IR 05000354/1989008
| ML20248G564 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/22/1989 |
| From: | Conte R, Florek D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20248G555 | List: |
| References | |
| 50-354-89-08OL, 50-354-89-8OL, NUDOCS 8910100299 | |
| Download: ML20248G564 (63) | |
Text
{{#Wiki_filter:_ _ _
,,
, i U.S NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO: 50-354/89-08 (OL) FACILITY DOCKET NO: 50-354 FACILITY LICENSE NO: NPF-57 LICENSEE: Public Service Electric and Gas Company
P.O. Box A Hancocks Bridge, New Jersey 08038 FACILITY: Hope Creek Nuclear Generating Station EXAMINATION DATES: July 17 - 20, 1989 EXAMINERS: T. Walker, Sr. Operations Engineer G. Robinson, NRC Consultant . William, xami er in Training CHIEF EXAMINER: NI M ( s D6nald Florek, Sr. Operations Engineer / Datqf BWR Section, Operations Branch, DRS APPROVED BY: Icie b 9 12 $ RichardJ.Conteghief ' Date ' BWR Section, Operations Branch Division of Reactor Safety SUMMARY: Written examinations and operating tests were administered to four reactor operator applicants. All of the applicants passed the written and operating tests which reflected good preparedness on the part of the facility licensee and the candidates.
During the examination the examiner noted poor condition of the submitted reference material and poor condition of certain control room drawings. The NRC staff also noted that a section of the Emergency Operating Procedures reflected a strategy different from the Owner's Group Guidelines.
8910100299 8909 M ppR ADOCK 0500
v ___ ___-_ - _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _
.- _.
L,. p.. a , i
DETAILS' 1.0 INTRODUCTION AND OVERVIEW The NRC examiners conducted this initial examination for four reactor
- operator (RO) applicants. The examinations were administered in accord-ance with NUREG 1021', " Examiner Standards'(ES)" Revision 5, dated January
~1, 1989. The results.are summarized below.
l R0-l l Pass /Faill l I I l Written l '4/0 l
l l l l l l Operating l 4/0 l l l l l l l l Overall l 4/0 l
I l 2.0 EXAMINATION RELATED FINDINGS / CONCLUSIONS Due to the limited number of applicants for this examination no generic strengths and weaknesses were identified on either the written or operating portion of the examination. Overall the candidates were well prepared for the examination.
The reference material provided by the licensee for the preparation of the examination had several examples of poor quality control during assembly.
. Many missing pages were noted in the simulator malfunction book and in the Sequence of Alarm book, missing procedures were noted when compared to the index of procedures in the reference material package, the index of procedures was not current with the procedures submitted and the E0Ps submitted were barely readable. The facility provided acceptable material following NRC request.
The licensee representative acknowledged the examiner's request that future submittal of reference material to the NRC include Procedure SA.AP.ZZ-002 Conduct of Operations as well as administrative procedures to control maintenance activities as noted by the NRC 90 day letter.
3.0 ADDITIONAL FINDINGS During the course of the operating test the NRC examiners observed that several of the Piping snd Instrument Diagrams (P& ids) in the control room were torn or ripped such that some information on the P& ids were not readable.
It appears that this was due to the extensive use of the P& ids by the operations department. The licensee representative agreed to follow up on the concern.
- - _ _ _ _ _ _ _ _ _ _ -
' , . .
The strategy of the Owners' Group Guidelines with respect to the pressure control leg of the reactor pressure vessel (RPV) section of the E0P is to conduct a normal cooldown (within technical specification cooldown rate limits) during emergency conditions. The licensee's implementing proce-dure permits staying at hot standby during emergency conditions. The , licensee representatives could not provide written justification for the apparent change from the guideline's strategy. At the exit interview licensee representative agreed to review the staff's concern.
The licensee representative noted that they are revising the E0P's to reflect Revision 4 of the Owners' Group Guioelines.
4.0 MANAGEMENT MEETING 4.1 ATTENDEES U.S. Nuclear Regulatory Commission R. Conte, Chief, BWR Section D. Florek, Sr. Operations Engineer G. Meyer, Sr. Resident Inspector T. Walker, Sr. Operations Engineer H. Williams, Sr. Operations Engineer Public Service Electric and Gas Company C. Vondra, Operations Engineer W. Gott, Principal Training Supervisor G. Mecchi, Principal Training Supervisor M. Cire11y, Engineer P. Opsal, Engineer 4.2 SUMMARY COMMENTS A pre-examination review was conducted on July 17, 1989, with facil-ity representatives from the Training and Operations staff. During I the course of the pre-examination review positive comments were provided by the facility representatives which resulted in improve-i_ ments to the examination which were incorporated into the examination ! before it was administered. The facility formally provided four additional comments at the exit meeting as noted in Attachment 2.
Access to the facility went smoothly with no problems noted.
The operations staff in the control room maintained an environment that was conducive to the administration of the operating test.
The final results were not discussed during the exit meeting.
Every effort would be made to provide the applicant results in approximately 30 days.
_ _. _ _ _ _ _. ._____-__ _ __-_ ,5 e.
- .'
The additional-findings, identified in Section 3.0 above, were discussed during the exit meeting.
.. 5.0 POST-EXIT MEETING' At the request.of the facility, a meeting with the NRC staff to further L discuss the NRC concerns regarding Emergency Operating Procedures was held on August 2, 1989. The fo'llowing individuals met in the Region I office: M. Cirelly, PSE&G P. Opsal, PSE&G-J. Galamback, General Physics Corp.
J. Murry, General Physics Corp.
D. Florek, NRC C. Sisco, NRC T. Walker, NRC The discussions again focused on the initiation of a normal cooldown, within the' technical specification rate, during an amergency. The licen-see's procedure for the pressure control leg of the reactor pressure vessel. procedure appear to be a change in ' strategy-from the BWR Owners, Group Emergency Procedure Guidelines, as described in Section 3.
Based on the discussion the facility will assess the NRC concern and address the issue. The facility plans to also discuss the NRC concern with the BWR Owner's Group for further clarification.
Attachments: 1.
Reactor Operator Written Examination and Answer Key 2.
Facility Comments on Written Examination after Facility Review 3.
NRC Response to Facility Comments 4.
Simulator. Fidelity Report ___ _ ___ ____ _ _ -
__- - __ _ pTTPLDnEMT "\\ pgp '
' U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 1 FACILITY: HOPE CREEK REACTOR TYPE: W R - GE4 ~ DATE ADMINISTERED: 89/07/18 INSTRUCTIONS TO CANDIDATE: Use _ separate paper for the answers. Write answers 'on one'_ side only. ' Staple ovestion sheet on _ top of - the answer sheets.. Points f or each question are - . indicated in parentheses after the Question.
The passing grade rc:;uires at least 70% in~ each category and a final grade of at least 80%. Examination papers will: be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY '/VALUE-TOTAL SCORE VALUE CATEGORY , .\\ i3 25.00 25.20 1.
REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (II%) (FUNDAMENTALS EXAM) i i3 2.
EMERGENCY AND ABNORMAL PLANT 27.00 27.90 _ EVOLUTIONS (27%) 'n.so 47.74-46-09- ' 4Br00-3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC ' RESPONSIBILITIES (10%) 99.se % TOTALS-100-09- _ FINAL GRAPE All work done on this examination is my own.
I have neither given nor received aid.
- Cancicate*s Signature
9 _ _ _ _. - _ _ _ _ _ _ _ _ _ _ _.. _ _ _ _ _ _ _ _ _ _ _______ _-_ __
- __ - - __ _ . p.
I.1 ( i f _ '
se Le .NRC: RULES.AND GUIDELINES' FOR LICENSE EXAMINATIONS. , 3.; ~ DuringEthe administration'of-this examinationLthe following rules apply: "1; Cheat'ing onLtheLexamination means an automatic denial of your application and could result:in:more' severe. penalties.
E2. Afterfthe examination has been. completed, you must sign the statement on the. cover sheet indicating that the work is your own and you have not ~ received._or.given assistance in comp 39 ting the examination.
ThisJmust be.
.done: after; you; complete the examination.
' ~3.
Restroom trips'are to be limited and only one candidate at a. time may leave. LYou must avoid all contacts with.anyone outcide the examination
- room 1tocavoid even the appearance or possibility of cheating.
'4.
Use black. ink or dark pencil only to facilitate legible reproductions.
5; Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
56. Fill in the date on the cover sheet of the examination-(if necessary).
'7.
You may write your answers on the examination question page or~on a separate sheet of paper.
USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON' THE BACK SIDE OF THE PAGE.
, '\\ 8..If you write your answers on the examination question page andryou need more space to answer a: specific question, use a separate sheet of.the paper provided and insert it directly after the specific question.
DO NOT ~ WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
9.. Print your name in the upper right-hand corner of.the first page of'each section of your answer sheeth whether you use the examination question pages or separate sheets of paper.
Initial each page.
'10. Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing yrur answers on the. examination question page.
-11. If you are using separate sheets, number each answer as to category and number (i.e. 1.04, 6.10) and skip at least 3 lines between answers to allow space for grading.
12. Write "End of Category " at the end of your answers to a category.
. 113. Start each category on a new page.
114. Write "Last Page" on the last answer sheet.
15. Use abbreviations only if they are commonly used in facility literature.
Avoid using symbols such as < or > signs to avoid a simple transposition error resulting in an incorrect answer.
Write it out.
16. The point value for each question 5. indicated in parentheses after the question.
The amount of blank space on an examination question page is NOT an indication of the depth of answer required.
i - - _ _ _ _ _ - - _ _ - - - _
l' 'g
4 17ifShow-all calculations, methods, or assumptions used to obtain an answer.
t.
. 18. Partial credit may be given.
Therefore', ANSWER ALL PARTS OF THE QUESTION i AND DO NOT LEAVE ANY ANSWER BLANK.
~ NOTE: partial credit will NOT be given on multiple choice questions.
19. Proportional grading will be applie'd'. Any additional wrong information that is provided.may count against you.
For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth 0.20 points.
If one of your five responses is incorrect, 0.20 will be ' deducted and your total credit for that question will be 0.80 instead of 1.00 even though you got the four. correct answers.
20.'If the intent of a question is unclear, ask questions of the examiner caly.
21. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets.
In addition, turn in all scrap paper.
22. To pass the examination, you must achieve an overall grade of 80% or greater and at least 70% in each category 23. There is a time limit of (6) hours for completion of the examination.
(or some other time if less that the full examination is taken.)
\\ 24. When you are done and have turned in your examination, leave the examin-ation area as defined by the examiner.
If you are found'in this area while the examination is still in progress, your license may be denied or revoked.
l .- _ -_.-_-_____--___- - -_ _
.m 0 '*: '
- ;'
. L
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 23-(27%) -QUESTION .:2.01 (1.00)
- In accordance with OP-AB.ZZ-105(Q), " LOSS.0F CRD REGULATING FUNCTION",
'WHICH ONE (1) of.the below named conditions require that the operator- ' manually scram the reactor? (1.0) ' -a.
Reactor pressure is 860 psig and more than one accumulator-alarm present.
b.
Reactor pressure is 860 psig,and charging water header pressure.canLnot be restored within 20 min.utes.
c.
Reactor pressure is 980 psig and more than one accumulator alarm prgrent.
.d.
' Reactor pressure is 980 peig and charging water herder pressure can not be restored within 20 minutes.
. \\ . . (***** CATEGORY 2 CONTINUED CN NEXT PAGE
- )
. . - _.. - _ - - -... _ - -. _. _ _ _ -. _. - _ _ _ _ _. _ _ _..... _ _. - - _ - - ..
_ -. _ _ . _ _ _ _ - _ - _ - - - _ - _ _ _ _. _-__- __ -____ - =1 . ;, ,. $ ~.- b l. J (; _.: ;;, ' - >:,. d t
. . / l 2.. -EMERGENCY AND ABNORMAL'P'LANT EVOLUTIONb 'Page 2fs (27%) Q (QUESTION-
- 2.02_
(3.00) . 6 '- 'Inlaccordance with'OP-AB.ZZ-111(Q), " JET PUMP ~ FAILURE", STATE the THREE-L(3): symptoms.which when-differing by more.than 10~. would
- indicate a Jet pump had' failed.
-( 3. 0 ). . . . - I f. - _.
h \\ , ,- .. . ' ,. p.- l-I l l l.
.. l;
i I (***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
_ _ _ _. __- _ ____________________________________________j
_ _ , ___ .. . _ - _ --. , l s[, ) lj' '. ^ ' , , &;! 2x-t .. ' < 3.., ,, a s .f
- l'
, r ' ' ' L 2.' ' EMERGENCY ' AND ' ABNORMAL ~ PLANT EVOLUTIONS- .P' age :25
l' (27%)-
, .. ci $.kUESTION-2.03 (1.00)- . , ,
. k:Upsn - a main generator..-load L ref ection at f ull - power, La reactor scram' fisLinitiated to. reduce: reactor power in anticipation.of-:a .( 1 '. 0 ) : . , .0; ' 1;:c. .a.
. Reactor: water. level increase.
b.' Reactor ~ water' level decrease.
' , ,. .c.- Reactor pressure. increase.
., .,. . n.. . .- , l
, d.- -Reactor pressure: decrease.- .
- +
' 'i.
' , ..a.
p-
o
i .j l . i s ,: \\. j 'l
- l
- a
, I') ll i
!
- j
-) i l
1-j
I , ! 'l ! I l ) l J
(*****- CATEGORY 2 CONTINUED ON NEXT PAGE
- )
- -- - _ _ _ _ _ _ - _ _ _ - _ _ _ _
.. . -_-. - .
- .
L.,;; .. .: 2.. EMERGENCY AND' ABNORMAL PLANT EVOLUTIONS Pase
(27%)- ' 'QUEGTION 2.' O h-(1.00) i l.: Procedure OP-EO'.ZZ-102, " CONTAINMENT CONTROL", contains a caution that reminds the operator notto initiate'drywell sprays if the suppression pool level is above 142.5 inches.
EXPLAIN the basis for
thisl caution.
(1.0) ! .. \\ l . (***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
__ - _ _ - _ _ _ _ - - _ - _ - _ _ _ - _ _ - _ _ _
-- _ .... .. 2 2.. EM RGENCY AND ABNORMAL. PLANT-EVOLUTIONS Page~ 27-(27%) QUESTION 2.05 (2.00) MATCH the automatic actions in Column A with the appropriate value > of' condenser vacuum 1in Column B.
A value in Column B may be . utilized ONLY once'.- (2.0).
ECOLUMp A COLUMN B-a.
MSIV Closure 1.
4.5 in HGA b.- Main Turbine Trip 2.
5.8 in HGA.
c.
Bypass Valve. Closure 3.
7'. 5 in HGA-d.
. Reactor Feed-Pump Trip 4.
10.0 in HGA 5.
21.5 in HGA 6.
22.9 in HGA . \\ , , i , (***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
, )
., -. -. -- - - .. ... [:. ' ' PLANT EVOLUTIONS page
E 2. EMERGENCY AND ABNORMAL (27%) QUESTION 2.06' (1.00) AS indicated in OP-AB.ZZ-135(Q), " STATION BLACKOUT // LOSS.OF L OFFSITE POWER // OIESEL GENERATOR MALFUNCTION", upon loss of power (LOP).all Class 1E System Instruments are powered from , (a) supplies which auctioneer to their associated (b) VDC supply.
(1.0) ! .. , i , -\\ , l.
(***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
- - _ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_ _ _ _ _ _ _ _ _
- '
... .. ,,, '2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page
(27%) QUESTION 2.07 (3.00) c '. Indicate the TWO (2) plant conditions given in OP-AB.ZZ-300(Q), " Reactor Power Oscillations", which require placing the reactor mode switch in the SHUTDOWN position if these conditions occur.
(2.0) ,b'. Why should NEITHER the CRIDS NOR the SPDS displays be used to monitor.for core oscillations? (1.0) i i .
i
l l l l (***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
I i - - _ _ _ - - - - - _ _ _____--______u
-, _ - e . ,,., ..
L "2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page
l l-(27%) l . QUESTION 2.08 (3.00) For each PLANT CONDITION listed below, IDENTIFY the appropriate PROCEDURE (S) to be utilized.
If none, STATE NONE.
(3.0)
.. ' Consider each plant condition separately.
' ' NOTE: A PROCEDURE may be used more than once or not at all.
PLANT CONDITION PROCEDURE .. a.
Suppression Pool level 1.
OP-EO.ZZ-101 of 71 inches.
RPV Control b.
Sample analysis of gaseous 2.
OP-EO.ZZ-102 effluent (total all vents) Containment Control '10 microcuries per sec.
\\ o,f Iodine-131.
3.
OP-EO.ZZ-103 Reactor Building Control c.
Reactor pressure 1048 psig.
4.
OP-EO.ZZ-104 d.
MSIV closed on a valid high Radioactive Release 5%mionet teepera%te, imkhcn 5(gnal, 5.
OP-EO.ZZ-318
e.
Reactor Building Diff. Press.
Containment Venting 0 inches water.
f.
Drywell temperature 142 degrees F.
(***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
. _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ - _. - _ _ _
i .. , . l ' 2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page
) (27%).
QUESTION 2.09 (2.00) j During a plant shutdown with Reactor Pressure at 65 psig, it is discovered that the Shutdown Cooling System cannot be placed in service and the Recirculation pumps are not available.
In accordance j with OP-IO. ZZ-004 (Q), " Shutdown From Rated Power to Cold Shutdown", { a reactor water level of greater than or equal to 80 inches should be maintained.
a.
WHY is this level required? (1.0) b.
IDENTIFY the level instrumentation range required to be used to indicate this level.
(0.5) c.
WHAT system is utilized to remove decay heat? (0.5) . \\ . r
(***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
_ _ _ _ - _ - _ __ _ __-__--_-__ -
{ 7; p.. ..::. . !; 2.
EMERGENCY AND. ABNORMAL FLANT EVOLUTIONS Page
-(27%) l ' , . QUESTION 2.10 (2.00) Procedure OP-EO.ZZ-100(Q), " Reactor Scram", conteins an Operator Caution that prohibits operation of HPCI or RCIC below 2150 RPM.
Statefthe TWO-(2) reasons that form the basis for this caution.
(2.0) . \\ . , (***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
_ _ - _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ - _ _ _ _
(. . -- . _. l-('. ' .. t- .- L
- .
y2.
EMERGENCY AND ABNORMAL' PLANT EVOLUTIONS Page
i.
(27%) -QUESTION 2.11-(1.5) ' In Procedure OP-EO.ZZ-101, "RPV Control", step RC/L-9 states "If RPV LEVEL FALLS BELOW - 129" THEN DSLAY ADS INITIATION BY RESETTING' JTHE TIMERS".. Give THREE (3) reasons WHY this step is necessary.
(1.5) x , . \\ , - j (***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_ _ _ _ _. _ _ _ _, ... < ,.. }. ' .
- 2.. EMERGENCY AND AlsNORMAL PLANT EVOLUTIONS .Page
-(27%) QUESTION 2.12 (1.50) 'l-In accordance withOP-AB.ZZ-117(Q), " Reactor High Level", f INDICATE All the automatic actions which would occur when' LEVEL 8 is reached.
(1.5) ., i . . . l l .
I (***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
' _ _ _ _ - _ _ _ _ - _ - _ _ _ _ _ - _ _ -
_ _ -- - _ _ _ _ _ -. - . ... .. 'G- . 1. 2.. EMERGENCY:AND ABNORMAL PLANT EVOLUTIONS Page
t h . -( 2 7 % )
- QUESTION 2.13-(2.00)
During normal operation' at f ull power, a decreasing reactor vessel " level is noted.
As indicated in OP-AB.ZZ-200(Q), " Reactor Low' Water Level", WHAT TW0 (2) immediate operator actions. should be taken, if appropriate, to restore. vessel level to between Level 6 and Level:7? (2.0) ,
.
. $
(***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
x _ _. _ _ _ _ _ _ _. _ _.. _ _ _ _. _ _ _. _ _ _ _.. _ _ _ _ i
. ___ - ___ -__,_- _ - _ ___ _ - - - - -_ L F,. c.: ; , .. p. f2.- : EMERGENCY AND ABNORMAL'-PLANT ~ EVOLUTIONS Page
L
- ( 2 7 %)'
-. '; QUESTION 2.14;
- ( 3 '. 0 0 ) '
, I lAssume the reactor is. operating at full power. ' Column 2 lists ~ [' l Column -1lists isolation parameters.. For each parameter - given in ceven --.i ndividual~ pr.imary containment 'i sol ation val ve. groups.
~ ~ Column.1',LSE. LECT the; group (s) from Column;2;that use;this parameter- -
- to'
- generate an: isolation signal for ANY or ALL of,the valves in
- t hat ' g roup.. ' NOTE': Each' parameter.may have more than one group
' listed.
If the. parameter generates no isolation signal, STATE NONE.
' COLUMN-1 COLUM,N 2 g gt, O f g d M Q \\/ ' a.- Drywell Pressure HIGH-Ht60 1.
Group 1-MSIV ealing . . System Isola, tion-Valves b.
Reactor' Vessel Water l5 VEL I 2.
' Group 2 - Reactor c.
Main' Steam Line Recirculation' Water Sample- ' E Radiation - HIGH-HIGH System v . . . . ~d.
Reactor' Vessel Water-3.
GROUP 8 - Torus Water \\' ' LEVEL 2' Cleanup System s . .e.
Main Steam'Line.
4.
GROUP 10. -Drywel l Cool' ers - -' Pressure --Low Recirculation.
5.
GROUP 11 - f.
Reactor Building Exhaust Pump Seal LWice Isciab MVec.
-Radiation - HIGH ~ 12 - Containment 6.
. GROUP , ' Atmospheric Control System 7.
Group.16.- Reactor Auxiliaries-Cooling. System (***** END OF CATEGORY 2
- )
_ - _ __ ___-_---_-_____-__O
, _ . - _ _ .-_ y
-{
, '...;. , - , ' , l '3.
' PLANT-SYSTEMS-(38, AND' PLANT-WIDE GENERIC Page' 37 , - RESPONSIBILITIES-(.,%) L IQUESTION- -- 3. 01'- (1.00) .s -
- INDICATE'which ONE (1)'of the following conditions will NOT.cause
. ' , ' ' En APRM'INOP.. trip.
(1.0) ,. a.- Lessithan.two LPRM inputs.per level.
b.
Less than fourteen (14) LPRM inputs.
c.
Channel mode switch'out of operate, t i 'd.- Module unplugged i / \\' . r
(***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
- _
.. _ - _ _ _ -., _ _ _ . - -- -. .- .- _. _. {{s , , < < + . y3 7 :....j..,.,^', .j.
, . Of;h . - . y% . ,, u.,z ,
' & J3l PLANT'SYSTEMSC(38%)'AND PLANT-WIDE GENERIC Page. 38~ -RESPONSIBILITIES (10%) ' o f QUESTION 3.02-(2.00)L Concerning,the Core Spray.Line Break Detection System: - a.
- HOW is'.alline; break detected?
(1.0)- . , ' b.
WHEN'is the line. break indication'NOT valid?. (1.0) .. .. . . . . d 0, - . .g . ,
.
4- . I ' i l (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
, !, ___ _--_-.._.___-_---_ _ - -
,., -__;_ .- - - , .: +. .. .. -3.- PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page
RESPONSIBILITIES (10%) ' QUESTION.
3.03 (1.00) SELECT the ONE (1) correct statement given below that applies to'th Rod Worth Minimizer (RWM).
(1.0) a.
One insert error will initiate a rod block action.
b.
If the pull sheet minimum limit is notch 10, the alternate position is notch 12, c.
'one withdraw error will not initiate a rod block action.
d.
For notch 00, the RWM alternate position is notch 02.
\\ ! (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
. - - _ _ - _ - _ - _ _ - _ - _ _ _ _ _ _ - _
__ .. .,
3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page
RESPONSIBILITIES (10%) QUESTION 3.04 (1.50) While operating at full power, ONE (1) level transmitter in the Radundant Reactivity Control System (RRCS) fails downscale.
A spurious water signal of -44 inches is received for three c conds by the other transmitter in that channel.
a.
Does the reactor scram? Briefly explain WHY or WHY NOT.
(0.75) b.
Do the recirculation pumps trip? Briefly explain WHY or WHY NOT.
(0.75) \\ i I i I (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
_ -_ - _ _ _ - _ -. - _ _ _ _ -
- _ _ _ _ _ _ _ ., . , 3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 41 RESPONSIBILITIES (10%) QUESTION 3.05 (3.00) Concerning the Reactor Water Cleenup System (RWCU): a.
For the blowdown flow control valve (FO33): 1.
State the TWO (2) conditions that will cause the valve to auto-close.
Include setpoint and location of sensor relative to the valve.
(1.5) 2.
WHAT is the failed position of the valve upon Loss of Instrument Air? (0.5) I - b.
WHAT is the purpose of the blowdown line restricting orifice
(FO-D001)? (1.0)
\\ ! ! (=**** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
o
-. - - - - - - - - - _ _ _ _ _ - - - _ __ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ - - - - - - - - -. _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. - - _ _ _ _ _ _ _ _ ... - ... . 3.
PLANT SYSTEMS-(38%) AND PLANT-WIDE GENERIC Page
RESPONSIBILITIES-(10%) QUESTION 3.06 (1.00) .In accordance with SA-AP.ZZ-046,." Radiological Access Control- , Program", a self-reading dosemeter: a.
Shall be rezeroed when the readout exceeds (1) when issued and when the readout reaches (2) during.
use.
(0.5) b.
Shall be read every (1) minutes when working in a HIGH Radiation Area.and every-(2) . minutes when working in a Radiation Area.
(0.5) \\ (***** CATEGORY'3 CONTINUED ON NEXT PAGE
- )
i - .-- . _ _ _ _. _ _ _. _ _ _ _ _ _ _ _ _ _. _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
-_ .-- _ _ _ _ - . - - - _ - _ - - - _ _. - - - - - - _ _ _ _. - - _ - _ _. - - - -. - _. - - - - _ - - - - - - - - _ - _ _ _ _ _, ... -j- . + ) m 3.
PLANT SYSTEMS-(38%) AND PLANT-WIDE ^ GENERIC Page
RESPONSIBILITIES (10%) QUESTION 3.07 (2.50) MATCH ~the' automatic function given in Column A with.the correct reactor water level in Column B.
Levels can be used more than .once or'not at all.
(2.5)
!
- COLUMN A COLUMN B
! i AUTOMATIC FUNCTION REACTOR WATER LEVEL l
= . . c.
Auto start of diesel generator 1.. +54 inches l . . l b.
Reactor. scram 2.
+39 inches . ! c.
Reactor Building Filtration, 3.
+30 inches Recirculation, and Ventilation System (FRVS). auto starts 4.
+12.5 inches l 'd' MSIV closure.
5.
-38 inches 's . o.. Shutdown cooling. isolation 6.
-129 inches' ' valves close i i l l i l i i I , .. l I i i i I I ! i i l (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
. ---_-----__---_---._---._-_-------)
-- . -.. _ ._ . - _ _ - _. _ _ _ _ - - _ _ _ - _ - _ _ _ _ _ _ - _ _ _ _
_L, .
. 3.- PLANT SYSTEMS'(38%) AND PLANT-WIDE GENERIC Page' 44 RESPONSIBILITIES (10%) ' QUESTION 3.08.
(1.00) Assuming full power generation, automatic three-element control from'the Haster Level Controller and.no operator action, SELECT which~ONE (1) of the following statements would be'the expected reactor water level control system response, if the selected level transmitter failed HIGH.
(1.0) a.
RFP turbines would lock due to loss of level. signal input and level would remain approximately the same.
b.
RFP turbines reduce speed in response to high level signal and level will continue to drop until reactor scrams.
c.
Steam and'feedwater flow inputs would compensate for the error' signal and level would stabilize at a slightly lower level.
d.
Level input would automatically transfer to the other.
'\\ level transmitter and level would remain approximately - the same.
I i (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
J l _ ._ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
m... .. .', ". - ,. "'
--
,, 'u i!{. E?-
'7 1. l?2 di h ' f:,g, ' ' , , .. . 4. - , ,M 3.
PLANT SYSTEMS:(38%) AND PLANT-WIDE GENERIC- 'Page'.45,
- '
i. t t . RESPONSIBILITIES (10%) r ' QUESTION' . 3.09: (1.00).
,
STATE the: reason ~WHY the HPCI-system reactor'high water level Ltrip bypass. switch was installed.
(1.0) u.
.:\\l
- F.,
. L , ,a.- \\ .. (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
' ' .--_-__--___ - _ ______ -________ - - _.
'. . . . l ! l l 3.
PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page
I RESPONSIBILITIES (10%) . QUESTION 3.10 (1.00) ] Which ONE (1) of.the following provides the signal for the Turbine Control Valve (TCV) Fast Closure scram? (1.0) j
a.
TCV position limit switches.
I I , b.
Rate of TCV position change.
' c.
Power to the TCV fast acting solenoids.
- d.
ETS oil pressure at the TCV.
, ' . .. - . (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
-. _.. _ - _ _ _ -
. .. i 3o-PLANT SYSTEMS'(38%) AND PLANT-WIDE GENERIC Page
RESPONSIBILITIES-(10%) . QUESTION 3.11 (1.50) Concerning the Condensate System a.
With at least FIVE (5) of the SIX (6) condensate pumps running: 1._ Any condition that results in the stopping of primary condensate pump (s) will trip the associated secondary condensate pump (s).
(0.25) 2.
Any' condition that results in the stopping of secondary condensate pump (s) will trip the associate reactor feedpump(s).
(0.25) b.
With all condensate and reactor feedpumps operating: 1.
The loss of ONE (1) primary condensate pump with \\ feedwater greater than 75 percent will cause a , feedwater pump runback to percent and a(n) recirculation pump runback.
(0.5) 2.
The stopping of ONE (1) secondary condensate pump, with feedwater greater than 85 percent will cause a feedwater runback to percent and a(n) recirculation runback.
(0.5) , (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
_ _ _ _ _ _ _ _ _ _ _ _ -_________ -
. - - - _. . ,, .. ~ ' ' ' s, , 13. ) 4 PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page. 48 i, . RESPONSIBILITIES (10%). 5 QUESTION 3;12.
(l'.50)'- G.
'With'the' mode switch lin STARTUP.and the IRM's indicating 20 .on Range 4, an operator'down-ranged to Range'3.- WHAT trip (s), if any, would occur? Briefly JUSTIFY your. answer.
(0.75) b.. 'With!the mode switch in STARTUP and.IRM "C" reading 11 on Range 7 WHAT trip (s), if any, would occur if IRM "C" was down-ranged'to Range'6? Briefly JUSTIFY your' answer.
(0.75)- , . . i
.(***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
L I l
>
- - _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _. y;; .[. . s' .
, s , , .3.
PLANT SYSTEMS'(38%)'AND PLANT-WIDE GENERIC-Page
RESPONSIBILITIES (10%)
- QUESTION 3.13 (1.50)
- Concerning the Reactor Recirculation System:
a.
STATE the TWO'(2) components that are cooled by~the Reactor Auxiliary Cooling System (RACS) during normal operati,on.
(1.0) b.
WHAT additional load do'es RACS cool automatically upon plant loss of' power? (0.5)- , t i .> (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
__ .-.. - - _,. _- _ -. . . -. 4.
.. p.A. L*:- a i '31 PLANT 1 SYSTEMS'(38%) AND PLANT-WIDE' GENERIC Page 50-l RESPONSIBILITIES (10%) -
- QUESTION- ;3.14
.(1.00) WHICH ONE.(1)-of the following conditions.Will bypass the.' ROD' . Block" Monitor?' (1.0) a.
Reference.APRM greater ~than 30'%. b.
Nulling sequence incomplete.
c.. RBM channel, mode switch NOT in OPERATE.
.d.
Peripheral rod-selected- . \\ l i-
i , l (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
_ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ -
__ y -. . l < l ' I 3.
PLANT.OYSTEMS (38%) AND PLANT-WIDE GENERIC Page
L RESPONSIBILITIES (10%) QUESTION 3.15 /(2.50) MATCH the appropriate Function given in Column A with the correct TGg in Column B.
Tags can be used more than once or NOT at all.
More than ONE (1) Tag may satisfy an individual Function.
(2.5) COLUMN A COLUMN B FUNCTION TAG a.
Indicates an abnormal operating 1.
Red Tag condition of the equipment.
2.
Yellow Tag b.
Used only on high voltage electrical equipment 3.
White Tag c.
Used only when associated with a 4.
EMIS Tag Tagging' Request.
d.
Used only as an information Tag.
, e.
Blocks and prohibits the operation of equipment.
(***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
__ -__ _--__- --_ -
_ _ _ _ - - _.
- .,.
... . .. 3.
-PLANT SYSTEMS-(38%) AND PLANT-WIDE GENERIC Page
RESPONSIBILITIES.(10%)
- QUESTION.
3.1'6 (2.50) La.
FILL in.the chart according to the exposure limits given in SA-AP.ZZ-024(Q), " Radiological Protection Program".
ASSUME a completed and signed form NRC-4 is'on file.
DO NOT consider .the extended limits for either the 10CFR20 or administrative exposures.
(2.0) 10CFR20 ADMINISTRATIVE' Quarterly (mrem) Quarterly (mrem) Whole Body, (1) (2) Extremities (3) (4) .b.
Approval to exceed the administrative requirements listed above is given by the (0.5) . \\ . (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
i ____________-_____-___-________D
g.-. -_
- .
... I%- l3; PLANT SYSTEMS-(38%) AND PLANT-WIDE GENERIC-Page-- 53.
RESPONSIBILITIES-(10%) QUESTION 3.17 (1.00)'- -IDENTIFY the. INCORRECT statement with reguard to the' Control Rod Hydraulic 1 System.
_ (1.0) a.
'The standby CRD' pump auto-starts when the running pump trips.
b.
The CRD pumpslare cooled by the Reactor Auxiliary Cooling System water, c.
The CRD pumps normally.take suction from the main c condenser reject.line.
d.
The CRD pumps will. trip on low suction pressure.
\\ l l~
l (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
_ _ _ - _ - _ _ _ _ -.___-_--_- - ___ - -
_ _ _ _ _ _ - - - _ _. _ _. _. _ - _ _ _. .: s. -. - , ... x f,3.
PLANT SYSTEMS-(38%) AND PLANT-WIDE GENERIC Page
l-RESPONSIBILITIES (10%) ' QUESTION 3.18 ( 1. 0 0 ). SELECT.ONE'(1)of~the following' statements that describes the conditions which will cause automatic initiat1on of the standby ~ liquid ~ control system (SBL).
High RPV Pressure (1071 psig) AND: (1.0) Low reactor water l'evel (-38 inches) and the 3.9 minute a.
timer timed out.
b.
Low reactor water level (-129 inches)-and the 3.9 minute-timer timed out.
c.
APRM's not.downscale and the 3.9 minute timer timed out.
d.
APRM's not downscale and low reactor water level.(-38 inches)'.
\\ . (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
_ _ _ _. _ _ _ _ - _ _ _ _ - _ - - _ - _ -
[Ph;;J E, ~ ~ ~ ~' ~~~~~ ~ ~ ~ ~~ " 3..
> i ,- .) .., - - a ;pys;- g i ,
- ,
.' M, N,u.-
,.7 -, _ l62 /~3. 4 PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 5 5.l .,-
1 RESPONSIBILITIES (10%)- s.
.e . . - .... .. M QUESTION, 3.19-(3.00); WHAT 5Lre:the FOURI(4); signals that--will' initiate an' automatic- ~ - isolation of:the: Reactor. Building'. Ventilation' Exhaust system-(closing secondary containment isolation dampers HD-9414 ' cA and-B)?. INCLUDE setpoints.
(3.0)- ' , , .] t ,. >- \\ i {l} ( )p' .. .. J, : ) .(*****- CATEGORY 3 CONTINUED ON NEXT PAGE
. _ -_- _ _ --__ - - -______ - ____ _._ -_-_ -._ _ _ _-_ -. - _ _ _ _ - _ _ - _ _ _ _ _ _ _ - - - _ _ -. _ _ _ _ _ _ - _ _ _ -
, y .' %.^ ,
-, - - -
- y.;
..;;.
- ,
. ;. - r' '# f, 3_ c;
- .g'
- 3r PLANT SYSTEMS <(38%)!AND PLANT-WIDE GENERICL.
- Page-56-
- <A-
- RESPONSIBILITIES (10%)
- * , .4 L.V UESTIONi' 3.20'- (2.50), '- Q You are / perfoiMOP -AP. ZZ-109 (Q) 4 Cvalve' line-up.x In accordance.with " Equipment Operational Control",--STATE HOW.
, , _ 'youiconfirm[the position of EACH of the'following: a. iManual closed valves (one step) -('O.5) ~ - b.
_ Manual. opened valve'.(two' steps)l (1.0)~ c.. Manual. throttled valve (two steps) '(1.0) f ' . \\ . i . . T.
- .., _ <
l l , (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
_ - _____-___________-_-______ - - -__ _ _ _ -
- _ - -. _-7.
. _ - _. - _ - __ _ _ . _ -.. - _ , _... -. _ _ - - _ _. - 1;c jj .... -, e . c 4,.' , ' 3b.
PLANT SYSTEMS'(38%) AND PLANT-WIDE-GENERIC Page 57.
' - RESPONSIBILITIES (10%) , / QUESTION. 3 ; 21.. (2.00):
Concerning.the safety Parameter Display, System:.(SPDS) a.
WHAT is the' significance of green characters on'a-white background?- (1.0) . ~b.' For-High'Drywell pressure: - 1. M WHAT drywell pressure does -Ne - control block ~ ( AdicJicr.) torn. RCD ? .(0.5) ' 2.- WHAT-is-the. significance of the' pressure referred to in part bl above?- ' (0.5) . ., , \\ , . .. .L'- . l (*****'- CATEGORY 3 CONTINUED ON NEXT PAGE
- )
,
g - - c- , - j.y - ] ., , .. , p y$ ' ;.7:.if > . - -q L ' ' ,. n4 . ' ;, ,. ! * :: g I'i i I;) tip - i > ' ' , , h6 ' PLANT SYSTEMSE(38%') AND-PLANT-WIDE' GENERIC- -;Pagei 58-W , RESPONSIBILITIES-(10%)- s.
.s , IQUESTION' 63.22 i(2.00)/ .n if In; OP-SO. AC-001,J-" Main' Turbine operation", '.the' following.
- Lcautions: arelgiven~.- Briefly I:XPLAIN.the.reasonL:for each-~ . , gy:L 2ccutioni , a;.Ma ntainithe: turbine at-100 RPM'for as short a. time .. - .as.possible to achieve the desired checks.. (1.0).
. 6'
- -b.-:Do not shutidown:the. Main Turbine Sealing Steam system-w 1while there!is a:va.cuum in the Main Condenser.
(0,5) ' . p; b-
- c.,;During' main turbine' warming, do not exce'ed.'a turbine'-
first stage pressure of-132.4..psig with the mainiturbine (;1 w 'stop' valves closed.' (0.5)~ w.. , I \\ g .
' .. . W- . o ? ' [ '-
r . , i ,9; < ':U _ \\; i L , -}- a ' ;.i:b L, ~ . r 'l ' '
0.. " (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
l: ' >
_ _ - - _ _ _ _ - - _ _ _ - _ _
wmqy -. ,y ,o >n:: , , p,, G;.;
- ', f N0.
- K h,jj a_ - , ., , , - > .; . , ' .m PLANT' SYSTEMS'{38%' AND PLANT-WIDE' GENERIC
- Page-59
) J3r ' s ! RESPONSIBILITIES (10%) ,
'y, ,. -e- . - .. , .., . - . jp. QUESTIONS :3123L .(2.50); ' D.
- .
. . . > , L MATCHitheLplant; condition:givenin Column A with'thefcorrect.RPS Lor RMCSlaction-in Column B' If no': action occurs. indicate ~ . , ' ' -NONE.
Actions'can'be?usedmore-than oncefor NOT atiall'. For s E-conditions:that produce.more'than';one~ action, CHOOSE the more iM>isevere" action-(i.e. half-scram is more: severe than'a rod block)'. (2.5)
- COLUMN A.
COLUMN.Bi g ,' PLANT CONDITION: ACTION-a.
- Loss offone.RPS MGl set .1.
Rod. Block n . ... , 2.
Half-scram
- b.:' Scram; discharge volume. level.
-
. isJat;111'ft., mode switch ., in.STARTUP 3.
Scram , lc. 'APRM B;downscale, mode switch !inRUN' - . s . . - -. \\ Ed.. Closure of ONE turbine stop . valve,freactor power at'75% &
o .- 19.
' Recirculation flow at 50% L re' actor' power at:80%
.I : ... . . !i , P p
- (*****
CATEGORY 3 CONTINUED ON NEXT PAGE
- )
.
. ... . . -l
8,;m ,, mi.
- -
-- _-_- _.
- _ 'h.
l $,'[ 4. . t t P.: ' -;. .. . 'f ! "M, , p# ' " , [. ,;-;; a- ' ' i U:s [h 32 LPLANT--SYSTEMSi(38%)J L AND PLANT-WIDE GENERIC Page'. 60 <
Q,y RESPONSIBILITIES (10%), ,
- p
.. s.N QUESTION'- D 3.-2 41 - ( 1 ; 00 )'. P .. a~ a' - Tha steam s supplyJ fori the maini turbine : passes-through fourz ~
L (;turb1ne f stop valves (MSV). ~. HSV--2J is the. 'only one that t has, K:. inn ' internal / bypass -.. valve.. STATE TWO:(2)-reasons'forfthe.- f-internal-l: bypass _ valve. -(1.0) m . a ., , . g --\\, ' ..g-s . . , ::.i; ' , .r i.
. - . l . (***** CATEGORY 3' CONTINUED ON NEXT PAGE
- )
n:n - -. - - - - - - - - - .. -- - -. _ _ - - - - _ _ _ _ _ _ _ _ _. - - _ - _ - _ _ - _ _
,-. . _ - _ _ - _ _ - _ _ _ _ _ _ _ _ - __ -____ - - - - -_ __ _ , ' . ...;, ,. ). L' 4 3i PLANT SYSTEMS : ( 38%) AND-PLANT-WIDE GENERIC Page
. RESPONSIBILITIES (10%) [ QUESTION 3;25 (2.50) '
Concerning the Rod Sequence Control System (RSCS): a.
-At'WHAT reactor power is the RSCS. automatically by- ' > pasised and HOW -is this parameter sensed? ( 1,0 ) ' b.
A rod' settles on.a f ailed '(open) - even reed switch' and causes a rod block.
WHAT indication coes the operator have that the rod has settled on a failed.re=J switch' (1.5)_ and:HOW does the operator remove.the rod block? i \\ . l
..t (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
-_. _ _. - - -__.
_ . - _ - - ___ _ _ -__ _ _ _ _ _- - -_ -_ _- - -__ __ - - _ _ _ - _ _- - _ _ -
.- _ _. - _ _ _ _ _ _ _.. _ _ _ _, _ _ _ _ _ _ _ , . '.,
.. .... I3.- ' PLANT SYSTEMS '(38%) AND PLANT-WIDE GENERIC ~Page 62' RESPONSIBILITIES (10%) QUESTION 3.26 .(2.00)
- Concerning the Emergency Diesel Generators:
La.
If the electrical governor fails during normal-operation, L the diesel will not shutdown.
Briefly explain.WHY.
(0.5) b.
One of the two air start solenoids fails to operate when-an emergency start signal is received.
Briefly explain WHY the diesel WILL.or WILL NOT start.
(0.75) , . c.
The' engine driven fuel oil pump fails to deliver fuel to the diesel-due to a gear drive failura during normal operation'at full load.
Briefly explain WHY'the diesel WILL or WILL NOT shutdown.
(0.75) \\ , . i
(***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
_ _ _ _ - - - _ _ _ _ _ _ _ _ .a
- - _ - _ - - -__ - - '
- .
. -. . .3.
PLANT SYSTEMS-(38%) AND PLANT-WIDE GENERIC Page
RESPONSIBILITIES (10%) . . 2.50 QUESTION 3,.27 (3-rOF) Concerning the Automatic Depressurization System (ADS): a.
STATE the required combination of core spray'and/or.
RHR pumps required to be operating for ADS automatic initiation.
Include the required discharge pressures.
(1.5) b.
STATE the NORMAL power supply to the ADS logic channels.
(0.5) o, In ddition-,tv shuli.ing-dcWn the RHR-and-ccre spray pumps, WHAT-spsrator-act-lons could be taken-tereclose-t41e Ixlief v&lves ence ADS-hea>-commenced blowdown -end--prror . to Leavi.vt yt es s ut e dectea5ing below 50 ps193 (0.5)- d.
WHAT system supplies the motive force for ADS SRV operation during an automatic ADS initiation? (0.5) . \\ . l l (***** END OF CATEGORY 3
- )
_ .. _ . - - - _ _ - _ _ - _ _ _ _ _ _ - - _ _ _ _
- - - _ _ - _ - _ - _
- .:
uc.
, e.'; , . J =2.
EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page1 70' - , , L (27%)- !
, g ' ! ANSWER 2 ' ~ 01 (1.00) .
- Letter'"d"-
(1.0) REFERENCE 1.
OP-AB.ZZ-105(Q) p.7 2.
LP 302HC-000.00-006 EO 14 p.9 .3...KA 295022G010 (3.7/3.5)~ < ANSWER '2.02 (3.00) 1.
The indicated recirculation loop flow (differs by more than ~ 10%) from the established pump speed - loop flow character-istics.- (1.0)~ 2.- The-indicated total' flow differs (by more tha 10%) from the . established total core flow value derived from recirculation loop. flow measurements.
(1.0) L 3. - The' indicated diffuser-to-lower plenum differential pressure of any individual jet pump differs from the established . patterns (by more than 10%). (1.0)- . REFERENCE ~ 1.
OP-AB ZZ-111(Q), p.1 2.
LP 302HC-000.00-019 EO 20 p.10 3.
KA 295001A205 (3.1/3.4) ANSWER 2.03 (1.00) . Letter "c" (1.0)
REFERENCE 1.
LP 302HC-000.00-048 p.88 2.
LP 302HC-000.00-048 EO 10b.
p.11 '3.
KA.295005K101 (4.0/4.1) 295005K302 (3.5/3.8) (***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
_ ._ . _ _ -. _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ - _ - _ _ _ -
-.
__ E
.. +., y .
- .T
& 12.
. EMERGENCY AND ABNORMAL PLANT' EVOLUTIONS Page: 71 (27%)- iANSWER .2.04! ( 1. 0 0 )..- 'e 7s Ensures vacuum breakers are not submerged.
-( 0 4) ~ and areJava11able for operation.
.(0 51 L o.3 REFERENCES 1. L'P 302HC-000.00-125B-p. 21, E06 p.
2. KAL295029K205 (3.1/3.3): . ' ANSWER 2.05 (2 00) 5.2.
(0.5) .b.. '3 (0.5)- c.- 6.
(0.5) , d.
(0.5) REFERENCE ~ ,. 1' ' 1.. OP-AB.ZZ-208(Q) p.1
- 2.
- LP.302HC-000.00-053 EO 11, p.6'
3.
KA 295002K302-(3.4/3.4) 295002K303 (3.3/3.3) 295002K304 (3.4/3.6) 295002K305 (3.4/3.4)
. ANSWER 2.06 (1.00) .a. CLASS 1E UPS (0.5) or zoveene e,w a e.
., 'b.
125 (0.5) I . REFERENCE .) I , ' ' 1. - OP-AB.ZZ-135(Q) 2.. KA 295003K201 (3.2/3.3) 290031C204 (3.4/3.5) l l
, (***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
_.
- - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ - _ _ _ - _ _ - _ - _ - - _ - _ _ _ .
- _ _. _.
_ _ _ _ _ _ _ _ - - _ _ - _ _ _ 1..... .. .: 2.
EMERGENCY MID ABNORMAL PLANT EVOLUTIONS - Page_ 72 (27%) ANSWER 2.07-(3.00) a.
Operating above the 100% Rod line (0.5) with indicated core flow "lessthang0%ofratedcoreflow. (0.5) 'APRM pcwer oscillations (0.5) exceed 10% power peak to peak. (0.5) b.
The designed up date time for screen displays is not adequate (0,5) to accurately display oscillation magnitudes (0.5).
REFERENCE li .OP-AB.ZZ-100(Q) p.1,2 2.
LP 302HC-000.00-114 EO 1 p.4 3.
KA 295014A105 (3.9/3.9) 295014A201 (4.1/4.2) ANSWER 2.08 (3.00) h.
d.
NONE \\ - .b. NONE e.
c.
f.
(6 at 0.5 each) REFERENCE
1.
LP302HC-000.00-124A-p.6; EO 2 p.4 ' 2.
LP302HC-000.00-125A p.6; EO 3 p.4 3.
LP302HC-000.00-127A p.6; EO 2 p.4 4.
LP302HC-000.00-128 p.5; EO 2 p.4 5.
LP302HC-000.00-153 . p. 5 6.
KA 295007G011 (3.9/4.1) 295012GO11 (4.1/4.4) 295017G011 (4.2/4.5) 295030G011 (4.3/4.5) 295035G011 (3.9/4.2) ANSWER 2.09 (2.0) a.
To' provide natural circulation (1.0) b.
Shutdown Range (LI-R605-B21) (0.5) c.
Reactor Water Cleanup System (0.5) REFERENCES 1.
LP 302HC-000.00 112D p.18; EO 8 p.4-2.
OP-IO.ZZ-400(Q) p.26 3.
KA'295021E301 (3.3/3.4) 295021G007 (2.9/3.2) 295021K304 (3.4/3.4)
(***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
- _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ - _ - - _ _ _
, - _ - -. -- . -- . _ _ -. . _ _ _ _ -. _ _ - - _ - _ _ - _ _ - - _ _ - _ _ _ - - - _ - - - - - _ _ y
,..
h '? ' , , Page
L '2' EMERGENCY-AND ABNORMAL PLANT EVOLUTIONS ,. . (27%) ANSWER .2'.10 (2.00).
1.- To maintain, oil flow necessary for adequate bearing cooling and lubrication.
.(1.0)
- 2.: ;To prohibit interruptions in~ turbine. exhaust-flow which may cause check valve chatter (and possible damage).
( 1. 0 ) L l' REFERENCE
, 1. z LP 302HC-000.00-123 p.12, EO 6 p.4 . 2.
- KA 295006G007-(3.8/4.1)
I ANSWER.
2.11' (1.50)- jay wxe* ADS ACTION 1.
Would. impose'a severe. pressure and temperature transient j on the RPV.
(0.5) 2.
Would complicate.the effort to' restore and maintain RPV water l evel'. (0.5) 3.
May lead'togloss of adequate core cooling.. (0.5)
Howws A cecss re noec ovroenn rsw ruera iros toec, we o reu r*< vs su . REFERENCE d b'O f*"'" " J# #l #" #
- * * O M M "k W&
.. 1.
LP 302HC-000.00-124A p.15, EO 4, p.4 2.
KA 295031K208'(4.2/4.3) .. - ANSWER.
2.12 (1.50) ^ 1.
Reactor feed pump trips (0.5)
- 2.
Main turbine trips (0.5) 3.
HPCI/RCIC turbines trip (0.5) REFERENCES 1.
OP-AB.ZZ-117Q p.1 2.- LP 302HC-000.00-114 EO 1 p.4 3.- KA 295008K202 (3.6/3.8) 295008K205 (3.8/3.9) 295008K206 (3.4/3.6) 295008K208 (3.4/3.5) .. - , _(***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
-_ __- _.- _ _-_-_ _ _-_-- - - _
n, - - -_ - 7,
- ,j ;
..~4- '.-
7- . ' .)_ < . ' 1: 2 '. - EMERGENCY AND ABNORMAL PLANT' EVOLUTIONS Page~,74- - (27%) , l ANSWER- !2.13' (2.00)
-1.
If AUTO level control system har. malfunctioned, maintain-Reactor level" manually.. l(1.0) .g
2.
REDUCE power-as necessary to restore vessel' level'. -(l'.0) LREFERENCE' ' 1.
.OP-AB.ZZ-200('Q), p.1 2.'- ( LP - 3 02HC-0 00. 00-114 - E01 p.4 L3.-:KA 295009G010.(4.2/4.0) , . ,. ANSWER-2'.14-(3.0) a.
l',3',5,6,7,4 .b., 1,1,4,5~,7' c.
'1,2' . j < ~d.
1,3,6,2
- o.
f '. 1,3,6 Each letter response (+0.5) each', proportionally graded REFERENCE-1.
LP 302hc-000.00044 Table ir EO 11-2.
KA 295031K212-(4.5/4.5) 295020G010 (3.4/3.5) -295020K201.(316/3.7)- 295020K203-(3.1/3.3) . 295020K204 (4.2/4.2) 295020K210 (2.9/3.1) ..
! (***** END OF CATEGORY 2
- )
_:_ _ _.- ______:_________-_-
"n~w
- y
} ' ID
- L Q h ;
its .j ^! c y.
3.
PLANT SYSTEMS (38%) AND PLANT-WIDE' GENERIC-PAGE-- 75' l ' ', RESPONSIBILITIES (10%)_ j F ANSWER- .3.01 .(1. 00 ).
j '. ' Letter.."a" (1.0) . .Raference' 1. : LP 302HC-000.00-016-p.36 and Table-1, EO 9 s - 2.
104 215005K401 :( 3.7/3. 7 ) ' ..c . ANSWER.
3.02 .(2.00) a.
A differential pressurefdetector monitors the differential
- pressure (0.5) between the'two. core spray loops (0.5)
.(downstream'of the. testable check valve).
.b.. When either core. spray loop is injecting into the vessel ,(0.5)-or HPC1 is. injecting into the vessel (0.5).
.. . _ \\ REFERENCE- - 1.
'LP 302HC-000.00-027 p.21- - 2.
1209001K404 (3.0/3.2) ' ANSWER 3.03' (1.00) - Letter "d"' (1.0) , . REFERENCE
- 1.
LP 302HC-000.00-009 p.10,11, EO 7d.
2.
KA 201006K401 (3.4/3.5) 201006K402 (3.5/3.5) (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
a .a.
-,' -]
- H
, q .,k. ' f3. - LPLANT' SYSTEMS 1 (38%)'AND PLANT-WIDE GENERIC Page. 76 RESPONSIBILITIES'(10%) . .j ' > ' ANSWER? ! 3.04 --(1.50) ' 12.
Reactor Scrams':( 0.25). immediately on: receiving two low water-
signals <in.one channel'. (0.5)L . 'b.
_ Recirculation pumps do'not trip-(0.25) because there is a nine-second delay built.into the trip circuit.
( 0.5 )- . ' REFERENCE.
1. ' LP.302HC-000.00-025 p.13,14, EO 3 2.
'KA'202002K604'(3.5/3.5) KA 212000K401 (3.4/3.6)- ANSWERc 3.05. '(3'.00'). 1. a'. .High pressure (0.25)1 greater or equal to 140 psig (0.25) Downstream of valve' (0.25) Low pressure (0.25) less than or equal to 5 psig (0.25) . Upstream cf valve (0.25) \\ b.--Closed'
- (0.5)
2.
To provide overpressure protection of the. low pressure downstream piping'.(0,5);during blowdown operations with the1 reactor.
- pressurized. -
(0.5) REFERENCE
1.
LP 302HC-000.00-021 p.31, EO 12 p.8~ 2.
KA'204000K402 (2.7/2.9) 204000K105-(2.7/2.7) j ANSWER 3.06-(1.00) .~ a.
.1. 1/4' scale (0.25) 2.
3/4 scale (0.25) b.
1.
15 minutes (0.25) 2.
30 minutes (0.25) , l REFERENCE-1.
SA-AP.ZZ-046 ATTACHMENT 4 2.
LP 301HC-000.00-113I EO 19,20 p.7 3.
KA 294001K103 (3.3/3.8) ' l '
(***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
L
l
r_ . ,.a.
- ..,) / f i 'g'? '._4; .
, 4.
3.
- PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page-77-RESPONSIBILITIES'(10%) ,, a... ~ - ANSWER '3. 07 ' (2.50).
, a.
6.
(0.5).' b.-
(0.5) " c..
(0.5).
d.
.6 . ( 0. 5 )' "c..
(0.5)- - REFERENCE 1.
LP-302HC-000.00-002 p.31-EO-5f 2.
LP 302HC-000.00-042 P.29 EO 6
- 3.
' KA 216000K501 (3.1/3.2).
ANSWER-3.08-(1.00)~ Letter "b"~ (1.0) ~ }- REFERENCE 1 '. LP.302HC-000.00-059 p.23,-EO 11 p.7 2.
- KA 259002A203 (3.6/3.7)
- ANSWER:
3.09 . (1. 00 ) ' .n an,a e p.
eew casss sutv. *resr!** oR e.$ To prevent inadvertent. system inoperability (0.8) due.totreactor. wide range level instruments indicating - . f alsely high.:at low reactor pressure' and temperature (O 51 y ca7 REFERENCE 1.
LP.302HC-000.00-026 p.103 .2.
-KA'206000K403 (4.2/4.1) .. (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
j.
__ _ ___ __________ ____ __ _ _ _ ___ -
. m - . _. - -. .. _.
.. . _ _ - _ - - -. - .y;. l}l ' ,
- i?
' ! .. ^' $.e, m ,
N 3 '. ' . PLANT SYSTEMS (38%) ANDtPLANT-WIDE GENERICJ Page' 78" ' RESPONSIBILITIES.(10%) i
DANSWER 3.10 (1.00)
- Letter "d"-
(1.0) REFERENCE g . L1. 2LP 302HC-000.OO-050 p.36, EO 5 p.6 L2./ KA 241000K405 (3.7/3.8).
. .. . ANSWER '3.11 ' ( 1. 5 0 ). y 0.- 1.
two.
(0.25)- ' J2.
.two (0.25) b., 1.
.70 percent..(0.25), full (0.25)
2.. 80. percent (0.25),' intermediate (0.25) - \\ REFERENCE' 1.
LP,302HC-000.00-052 p.50,.EO 17 ~2.- KA 256000K304 (3.6/3.7}- 202001K607 (3.3/3.3) ANSWER 3.12 ( 1. 50 )' LO.. NONE (0.25) 4 The IRM's would indicate 20 on ' Range 3L(0-40 scale) (0.5)~ ,.
- b.
~An.IRM upscale trip or.rodblock (0.25).
IRM would read 110-(on the 0-125 scale) A rodblock occurs at 108 (0.5) REFERENCE l '.. -LP 302HC-000.00-014 Table 2, EO 5 .. -2.
KA-215003A105 (3.9/3.9) , N i .(***** CATEGORY 3 CONTINUED ON NEIT PAGE
- )
. _ - _. _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ -
7'3.
@s lH, ' , , .m ) ]M < ;4 t \\ ' ^ ...i ): ,1 ,. t
- - L
='t w3 , , p.{4 .QQ -' ' '-
s '
l ,;' < , ' i, > < I
.- , , [y i I31-
- PLANT,SYSTEMSi(38%~)TAND PLANT-WIDE GENERIC:
Page';79 - , ? *: RESPONSIBILITIES (10%) ,, . f: > , f ANSWER ' 3.13 '
- ( 1. 50 ),
^) , . recirculation. pump ~ seal' water heat exchanger'or cooling-F' ,L la.
.. 'to' pump'sealsi . ( 0! 5 )J - Recirculation motor (upper and lower) bearings.f (0,5l' >- Ib. : Rebircuiatiion; pump motor:-air handling. unit ' or cooling to ' s . pump motor windingsJ (0.5)-
P . I REFERENCE' g . , 1.
LP 302HC-000.00-019'p.36,37: JEO-Sc,d 2.
KA.202001K107.(3.1/3.2)- 202001.'K602-(3.1/3.2)
I-ANSWER-3.14 (l'.00) , i.etter."d" ( 1.,0 ) i REFERENCE - l'... ' LP: 302HC-000. 00-017 Table = 1' EO-7 p.7~ t 12.. KAs215002K106.(3.0/3.1) ' , . ' t ANSWER ' 3.15' -
- ('2.50)
' ' Kl1
- o.-
f3 (0.5) . ' b. :. ~2 ( O '. 5 ) ' _.(graded proportionally): . . c.
1,'2;3.
(0.5)' L dr - 41 (0.5) le.: . 1: (0,5).
REFERENCE' .. 1 1. - SA-AP.ZZ-015(Q) p.
5-8,
-2;'.LP 301HC 000'.00-113 EO G1, p.7 L 3 ~. !KA 294001K102-(3.9/4.5)' (***** . CATEGORY 3. CONTINUED ON NEXT PAGE
- )
,y 7' , >; ; ,. __ _ .... _ _ _.
.. _ _. ._ ____.__.___m__ .__ _ _ _ _. _ _ _ _ _ _. _ _ _ _. _ _ _ _ _ _ _ _ _ _. _ _ _ _ _
.- [si., }- n-n
f[,
I 3.'- PLANT SYSTEMS '(38%) AND PLANT-WIDE GENERIC Page .80' RESPONSIBILITIES (10%) , ' . JANSWER; 3.16 (2.50) m ls .c.
- 1. -
1,250 (0.5, . 2.. .-1,000 (0.5) 3.
- 18,750 (0.5)
f.
4.
10,000' ._0.5) ( [ b.- Radiation Protection' Supervisor- (0.5) . ~ REFERENCE , , .1.
SA-AP.ZZ-024(Q) p.27-34.
L 2.
LP.301HC-000.00-APG1 IO K1,3 3.- KA,294001K103-(3.3/3.8)- ' v-ANSWER '3.17.
(1.00) Letter "a" (1.0).
- -REFERENCE , r 1.- LP 302HC-000.00-035 p.42 EO 24a,e 2.- KA 201001K101 (3.1/3.1) 201001K106-(2.8/2.8) 201001A201 (3.2/3.3) ANSWER 3.18-(1.00) Letter "c" (1.0) i . REFERENCE , , 1.
'LP-302HC-000.00-024 p.16, EO 7 p.7 2.
-KA 211000A308 (4.2/4.2) , .- , ! (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
- _ _ _.. . _ _ _ _ _ _ _ _ - - - _ - - _ _ _ _ _ _ _ _
g7, . , ....:-- W .j.
o -
- ,.
-s
- 3.
PLANT SYSTEMS-(38%) AND PLANT-WIDE GENERIC Page' 81 $ RESPONSIBILITIES (10%) i.; b ANSWER' 3.19 (3.00) y b, 1.
. Low reactor'-level ( 0; 5 ). -38 inches (0.25)- . 12.
LHigh drywell pressure (0.5) 1.68'psig (0.25) 3.
. Reactor building vent Hi-Hi rad (0.5) 1X10**-3 microC1/cc (O'25)E . 4.o Refuel flow vent exhaust Hi-H1 ('.5)'2X10**-3 O microC1/cc-(0.25) , REFERENCE , C> 1.
LP'.302HC-000.00-042 p.22, EO.20.p.10.
2.
KAL288000K402 (3.7/3.8) . - ANSWER' 3.20 (2.50) a..' Hove the handwheel in.the closed direction only (0.5)' \\ b.- Hove the handwheel.in the closed' direction enough to verify valve movement, Vindicating valve is open (0.5).
Then~ return.the valveito open (0.5) , c.
First fully close the valve (0.5), then open the required number.of. turns or match the alignment marks (either answer is. acceptable) (0,5) ' REFERENCE' 1.
OP-AP.ZZ-109(Q) p6 '2.
LPl 302HC-000.00-113C, E011, 13a, p.6 3.- KA'294001K1.01.(3.7/3.7) ANSWER' 3.21-(2.00) n.
White. background' indicates that some data input has failed the validation process (0.5) The green characters indicate the SPDS still has confidence in the displayed value (0.5) b.
1.
'Drywell pressure is equal to or greater than 14.8 psig (0.5) 2.
Drywell pressure of 14.8 psig is equal to the Suppression Chamber Spray Initiation Pressure.
(0.5) REFERENCE 1.. LP.'302HC-000.00-107 p.15,25, EO 3c,e f 2.
KA 294001A115 (3.2/3.4) 230000A103 (3.6/3.8) i (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
l
EN~ f!f[._ .Q ' )
- J ~
L 13. IPLANT: SYSTEMS'(38%)-1AND PLANT-WIDE GENERIC- 'Page
RESPONSIBILITIES-(10%) ' ANSWER
- 3. 22'
(2.00)' c.; WhenLturbine speed is' maintained-below 800 RPM for periods exceeding 5 minutes (0.5) turbine' damage could' result from ' non-detected rubs-(0.5)' " . To>preventipulling.in cold air"along the hot turbine rotor- ~b.* ., shaft'(0.5) ,;. c.. A reactor scram'will: occur- (0.5) REFERENCE ' e
- 1..
OP-50.AC-001 p.5,6 2.
LP 302HC-000.00-048;p.93,94,95, EO 18 p.14
- - 3..
KA 239001G010 (3.5/3.6)- [ ANSWER '3.23 (2.50)
(0.5) .\\ . l b.:
(0.5) lc.
(0.5)~ d.. NONE.
(0.5) -e.
(0.5) l REFERENCE 1.
HLP 302HC-000.00-022 p.27,29,36, EO 51p.8
2.
LP 302HC-000.00-007 Table 2 EO 11 p.8
- 3.
KA-212000K108 (3.3/3.5) 212000K110 (3.2/3.5) 212000K305 (3.7/3.8) 201002A104 (3.6/3.5) 201002A301 (3.2/3.1) ANSWER 3.24-(1.00) ytwf tw 1.
To-be.able to perform a slow warming of the main turbine ' steam chest.
(0.5) 2.
-To pressurize the below seat areas of the'other MSV's (to facilitate valve opening) (0.5) . 2" to h u w reg sac a fuss, mewe 3Mu ww'"' REFERENCE 1..'LP 302HC-000.00-036 p.22, EO 3c p.10 2 '. KA 245000K103 (3.2/3.3) 245000K409 (3.1/3.1) l- .. (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
l' ..
_ _. _ .. _ . j;' ,; .n, ,
- {.
" .. 3.
PLANT SYSTEMS-(38%) AND PLANT-WIDE GENERIC' Page
RESPONSIBILITIES (10%) -ANSWER 3.'25-(2.50).
'n.
When reactor power is greater than 20% (0.5) , ' Sensed by first-stage turbine pressure. (0.5) , 'b.
An " assumed rod"; position:(0.5) is-displayed in the window on the display unit (0.5) oc ' - + me orsnxf (c6) A5 4" X X (**S) 1eorcame ew - we i.
SEL SUB pushbutton must be depressed (0.5)~ ' REFERENCE- ~ i t '. - LP 302HC-000.00-019 p.21, EO 10 p.7
- 2.
KA 201004K102.(3.1/3.1) 201004K404 (3.3/3.3) 201004A101-(3'.3/3/3) ANSWER 3.26 (2'.00) a.
The mechanical' governor will take over.
(0.5) -b..-Diesel will start'(0.'25) because only one of the two air' start systems is required.
(0.5) c.
The diesel will not shutdown (0.25) because a motor driven standby pump will auto start and supply fuel to the diesel.
(0.5) .- REFERENCF, 1.. LP 302HC-000.00-068 p.40,56,60, EO 4f,J,7 2.
KA'264000G007 (3.6/3.8) 264000K601 (3.8/3.9) 264000K602 (3.6/3.6) 264000K406 (2.6/2.7) (***** CATEGORY 3 CONTINUED ON NEXT PAGE
- )
. - _ _ _ _ _ _ - _ _ _ - - _ _ -_ _ _ _ _ _ _ __ _ _ - _ -
.3 . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - , { gig inf9 y,
y,W.~',
- ,.j
,
,,. ,s _ V y
,
-
- 3. - ~ PLANT' SYSTEMS !(38%)-AND PLANT-WIDE GENERIC Page 8 4.-
, ' , RESPONSIBILITIES.-(10%)- ~ 2. So ' IANSWER 3.27 ' (het0 ' H 3.
CS' pumps B'and.D or;A.and C (0,5),. discharge pressure . greater;-than 145 psigi(0.25) or one RHR pump.-(0.5) . discharge: pressure greater-than 125 psig'(0.25) b.
125 VDC' (0.5)
' naprest otit-reret-swi-tches ' ( 0_54-. Octem b 'c: ' i d.: l.
EPrimary Containment Instrument Gas System (0.5) REFERENCE- .. 1.
LP'302HC-000.00-029 p.
26,30, EO 4,-10e- '2..:KA 218000K201-(3.1/3.1) 218000K501 (3.8/3.8) 218000K101"(4.0/4'1) 218000K404.(3.5/3.6) ' . , , \\ .' : '
(***** END OF CATEGORY 3
- )
___-____________-____:D
_ ,
- -
Armawwr t - ' f-PSEG Pubhc Semco l-tecinc amt Ga> Conquny POMo A Hmmcl A iin h~ l W. Jef se OC)?; Hope Creek Generating Station July 20, 1989 NTC-89-3147 , Mr. William Russell Regional Administrator U.S.
Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406
Dear Mr. Russell:
EXAMINATION REVIEW COMMENTS - HOPE CREEK LICENSE EXAMINATION Attached are comments on questions used on the written exami-nation administered at Hope Creek Generating Station on July 18, 1989.
These comments have been developed following the exami-nation.
They are in addition to comments provided by Messrs.
Sparks, Trum, and Martin during the pre-examination review conducted on July 17, 1989.
The number of post-examination comments is significantly reduced from previous examinations and indicative of a successful pre-exam review.
The following format has been used to document specific comments: A.
NRC question, answer, and reference; B.
facility comment including a recommendation for resolution; and C.
support documentation.
These comments are presented in the same order as originally numbered on the SRO examination.
I
_ _ _ _ _ I.
' - '4 ...
- William Russell-2-7/20/89 . If you have any questions, comments, or need additional infor-mation, please call G.
Mecchi, (609) 339-3857, or W.
Gott, (609) 339-3769.
They will provide the requested information or will see that you are contacted by the appropriate person.
Sincerely, l % Gl' 'd / Joseph J.
Ha an'v General Manager - '{ Hope Creek Operations ' l I Attachments i ! l ! i , i I
l
_ _ _ _ _
,- -. . .,
['2 ; ' EMERGENCY AND ABNOR' MAL PLAN 7' EVOLUTIONS page 2c j-l4 . ( 2 7 % )- j.
'! - . QUESTION-2.06 (1.00)' F lAs: indicated-in OP-AB.22-135(Q), " STATION BLACKOUT:// LOSS OF f OFFSITE POWER:// DIESEL GENERATOR. MALFUNCTION", upon loss of power.
(LOP) all, Class 1E System Instruments are powered-from ' (c) suppl.ies which' auctioneer to their-associated (b) VDC supply.
'(1.0) .. . ANSWER 2.06 (1.00) a. CI. Ass 15 UPS (0.5) b. 125 (0.5)., , , X.V <- 2[6 REFERENCE or . 1.
OP-AB.ZZ-135(Q)- 2.
EA.295003K201-(3.2/3.3) 290031C204 (3.4/3.5) . > . B.
Part (a)'of the question is confusing in the way that it is worded. The response for part "a" is Class IE UPS.
If this were read without using the initials "UPS", the answer would read: " Class 1E Uninterruptible' Power Supply Supplies.
The student could read this and miss the answer'due to the way it reads. The answer, " Inverter Power", should also be accepted.
- (***** CATEGORY 2 CONTINUED ON NEXT PAGE
- )
_ _ _ _ _ _ - _.
- _ _ - - - l . =. .. _ i -
- .
2.
' EMERGENCY'AND ABNORMAL PLANT EVOLUTIONS Page
(27%) k. QUESTION 2.11 (1.5) In Procedure OP-EO.22-101, "RPV Cont rol ", step RC/L-9 states "If 129" THEN DELAY ADS INITIATION BY RESETTING RPV LEVEL FALLS BELOW - THE TIMERS",. Give THREE (3) reasons WHY-this step is necessary.
(1.5) ANSWER 2.11 (1.50) - ADS ACTION 1.
Would impose a severe pressure and temperature transient on the RPV.
(0.5): 2.
Would complicate the effort to restore and maintain RPV water level.
(0.5) ' ' 3.
Nay lead to loss of adequate core cooling.
(0.5) , 1EFERENCE . 1.
LP 302HC-000.00-124A p.15, 50 4, p.4 <' 2.' KA 295031K208 (4.2/4.3) B.
The Answer Key for this question does not properly list all of the possible cnswers.
The Answer Key takes item 13a from page 15 of Lesson Plan 302HC-000.00-124A and breaks it down into three responses.
In fact, 13b and c. are also reasons listed in the lesson plan for this step and should be accepted as correct responses.
C.
See attached documentation.
. , f u ' -_ _ _ _ _ _ _ _ _ _ _ _ _
- VIil ^ f, ' . C . LESSON NAME ' OP-EO.ZZ-101 RPV LEVEL CONTROL SECTION ~ ~ b - INSTRUCTIONAL CONTENT: ' r " KEY / AIDS a) ABOVE +12.5".is displayed in green when vessel level is~ greater than +12.5".
b) ABOVE -38" and BELOW +12.5"~is. displayed ' in yellow.
c) BELOW,-38" is displayed'in' red.- This is - an. entry condition for OP-EO.ZZ-101.
13. RC/L-9 "IF RPV LEVEL FALLS BELOW -129"~THEN DELAY ADS INITIATION BY RESETTING THE TIMERS."
g-a.
ADS actuation. imposes a severe pressure and temperature transient on the RPV and complicates,
- the effort to restore and maintain RPV water level.. In severe cases, ADS actuation may' lead
. to loss of. adequate _ core cooling and subsequent L core damage which otherwise could have'been avoided.
b.
The conditions assumed in the design of-the ADS logic (no operator action for 10 minutes) do no't exist when the operator is executing'the steps of this. procedure.
Having access to more information than the ADS g logic, the operator is in a better position to judge when and how to depressurize the RPV while minimizing transient loads and optimizing adequate. core cooling.
- P c.
Note however, the actions specified are limited to manually resetting the timers, thereby affording a measure of automatic protection should.the operator's attention be required elsewhere.
14. RC/L-10 " RESTORE AND MAINTAIN RPV WATER LEVEL ABOVE TAF, EXIT RC/L."
As long as RPV water level can be maintained above TAF, adequate core cooling is assured through core submergence.
With level under control, it is . appropriate to exit RC/L.
{ l Page 15 Date: 10/05/88 l 302HC/2:25 Rev.:
i ! _ _ _ - _ _ _ _ - _ - _ _ - _ _ -
_, . .. ._ _ _ _ _ -- . _ - _ - _ _. _ _ _ _ _ - ___-_ - _ - - p c3 .- 2.
EMERGENCY ANDDABNORMAL PLANT EVOLUTIONS page-35 (27%)
.A; QUESTION' 2.16 (3.00) Assume the reactor'is.. operating at full power.
Column 2 lists , y geven individual. primary containment isolation valve groups.
' L LColumn.1 lists isolation purameters.
For each parameter given in L Column 1 SELECT the group (s) from Column 2 that use this parameter- ! to' generate.an isolation signal.for'ANY or ALL~of the valves in
- *
thatfgroup.
NOTE:;Each parameter may.have more than one group listed.
If the parameter generates no isolation signal, STATE .NONE.
COLUMN'1' COLUMN 2 MSL DmM @lV ~ a.
Drywe'll Pressure HIGH.HIGH 1.
Group 1-MSIV ealing i System Isola, tion Valves b b.
Reactor Vessel Water LiVS-l 2.
Group 2 - Reactor c.
Main Steam Line Recirculatier, Water Sample Radiation - HIGH-HIGH System d.
Reactor Vessel Water '3.
GROUP B - Torus Water a LEVEL 2 Cleanup System ' ,,:
- e.
Main Steam Line 4.
GROUP 10 -Drywell Cool e r s
Pressure?. Low ' 5.
GROUP 11 - Recirculation f.
Reactor Building Exhaust Pump Seal Lkke J.scichon 'MVer.
Radiation - HIGH 6.
GROUP 12 - Containment Atmospheric Control System 7.
Group 16 - Reactor Auxiliaries Cooling System . ANSWER" 2.14 (3.0).
e l-a.
1,3,5,6,7 b.
1,J',4,5,7 c.
1,2 d.
1,,3, 6
e.
f.
1,' 3, 6 ' Each letter response (+0.5) each, proportionally graded REFERENCE 1.
LLP 302he-000.00044 Table 1, EO 11 2.
KA 295031K212 (4.5/4.5) 295020G010 (3.4/3.5) 295020K201 (3.6/3.7) 295020K203 (3.1/3.3) 295020K204 (4.2/4.2) 295020K210 (2.9/3.1) - - - - _ - _ _ _ - _ _
.,,7 .- -.,. ' _ p %,..; 9: $. '. .x ' . i' ' 'B.
The Answer Key for' items a. and_b. in Column 1 are incorrect.- Item a.
l (Drywell' Pressure High-lligh):sheuld also include item 4 (Group 10)-from.
- Column 2 as an acceptable answer.
, , Item b. (Reactor' Vessel Water Level 1) lists items 2 (Group 2) in Column'2 as an acceptable answer. This is fncorrect and should not be included as an acceptable answer.
-1 .C.
See. attached documentation.
i l ,, e . .. . ... .. . .__ _.. _...,
_. _. _ __ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ i.
- ..,
< il l.
. .; l'?. . ..
- '.
e' Eo =.=. . U C C C eD w W 4D th CO @ es; tv N fw N N N N tw N N.
e e e e J w out 2 T T T T-C C C C I E.O @ M @ @ CD.C== et = m m m m m m m m m m y e= e= .= et c . .. . . .. . .. dkE N N N N N N N N N N ~fwQ c c., y . .. . . .. . . . et C e== m *= . m og
==e m em e c.a g A C M9
=.
w
w l
EE ' e= Ew . . E E E *= Zm f v :>= ' - m . E E nnJ m a=
== w ti.
N N N m m
e m E E.= N N m m e=e - N E EC E .
== E *= ( M.
w
- LM m
Cw ' .=. b . em @ w es s C e . m O at e >. C ..*
. * N. C.. C e-O t. e m w e th em m @ me am@ m m a m a >=i U > T m *== m
- =e**
- =q m u u u
u u
y b \\
w w w w w 4 E w
==d CC m.. Os e m.. e ch m Ch
- ..
E C = et m N==e N en W ee N to W e=q ' *=e m was e p.s C 6J eC 2 .e=e **==
- ee *=e e==
.e=e ens
- ==*==+=4
>EEC N e .. tC e
=
e.
aCw= ... . .. ... " *
- C=== & W
\\.N an C .e o e N .m N .e e g N .=.3 > C % = em a * * = = = = = *== m e= m a c= e J C
m e= a
== ==
m
E >
i a= >
- e l
4=.e C e
- = 4 en W
E
- e en
== ==d W D
4J =J O en
e-N >=== e
=== 3 e C b W X .C C b 2 9 .C
=d W
d M m &
M C
- e e
s w a=m e s x w .m e > . C e w C ) 3 W 3 e tlh t O 4== 3N & E DE O = w O
C 1:n
E
L tm C D = 6= = w 3 = * * * +8 m=
O=
== .d E @
wt TE e &W ' en OE TZ
en
=
== en > en = -
en W
- = q
.J .= en W W bh. 9
- ==
0'
- 8 W
J J
3 = C e =J b
,> Eh . ED C C >= .> a.
O2 am C C .=
C l u O.
C. O.
.O
== .
- s.
u E . .O.e w .d .O , m.+.8 *, ed s A *== Oe = W = O * C . = v v v== >=
== u *== 3 3. =T , e e m.
C ae \\ et C >. s n n w . C s
E E e4 N Q EE E Q Ed 43.
wo we e E SE &E E f e=
v' C E
==
6.
u
v T.
W C E . . w = m ,. a v T.
b . . .c Ele . - e N . HOPE CREEK 3/4 3-11 . t -
r: (
- C
- l.
' .; , . '3.-- PLANT SYSTEMS:(38%) AND PLANT-WIDE GENERIC-Page
RESPONSIBILITIES-(10%) $ -lQUE'STION 3.27 (3.00) , 1Concerning the Automatic Depressurization System'(ADS): L a.- STATE the required combination of core spray and/or RHR pumps. required to'be operating for ADS automatic initiation.
Include the required discharge pressures.
(1.5) K .b.
STATE the NORMAL power supply to the ADS logic channels.
(0.5) ~c.
In addition to shutting down the RER and core spray pumps, , WHAT operator' actions could be taken to reclose the ! relief valves once ADS has commenced blowdown and prior to reactor-pre:3ure decreasing below 50 psig? (0.5) d.
WHAT system supplies.the motive force for ADS SRV operation during an automatic ADS initiation? (0.5) ~ ANSWER '3.27 (3.00) .,. , a.
CS pumps B and D'or A and C (0.5), discharge pressure
greater than 145 psig 0.25) or one RHR pump (0.5) discharge pressure grea(ter than 125 psig (0.25) " _. b.
125 VDC (0.5) c.
Depress both reset. switches (0.5) . - d.
Primary. Containment Instrument Gas System (0.5) . REFERENCE 1.- LP.302HC-000.00-029 p. 26,30, EO 4; 10e 2.
KAi218000K201 (3.1/3.1) 218000K501 (3.8/3.8) 218000K101 (4.0/4.1) 218000K404 (3.5/3.6) B.
Question item "C" sets up a false set of conditions, once ADS has initiated, ' turning off the RHR and/or Core Spray purops has no effect or. the ADS valves.
, t; . They will remain open.
'C.
See attached documentation.
' i (***** END OF CATEGORY 3
- )
____-__Q
.. - ,. ,, , y
8 - ies
. I-r l
K
'
y: ,' C
gt
C g l'
D t
8 i V m ,
s
V gI e C
o D L /7 /7
V
I
1 n 5, R - ei S nt S ai 1 n ' s m 1, I B MI I A 5, mi i, b P l I E ' - Y B e i, , m
a
W ,,' , I K" D , F - H e , W>R
i t F .
s, - e ia n
-, m 1, KP
'r,Kg,$ - .I 8, - . E I
. . f m5, P
V
4 s a T K p hf c, S L e
- mI j A A g S
A D V , I
- - - B P EDI 5, r
B i Y Z I
i,o B l O a 1 - mI o
K n G , I -
,> - Kr N W R ' j' E E nt D L - i BW ,' B I E . B N a O f I T n Mi H S , - M -
R - . - Bhh KM# =
E U j A =
_.
- R K - d'B B . I' I !f F E H " H I
cu T T c[- sj O
mI n
BE P a1 Z I B / ' Tt R
$ 0' I S G t 8Hs d8o
ia
UR
R . K'
ME -
T K
~ N u - - F ~ F E i I S
- E B
4 B
1
KO A _ I
, ds
- K . u
n
,K, T D
-
NE M - .I rt -
B B . - . ei AMI b .
2 mi - K
F K Tn i BT ih . i ' 8 S I !
. 8, - 8' I K
S/ l EI n _ . - Om M M
/ ' K - . 1, _ ,
F T Aro S A t N ' Y SC _ E F _ . t r S . A _ . I K - - '{, d S L EG _ - t
l
E E HO . E_ A _ R R TL _ - t
laS 2
. _ , B
P h _ K eI K
I
_ S e ' H _ -
h T
_ c B i s( L E _ t L T w B - l S E O y ,I N K ,, W N Y R D - _ ' r
, _ -.. - _ - _ _ _ , _ _ - -, - - - - - -, [A i-AK(g{&{- } ' ', w.. r RESOLUTION OF HOPE CREEK R0 EXAM FACILITY COMMENTS QUESTION 2.06 PART a g r-FACILITY COMMENT.AND RESOLUTION ACCEPTED l:- QUESTION -.2'.11 ' FACILITY COMMENT AND RESOLUTION ACCEPTED QUESTION 2.14 PARTS a AND b FACILITY COMMENT AND RESOLUTION ACCEPTED .IN' ADDITION 2.14 ITEM d SHOULD INCLUDE ITEM 2 (GROUP 2) IN ACCORDANCE WITH TABLE 3.3.2-1 QUESTION 3.27 PART c PART c DELETED le L ! l ' l o_ _ ___ i
f.L y- -4 or l L-fggg d.
' k .. i I Sitt1ATION FFCILITY REPORT ' Facility Licensee: Public Service Electric and Gas Co.
j Hope Creek Nuclear Generation Station Facility Docket No: 50-354 Operating Tests Administered on July 19 and 20,1989 This form is to used to report observations. These. observations do not constitute audit or inspection findings and are not, without further verification.and review, indicative of nonm ompliance with 10 CFR 55.45(b).
These observations do not affect PFC certification or approval of the simulation facility other than to provide information which may be used in future evaluations. No licensee action is required in response to these ! observations.
During the conduct of the simulator portion of the operating tests, the , following items were observed. None of the items affected the simulator l scenarios.
' ITEM DESCRIPTION i B steam flow Flow reading was lcwer than other steam lines.
, indicator I A5 74 IDS screen Screen frequently turned off l DC b as indication Bus loading indication was downscale TCS chiller One chiller indication was downscale, indication During the IRC preparation of scenarios the following items were observed.
, ITEM DESCRIPTION Malfunction The simulator is limited in the malfunctions wh.tch fail the automatic action f rom occurring tut allow the manual portion to function (ie Failure of auto RPS also prevents i manual scram and diesel generator auto start failure also prevents manual start capability). Isolations Additional simulator capability to provide additional isolations than can be prevented from occurring would j allow broader testing of operator verification of isolations.
I I Secondary Additional simulator capability to provide additional ' containment malfunctions that challenge secondary containment challenges integrity from high energy pipe leaks would allcw broader testing of use of Secondary Containment EOPs.
l , - _ _____________ - __ - _ _ - - - - }}