ceeded 23 psia.
What are your actions / verifications (there are three)?
QUESTION 4.12 (2.00)
List the immediate action substeps that are required to complete the step to verify that the AC Buses are energized in EP-1.00.
I
(***** CATECORY 04 CONTINUED ON NEXT PAGE *****)
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~~~~EADf6L665 CAL 66 TEEL GUESTION 4.13 (2.00)
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' Answer .the fo110 wing questions regarding-a "Non-Recoveable Loss of Air'r AP-40, on Unit it a) What are the three conditions that.re. quire the RCPs'to be secured due to the loss.of Component Cooling?
b) Aside from the1RCPs, what 5 different pumps'(there may1be more than one of1a particular pump, eg. 3 charging pumps) are secured .-as part of :the-immediate actions?
QUESTION 4.14 (1.50)
Fill in the' blanks to correctly compl ete the statements regarding limits and' pre. cautions associated with the RCS and RHRS.
a) The maximum-temperature differential allowed between the pressurizer and the spray flow is _____ degrees F.
~
'b ) The maximum cooldown rate allowable while using the RHRS.is _____ des /hr c).. The reactor - must not begin producing reactor power until the H2 concentration is at least _____ ec/kg.
-GUESTION- 4'.15 (1.50)
-AP-16, ' Excessive Primary Leakage', identifies numerous methods by which RCS-leakage-may'be determined.' List 5 radiation monitor alarms which could be.. symptoms.'of RCS leakage. (Monitors that check for the same problem like~several ef. fluent line monitors count as one)'
.GUESTION 4.16 -(1.50)
List three administrative precautions that must be met to enter-a Locked High Radiation Area () 1r/hr).
QUESTION 4.17 (1.00)
List two different conditions when an Inverse Count Rate Ratio Startup is required.-
(***** CATEGORY 04 CONTINUED ON NEXT PACE *****)
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QUESTION 4.18 (1.00)
If control room evacuation was required due to a fire and you were unable to trip the reactor before you left (assume the plant is still operating at 50% power)r what are the required imnediate actions before reporting to the Auniliary Shutdown Panel?
OUESTION 4.19 (1.50)
Give the location of the following support centers that are manned during a plant emergency; a) Operations Support Center b) Technical Support Center c) E n.e r g e n c y Operations Facility OUESTION- 4.20 (1.50)
During a small break LOCA (SBLOCA)r it is required to trip the RCP if the trip criteria are met. If forced flow through the core promotes cooling, why are the RCPs tripped.
QUESTION 4.21 (1.50)
- a. While performing a step in a Periodic Test the operator finds a step he can't perform due to the plant status. What actions should the operator take to docunent this inability to perform a step?
- b. Due to plant conditions (e.g. mode in which system not required) the performance of a Periodic Test can not be conpleted. How does the operator decement non performance of the procedure?
DUESTION 4.22 . M N' N Describo the basic method by which the plant is shutdown from 2% power to hot s h u t rio u n . Include in your discussion the mode of rod control utilized and any indications that you are required to observe to ensure that the shutdown is progressing correctly.
(***** CATEGORY 04 CONTINUED ON NEXT PACE *****)
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- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 22
~~~~UdDE6EUUECEL~EUUTUEL~~~~~~~~~~~~~~~~~~~~~~~~
GUESTION 4.23 (1.00)
Explain why EP.-l.028, ' Natural Circulation.Cooldown with Void in Rx Vessel
- has you ensure PZR_ level is no greater than 30% pr2,r to initiating the cooldown and place the Par level control in manual.
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(***** END OF CATEGORY 04 *****)
(************* EtlD OF EXAMINATION ***************)
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Water Parameters Miscellaneous Conversions 1 gal. = 8.345 10m. I curie = 3.7 x 1010 dps 1 gal. = 3.78 liters 1 kg = 2.21 lbm 1 ft* = 7.48 gal 1 hp = 2.54 x 10 Btu /hr .
Density = 62.41 /ft3 1 m = 3.41 x 10 Btu /hr Density = 1 gm/c lin = 2.54 cm Heat of vaporization = 970 Stu/lem 'F = 9/5'C + 32 Heat of fusion = 144 Btu /lbm , 'C = 5/9 ('F-32,:
1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf 1 ft. H 2O e 0.4335 lbf/in.
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'[ Water Evsp Steam r,
Water A, A g. A, s, sg s, v, vg
-0.02 1075.5 1075.5 0.0000 2.1873 2.1873 at 32 0.08859 0.01602 3305 3305 3 00 1073.8 1076.8 0.0061 2.1706 2.1767 35 35 0.09993 0.01602 2948 2948 40 8 03 1071.0 1079.0 0.0162 2.1432 2.1594 40 0.12163 0 01602 2446 2446 45 13.04 1063.1 1081.2 0 0262 2.1164 2.1426 45 0.14744 0 01602 2037.7 2037.8 18.05 1065.3 1083.4 0.0361 2.0901 2.1262 to 90 0.17795 0.01602 1704.8 1704.8 28.06 1059.7 1087.7 0.0 M 5 2.0391 2.0946 50 60 0.2561 0.01603 1207.6 1207.6 38.05 1054.0 1092.1 0.0745 1.9900 2.0645 70 70 0.3629 0.01605 868.3 868 4 48.04 1048.4 1096.4 0.0932 1.9426 2.0359 80 90 0.5068 0.01607 633.3 633.3 468.1 58.02 1042.7 1100A 0.1115 1A970 2.0086 to 90 0.6981 0.01610 468.1 300 68 00 1037.1 1105.1 0.1295 1.8530 1.9825 100 0.9492 0.01613 350.4 350.4 77.98 1031.4 1109.3 0.1472 1A105 1.9577 110 110 1.2750 0.01617 265.4 265.4 87.97 1025.6 1113.6 0.1646 1.7693 1.9339 120 120 1.6927 0.01620 203.25 203.26 97.96 1019A 1117A 0.1817 1.7295 1.9112 130 130 2.2230 0.01625 157.32 157.33 107.95 1014.0 1122.0 0.1985 1.6910 1A895 140 140 2A892 0.01629 122.98 123.00 117.95 1008.2 1126.1 0.2150 1.6536 1.8686 150 150 3.718 0.01634 97.05 97.07 127.96 1002.2 11302 0.2313 1.6174 1A487 160 160 4.741 0.01640 77.27 77.29 62.06 137.97 996.2 1134.2 0.2473 1.5822 1A295 170 170 5.993 0.01645 62.04 130 50.22 148.00 990.2 1138.2 0.2631 1.5480 1A111 180 7.511 0.01651 50.21 1.7934 ISO 40.96 158.04 984.1 1142.1 0.2787 1.514S 190 9.340 0.01657 40.94 300 168.09 977.9 1146.0 0.2940 1.4824 1.7764 200 11.526 0.01664 33.62 33.64 178.15 971.6 1149.7 0.3091 1.4509 1.7600 210 210 14.123 0.01671 27.80 27.82 180.17 970 3 1150.5 0.3121 1.4447 1.7568 212 212 14.696 0.01672 26.78 26.80 188.23 965.2 1153.4 0.3241 1.4201 1.7442 220 220 17.186 0.01678 23.13 23.15 19833 958.7 1157.1 0.3388 1.3902 1.7290 230 230 20.779 0.01685 19364 19381 240 208.45 952.1 1160.6 0.3533 1.3609 1.7142 240 24.96S 0.01693 16.304 16.321 218.59 945.4 1164.0 0.3677 1.3323 1.7000 250 250 29.825 0.01701 13.802 13.819 228.76 938.6 1167.4 0.3819 1.3043 1.6862 260 260 31.427 0.01709 11.745 11.762 270 238.95 931.7 1170.6 0.3960 1.2769 1.6729 270 41.856 0.01718 10.042 10.060 ISO 249.17 924.6 1173A 0.4098 1.2501 1.6599 300 49.200 0.01726 8.627 8.644 250 259.4 917.4 1176.8 0.4236 1.2238 1.6473 290 57.550 0.01736 7.443 7.460 300 6.466 269.7 910.0 1179.7 0.4372 1.1979 1.6351 300 67.005 0.01745 6.448 280.0 902.5 1182.5 0.4506 1.1726 1.6232 310 310 77.67 0.01755 5.609 5.626 320 4.914 290.4 894.8 1185.2 0.4640 1.1477 1.6116 320 89.64 0.01766 4.896 340 3.788 3113 878.8 1190.1 0.4902 1.0990 1.5892 340 117.99 0.01787 3.770 1.5678 350 2.957 332.3 862.1 1194.4 0.5161 1.0517 360 153.01 0.01811 2.939 1.5473 380 2335 353.6 844.5 1198.0 0.5416 1.0057 380 195.73 0.01836 2.317 825.9 1201.0 0.5667 0.9607 1.5274 400 247.26 0.01864 1.8444 1.8630 375.1 400 806.2 1203.1 0.5915 0.9165 1.5080 420 30S.78 0.01894 1.4808 1.4997 396.9 420 785.4 1204.4 0.6161 0.8729 1.4890 440 440 381.54 0.01926 1.1976 1.2169 419.0 763.2 1204.8 0.6405 0.8299 1.4704 460 4663 0.0196 0.9746 0.9942 441.5 460 1204.1 0.6648 0.7871 1.4516 480 0.0200 0.7972 0.8172 464.5 739.6 450 566.2 7143 1202.2 0.6890 0.7443 1.4333 500 680.9 0.0204 0.6545 0.6749 487.9 500 687.0 1199.0 0.7133 0.7013 1.4146 520 812.5 0.0209 0.5386 0.5596 512.0 520 657.5 1194 3 0.7378 0.6577 13954 540 962.8 0.0215 0.4437 0.4651 536.8 540 6253 1187.7 0.7625 0.6132 1.3757 560 1133.4 0.0221 0.3651 0.3871 562.4 SCO 0.3222 589.1 589.9 1179.0 0.7876 0.5673 1.3550 580 580 1326.2 0.0228 0.2994 0.2675 617.1 550.6 1167.7 0.8134 0 5196 1.3330 600 500 1543.2 0.0236 0.2438 1.3092 620 0.2208 646.9 5063 1153.2 0.8403 0.46S9
$20 1786.9 0.0247 0.1962 540 0.1802 679.1 4 54.6 1133.7 0.8666 0.4134 1.2821 640 2059 9 0.0260 0.1543 1.2498 560 0.1443 714.9 392.1 1107.0 0.8995 0.3502 660 2365.7 0.0277 0.1166 1.2086 680 0.1112 758.5 310.1 106P.5 0.9365 0.2720 640 2708.6 0.0304 0.0808 0.0752 822.4' 172.7 995.2 0.9901 0.1490 1.1390 700 700 3094.3 0 0366 0.0386 0 1.0612 705.5 0 0.0508 906.0 0 906.0 1.0612 705.5 3208.2 0.0508 TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (TEMPERATURE)
A.3
Wolume. fi'/st, Enthalpy. Stu/tt Ent'opy 8tw/ b a F Ene rgy. 8 twAb Pre i 13mP yrster Evap Steam Water tvrp Steam Wett' Lvap 6 team Q:te' Steam
,, ,, ,, s, s. s, 4, 4, 4, ., ,,
0.01602 3302.4 3302.4 0.00 1075.5 1075.5 0 2.1872 2.1872 0 1021.3 Casa 6 0.0486 32.018 35.023 0.01602 2945.5 29455 3 03 1073 8 1076.8 0.0061 2.1705 2.1766 3A3 1022.3 0.10 0.10 13.50 1025.7 0.15 45.453 0 01602 2004.7 20047 13.50 1067.9 1081.4 0 0271 2.1140 2.1411 0 15 L3.160 0 01603 1526 3 1526 3 21.22 1063 5 1084 7 0 0422 2.0778 2.1160 21.22 1028 3 0.20 0.20 32.54 1032 0 0.30 64 484 0 0lf.04 1039.7 1039.7 3?.54 1057.1 1089.7 0.0641 2 016S 2.0809 0.30 72.869 0.01606 792.0 792.1 40.92 1052.4 1093.3 0.0799 1.9762 2.0562 40.92 1034.7 0.40 0.40 79.586 0 01607 641.5 641.5 47.62 1048 6 1096 3 0 0925 1.9446 2.0370 47.62 1036.9 0.5 0.5 85.?!S O01609 540.0 640.1 53 25 1045 5 1093.7 0.1028 1.9186 2.0215 5324 1038.7 0.6
's.,. 9.6 0.B . /.. .18866, 2.0083 58.10. 1043 3 . 0.7
- 0.7 .'" 190 09'- ' O.01%10.* 465 33'
' 466 94 58 to -1042 7 .4100 8s 94.38 0.01611 411.67 411.69 62.39 1040.3 1102.6 0.1117 1.8775 1.9970 62.39 1041.7 0.4 0.8 66.24 1042.9 0.9 98.24 0.01612 368 41 368 43 66.24 1038.1 1104.3 0 1264 1.8606 1.9870 0.9 0.01614 333.59 333.60 69.73 1036.1 1105.8 0.1326 13455 1.9781 69.73 1044.1 1A 1.0 101.74 2A 2.0 126.07 0.01623 173.74 173.76 94.03 1022.1 1116.2 0.1750 1.7450 1.9200 94A3 1051A 14147 0.01630 118.71 118.73 109.42 10132 1122.6 0.2009 1.6854 1.8864 109.41 1056.7 3.0 3.0 120.90 1060.2 4.0 4.0 152.96 0.01636 90 63 90.64 120.92 1006.4 1127.3 0.2199 1.6428 1A626 73.515 73.53 130 20 1000.9 1131.1 0.2349 1.6094 13443 130.18 1063.1 6.0 8.0 162 24 0.01641 61.967 61.98 138 03 996.2 1134.2 0.2474 1.5820 1A294 138.01 1065.4 6.0 6.0 170.05 0.01645 7.D 176 84 0.01649 53 634 53.65 144A3 992.1 1136 9 0.2581 1.5587 12168 14431 1067.4 7.0 3.0 182.86 0.01653 47.328 47.35 150.87 988.5 1139.3 0.2676 1.5384 1A060 15034 1069.2 E.0 9.0 189.27 0 01656 42.385 42.40 156.30 985.1 1841.4 0.2760 1.5204 1.7964 15628 1070.8 9.0 10 193.21 0.01659 38.404 3842 161.26 982.1 1143.3 0.2836 1.5043 1.7879 16123 1072 3 10 26.782 26.80 180.17 970.3 1150.5 0.3121 1.4447 1.7568 180.12 1077.6 14.696 14.696 212.00 0.01672 15 213.03 0.01673 26.274 26.29 181.21 969.7 1150.9 0.3137 1.4415 1.7552 181.16 1077.9 15 20 227.96 0.01683 20.070 20.087 19627 960 1 1156.3 0.335B 1.3962 1.7320 19621 1082.0 to 30 250.34 0 01701 13.7266 13.744 218.9 945.2 1164.1 0.36B2 1.3313 1.6995 2185 1087.9 30 40 267.25 0 01715 10 4794 10 497 236.1 933.6 1169.8 0.3921 1.2844 1.6765 236 0 1092.1 40 8 4967 8.514 250.2 923 9 1174.1 0 4112 1.2474 J.6585 250.1 1095.3 50 50 261.02 0.01727 60 292.71 0.01738 7.1562 7.174 262.2 915.4 1177.6 0.4273 1.2167 1.6440 262.0 1093.0 60 70 302.93 0.01748 6.1875 6 205 272.7 907A 1180.6 04411 1.1905 1.6316 272.5 1100.2 70 80 312.04 0.01757 5 4536 5471 232.1 900.9 1183.1 0.4534 1.1675 1.6208 281.9 1102.1 30 90 320.28 0.01766 4.8777 4.895 290.7 894.6 1185.3 0.4643 1.1470 1.6113 290.4 1103.7 to 100 327.82 0 01774 4.4133 4.431 298.5 888.6 1187.2 0.4743 1.1284 1.6027 2982 1105.2 100 120 341.27 0 01789 3 7097 3.728 312.6 877A 1190 4 0.4919 1.0960 1.5879 312.2 1107.6 120 140 353 04 0 01803 3.2010 3 219 325.0 868.0 1193 0 0.5071 1.0681 1.5752 324 5 1109.6 140 160 363 55 0 01815 2.E155 2234 336.1 859.0 1195.1 0.5205 1.0435 1.5641 335.5 1111.2 160 180 373 08 0.01827 2.5129 2.531 346.2 850.7 1196.9 05328 1.0215 1.5543 345.6 1112.5 180 200 351.80 0 01829 2.26S9 2.287 355.5 842.8 1198.3 0.5438 1.0016 1.5454 3543 1113.7 200 250 40097 0 01865 1.8745 1.8432 376.1 825 0 1201.1 0.5679 0 9585 1.5264 375.3 1115.8 250 300 417 35 0 038E9 1.5239 1.5427 394 0 808.9 1202.9 0.5ES2 09223 1.5105 392.9 1117.2 300 1.3255 409.8 794 2 1204 0 0 6051 0 890-) 1.4968 408.6 11IB 1 350 350 411.73 001913 1.3064 422.7 400 400 444 (0 0.0193 1.14162 1.1610 424.2 760 4 1204 6 06217 0 8630 1.4847 111E 7
.l.0318 437.3 767.5 1204.8 0.6360 0.8378 1.473F 435.7 1118.9 450 450 456 28 00195 1.01224 0 90787 0 9276 449.5 755.1 1204 7 06490 0 8148 1.4639 447.7 1118 8 500 500 467 01 00199 550
$50 476 94 00199 082183 0 8412 460.9 743.3 1204 3 06611 0.7936 1.4547 458.9 1118 6 0.74962 0.7698 471.7 732.0 1203 7 0.6723 0 7738 1.4461 469.5 11 t E.2 600 400 48620 0 0201 700 700 .503 08 0 0205 0.63505 06556 491.6 710.2 1201.8 0692R 07377 1.4304 4S8.9 1116.9 B00 51d 21 0 0209 0.54809 0.5690 509.8 689 6 1199 4 07111 0.7051 1.4163 506 7 1115.2 300 900 53195 0 0212 04796S 05009 526 7 669 7 1196 4 07279 06753 1.4032 5232 1113.0 900 1000 544.59 0 0216 0 42435 0 4460 542.6 (50 4 1192.9 0.7434 0 6476 1.3910 5306 1110 4 1000 0 4006 557.5 631.5 1189 1 0 757S 0 6216 1.3794 553.1 1107.5 1100 1100 55t 2c' O.0?20 0 37af.3 0 0223 0 34013 0.3625 571.9 613.0 1184 8 0.7714 0.5969 1.36S3 556 9 1104.3 3200 1200 1300 l 367.19 577 42 0 0227 0 30722 0.3299 585.6 544.6 1180 2 0.7843 0 5733 1.3577 580.1 1100 9 1300 598 8 576 5 1175 3 0.7966 05507 1.3474 592.9 1097.1 1400 ItCD 537 07 0 0231 0 270/1 0 3018 1500 596 20 0 0235 02b372 0 27/2 611.7 550 4 1170 1 0.8035 0 5233 1.3373 6052 1033 1 1500 2000 635 80 0 02* ? O16766 01883 6721 465 2 1133 3 0 862*: 04256 1.7881 662 6 10GB6 2000 010209 01307 731 7 3616 1093 3 C 9139 0 32&5 1.2345 116 5 1032.9 2500 2500 E'd 1 I O D2c4 300; 3000 0 0343 0 050/3 0 0850 8318 216 4 1070 3 0 9725 01801 1.1619 7828 973.1 Et 5 33 O 050d 906 0 0 906 0 1.0612 0 1.0612 875.9 875 9 37082 329B2 70: 47 0 0%)B O l
TABLE A.3 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (PRESSURE)
A.4
' hmperstce. F Abe prest 4:r> S00 600 700 800 900 1000 1100 1200 1300 1400 1500 (o to p) 100 200 700 e 0 0161 392 5 452.3 611.9 571.5 631.1 690 7 3 4 68 00 ll50 2 1195 7 1241.8 1288 6 1936 1 1384 5 (101 34) s 01295 2 0509 211L2 21722 2.2237 2.2708 IJ144 e 00161 76 14 90 24 102.24 11421 126 15 138 08 150 01 161.94 173 86 185 78 197.70 209 62 221.53 233 45 6 6 68 01 I14& 6 Iled 8 1241.3 1788 2 1335 9 1384 3 1433 6 1463 7 1534 7 1526 7 1639 6 1693 3 1748 0 1801
-(167.24) s 01795 1.8716 1.9369 1.9943 2 0460 2 0932 2 1369 2 1776 2 2159 22521 2.2866 2.3194 23509 2.3811 24101 e 00161 38 B4 44 93 51 03 57.04 6303 69 00 74 98 80 94 86 91 9287 98 84 104 80 110 76 116 72 30 6 68 02 1146 6 11937 1240 6 12W.8 1335 5 13840 1433 4 14835 1534 6 15866 16395 1693.3 1747.3 18:,3 4 (192.21) s 01295 1.7926 1.8593 1.9173 1.9692 2 0166 2.0603 2.1011 2 1394 2 1757 2.2101 2.2430 2.2744 2.3046 2.33 v 00161 0.0166 29 E99 33 963 37.985 41.956 45978 49 % 4 53 946 57.926 61 935 65 882 69358 73 833 77.807 16 6 68 04 168 09 1192 5 1229 9 1287.3 1335 2 1383 8 1433 2 1483 4 1534 5 1586 5 1639 4 16932 17472 1833 4 (213.03) s 0 1295 0.2940 1.8134 1.8720 1.9242 1.9717 2.0155 2.0563 2.0946 2 1309 2.1653 2.1982 2 2297 2.2599 2.2890 i e 0 0161 0.0166 22.356 25428 28 457 31.466 34 465 37.458 40 447 43 435 46 420 49 405 52.388 85.370 58.35 30 & 68 05 168 11 1191.4 1239.2 1286.9 1334.9 1383 5 1432 9 1483.2 1534.3 1586.3 1639.3 1493.1 1747A 1803 (227.96) s 0.1295 0.2940 1.7805 12397 1A921 1.9397 1.9836 2.0244 2.0628 2.0991 2.1336 2.1665 2.1979 2.2282 2.2 e 0.0161 0 0166 11.035 12.624 14.165 15 685 17.195 18 699 20 199 21 697 23 194 24 699 26183 27.676 2 40 6 68 10 168.15 1186 6 1236.4 1285 0 1333 6 1382.5 1432.1 1482.5 1533.7 1585.8 16388 1992 7 1747.5 1803 (267.25) s 0.1295 02940 1.6992 1.7608 1A143 13624 1.9065 1.9476 1.9860 2.0224 2.0569 2.0899 2.1224 2.1516 1.
e 0.0161 0.0156 7.257 8354 9 400 10 425 11.435 12.446 13.450 14 452 15.452 16.450 17A48 18.445 19.441 60 6 68 15 168 20 1181 6 1233.5 1283.2 1332.3 1381.5 1431.3 1481.8 1533.2 1555.3 1638 4 1692.4 1747.1 18 (292.71) s 0.1295 0.2939 1.6492 1.7134 1.7681 1A168 1A612 1.9024 1.9410 1.9774 2.0120 2.0450 2.0765 2.1068 2.13 e 0.0l61 0.0166 0.0175 6 218 7.018 7.794 S.560 9.319 10.075 10 829 11 581 12.331 13.081 13.829 14.577 to & 68 21 16824 269 74 1230.5 !?81 3 1330.9 1380.5 1430.5 1481.1 1532 6 1584.9 1638 0 1692.0 1746.8 1802.5 (312.04) s 0.1295 02939 0 4371 1.6790 1.7349 1.7842 1A289 1 8702 1.9089 1.9454 1.9800 2.0131 2.0446 2.0750 2.1041 e 0 0161 0.0166 0 0175 4 935 5 588 6.216 6833 7.443 8050 8655 9258 9260 10.460 11.060 11.659 100 6 68 26 1E829 2E9 77 I?? 7.4 1279.3 1329 6 1379 5 1429 7 1480 4 1532.0 1564 4 1637.6 1691.6 1746.5 1802.2 1.6510 1.70ES 1.7586 1.8036 1A451 13839 1.9205 1.9552 1.9883 2D199 2.0502 2.0794 (327.82) s 0.1295 0.2939 04371 e 0 0161 0 0166 0 0175 4 0786 4.6341 5.1637 56831 6.1929 6 7006 7.2060 7.7096 8.2119 8.7130 9.2134 9.7130 120 A 6831 168.33 269 81 1.6286 1224.1 1277.4 1328.1 1378 4 1428.8 1479.8 1531.4' 1583 9 1637.1 1891.3 17462 1802.0 (341.27) s 0.1295 02939 04371 1.6872 1.7376 1.7829 1A246 1A635 1.9001 1.9349 1.9680 1.9996 2.0300 2.0592 e 00161 0 0166 0 0175 3 4651 3 9526 4 4119 4 2585 5.2995 5.7364 6.1709 6.6036 7J0349 7A652 7A946 83233 140 4 68 37 168 38 269 85 1220 8 1275 3 1326 8 1377.4 1428 0 1479.1 1530 8 15834 1636 7 1990.9 1745.9 1801.7 (353 04) s 0 1295 0 2939 0 4370 1.6095 1.6686 1.7196 1.7652 1.8071 13461 1AB28 1.9176 1.950S 1.9825 2.0129 2.0421 i , 0 0161 0 0166 0 0175 3 0060 3 4413 3.8480 4.2420 4 6295 5.0132 5.3945 5.7741 6.1522 6.5293 '6.9055 7.2811 140 6 68 42 1E8 42 269.89 1217.4 1273 3 1325 4 1376 4 1427.2 1478 4 1530.3 1582.9 1636.3 1990.5 1745.6 1801.4 1.5906 1.6522 1.7039 1.7499 1.7919 1A310 1A678 1.9027 1.9359 1.9676- 1.9980 2.0273 (363 55) s 0.1294 0 2938 0 4370 e 0 0161 0 0166 0 0174 26474 3 0433 3 4093 3.7621 4.1064 4.4505 4.7907 5.1289 5 4657 52014 5.1363 6.4704 180 6 68 47 168 47 2009/ 1213 8 12712 1324 0 1375.3 1426 3 1477.7 1529 7 1582 4 1635.9 16e0 2 1785.3 1801.2 (373 Cal : C 1294 0.2938 04370 15743 1.6376 1.6900 17362 1.7784 1A176 1.B345 1.8894 1.9227 1 9545 1.9649 2.0142 e 0 01(1 0 0166 0 0174 2 3598 2.7247 3.0583 3.3783 3 6915 4 0008 4.3077 4.6128 4.9165 52191 5.5209 5A219 200 > 68 E2 10851 2C9 96 1210 1 12690 1322f 1374.3 1425.5 1477.0 15291 1581.9 1635 4 1689 8 1745.0 1800 9 (351.60) s 01294 02935 0 4359 1.5593 1.6242 1.6776 1.7239 1.7663 13057 1.6426 1A776 1.9109 1.9427 1.9732 2JD025 e OC161 0 01E6 0 0174 0 0166 2.1504 24662 2.6872 2.9410 3 1909 3 4382 3 6837 3 9278 4.1709 4 4131 4.6546 250 6 68 66 IE6 03 270 05 3/5.10 1263 5 1319 0 1371.6 1473 4 1475 3 1527.6 1580.6 1634.4 1688 9 1744.2 1800.2 1.5951 1.6502 1.6976 1.7405 1.7601 1.8173 1.8524 1.8d58 1.9177 1.9482 1.9776 (400 97) s C 1294 02937 04366 0 M67 e t00161 0 0165 0 0174 0 0186 1.7666 2.0044 2.2263 2.4407 2.6509 2 6555 3 0643 3.2688 3 4721 3.6746 3A764 300 A I 66 79 1 % 74 27u ld 375.15 1237.7 1315 2 1368 9 1421.3 1473 E 1526.2 1579 4 1633 3 1688 0 1743 4 1799.6 (417.35) s 0.1294 0 2937 04337 C5%5 1.5703 1.6214 1.6758 1.7192 1.7591 1.7964 1A317 12652 1A972 1.9278 1.9572 e 0 0161 0 0105 0 0174 0 0186 I.4913 I.7028 IE970 2 0332 2 2652 2 4445 2.6219 2.7980 2.9730 3.1471 332C5 350 m 68 92 1ES 85 270 2'. 375 ?! 1251 S 1311 4 1366 2 1419 ? 1471 6 1524 7 15782 1632.3 1C67.1 1742.6 1798 9 (431.73) o 0 1293 0 29 % 0 4357 0 5E',4 1.5483 1.6077 1.6571 1.7009 1.7411 1.7787 1.8141 1A477 12793 1.9105 1.9400 e 0 0161 0 0106 0 0174 0 0162 12841 1.4763 1 6493 1.8151 1.9759 21339 2 2901 2 4450 2.5997 2.7515 2.9037 400 e 69 05 16e47 270 33 37627 1245 1 1307 4 1363 4 1417.0 1470 1 1523 3 1576 9 1631.2 16362 17419 1793 2 (444 60) s 01293 02935 0 43t.t 05%3 1.528? 1.5901 1 6400 1 6850 1 7255 1 7632 1.79BB 1.8325 1A647 1.8955 1.9250 l e 0 0101 0 01 % 00174 0 01E0 0 9919 1 1584 1 3037 1.4397 1.5706 1 6997 1.8756 1 9507 2 0746 2 1977 2.3200 500 > 09 32 119 14 270 51 34 3R 1231 2 !?991 1357.7 l'12 7 1466 0 1520 3 1574 4 16291 1634 4 1740 3 1796.9
( (457.01) : 0 1297 L ma 0 4?M O ttto 149">l 1 % 93 10323 IES/8 If990 17371 1 7730 1.8069 12393 1.6702 1.8903 TABLE A 4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE)
A.5
, Ahip**st Tempe estve, I lbl*4 la (ut. temp) 100 200 300 400 600 600 700 000 900 1000 1100 3200 IE0 laDO 1500 o 0 0161 0 01W. 0 0174 0 0186 0 7944 09456 10726 1.1892 1.D006 14093 15160 I6711 I7252 18764 1.9309 880 6 69 58 169 42 270 70 375 49 1215 9 1790 3 1851 8 3408 3 3463 0 1517.4 15739 1627.0 1682 6 1738 8 1795 6 (48620)s 01292 0.2933 04h2 0 % 57 14590 1.6329 15844 1.6351 86769 3.71 % 3.7517 1.7859 I A184 13494 13792 e 00161 0 0166 0 0174 00186 0 0704 0 7928 0 9072 1.0102 1.1078 17023 1 7948 l.3858 1.4757 1 % 47 1.6530 700 4 69C4 169 65 270 89 37561 487 93 1781 0 1345 6 1403 7 1459 4 15144 1%94 1624 8 166b 7 17372 3794 3 (503C4)s 01291 02932 04%0 0 % 55 0 6609 1.5090 1.% 73 16154 1.6 2 0 16970 1 7335 3767b 1 800., 18)18 18617 e 0 0161 00166 0 0374 0 0186 0 0704 0 6774 0 7823 0 8759 0 963) 1 N70 11289 1.2093 1.28?5 13%9 1.4446 800 > 70.11 169 8'., 271.07 375 73 487.8P 1273.1 1339 2 33991 1455 B 1511 4 1%69 1622 7 167E 9 17b 0 1792.9 (5182.) . 0.1290 0 293C 0 4358 0.5652 0 6885 14869 15484 1.%B0 1.6413 16607 1.7175 17522 17851 18164 1.5464 e 0 0161 0 0166 0 0174 0 0186 0C?ad 05869 06658 07713 08504 0 92(2 0 99 % 10720 11830 1 2131 1.2625 900 6 70.37 170 10 271.2G 37534 487A3 1260 6 1332 7 1394 4 1452.2 1506 5 1%44 1620 6 1677.1 17343 1791 f.
(531.95) s 0 1290 0.2929 0 4357 0 5649 0 6881 1.4659 1.5311 1.5822 1 6263 1.6662 1.7033 1.7382 1 7713 16028 14329 l e 0.0161 0 0166 0.0174 0.0186 0 0204 0 5137 0 6000 0 6875 0.7603 0 8295 0 8966 0 9622 1.0766 1.0901 1.1529 4
3000 6 70.63 170 33 271.44 375.96 487.79 1249.3 1325.9 1389.6 1448.5 1504 4 1 % 1.9 1618 4 1675.3 1732.5 1790.3 (544.58) s 0.1269 0.2928 0.4355 0.5647 0.6876 1.4457 1.5149 1.5677 1.6126 16530 1.6905 1.7256 3.7589 1.7905 1.8207 e 00161 0 0166 0 0174 0.0185 0 0203 0 4531 05440 0 6188 06865 07505 0 8121 08723 05313 0 9894 1.0468 1100 6 70 90 170.56 271.63 376 06 467.75 1237.3 1318 8 1384 7 1444.7 1502 4 1559 4 1616 3 1673.5 1731.0 1769.0 (5% 28) s 0.1269 0.2927 0.4353 0.5644 0.6872 1.4259 1.4996 1.5542 1.6000 1.6410 1.6787 3.7141 1.7475 1.7793 1A097 e 0 0161 0 0166 0.0174 0 0185 0 0203 0 4016 0 4905 0.5615 0 6250 0 6845 07418 C.79'4 0 8519 0.9055 0 9554 l 3200 6 71.16 170.78 271A2 37620 487.72 1224.2 13115 1379.7 14:09 1449 4 1556 9 3614.2 1671.6 1729 4 1787.6 (567.19) e 0.1288 0.2926 0.4351 0.5642 0.6868 1.4061 1.4851 1.5415 1.5883 1.6298 1.% 79 1.7035 1.7371 1.7691 1.7996 e 0 01Cl 0 0166 0 0174 0 0185 0 0203 0.3176 0 4059 0 4712 0.5282 0 5809 0 6311 0 6794 0 7272 0.7737 0 8195 1400 6 71.68 171 24 272.19 376 44 487.65 1194.1 12961 1369 3 1433 2 14932 15518 1609 9 1668 0 1726 3 17850 (587.07) s 0.1287 02923 0 4348 0.5636 0.6859 1.3652 1.4575 1.5182 1.5670 1.6096 3.6484 1.6845 1.7185 1.7508 1.7815 e 0.0161 0 0166 0.0173 0.0185 0 0202 0.0236 0.3415 04032 0 4555 0.5031 0 5482 0 5915 0 6336 0 6748 0.7153 '
4 1600 4 72.21 171.69 272.57 376 69 487.60 61( 77 1279 4 135E5 1425 2 14E! 9 1546 6 16056 1664 3 17232 1782.3 (6G4 87) s 01266 0 2921 0 4344 0.5631 0 6651 0.8129 1.4312 1.4968 1.5478 1.5916 1 6312 1.6675 1.7072 1.7344 1.7657 e 0 0160 0.0165 0 0173 0.0185 0 0202 0 0235 0 2906 0 3500 0.3988 0 4426 0 4836 0 5229 0 5604 05980 06?43 3800 a 72.73 172.15 272.95 376 93 487.56 615.58 1261.1 13472 1417.1 1480 6 1541.1 1601.2 16607 1720.1 1779 7 i (621/12) s 0.1284 0.2918 0.4341 0.5626 0.68*3 0 8109 1.4054 1.4768 1.5302 1.5753 1.61 % 1.6528 1.6876 1.7204 1.7516 e 0 0160 0.0165 0.0173 0.0184 0.0201 0.0233 0.2488 0.3072 0.3534 0.3942 0 4320 0 4680 0.5027 0.5365 0.5695 2000 h 73.26 172.60 273.32 377.19 487.53 614 48 1240.9 1353 4 1408 7 1447.1 1536 2 15 %.9 1657.0 1717.0 1777.1 (635 80) s 0.1263 0.2916 0 4337 0 5621 0 6834 02091 1.3794 1.4578 1.5138 1.56G3 1.6014 1.6391 1.6743 1.7C75 1.7369 e 0 0160 c.0165 0.0173 0.0184 0.0200 0 0230 0.1681 0.2293 0.2712 0.3068 0.3390 0 3692 0.3980 0 4259 0 4529
! 2500 6 74.57 173.74 274.27 377.82 487.50 612.08 1176.7 1303 4 1386.7 1457.5 1522.9 1585 9 1647A 1709 2 3770 4 (666.11) s 0.1280 0.2910 0.4329 0.5609 0.6815 0.8048 1.3076 1.4129 1.4766 1.5269 1.5703 ~ 1.6094 1.6456 1.6796 1.7116 e 0 0160 0 0165 0.0172 0 0183 0 0200 0.0228 0 0982 0 175S 0.2161 02484 0.2770 0 3033 0.3282 0.3522 0.3753
! 3000 A 75 83 17t88 275.22 378 47 487.52 610 06 10$0.5 1267.0 1363.2 1440.2 150').4 1574.8 1635 5 170: 4 17(1.8 I
((95.33)s 0.1277 0 29J 0.4320 0.5597 0 6796 0 8009 1.1966 1.3692 1.4429 1.4976 1.5434 1.5641 1.621/ 1.6561 1.6688 e 0.0160 0 0165 0.0172 0 0183 0 0199 0 0227 0.0335 0.1588 0 1987 0.2301 0 2576 0 2827 0.306% 03291 0.3510 3200 & 76 4 175.3 275 6 378 7 487.5 609 4 8008 1250 9 1353 4 1433.1 1503 8 1570 3 1634A 1698 3 17612 (705 08) s C1276 0 2902 0.4317 0.5592 06768 0.7994 0 9708 1.3515 1.4300 .1.4866 1.5335 1.5/49 14126 1.6477 1.6806 e 0 0160 0 0154 0 0172 0 01E3 00199 0 0225 0.0307 0.1364 01764 02066 02326 0 2563 0.2784 02995 0.319S 3500 6 77.2 1760 276.2 3791 487.6 6064 779 4 1224 6 1338 2 1422 2 1495 5 1563 3 16292 1693 6 1757.2 i
e 0.1274 0.2899 0 4312 0 5585 0 6777 0 7973 0 9508 1.3242 1.4112 1.47D9 1.5194 1.5618 1.6002 1.635S 1.6691 e 0 0159 0.0164 0.0172 0.0182 0.0198 0 0223 0 0287 0 1052 0.1463 0.1712 0 1994 0.2210 0 2411 0.2601 0.2783 4000 & 7e.5 177.2 277.1 379.8 487.7 606.5 763 0 1174.3 1311.6 1403L 1481.3 1552.2 1619.8 1665 7 1750.6 1
- e D1271 02a93 0.4304 0.5573 0 6760 0 7940 0 9343 1.2754 1.3807 1.4461 1.491G 1.5417 1.5812 1.6177 1.6516 e 0 0159 0.0164 0 0171 0 0181 0.01 % 0 0219 0 0268 0.0591 0.1038 0.1312 0 1529 01718 016*3 0 2050 02203 1
8300 4 81.1 179 5 279 1 381.2 488.1 604 6 746 0 1042 9 1252.9 1364 6 1452 1 15291 16009 1670 0 17?7.4 s 0.1965 0.26b1 0 4267 0.5550 06726 0.7880 0 9153 1.1593 1.3207 1.4001 1.4582 1.5061 1.5481 1.566J 1.621G
- 00159 0.0163 0 0170 C 0160 0 0195 0 0216 0 0256 0 0397 0 0757 0.1020 0 1221 0.1391 0.1544 0 1654 0 1817 60C0 h 63 7 181 7 281.0 3b2 7 APS 6 602 9 7363 9451 1168 8 1323 6 1422 3 1505 9 1552 0 1654 2 17241 s 0 1258 0.2670 0 4271 0 5528 0 6693 0 7826 0 9326 1.0176 1.2615 1.35N 1.4229 1.4743 1.5194 1.5593 159s,2 I e 00158 0 0163 0 0170 0 0180 0 0193 00?)3 0 0248 0 0334 0 0573 0 0316 0 1004 0 1160 0 1295 0 1424 0.1542 7000 & B6 2 1P4 4 283 0 384 2 429 3 601 7 729 3 90) B 11739 !?P17 1392 2 1492 6 15631 1639 6 1711I s 01252 02H9 0 4?56 0 t'.07 06563 0 7/77 0E97( 10350 1 2055 1.31,1 1 1934 144e6 149M 1 5.M 1573!
TABLE Ad PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE) (CONTINUED)
A.(
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PROPEL 4 TIES OF WATER Density c Sbsfit')
PSIA Temp Saturated _
2300 2400 2500 8000 1000 2000 2100 2200
(* F) Liquid 62.909 62.93 62.951 63.056 62.637 62.846 62.867 62.888 32 62.414 62A46 62.87 62.99 62.75 62.774 62.798 62.822 60 62.38 62.55 62.446 62.465 62.559 62.371 62.390 62.409 62.427 100 61.989 62.185 60.606 60.702 60.549 60.558 60.587 60.118 80.314 60.511 60.53 200 67A36 67.859 67.882 67A98 67.537 67.767 67.79 67.813 300 67.310 64.311 64.342 64.373 64.529 63.903 64.218 64.249 64.28 400 63.651 63.925 63.95 64.11 63.79 63.825 63.86 63A9 410 63.248 63.475 63.53 63A9 63.40 63.425 63.46 63.50 420 62.798 63.025 63.36 63265 62.99 63.02 63.065 63.09 62.356 62.575 62.925 62.95 430 62.51 62.54 62.56 62.275 62.125 62.42 62.45 62.475 440 61.921 62.175 62.21 62.41 62.025 62.065 62.10 62.14 450 ' 51.546 61.66 61.76 6136 61.61 61.64 61.6B 61.725 460 61.020 61.175 61.56 61.50 61.175 ' $1.22 61.25 61.30 50.505 50.70 61.1 51.14 470 51.035 60.7 60.74 60.76 60.625 60.00 60.20 60.62 60.66 480 60.31 60.35 60 575 49.685 60,13 60.175 60.22 60.265 4DO 49.505 49A1 49.858 60.098 49.618 49.666 49.714 49.762 600 48.943 49.097 49.305 49.56 49.101 49.152 49.203 49.254 48.31 48.51 49.05 49.01 610 48.57 48.625 48.68 48.735 47.85 47.91 48.46 48.515 620 48.037 48.096 48.155 48.45 47.29 47.86 47.919 47.978 630 47.17 47.494 47.56 4729 47.23 47.296 47.362 47.428 640 46.51 46.794 46.862 46.93 4727 46.59 46.658 46.726 650 45.87 46.216 46.29 46.66 45.92 45.994 46.068 46.142 660 45.25 45.54 45.62 46.02 45.22 45.30 45.38 45.46 670 44.64 44.844 44.93 45.36 44.50 44.585 44.672 44.758 680 43.66 44.015 44.11 44.205 44.68 43.73 43.825 43.92 SSO 43.10 43.33 43.434 43.956 42.913 43.017 43.122 43126 600 42.321 42.432 42.55 43.14 41.96 42.08 42.196 42.314 6*O 41.49 41.35 41.483 41.616 42283 40.950 41.083 41.217 620 40.552 41.44 630 39.53 40.388 640 38.491 39.26 650 37.31 38.008 660 36.01 36.52 670 34.48 34.638 680 32.744 32.144 690 30.516 TABLE A.6 PROPERTIES OF WATER, DENSITY A.8
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= l-OP-lC APPENDIX A Page 1 of 10 1.0 Procedure Fgg 3 81986 Ectinated Rod Bank Position After Shutdown or Trip NOTE: Equilibrium condition is defined to be: No change in power j of greater than 1 5% during the previous 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
1.1 Previous Equilibrium Critical Conditions 1.1.1 Date: /6 dM D l 1.1.2 Time: 3 00 l 1.1.3 Power Level Prior to Rampdown or Trip /Ch %
1.1.4 Core Burnup: 7@O MWD /MTU 1.1.5 Control Rod Worth at Previous Conditions:
1.1.5.1 Bank C .2d steps 1.1.5.2 Bank D I steps 1.1.5.3 Total Inserted Worth (Curve Pages 23 through 27) = (-) /10 pcm
! 1.1.6 Boron Concentration at Previous Critical Conditions 1.1.6.1 Previous Boron Concentration Nb ppm 1.1.6.1.1 Date and Time of Boron Sample: / TMk [5 2/M i .1.1.7 Xenon Worth at Previous Critical Conditions 1.1.7.1 Xenon Worth (Curve Page 30) = (-)M @ pcm
( 1.1.8 Power Defect at Previous Critical Conditions 1.1.8.1 Power Level from step 1.1.3 = /O O %
NOTE: Use boron concentration from 1.1.6.1.
1 j 1.1.8.2 Power Defect (Curve Page 29) =
(-) /f CC pcm i
i
- -of se APPLNDIX A l
Page 2 or 10
'IALS :-
1.0 FEB 2 81986 Procedure [ continued]
1.1 Previous Equilibrium Critical Conditions (continued) 1.1.9 Briefly describe shutdown maneuver: (example:
"150MWe ramp from 97% starting at 0137, trip at 27%".)
(E+- TILW FEDM (00Yo hui To LOM GF viral tutit. 805 E
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1 1(
APl!% DIX A Page 3 of 10 f1A1.S - - -
FEB 2 61986 1.0 Procedure [ continued) 1.2 Projected Startup Conditions 1.2.1 Projected Date of criticality: /6 ) 9 /k 1.2.2 Projected Time of criticality: 2 A @O 1.2.3 Desired Rod Height for Criticality 1.2.3.1 Bank C M steps 1.2.3.2 Bank D /f steps 1.2.3.3 Total Inserted Worth Curve Pages 23 through 27 = (-) M YO pcm 1.2.4 HZP Boron Coefficient (Curve Page 21 HZP) =
(-) /O' !h Pcm/ ppm 1.2.5 Xenon Worth at criticality 1.2.5.1 Time af ter shotdown (5.2.2 - 5.1.2) =
M hrs.
1.2.5.2 Average power for Xenon (Appendix B) =
/DO z 1.2.5.3 Did a rampdown of power occur before shntdown?
1.2.5.4 If 1.2.5.3 is yes , proceed to Appendix C.
1.2.5.5 7.cnon Worth (Curve Page 32, 33, 34 or Appendix C) = (-) h pcm
, . i.
nlTL:,isik I, l'ai,e 4 of 10
!IALS .s g gg gg 1.0 Procedure-(continued) 1.2 Projected Startup Conditions [ continued]
1.2.6 Temperature Defect 1.2.6.1 Proj ected T4;nperature at Criticality =
M7 r 1.2.6.2- Temperature Defect (Curve Page 28) =
(2) pcm NOTE: If the projected temperature is greater than 547'F, the temperature defect is negative. If the proj ected temperature is less than 547'F, the temperature defect is positive.
i
A h i h1, . i.
hqo 5 of 10 1ALS . a- FEB 2B DE6 1.0 Procedure (continued) 1.3 Reactivity Balance 1.3.1 Change in rod worth from previous critical conditions to estimated critical conditions
(-) /20 - (-) 2 4 0 = /20 pcm 1.1.5.3 5.2.3.3 1.3.2 Change in xenon worth from previous critical conditions to estimated critical conditions
(-) 1.1.7.1 2kb - (-) 2 40 1.2.5.1
= - YOO pcm 1.3.3 Change in defects from previous critical conditions to estimated critical conditions
(-) / 700 - (-) O = /50 pcm
. 1.1.8.2 1.2.6.2 1.3.4 Total change in reactivity from previous critical conditions to estimated critical conditions l70 , . q o.) . e cca , _ gpga ,,,
1.3.1 1.3.2 1.3.3 1.3.5 Equivalent change in bo'ron concentration "I7fO + -/C19 = 19 I ppm 1.3.4 1.2.4 3 1.3.6 Zero- over critical boron concentration P + IT = 997 ppm 1.1.6.1 1.3.5 NOTE: Step 1.3.6 represents the critical boron concentration at the specified date and time, RCS average temperature, and rod position.
1
l
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REACTOR OPERATION
- 8. Coeffecients and Control (continued) l POINT OF OPTIMdM MODERATION l
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CHARGING PUMP SUCTION Figure 3-1
O e
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 23 THERMODYNAMICS, HEAT TRANSFER AND FLUID PLOW ANSWERS -- SURR't 182 -86/07/21-DEAN, WM ANSWER 1.01 (1.00) a REFERENCE Westinghouse Reactor Physics, pp. I-2.19 - 21 HBR, Reactor Theoryr Seccion 14, p. 3 DPC, Fundamentals of Nuclear Reactor Engineering, p. 53 Surry ND-86.1-LP-5 001/000-K5.57 (3.0/3.2) GE energy decrenent per collision.
ANSWER 1.02 (1.00)
REFERENCE Compeehensive Nuclear Training Operations (CNTO)i pp c-16/27 001/000; K5.13(3.7/4.0)
ANSWER 1.03 (1.00) d.
! REFERENCE l 002/0003 A1.09(3.7/3.0) & A1.13(3.3/4.0) l l
l l
ANSWER -1.04 (1.50) l a) Lower cr.tical rod position (+.5 ea) b) Higher caitical rod ceosition c) Lower critical rod position REFERENCE SURRY OP-1C 001/010; A4.03(3.5/3.9)
\
g UNITED STATES , ,
- p s afCo,f.o - NUCLEAR REGULATORY COMMISSION
- g. so
. f., REGION il
, f $ 101 MARIETT A STREET, N.W., SulTE 2000 ATLANTA, GEORGIA 30323 o, [
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4 e ,.w e - -- , . , , . , . , , .--..-,r-m ,,ce.,.,,-.,,,,,. -.- --m-.,,.__,ven..r.m w ,-..--.. .--,---,.v--,-...m,,-,.-.,.,-.e,,-r..w,n. - , , . , . , , , , - . , ,,.s.m..e- , - - , ,
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- 1. PRINCIPLES OF NUCLEAR DOWER PLANT OPERATION, PACE 24 THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW ANSWERS - SURRY 18.2 -86/07/21-DEAN, W M ANSWEP $ .05 (1.00) a) Lower (+.5 ea) b) Higher i REFERENCE Surry ND-83-LP-8, pp 8.o/10 Appendir A' Centrifugal Pump Improper Operation (2.9/3.2)
I ANSWER 1.06 (e.a t a. High relative #1ur - causes a greeter reactivity change due to CRW being
, proportionel to flux tip/ flu > avg. therefore, the higher the relative l flu:- the greater the change. (0.333 for' area /0.5 for Exp.)
- b. larger effect for the niddle - due to absorption of neutrons which have j a high probability of causing fission. Whereas control rods at the edge I absorp neutrons which have a high probability of leakage.
I
- c. %1 has higher uorth. When inserted il depresses the flu > around itself, this increases the f l u :- in other regions, when 12 is inserted the flur has been depressed therefore its worth is lower (than its worth in an unrodded cere).
REFERENCE North Anna ROP- pp. 6.11,6.12,6.19 Obj. 9 CURRY ND-86.2-LP-6
'< / A . 0 01 - 0 0 0 - M S . 0 2 (2.9/3.4)
I I ANSWER 1.07 ( .50)
Optimum point would move down and to the left (+.5)
REFERENCE SON /WBN License Cer+ 'e ns , ie -
sc tivi ty Coe f f ic ients
- Surry ND 86.2-Lo pp 9.12/13 004/000; '5.15 (3.3/3.5)
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p* "'4 UNITED STATES , ,
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9[o g, NUCLEAR REGULATORY COMMISSION 2 -f, c5 REGION il 0 .t 101 MARIETTA STREET,N.W., SulTE 2000
- 2 o, ATLANTA, GEORGIA 30323
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- 1. PRINCIPLES OF N'UCLEAR POWER PLANT OPERATION, PAGE 25 i ~~~~TUEE566YU555C57~sE5T TEdUEEEs~5U6~ELUf6 FLOU
, ANSWERS -- SURRY 1&2 -86/07/21-DEAN, W M i
l l ANSWER 1.08 -(2.00)
- 1) Pu-240 buildup--More Negative (+.5 ea)
I 2) Accumulation of Fission P.roduct gases--More Negative i
- 3) Fuel Densification--More Negative '
- 4) Clad Creep--Less Negative REFERENCE I l TPT Requal' Lesson Plan, Cycle I, 1985 ' Core Life Changes", pp 16 ,
CNTO, ' Reactor Core Control', pp'2-44/45 Surry, ND-86.2-LP-1 & LP-10 001/000; KS.49(3.4/3.7)
ANSWER 1.09 (2.00)
- 1) Fuel . pel.l et length (+.25 ea up to 2.0)
- 2) Thermal conductivity of the fuel
- 3) ' ' ' '
gap
- 4) clad
- 5) crud i 6) Crud thickness *
- 7) Gap size
- 8) Surface area of clad
- 9) Clad thickness
- 10) Convective heat >:f er coefficient REFERENCE !
j Surry ND-86.3-LP-1, pp 1.12 '
- 002/000; KS.01'3.1/3.4) [
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l ANSWER 1.10 (1.50)
- Deta effective decreases (+.5) due to Pu-239 producing more of the core's
{ power (+.5) and having a smaller Beta fraction of approx. .0020 (+.5) l REFERENCE
{ SON /WBN. Instr. Guide, ' Neutron hinetics*, pp 6 Surry ND-86.2-LP-9~& 86.1-LP-9.
- 001/000; K5.47 (2.9/3.4) F i.
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- 1. PRINCIPLES OF NUCLEAR POWER DLANT OPERATION, PAGE 26
~~~~ TUEk55D7bd5EC57~sE5T~TEdUEFER~550~FLUEE"FEUU ANSWERS -- SURRY 182 -86/07/21-DEAN, W M ANSWER 1.11 (1.00)
Due to the greater decrease in the temperature of the coolant e:<iting the core relative to the decrease of the inlet coolant, (+.5) more positive reactivity will be added in the upper' core regions, resulting in 6 more positve (less negative) AFD (+ 5)
REFERENCE Westinghouse Nuclear Training Operations, Ch 8 Surry ND-86.2-Lo-8, pp 8.14/15 001/000; K5.27 (3.7/3.9)
ANSWER 1.12 _.sud/'O)
- 1. Minimum time necessary to cause boric acid in the vessel / core aegion to
~~
approach the solubility limit - (/, c}
REFERENCE North Anna NCR00P-95.2 Surry ND-91-LP-3r pp 23 l K/A 000-011-EK3.13 (3.0/4.2)
ANSWER 1.13 (1.00)
The ability to deliver a certain number of amperes for a specific number of hours before the ce!' voltage crops to a specific minimum value.
REFERENCE f Morth Anna: NCR00P 90.3 Sec. I Sorry ND-90.3-LP.6e pp 6.5/6 063/000; A1.01(2.5/3.3) l l
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- 1. PRINCIPLES OF NUCLEAR POWEP PLANT OPERATION, DAGE 27
~"'T5EE56DEUd55C57~555T ~ik5U5FER~5UD~E[UE5'E LUU ANSWERS -- SURRY 182 -86/07/21-DEAN, WM ANSWEP 1 .14 (2.50) a) INCREASES (+.5) as P2P temp risesr so does Pressure, hence the margin to saturation increasec. (+.5) b) INCREASES (+.5, the DELTA 7 across the core will be lower to produce the same power, so Th will decrease and the coolant in the upper core regions will be farther r o n saturation. Alsor coolant flow will be more effective in scrubbing bubbles fron rod surfacer. (*1.0)
REFERENCE SURRY ND-96.3-LP.2, pp 2.?t/12 002/000; K5.01(0.1/3.4)
ANSWER 1.15 ( 3. 0 0 ) (pr 50T3 b"'f 3 8"J"##
- 1) Pressurizer Level at 22% V(+.4 parameterr +.1 setpcint) which is an indication core is covered (+.5 for description) 2)- RCS subcooling >/= 50 degreec, subcooled water . implies no voids 3 9G 1evel in at leect 1 SC >/= 33%, ensuret heat sink maintained
((I c5fesssort > 7.@pgit b enturt N NEttkust fu6Coolkf SURRY rJ0-06 3-LP-4, pp c . 9 / ? / fure., Ap-29 EPE-015; EMI.01(4.4/4.6) & EM3.07(4.1/4.2)
ANSWER 1.16 (1.00)
Concave doun REFERENCE NUE Vol 3, CH 12 015/000; K5.05(4.1/4.4)
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- 1. _ PRINCIPLES OF NUCLEAR DOWER PLANT OPERATION, PAGE 28
, ~~~~T5ER506 UE5fC5~~5EST~TR5 5F5E~dU6~FEU56~FEUU ANSWERS -- SURRY id2 -86/07/21-DEAN, W H
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AliSWER 1.17 (1.50) i a) k encess = k-1 (excess reactivity in the fuel) (+.5) b) fuel burnup (+.25 ea) fission product poison buildup power defect heatup (effect of FTC, MTC and press coefficient)
REFERENCE Surry ND-86.2-LP-Sr pp 5.4/5 001/000;.M5,19(3.1/3.4), K5.30(2.9/3 1), K5.54(2.8/3.2)
ANSWER 1.18 (2.00) o) Unit 1 (+.5) due to a higher Beta coefficient at SQL (+.5) b) . Unit 2 (+.5) due to MTC being more nesetive, so Tavs will decrease less to add same + reactivity (+ 5)
REFERENCE Surry ND 86.2-LP-2 and 86.1-LP-9 001/000; K5.49(2.9/3.4) and MS.10(3.9/4.1) f ANSWER 1.19 (1.00)
I 3, 1, 2, ' 4 ( 25 for each switch to get in correct order)
REFERENCE Surry ND-86.3-LP-1, pp'1.19/20 002/000; K5.02(3.1/3.4) i i
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- 1. PRINCIPLES 0F NUCLEAR POWER PCANT OPERATION, PAGE- 29 '
l- THERMODYNAMICS, HEAT TRANSFER AND. FLUID FLOW
!. ANSWERS -- SURRY.182 -86/07/21-DEAN, WM -
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' ANSWER 1.20 (1.00) ;
i at :2240 psiar hs = 1115 BTU /lb :(+.5'for h determination) l
- j. at.20 psiar for saturation conditionsi h3= 1156 BTU /lb 2. h f = 196~ ;
! ifrom a Pollier Diagram, moisture content is approximately~5% (95% quality). ,
calculatins*(1156-1115)/(1156-196) = .043 >> 95.7% qua~1ity
(+.5 for' quality determination) l-
- REFERENCE
!. -Steam Tables and Moll-ier Diagram
' .010/000; K5.02(2 6/3.0)
[
l ANSWER 1.21 (1.50)-
1 -.
j .q=m(Delta T) (+.5)
! 100%=~~100%(60)
- 3%= x%(35) -(+.5) l x%= 3%(60/35)= 5.1% (+.5) i REFERENCE 1
Surry ND-86.3-LP-4 EPE-017; EK1.01(4.4/4.6) l-i.
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ANSWER 2.01 (1.00) a c 1 REFERENCE l I Surry ND-88.1-LP-3r pp 3.13 ,
010/000; A4.01(3.7/3.5) .
ANSWER 2.02 (1.00) >
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059/000; K1.03(3.1/3.3) .
ANSWER 2.03 (1.00) d '
l REFERENCE I Surry ND-93.3-LP-10 .
012/000; K1.03(3.7/3.8) ,
l ANSWER 2.04 -(1.00) '
c ,
REFERENCE Surry ND-88.4-LP-8, pp 8.6 ;
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2, *LANT DESIGN I?CLUDING SAFETY AND EMERGEt!CY SYSTEMS OAGE 31 ANSWERS -- SURRY 1&2 -86/07/21-0EAN, W M ANSWER 2.05 (1.00) b l REFERENCE I c urry ND-91-LP-3, pp 3.*.7/10 l
013/000; M1.0S(3.6/3.8) l ANSWER 2.06 (2.00) a) Close (+.25 ee) b) Open c) No d) Open e) Close
") Close
, 3) NO
( h) No RECERENCE Surry ND-91-LP-2/3 013/000* K2.ceries( 3.3-4.2/3.7-4.4)
ANSWEP 2.07 (1.50) a) Stops discharge "non cont,ainment vacuum systen and saste decay t a n k.s (S5vts RCV-GW-160, 260, 101) (+.75)
~ ~'
b) Trips Unit l's purge supply __ fans, shuts purge air butter fly valves (MOV-V3-100A, B, C, D) (+.75) cercRCN'CC- -
/ (sm p oetst/t .
TPT SD6G ' Radiation Monitoring and orotection Systen", pp 34/35 JY.< e fr o^
Surry TS Table 3 . 7-5 , /4 P f % 57t? T. t-J l EPE-059 R 060; EA2.05(3.6/3.9) & (3.7/4.2) i l
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- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 32 ANSWERS -- SURRY 1&2 -86/07/21-DEAN, W M ANSWEP 2.08 (1.50)
- a. Latch housing and rod travel housing (0.25 ea.)
- b. The volte3e on the coils is reduced to prevent overheating of the stationar.y coils which could cause damage to the insulation. (1.0)
REFERENCE North Anna: NCRODP 93.3 Sec. I 1 II Surry ND-93.3-LP-3, pp 3.15/16 E ND-08.1-LP-2 001/000; K1.04(3.2/3.4) & 001/010: K4.05(2.8/3.0)
ANSWER 2.09 .,
N00)
- a. rods out CO.253 'ref will be na> so Tave/ Tref mismatch and NI/ Turbine power mismatch will both give a rods out signal CC.753
- b. rods in E0.252 Loop 1 Tave increases and auctioneered high Tave also increases. Tave/ Tref mismatch gives a rods in signal E0.752
- c. rods out CO.25] the power mismatch circuit of the reactor control unit responds only to rate of change of deviation between turbine and nuclear power but rod notion will occur due to the Tave - Tref difference. E0.753 REFERENCE Topic 6 Lesson 2 Fig. RS-5 and pp 55, 19, 20 North Anna NCRODP 93.5 ANSkER 2.10 ( .50)
From its own 125 DC Distribution Systen (+.5)
) REFERENCE Surry ND-90.3-L?-2, pp 2.8/9 064/000; K1.04(3.6/3.9)
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- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 33 ANSWERS -- SURRY 182 -86/07/21-DEANi W M ANSWER 2.11 (1.00)
TO limit the rate o f' S/G blowdcun during a main -s team line break (+1.0)
REFERENCE Gurry ND-09.1-LP-27 PP 2+4/5 EPE-040;EK3.01(4.2/4.5)
ANSWER 2.12 (2.50)
- 1) LHSI discharge to CHG Rump suctinn(MOV 863A, 9) start to open while LHSI recite valves (MOV 885Ar Br C, D) stert to close (+.75)
A white s t.3 t u s light illuminates (+.25)
- 2) 2 minutes later, HHSI nornel suctions (LCV 1158, D) close and the LHSI suctions rron CNTMT sump (MOV 860Ar 9) open. (t.75)
An amber stetus light i l l o n.i n c t e s (+.25)
- 3) When POV 8604, B are f u l l ', apen, LHSI punp n o r r. a l suctions close (+.5)
REFERENCE Surry NO-91-LP-37 pp 3.21'23 006/020; A3.04(4.2/4.3)
ANSWER 2.13 (1.00) outcide; CLS; inside; CLS is reset (+.25 ea)
REFERENCE Surry NO-91-LP-6 013/000; M1.05(4.1/4.4)
ANSWER 2.14 ( .50)
( W en thn s u p m l- 25%. (+.5, Of- 4 ja To for/ ing pga Jagega)\
b u s voltese is reduced l
l k, r e p : N~r r I
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- 2. LPLANT DESIGN INCLUDING _ SAFETY AND EMERGENCY SYSTEMS PAGE 34 ANSWERS --~SURRY 182 -86/07/21-DEAN, WM ANSWER- 2.15 (1.00) a) Vital Suses-IIr III.and IV all. supply cooling to RCP motors / bearings
(+.5) b) Vital ~ Buses I and IV (+.5)
REFERENCE Sorry.ND-90.3-LP-5, pp 5.5/5.19 062/000; .K2.01(3.3/3.4) and A2.01(3.4/3.9)
ANSWER 2.16 (1.50)
CN-TK-1A (ECT) (+.3 ear subtract +1 for incorrect place)
CN-TK-3 (EMT)
CN-TK-2 (CST)
Unaffected Unit's AFW supply Firemain makeup REFERENCE Surry ND-89.3_1p-4, pp 4.13
.061/000; K4.01(3.9/4.2)
ANSWER ' 2 .17- '(1.50)
Gases, particularly Hydrogen from the VCT (and some f.p. 'sases) come out of. solution as they are sprayed into the PZR. (+1.0) this creates larger pressure oscillations during transients:(+.5)
REFERENCE Surry ND-88.1-LP-3, pp 3,27 010/000; PWG-7(3.4/3.9)
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- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 35 ANSWERS'-- SURRY 182 -86/07/21-DEAN, W M ANSWER 2.18 (2.00)
.Open ALL 3 feedwater bypass control valves a sna11 increment (+1.0) observe level behavior and readjust only if levels aren't changing as
' ' " ' ' ~ -
anticipated (+.5)
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... observe. behaur o F kei e neden;/pdneka, rn No.u/pam REFERENCE I4
- I.
Sorry ND-88.1-L?-5, pp 5.16j U3#d 035/010; A2.04(3.6/3.8) l ANSWER 2.19 (P.00)
- 1) Motor current (+.4 ea)
- 2) 9 earing temperatures
- 3) Seal Injection rlow (6 spn)
- 4) Seal Leakoff (.2 spm)
- 5) 11 Seal D/P (200 psidi REFERENCE ,
Surry ND-88.1-LP-61 pp 6. 28/29 ' of f. E fr3 j
003/000; PWG-7(3.5/3.9) l ANSWER 2.20 (3.00)
- a. The two pumps not in Pull to Lock (1.0) i b. 1. LNSI can only deliver enough flow to provide sufficient suction pressure to two HHSI pumps. (1.0) ;
2.. (for NA)The pumps are ?O0hp each this action 11~ tits loading on the l EDG to within specifications. (1.0)
- 2. (For Surry)To conserve RWST water during the injection phase (1.9) t t o)
REFERENCC 8I E preast Pr$
borth Anra: NCRODP cl.1 "f b)
Surry.ND-91-LP-2r pp 2.14/16 l
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PLANT DESIGN INCLUDING SAFETY AND EMERGENCY. SYSTEMS PAGE 36 ANSWERS -- SURRY 1&2 .-86/07/21-DEAN, WM ANSWER 2.21 (1.50)
- 1) Completely close the handwheel.(+.5 ea)
- 2) Re-engage.and reset the trip hook mechanism
- 3) slowly reopen valve fully (less 1/4 turn) and verify nechanism open
.and.relatched REFERENCE-Surry ND-89.3-LP-4, pp 4.14 061/000; K4.07(3.1/3.3)
ANSWER 2.22 (1.00)
The attached pump supplies all needs above 30 psis. Up until that-Pointe the motor driven supplies a decreasing-portion of the fuel oilr as it recircs to the base tank via a 30 psi relief valve. (+1.0)
REFERENCE i
Surry ND-90.3-LP-1, pp 1.'14 064/000* K1.03('3.6/4.0)
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- 3. INSTRUMENTS AND CONTROLS PAGE 37 ANSWERS -- SURRY 1&2 -86/07/21-DEAN 7 W M ANSWER 3.01 (1.00) 3 or b REFERENCE WBNr Drawing 47W611-99-1 CAT, PSM, CN-IC-IPE. p. 6 Svery ND-93.3-LP-19, pp 16.6/7 012/000-K6.10 (3.3/3.5)
ANSWER 3.02 (1.00) e REFERENCE SONP System Oescrip. "RPS", pp 10 & ROS Mechanical Logic Orawing Surry ND-93.3-LP-10 pp 10.15 012/000; K6.03 (3.1/3.5)
ANSWER 3.03 (1.00) b er C PEFERENCE Evrry ND-93.3-Lo-3r pp 3.0 001/000; K4.09(3.2/3.4)
ANSWER 3.04 (1.00) b.
t REFERENCE North Anne NCRODD 93.10 Surry ND-93.3-LP-14, pp 14.7/o
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1 012/000; K4.02(3.9/4.2) i
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- 3. INSTPUMENTS AND CONTROLS DAGE 38 ANSWERS -- SURRY 1&2 -86/07/21-DEAN, W M ANSWER 3.05 (1.00) a) Arm anly (+.5 ea) b) Arm and Actuate REFERENCE TPT SD105 ' Steam Dump System'r pp 9-16 Surry NO-93.3-LP-?
041/020; K4.14(2.5/2.0), (4.18(3.4/3.6)
ANSWER 3.06 (1.50) a) Modulated (+.3) b) Closed c) Open d) Closed e) Modulated REFERENCE Surry ND-88.3-LF o 004/010; A4.03(3.9/3.7)
ANSWER 3.07 (1 o s)
Prevents voltage dr .ps dur ing the diesel load sequence (+.5) from causing subseque- . load shedding (+.5) negeting the loading of the diesel.
REFERENCE NCRODP 90 r "EDG' Sorry Nr jg,3_(c_7 064' 00; K4.10 (3.5/4.0) l ANSWER 3.09 (1.50) 30% setpcint from 0 - 2 0 ;. (+ 51 Turbine Power (+.25) r and linearly fran 39-100'; 2a urbine :'ower goes # rom 20-100% (+.75)
REFERENCE NCRODP 91.1, 'ESF-SI or ECCO*
Surry ND-91-LR-3, sp 3.0 t
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ANSWER 3.09 (1.25) 3; 2/1 2; 4; 10 (+.25 ee)
PECERENCE TPT SD4
- E::c o r e NIS"r pp 69-70; TS Table 3.5.1 Surry TS table 3.7-1 j dP-Y 015/020; PWC-7(3.5.a 0)
ANSWER 3.10 (2.00) a) SI Train A (+.5 ea)
No Ch3 Pump breakers closed b) SI Train 8 c) Letdowr- Temp 145 degreet REFERENCE Sorry ND-88.3-LF-27 op 2.13/20 004/000; K4.03(2.8/2.9) & 0 0 4 / ^ 1 0 i K-1 . 0 3 ( 3 . 1 / 3 . 6 )
ANSWER 3.11 (1.00) 2/4 RWST levels reach 18.5 % (+.75)
AND RMT keyswitch in ?MT made (+.25) *
, REFERENCE I
Svery NO-91-LP-3, pp 3.20 006/030; K4.03(3.4/3.6) l ANSWER 3.12 .50)
Turbine First Stege Inevice c' r e t s u r e ( s e l e c t a b l e ) (+0.5)
REFERENCE Surry NO 03,3-LE=-G- pp E,a l
075/010; -fc 01(3.5/3.9)
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' ANSWERS -- SURRY 1&2 -96/07/21-DEAN, WM ,
ANSWER 3.13 (1.00)
Lo-Lo Level in 2/3 S/Gs (+.5 ea)
Loss of Voltage on- 2/3 4160VAC. Station Service Buses REFERENCE Surry ND-69.3-LP-4, pp 4.-9 i 061/000; K4.02(4.5/4.6) l i ANSWER 3.14 (1.00)
PT-458 (PZR) and PT-403 (Loop C Hot les) (+.5)
'NDT REQUIRED' and 'NDT HIGH PRESSURE
- REFERENCE Surry i:D-93.3-LP-6, pp 6.6/6.7 010/0003 K4.03(3.0/4.1)
ANSWER 3.15 (1.50)
- 1) Rod control (+.25 ea)
- 2) P:t level control
- 3) Steam dump control
- 4) Tavg/ Tref comparator
- 5) Tavg/Trer recorder
ANSWER 3.16 (1.00)
- 1) Phase Failuee (+.25 ea)
- 2) Regulation Failure
- 3) Logic Error
- 4) Multiplexing Irrcr r
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ANSWERS -- SURRY 1&2 -86/07/21-0EAN, WM REFERENCE Surry ND-93.3-LP-3r pp 3.22 001/050; K4.01(3.4/3.0)
ANSWER 3,17 (1.00)
- 1) Avetioneet .
- High Delta T (+.5 ea)
- 2) P/A Converter Actual Rod Denand Signal REFERENCE Surry NO-93.3-LP-3, pp 3.25/26 001/000; K5.04(4.3/4.7)
ANSWER 3.18 (2.S0)
- 1) Hi Stn Flow coincident with to Stm Press or to Tave (+.25 ea part) 2/3 Tave < 543 degrees Manual block
- 2) Stm Hdt/Stn Line D/P Both Th and Te loop stops closed for that loop.
Par Press 2/3 < 2000 psis Manual Block
- 3) P:t' Low Precsure 2/3 - 2000 psis Manual block REFERENCE Surry ND-91-LP-3r pp 3.10/12 0.13/000; K4.12(3.7/3.9) l
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ANSWER 3.19 (2.00)
- 1) S/G Pressure (+.25 ea)
- 2) WR Tc (Loops A/B)
- 3) ER counts f '4) % reactor power 4
- 5) WR'S/G Levels
- 6) WR Th (Loops A/B)
- 7) P:t level-
- 8) P:r Pressure REFERENCE i
Surry ND-93.4-LP-6, pp 6 5 EPE-068; EK2.01(3.9/4.0)
ANSWER 3.20 (1.00)
Emergency Generator Isolation Switch (+.5 ea)
- Switches for the three lockout relays REFERENCE Surry ND-90.3-LP-2, pp 2.29 i 064/000; A4.01(4.0/4.3) i i
ANSWER 3.21 (1.25)
! The highest reading upper / lower detector is compared to the averase of the j opper/ lower detectors (+.5) and senerates an alarm at 1.02 increasins(+.25).
The circuit auto defeats below 50% power on ALL channels (+.3)
REFERENCE SONP System Descrip, ' E::c o r e NIS'r pp 17 Surry ND-93.2-LP-4 015/000; K6.04 (3.1/3.2) & A1.04 (3.5/3.7) l 4
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' ANSWERS -- SURRY 1&2_ -86/07/21-DEAN, WM ANSWER- 3.22' (1.00)
Level III Channel (+.5) failed high (+.5)
REFERENCE Westinghouse PWR Systems Manual " Primary System Control', pp 12-14 TPT SD9 'PZR and Pressure Relief",;pp 38-40, 57; .DWG 5610-T-D-15 Surry ND-93.3-LP-7 011/0003 A2.10(3.4/3.6)
-ANSWER 3.23 (1.50) a) COMPUTER PRINTOUT ROD CONTROL SYSTEM (+.5) b)- No (+.5) Due to induced electrical noise, the setpoint is' increased (to +/- 37 steps)- (+.5)
REFERENCE Surry ND-93.3-LP-3, pp 3.32/33 014/000;-K4.06(3.4/3.7)
ANSWER 3.24 (1.50) 2/3 relay.s / 90% (+.25) at 10 seconds, you get a UV alarm (+ 25) at 50 seconds, the EDG starts (+.25) at 60 seconds, the bus feeder from the transfer bus gets a trip signal, if it doesn't open, the RSS feeder to the xfer bus opens and the EDG output breaker shuts (+.75)
REFERENCE Sorry ND-90.3-LP-7, pp 7.14/15 062/000: K3.02(4.1/4.4)
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i ANSWERS -- SURRY 1&2 -86/07/21-DEAN, WM i
j ANSWER 4.01 (1.00) 1 e REFERENCE 4
McG, AP/2/A/5500/23, P' 2 Svery AP-14, pp 3 EPE-051; PWG-11(3 7/3.7)
} ANSWER 4.02 (1.00) 1 a
REFERENCE MNS, AP/2/A/5500/14, Case I, p.2.
l CAT, AP/1/A/5500/15, Case I, p.2.
! Svery AP-1,1, pp 3 001/050; PWG-11(4.4/4.4) l ANSWER- 4.03 (1.00) i d i
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! 000/074; CK3.07(4.0/4.4)
ANSWER 4.04 (1.00)
( b REFERENCE Surry Eo-1.01 EPE-024; PNG-7(3.5/4,4) l l
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ANSWERS -- SURRY 1&2 -G6/07/21-DEAN, W M ANSWER 4.05 (1.00) b REFEKENCE Sorry EP-4.00 EPE-038; Ek3.06(a.2/4.5)
ANSWER c.06 ( .50)
True REFERENCE Surry EP-1.00, pp :1 026/020; PWG-11 (4.5/4.5)
ANSWER 4.07 (1.50) a) False (+ 5 ea) b) True c) False REFERENCE Westinjhouse User's Guide for EOPs, pp 5-12 PWG-22(4.3/'" 31 (4NSWER 4.08 ' 1. i.: 0 )
- 3. 100 (0.5) b- 60 (0.5)
- c. 1 (0.a)
REFERENCE C l *, . EP/1/A/5000/201, pp. 16 Surry fro-P.'.. pp12 E P E - 0 6 o ; P W G - 7 ( 3 . 4 / 3 . o '-
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ANSWERS -- SURRY 182 -86/07/21-DEAN, W M ANSWER 4.09 (1.00)
For 0.5 points each.
(a) 750 nr/qtr (b) 2750 mr/qtr REFERENCE NAPS Radiation Protection Manuale P 2+3-7.
Surry HP Menval, beetion 1.2.pp 5 PWG-15' Radeen Knouledge (3.4/3.9)
ANSWER 4.10 (1.00)
- 1) Require permission of the Operations Superintendent (+.5 ea)
- 2) CO AND RCS it borated to the Cold Shutdown condition eR ECS kors4tl 4e ka+MMW fren F Memtemej c,f- +4Sb, REFERENCE
- Sorry OP-1.1, pp 6, Pc1 tr 3j A/b -pd.24e 7 PWG-7(3.5/4.0)
ANSWEP 4.11 (1.50) c14*y 3
- 1) Verify MSTV closure (+,5 ea) af) Ckeck (edri,.esw ebfray .fys/eW I
- 2) Verifj ohase 3 isolation "C3 PomPi Nonio) -RiaIr 4 r
- 3) Stop RCPs in 2 minutes 'Cf N*w -c,97 4 uj u 7J; REFERENCE f) chick CAAThr f@(tes Spray fpg Sorry E0?-1.00 s t e rs ?) toj il,. .qg ppg pu, ,
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ANSWER 4.12 (2.00)
- 1) Verify at l e e r t. H or J bucet energized (+.5 es)
- 2) Verify SS Auto Gwap-over
- 3) Unaffected unit supplied by RSS
- 4) Vertfy load obed using a t '. a c h m e n t t o 4, -racedure i
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ANSWERS -- SURRY 1&2 -86/07/21-DEAN, W M REFERENCE Eurry EF-1.00, step 3 EPE-007; P L' G - 11 ( 4 . 4 / 4 . 5 )
ANSWER 4.13 (2.00) a) High Eearing Temp Alarm (+.25 es response)
Hi3h Stator Winding Ten.P 2 minutes elapsed b) Containment '! a c u u n Pumps Main Feed Fumps HP FW Drein Pumpa Chilled CC r umps Cire Water P umps REFERENCE Sorry AP-40, pp 3 EPE_065; PWG-11(3.9/3.9)
ANSWER 4.14 (1.50) a) 320 (+.5 ec) b) 50 c) #V REFERENCE Surry PL E S, pp 36, 39, 53 J of lO [JW f*VI l 002/020; PWG-7(3.7/4.3) 2nd 005/000; PWG-7(3.5/3.8)
ANSWER 4.15 (1.50)
- 1) CNTM Air Particulate Monitor (Any 5 for +.3 ea)
- 2) CNTM Radioactive Gas Monitor
- 3) Component Coolin3 Liquid Monitor
- 4) Ccndenser Air Ejector Gas Monitor
- 5) S/G Blowdoun Monitor Am Bi Area Monitort 6))
? Vtot -Ve'ldl dRm nq REFERENCE TPT ONOP 1000.2, p t: 2 Surry A P -- 1 6 , pp 3
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ANSWER 4.16 (1.50)
- 1) Oose Rate Meter is required to be en/ monitored continuously (+.5 ea for any 3)
- 2) Use of buddy system is required (two people in constant contact or communicaticn)
- 3) Two people must sign for key 1scue c) The entrance is gu2rded while area is occupied (can be locked if egress is not hindered)
REFERENCE Svery HP Manual 2-12, pp 3/4 PWG-15(Radcon) (3.4/3.9)
ANSWER 4.17 (1.00) (
11 Following refueling (+.5 ee) j
- 2) If a change in c r i r,1 c a l conditions of , 500 per since lao + criticality <
has occurred REFERENCE Surry OP-1C and OP-58.2.1 001/010; K5.16(2.9/3.3)
ANSWER 4.18 (1.00)
Trip the Turbine BEFORE locally tripping the reactor by opening the r trip or MG set breakerc (+1.0)
RE'ERENCE 3
Sorry AP-20, pp 5 EPE-068;PWG-11(4.5/4.5) l i
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ANSWERS -- SURRY 1&2 -86/07/21-DEAN, WM ANSWER 4.19 (1:50) a) 3rd floor of the maintenance building (+.5 ea) b) Adjacent to the control room c) Next to the Simulator building REFERENCE Surry Emers Plan, pp 1.5/7 PWG-36(2.9/4.7)
ANSWER 4.20 (1.50)
To prevent e:<cessive depletion of RCS inventory (+.75) such that the RCP trip occurs at a point where the break would completely uncover the core (+.75)
REFERENCE Westinghouse background info for E0Ps, 'RCP Trip / Restart' 000/009; EK3.23(4.2/4.3)
ANSWER 4.21 (1.5'0)
~
- a. record this on the critique sheet and initiate procedure deviation (+.5)
- b. Submit PT critique sheet (+.5) and complete the Scheduling Data-Sheet noting reason for non-completion (+.5)
REFERENCE North Anna Admin 11.2 p'10 Surry ADM-89, pp 13 PWG-1(Operator Responsibility during Tes+,s/ Maintenance) (3.5/3.9)
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ANSWER 4.22 t2.""1 Insert control rods in the MANUAL mode (+.25) while maintaining Tavg as necessaryh5) Ensure Tavs is not decreasing when the IR is below the PGAH M ensure Audio count rate meter is on and a SR recorder is selected and the High F l u:- at Shu+down in in block (4 .5) Trip the reactor, ensure ~ ~ ~
all rods on the bottor 3 , ,
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REFERENCE Surry OP-3.1 001/050; PWC-12(3.7/3.7)
ANSWER 4.23 (1.00)
This ensure _ adequate space exists in the PZR, since the potential for void fore 7 tion in the upper head region e::i s t s , and allows increases in the PZR level to accomodate this growth.
REFERENCE Westinghouse Guidelines for ES-0.3, 'NC Cooldown w/ Voids and RVLIS' PWG-7(3.5/4.0) l l
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ENCLOSURE 3 July 28, 1986 Mr. W. M. Dean, Chief Examiner Operator Licensing Section Division of Reactor Safety Docket Nos. 50-280 Region II 50-281 U. S. Nuclear Regulatory Commission License Nos. DPR-32 Suite 2900 - DPR-37 101 Marietta Street, N. W.
Atlanta, Georgie 30323
Dear Mr. Dean:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NOS. 1 AND 2 WRITTEN LICENSE EXAMINATION COMMENTS In accordance with NUREG-1021, Section ES-201, the following comments ~ are submitted concerning the Reactor Operator and Senior Reactor Operator written examinations administered at Surry on July 21, 1986.
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REACTOR OPERATOR EXAMINATION QUESTION f COMMENTS 1.12 Accept on answer key additional reasons listed in referenced lesson plan ND-86.1-LP-5:
Collapse voids
- Backflush boric acid 1.15 Answer could depend on which reference used. In addition to listed parameters, abnormal procedure AP-39, Natural Circu-l lation of Primary Coolant, gives " pressurizer level should be ' 50%, RCS pressure 8
2000#, Subcooling indicated, and S/G lavels at NOL."
! 2.07b Technical Specifications Table 3.7-5 does not accurately l
reflect current system design in that the purge exhaust fans l were removed and replaced by CAT-1 Auxiliary Ventilation Fans which do not trip for any radiation monitor alarms.
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Mr. W. M. Dean Page 2 Recommendation is to remove from answer key the .part referring to the trip of the purge exhaust fans. Also, an additional function provided by this lui is the swap of the Containment IA Compressor Suction from $nside cortainment to the safeguards area.
Reference:
Abnormal Procedure AP-5.8, Step 5.2.1
". . . purge air supply valves close, purge air exhaust valves close, and supply fans trip. Ensure TV-IA-101A & B' close and that alternate suction, A0V-I A-103, opens."
2.09 Total point value for this question is three (3) points (1 point per condition) as per the answer key: Exam shows only 1 point total for the entire question. Due to the depth of knowledge required for this question, 3 points should be correct and the total points for the section changed to reflect this.
2.14 An additional signal which trips this breaker is a 60 second time delay after a 90% undervoltage.
Reference ND-90.3-LP-7, Page 7.18.
2.20b This question implies the lockout of an operating SI pump after the SI signal is received. The referenced lesson plan
' jalltimes. For the question to remain valid, the answer key
~ 'should accept additional answers such as Pressurized Thermal Shock conditions and potential emergency bus overloading conditions otherwise, the question should be deleted from the exam.
3.01 Answers "A" and "B" are both correct responses for this question (meaning that neither A nor B are functiens of permissive P-4).
Reference:
ND-93.3-LP-16, Page 16.6 and 16.7.
3.03 Answers "B" and "C" are both correct responses for this question (meaning that both conditions will result in a higher output from the variable gain unit) . I'f the gain unit has a higher incoming signal, it will have a higher output signal.
Reference:
ND-93.3-LP-3, Page 3. 8.
3.07 Question should be deleted. LOAD SHEDDING is the system associated with the Station Service Buses of both units being simultaneously connected to the Reserve Station Service Buses.
4.05 The answer key responses associated with this question are not correct. This question is an older question from the Revision 0 Emergency Procedures. This question is not valid for the Revision 1 Emergency Procedures.
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Mr. W. M. Dean Page 3 4.10 Answer listed in answer key is not complete. OP-1.1 does not contain a complete quote of the PLS manual statement associated with this question. Answer key should contain Superintendent of Operations permission and either of the following: 1) RCS is borated to CSD concentration, or 2)
RCS is borated to hot xenon free concentration and being maintained at HSD.
Reference:
ND-86.2-LP-7, Page 7.7 and PLS Manual, Page 3.
4.11 This question asks for "substeps" from a " Response Not Obtained Column." Other answers more related to a hi-hi CLS initiation (23 psia), such as verify Containment Spray pumps and Inside and Outside Recirculation Spray pumps operating, should be accepted.
Reference:
EP-1.00, Steps . 9 through 12.
4.14c. There is more than one answer to this question. PLS Manual states 5 cc/kg as given in the answer key. However, Operating Procedure OP-1.3, (Unit Start-Up Operation from 350/450 to HSD) Step 5.43.3 on page 17 of 17, states to 4 verify that RCS hydrogen concentration is 25 - 50 cc/kg.
Therefore, 25 cc/kg is also an acceptable response.
~
4.15 Answer key should have the Ventilation Vent Radiation Monitor (Vent-Vent RM) added to the list. This monitor 3 would have an activity increase if there was a RCS leak in the CVCS charging or letdown lines in the Auxiliary Build- :
ing.
4.17 Add to the list of acceptable answers:
- Outside the band given in an ECP calculation.
Reference:
ND-86. 2-LP-7, Page 7.15.
4.18 It appears, from the answer key, that this question is asking for the sequence of the immediate actions. However, the question does not ask or imply that the sequence must be' given.
4.22 This question should be cut off at the point where the reactor is tripped. To most trainees the tripping of the reactor will probably be considered the point where HSD will be achieved. Suggestion is to stop the answering of the question at the point where the reactor trip occurs.
r
- - - _ _ - - - ,-,..---,-n, -- -- - .-_c ,, - - , -
Mr. W. M. Dean Page 4 SENIOR REACTOR OPERATOR EXAMINATION QUESTION i COMMENTS 5.02 Since the writing of the lesson plan, Technical Specifica-tions have been changed to state that the heat flux HCP is where the rod bowing effects are compensated. Suggestion is to change answer key to make item "B" correct.
Reference:
Technical Specifications section 3.12, Page 3.12-15, Paragraph #2.
5.12 Comment the same as R0 question #1.12.
5.15 Comment the same as R0 question #1.15.
6.04 Comment the same as R0 question #3.03.
6.06 Comment the same as R0 question #3.07.
6.08 Comment the same as R0 question #2.07b.
6.20b. Comment the same as R0 question #2.20b.
7.03 Monitoring of the CSF status trees are implemented by the Shift Technical Advisor upon his arrival in the Control Room followinganyreacjoritrip. At Surry, there is no guidance directing the speciTid. ' implementation of CSF status trees while using EP-1.00. Recommendation is to delete the question from the examination.
7.05 Comment the same as RO question #4.05.
7.07 According to the EP-1.00 foldout page, the correct indicated response for item "B" is that it is not a red path. The red path summary, according to the foldout page, is " narrow range in all S/Gs less than 32% AMD total feedwater flow less than 350 gpm." Recommendation is to change answer key
.to accept "no" as the correct answer. Reference the EP-1.00 foldout page.
7.09 Comment the same as R0 question #4.10.
7.10 Comment the same as R0 question #4.11.
7.13c Comment the same as RC question #4.14c.
l
l Mr. W. M. Dean Page 5 l 7.19 " Plant Staff" does not incorporate Corporate Management which are located in Richmond (example is Senior Vice President - Power Operations for the extension to 2.75 R/qtr). Recommendation is that answer key should be limited
] to 1.25 R/qtr which is approved by Health Fhysics and 1.75 i R/qtr which is approved by the Station Manager. The 1.75 a R/qtr would be the highest quarterly limit approved by 4
" plant staff."
Reference:
Form HP-12, Pages 2 through 5 i (Attachment).
7.22 Comment the same as R0 question #4.22.
7.24 The required knowledge for loss of refueling cavity level, concerning makeup priorities, is to use the LHSI pumps on the affected unit RWST, HHSI pumps on the affected unit RWST, swap to the affected unit containment sump when the affected unit RWST is less than 7%, and the last priority is to swap over and use the other unit's RWST. The inclusion of makeup source parameters as indicated in selection #4 does not alter the priority. It only served to cause confusion within the question as to whether the conditions given in selection 4 applied to only one choice, one choice and all remaining selections, or all four choices listed.
This question does not accurately test the proper sequence
- - of makeup priorities. Recommendations are to either (1) only grade the top two priorities (i.e., choice #3 first followed by choice #1) or (2) accept choices 3, 1, 4, 2 as the most acceptable sequence response for this question.
8.08 The answer key for the question is not correct. Technical Specifications Section 3.0.2 allows a component to be in-operable solely because one of its power sources are inop-erable. However, it also specifies that this specification is ". . . not applicable in cold shutdown or refueling shut-down conditions." This makes the "A" RHR pump inoperable.
Technical Specification 3.10.6 states that at least one RHR pump and heat exchanger shall be operable. Removing the "B" RHR pump from service would violate this specification.
Specification 3.10.6 also states that the RHR' loop may be removed from operation for up to I hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of core alterations or reactor vessel surveillance inspections. The performance of RHR pump motor surveillance is not considered to be " core alterations" or
" reactor vessel surveillance inspections."
Mr. W. M. Dean Page 6 The recommendation for this question is to' change the answer key.to reflect that maintenance cannot be performed because-T.S. 3.0.2 is not applicable during refuelir.g shutdown conditions and removal of the pump from service would violate T.S. 3.10.6.
8.13 The term "aside from reactor operators" will eliminate the "Radwaste/ Third Reactor Operator (1)" from the answer list.
. By using the phrase which excludes the inclusion of any Ros, it is implied that no reactor operator positions need be listed. Recommendation is that the position for the "Radwaste/ Third R0 (1)" be removed from the answer key.
Very truly yours, WW -
Q,G R. F. Saunders Jf A. Bailey Surry Station Manager S aerintend t - Nuclear Training bc: Mr. R. F. Saunders Mr. D.' A. Benson Mr. H. L. Miller Mr. D. A. Christian .
Dr. B. L. Shriver N)#
Training Department - Surry GOV ,02-54 i
k
POW 24-03 HP-3.1.2 (FORM hP-12) ATTACHMENT #9 Pass 2 oi 11 RADIATION EXPOSURE EXTENSION FORM JUN 3 1986.
TLD NO LAST NAME FIRST NAME M1 AGE SOC SEC NO COMPANY DEPARTMENT CRAFT
- x*******************xe*****g QUARTERLY EXPOSURE EXTENSION FROM 750 MREM NOT TO EXCEED 1250 MREM .
- n***********************************************************xa********
CURRENT ADMINISTRATIVE LIMIT 750 MREM NRC FORM-4 IS ON FILE YES CURRENT QUARTER ONSITE hREM .
CURRENT QUARTER OFFSITE MREM TOTAL QUARTER MREM YEAR TO DATE ONSITE MREM YEAR TO DATE OFFSITE MREM TOTAL YEAR TO DATE MREM.
LIFETIME TO DATE EXPOSURE REM PAD REMAINING TO DATE REM AUTH0kIZATIONS/ APPROVALS FOR EXTENS, ION NOT TO EXCEED 5000 MREM YEARLY st :s
' ~
INDIVIDUAL; DATE:
IMMEDIATE SUPERVISOR: DATE:
DEPARTMENT HEAD: DATE:
SUPERVISOR HEALTH PHYSICS: DATE:
l REASONS FOR EXTENSIONS:
1 l
.- * ," POW 24-03 HP-3.1.2 (FORM HP-12) ATTACHMENT #9 Page 3 of 11 JUN 3 1986 RADIATION EXPOSURE EXTENSION FORM TLD NO LAST NAME FIRST NAME MI AGE SOC SEC NO COMPANY DEPARTMENT CRAFT
- n********************************************************************g g QUARTERLY EXPOSURE EXTENSION FROM 1250 MREM NOT TO EXCEED 1750 MREM
- nn***********************************************************************
CURRENT ADMINISTRATIVE LIMIT 1250 MREM NRC FORM-4 IS ON FILE YES CURRENT QUARTER ONSITE HREM -
~'
CURRENT QUARTER OFFSITE MREM TOTAL QUARTER MREM YEAR TO DATE ONSITE MREM YEAR TO DATE OFFSITE MREM TOTAL YEAR TO DATE MREM-LIFETIME TO DATE EXPOSURE REM PAD REMAINING TO DATE REM AUTHORIZATIONS / APPROVALS FOR EXTENSION h0T TO EXCEED 5000 MREM YEARLY INDIVIDUAL: DATE:
IMMEDIATE SUPERVISOR: DATE:
DEPARTMENT HEAD: DATE:
SUPERVISOR HEALTH PHYSICS: DATE:
STATION MANAGER / ASSISTANT MANAGER: DATE:
REASONS FOR EXTENSIONS:
l I
i
+- . POW 24-03 hP-3.1.2 (FORM HP-12) ATTACHMENT fl9 Page 4 of 11 RADIATION EXPOSURE EXTENSION FORh TLD NO LAST NAME FIRST NAME M1 AGE SOC SEC NO COMPANY DEPARTMENT CRAFT I
- n************************************************************************
- QUARTERLY EXPOSURE EXTENSION FROM 1750 MREM NOT TO EXCEED 2250 MREM *
- =***************************************n*******************xa**
CURRENT ADMINISTkATIVE LIMIT 1750 MREM NRC FORM-4 IS ON FILE YES CURRENT QUARTER ONSITE MREM -
CURRENT QUARTER OFFSITE MREM TOTAL QUARTER MREh YEAR TO DATE ONSITE MREM YEAR TO DATE OFFSITE MREh TOTAL YEAR TO DATE MREM-LIFETlME TO DATE EXPOSURE REM PAD REMAINING TO DATi REM AUTHORIZATIONS / APPROVALS FOR EXTENSION NOT TO EXCEED 5000 MREM YEARLY ...
- Si
- 1 9 INDIVIDUAL: DATE:
t IMMEDIATE SUPERVISOR: DATE:
DEPARTMENT HEAD: DATE:
S'JPERVISOR HEALTH PHYSICS: DATE:
STATION MANAGER / ASSISTANT MANAGER: DATE:
VICE PRESIDENT - ~ NUCLEAR OPERATIONS DATE:
RECEIVED BY: TIME:
REASONS FOR EXTENSIONS:
1-l r
. - _ .. ~ _, - _ _ , _ _ _ . . _ _ . . . _ _ _ - - _ _ _ , , . . _ . _ . _ . . _ _ . _ _ _
.************a*******************x**********************************************g g QUARTERLY EXPOSURE EXTENSION FROM 2250 MREM NOT TO EXCEED 2750 MREM *
- x***********************************************************x**********
CURRENT ADMINISTRATIVE LIMIT 2250 MREM NRC FORM-4 IS ON FILE YES CURRENT QUARTER OhSITE MREM .
CURRENT QUARTER OFFSITE MREM TOTAL QUARTER MREM YEAR TO DATE ONSITE MREM YEAR TO DATE OFFSITE MREM TOTAL YEAR TO DATE MREM.
LIFETIME TO DATE EXPOSURE REM PAD REMAINING TO DATE REM AUTHORIZATIONS / APPROVALS FOR EXTENSION NOT TO EXCEED 5000 MREh YEARLY
- {d .
, INDIVIDUAL: DATE:
. IMMEDIATE SUPERVISOR: DATE:
DEPARTMENT HEAD: DATE:
l SUPERVISOR HEALTH PHYSICS: DATE:
- STATION MANAGER / ASSISTANT MAlULGER
- DATE:
VICE PRESIDENT - NUCLEAR OPERATIONS DATE:
RECEIVED BY: TIME:
SR. VICE PRESIDENT - POWER OPERATIONS DATE:
RECEIVED BY: TIME:
REASONS FOR EXTENSIONS:
- . _ , . - - _ - . . _ . - . - _ _ - - - . - . . . - . . - . . . - . . - . .- .