IR 05000333/1997009: Difference between revisions

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{{Adams
{{Adams
| number = ML20197H429
| number = ML20216B260
| issue date = 12/15/1997
| issue date = 03/09/1998
| title = NRC Operator Licensing Exam Rept 50-333/97-09 (Including Completed & Graded Tests) for Tests Administered on 971104-07
| title = Forwards NRC Operator Licensing Exam Rept 50-333/97-09 for Exams Administered on 971103-07
| author name =  
| author name = Curley V
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000333
| docket = 05000333
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = 50-333-97-09, 50-333-97-9, NUDOCS 9712310277
| document report number = 50-333-97-09, 50-333-97-9, NUDOCS 9803130022
| package number = ML20197H399
| document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE
| document type = EXAMINATION REPORT, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 1
| page count = 170
}}
}}


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March 9, 1998  l NOTE T0: NRC Document Control Desk Mail Stop 0-5-D-24
U.S. NUCLEAR REGULATORY COMMISSION--
  '
    - REGION I-Docket No. '_
FROM: $c t I- oa fe n .L Opera';ing Licensi "BranchRpnsingAssistant SUBJECT:
_5 0 3 3 3.~
OPERATOR llevendetr 3-7LICENSING 1997 . ATEXAMINATION ADMINJSIERED ON d. R. Fitz t'a7xich' .
License No.-  : DPR 59 Report No,' -97 09
  ' DOCKET #50.dja On vemlea A-7 n 97 Operator Licensing Examinations were administered at the referenced' facility. Attached. you will find the following information for processing through NUDOCS and distribution to the NRC staff, including the NRC PDR:     j
- Licensee:  New York Power Authority Post Office Box 41 Scriba, New York 13093
      )
: Facility Name:
Item #1 - a) Facility submitted outline and initial exam submittal.
  .
James A. FitzPatrick Nuclear Power Plant
- Examination Period: November 4 7,1997
. Examiners:  . D. Florek, Senior Operations Engineer '.
S. Dennis, Operations Engineer
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C. Sisco, Operations Engineer Approved by: G. Meyer, Chief, Operations and Human Performance Branch Division of Reactor Sciety  i L
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designated for distribution under RIDS Code A070.
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I ":9712310277 971215 PDR: ADOCK 05000333-PDR
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y-  ,


  .4-
b) As given operating examination. designated for distribution under RIDS Code A070.
    , _ . . -


_ _ _ _ _ _ _ _ _ _
Item #2 - Examination Report with the as given written examination attached, designated for distribution under RIDS Code'IE42.
EXAMINATION SUMMARY -
Examination Report 50 333/97 09 (OL)
Initial exams were administered to four senior reactor operator (SRO) instant applicants and four reactor operator-(RO) applicants during the period of November 4 7,1997, at the Jarnes A. FitzPatrick (JAF) Nuclear Power Plan OPERATIONS All eight applicants passed the exam. All applicants were well prepared for the examination. The JAF training staff and a contractor developed the examination. .The quality of the initial submittal was not at the level that met NRC expectations as defined in NUREG 1021. However the JAF training staff responded to the NRC comments on the proposed examination and developed a fina' examination that was acceptabl ' An unresolved item was identified related to a change made to the Emergency Operating Procedures regarding initiation of isolations that should have occurred but did no On the operating test, the examiners noted very good performance regarding team work, use of prints, communication, procedure use, and peer checking. Also, the examiners noted weak performance related to a1 alternate path task related to the refueling interlock test, ii
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Reoort Details 05.1 Operator Initial Exams $1QQg, The examiners administered initial examinations to four RO and four SRO instant applicants in accordance with NUREG 1021, " Examiner Standards," Interim Revision 8. The examinations were prepared by Jarr.es A. FitzPatrick (JAF) staff and were approved by the NRC JAF staff administered and graded the written examination. The NRC administered and graded the operating test and concurred with the JAF staff grading of the written examination, Observations and Findinas The results of the initial examinations are summarized below:
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;88 188!i 8188822a V PDR lllllllllllllll!,11Bll11
l SRO RO  Pass / Fail Written    4/0  4/0  8/0 Operating    4/0  4/0  8/0 Overall    4/0  4/0  8/0 The examinations were prepared by JAF staff. The JAF staff involved with the development of these examinations signed security agreements to ensure the integrity of the initial examination proces .
      .
JAF staff submitted their proposed sample plan on August 27,1997. The NRC Chief examiner made minor changes to the submitted sample plan which were made by the JAF staf The JAF proposed SRO and RO written examinations were submitted for NRC approval on September 25,1997, and the operating tests the following week as agreed by the Chief Examiner. The JAF initial submitted examination was not an examination capable of discriminating between acceptable and unacceptable license candidates and required modification to meet NRC Examiner Standards. The following is a summary of the problems noted with the prope, sed examinatio Simplistic written, JPM and admin questions
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Poor written questiun distractors which were easily eliminated
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Written questions which did not correlate with the assigned K/A
  -
Awkwardly worded written and JPM questions
  -
Written and JPM questions that did not solicit the answer in the answer key


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December 15, 1997 h p_ (=, bC
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  ,  EFAm i '. LE
      .
Mr. Michael Site Executive Officer New York Power Authority    )
James A. FitzPatrick Nuclear Power Plant    j Post Office Box 41      i Lycoming, NY 13093      l SUBJECT: FITZPATRICK EXAMINATION REPORT 50 333/97-09


- Double jeopardy questions
==Dear Mr. Colomb:==
- Lack of balance in the written distractors
-- More than one correct answer
- Inadequate cues for in-plant JPMs
- JPM and admin questions not written at the SRO level
- JPM questions writtnn as direct look up rather than "open reference" use
- Inadequate operator actions in the proposed simulator scenarios
- Sperification of scenario critical task 4
- Inadequate malfunctions to assess each operator in the competency evaluation The NRC examination team held an examinav e > reparation visit the week of September 20,1997. As a result of the NRC and JAF staff interaction, an acceptable examination was developed and administere JAF staff administered the written examinations on November 3,1997. The NRC examiners administered the operating examinations in the period of
,
,
November 4 7,199 By letter, dated November 12,1997, JAF staff provided the grading of the written examination and identified comments on five questions. A copy of the JAF letter is contained in Attachment 3. The NRC accepted the JAF comments on the written examination as described in Attachment 4. The examiners reviewed the grading of the written examinations and concurred with the grading by JAF staf During the walkthrough portion of the operating test, the SRO instant applicants performed poorly in the following task:
i
Alternate path task related to the refueling interlock tes During the operating test, the following items were significant and consistent positive observation P&lD, electrical, and logic prints were effectively used by the applicant Teamwork within the crews was very goo Communication within the crews was very good. Crew briefings were concise, timely, and appropriate. The applicants were very poise Procedures, including alarm response procedures, were effectively used during the scenario Effective use of peer checking, Conclusions The applicants were well prepared for the examination, and as a result,8 of 8 applicants passed the examinations and were subsequently issued license JAF staff did not have a complete understanding of the NRC expectations in the development of their proposed initial examination. Significant interactions between '
      '
the NRC and JAF staff were required to develop an examination that was consistent with the NRC Examiner Standards, in the end, JAF staff were successful in Jeveloping an acceptable examination.
During the period of November 4-7,1997, the NRC administered initial exams to eight employees of your company who had applied for licenses to operate the James A.


03.1 Emeraency Operatina Procedures (EOPsl Scope The examiner reviewed the change to EOPs which changed the Emergency Procedure Guideline (EPG) step HC,,L-1 from " Initiate each of the following which should have initiated but did not" to " Verify initiation of". Observations and Findinas During the examination the examiners noted that the applicants did not always
FitzPatrick Nuclear Power Plant. At the conclusion of the examinations, the prelimi, nary findings were discussed with Mr. Topley and members of your staff.
" Verify initiation of" during the execution of the EOPs. The examiners noted that the EOPs were revised to change the step as a concurrent step rather than a series step and also " Initiate" was chenged to " Verify initiations".


At JAF, in accordance with AP-02.01 " verify initiation" meant "to observe that the associated activities have been performed or that the expected conditions or characteristics exist." This was not the same as " Initiate each of the following which should have but did not". AT JA.F " verify" was performed on a concurrent, when available basis by the ROs informing the SRO what actions should have initiated but did not. The SRO was allowed to decide as to whether to initiate those actions. At JAF " ensure" was used to mean initiate each of the following which should have initiated but did no The EOP procedure change, dated December 6,1996, which made the change and the resulting plant specific technical guide (PSTG) indicated that this was plant specific terminology and did not specifically identify whether the wording change was meant to be identical in interpretation. In addition,the change from series to concurrent execution of initiate isolations was not specifically addresse Conclusion
All eight applicants passed the exams. All applicants were well prepared for the examination.
- An unresolved item was identified for JAF to provide an assessment of whether
"
Verify isolations" was meant to be equivalent to " initiate each of the following which should have but did not". 'If this was not the case, then the procedure i change documentation _should be reassessed for completeness and adequacy. In addition the adequacy of the change from series to concurrent, when available execution should be documented.- This is unresolved item (50 333/97 09-01)- Review of UFSAR Commitmerits A recent discovery ~of a licensee operating their facility in a manner contrary to the updated final safety analysis report (UFSAR) description highlighted the need for a special focused review that compares plant practices, procedures and/or parameters to the UFSAR descriptions. While performing the examination activities discusssd l In this report, the examiner reviewed portions of :he UFSAR that related to a main steam line break accident examination question. The selected examination question reviewed was consistent with the UFSA V. Manaaement Meetinas X1 Exit Meeting Summary At the conclusion of the examination, the examiners discussed their observations of the examination process with members of JAF management. The examinations noted that no simulator fidelity concerns had been observed or identified. JAF management acknowledged the examiner observations.


The JAF personnel present at the exit included the following:
Your staff developed the initial examinations. However, the quality of your staff's initial input did not meet our expectation. Based on the interaction between the chief examiner and your staff, an acceptable examination was eventually developed and subsequently administered. We hope that the lessons learned will be applied during future examination development efforts.
P. Brozenich, Operations Manager R. Locey, Training Manager J. Morris, initial Program Administrator J. Romanowski, Operations Training Supervisor D. Topley, General Manager, Maintenance Attachments:
1. SRO Examination and Answer. Key 2. RO Examination and Answer Key 3. JAF Comments on the Written Examination 4. NRC Resolution of JAF Comments on the Written Examination
    . _


ATTACHMENT 1 SRO EXAMINATION AND ANSWER KEY
An unresolved item was identified related to a change made to your Emergency Operating Procedures.
.,


    '- -%>- &  a---- 4
In accordance with 10 CFR 2.700 of the NRC's " Rules of Practice," a copy of this letter and its enclosures will be placed in the NRC Public Document Room (PDR).
.
NEW YORK POWER AUTHORITY    EXAMINATION / QUIZ JAMES A. FITZPATRICK NUCLEAR POWER PLANT  COVER SHEET Examination Title: USNRC SENIOR REACTOR OPERATOR EXAMINATION Examination Submitte By:) MA  Date: 11/03/97
.,
Supervisor Approval:  C 1 4 . M o t t i_S  Date: fo lt) $7 Authorized Reference I: ATTACHED Minimum Acceptable Grade: 80  Total Exam Points: 100 9 ade:  Graded By:  Time Limit: 4 hours __
STUDENT DATA Name:    S.S.#:
Last First  M, Employer: NEW YORK POWER AUTHORITY  Date:
Department:
GUIDELINES 1, Remain quiet during the exam, if you have any questions during tho exam, raise your hand, Your instructor will provide clarification wherever possibl . You are expected to do your own work and not to help anyone else, 3, Use only the authorized reference materia . At the complet:on of this examination, you are to sign the following certification, I certify all answers contained in this examination are my own, in addition, I have not received nor given any unauthorized istance, nor have used any unauthorized reference Student Signature:    Date:


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SENIOR REACTOR OPERATOR EXAMINATION i 1-        ,
Question 1l        }
  : With the plant operating at 50% power, which'one of the following Main Generator faults
  .
          {
will cause an automatic reactor scram?1
  -- High Stator. Winding Temperatur ,
  . -
          :
i liigh Differential Current.


. c.- Loss ofIsolated Phase Bus Duct Coolin ; t.
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*
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Mr. Michael Should you have any questions regarding this information, please contact Don Florek of my staff at (610) 337-5185 or me at (610) 337-5211.


* : Low Hydrogen Pressure.
Sincerely,


<
Glenn W. Meyer, Chief Operations and Human Performance Branch Division of Reactor Safety i
          ,
Docket No.: 50-333 License No.: DPR-59 Enclosures: Examination Report 50-333/97-09 s.g.w/ encl: w/o Attachments 1-4:
a h
C. D. Rappleyea, Chairman and Chief Executive Officer  )
*
E. Zeltmann, President and Chief Operating Officer R. Hiney, Executive Vice President for Project Operations J. Knubel, Chief Nuclear Officer and Senior Vice President
.
      )
i Question 2
H. P. Salmon, Jr., Vice President of Nuclear Operations W. Josiger, Vice President - Engineering and Project Management J. Kelly, Director - Regulatory Affairs and Special Projects T. Dougherty, Vice President - Nuclear Engineering R. Deasy, Vice President - Appraisal and Compliance Services R. Patch, Director - Quality Assurance G. C. Goldstein, Assistant General Counsel C. D. Faison, Director, Nuclear Licensing, NYPA K. Peters, Licensing Manager    ,
:  Which one of the following is the reason that the Reactor Mode Switch should be taken out of the RUN position immediately after a Reactor Scram?
R. Locey, Trainira Manager    l T. Morra, Executive Chair, Four County Nuclear Safety Committee Supervisor, Town of Scriba C. Donaldson, Esquire, Assistant Attorney General, New York Department of Law P. Eddy, Electric Division, Department of Public Service, State of New York G. T. Goering, Consultant, New York Power Authority J. E. Gagliardo, Consultant, New York Power Authority E. S. Beckjord, Consultant, New York Power Authority F. William Valentino, President, New York State Energy Research and Development Authority J. Spath, Program Director, New York State Energy Research and Development Authority
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          ' Enable SRM and IRM rodblock b.'- Prevent MSIV isolation; e Enable the SDIV high level bypass circuitr , Lower the APRM scram setpoint to ISR
:        s.


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Mr. Michael Distribution w/enci and Attachments 1-5:
      ... - , . - , v , r . _ . _. . _ _ _ _ . _ . _ . . - - _ . . . _ -
DRS Master Exam File PUBLIC Nuclear Safety information Center (NSIC)   *
      ...__..- _ _ _ _ _ -. ._ _ _ _
Distribution w/ encl: w/o Attachments 1-5:
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H. Miller, RA/W. Axelson, DRA (1)
ir
J. Wiggins, DRS D. Screnci, PAO (2)
          '
Nuclear Safety Information Center (NSIC)
  . SENIOR REACTOR OPERATOR EXAMINATION -
PUBLIC NRC Resident inspector Region i Docket Room (with concurrences)
._ . Question 3'      _
J. Rogge, DRP R. Barkley, DRP R. Junod, DRP D. Florek, Chief Examiner, DRS OL Facility File    .
          ,
Distribution w/enet: w/o Attachments 1-5: (VIA E-MAIL)
  : A reactor scram has just occurred followed by a Residual Transfer. Which one of the
M. Leach, R1 EDO Coordinator S. Bajwa, NRR K. Cotton, NRR W. Dean, OEDO (WMD)
  ' following describes the operators' concerns regarding the MSIVs under these conditions?  .
D. Hood, NRR M. Campion, RI Inspection Program Branch, NRR (IPAS)
          :
DOCDESK DOCUMENT NAME: A: FITZ9709.lNS
a. _ Ensure the MSIVs close to minimize the possibility of Main Turbine overspee _
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  . : Ensure the MSIVs close to minimize the possibility of Turbine Building  ,
Contaminatio Ensure the MSIVs remain open to minimize Torus heat loa Ensure the MSIVs remain open to rnaintain availability of Turbine Scaling stea .
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Question 4 Following an automatic IIPCI initiation, the operators note that liPCI trips and then later restarts with no operator action. Which one of the following was the cause of the trip? liigh turbine exhaust diaphragm pressur Iligh steam flow rat . liigh RPV leve d.- _liigh HPCI area temperatur _
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m 2 .- ...c- - w- w-m OFFICE Rigg // l Rl/DRP/ l Rl/DRS [ Rl/ l Rl/
NAME      l l D"'eff V JRogge GMeyer Qj  [
DATE- 12/9597 12f /97 12/pf97
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9'' 12/ /97 12/ /97 l OFFICIAL RECORD COPY
      .


l SENIOR REACTOR OPERATOR EXAMINATION
. j U.S. NUCLEAR REGULATORY COMMISSION '
      !
. Question 5 A' power ascension is in progress with the following conditions:
. Power level is 70%.    ,
. Load line is 100%.
. Two Feedwater pumps are operatin Which one of the following describes when and how the Recire. Pumps will runback if one Feed Pump trips? Immediately runback to minimum spee When RPV level lowers to 196.5 inches; runback to minimum spee Immediately runback to 44% spee When RPV level lowers to 196.5 inches; runback to 44% spee Question 6 The following conditions exist:
. A Group 11 isolation has occurred due to high Drywell pmssur . Present Dry,vell pressure is 5 psi . The EMERG OVERR DRYWELL 111 PRESS keylock switch on the PCP panel has been taken to its OVERRIDE positio . No other operator actions have been take Which one of the following describes the CAD isolation valves that can be opened at this time? All CAD isolation valves, All CAD isolation valves except 27AOV-111 through 118 (CAD vent valves), All CAD isolation valves except 27MOV-113. I17,122,123 (CAD purge valves). All CAD isolation valves except 27AOV 131 A/B,132A/B (CAD make-up valves).


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==REGION I==
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Docket No. 50-333 License No. DPR-59 Report No. 97-09 Licensee:  New York Power Authority Post Office Box 41 Scriba, New York 13093 Facility Name: James A. FitzPatrick Nuclear Power Plant Examination Period: November 4-7, 1997 Examiners: D. Florek, Senior Operations Engineer S. Dennis, Operations Engineer C. Sisco, Operations Engineer Approved by: G. Meyer, Chief, Operations and Human Performance Branch Division of Reactor Safety iI
 
    )
SENIOR REACTOR OPERATOR EXAMINATION Questica 7 The plant is operating at full power when the following occur:
i D+b I D 2 i ~/'
. Generated MWe starts to decreas * Reactor power starts to decreas Which one of the following could have caused these symptoms? Decrease in grid frequenc Jet Pump malfunctio Loss of feedwater heatin Inadvertent SRV openin Question 8 With a his,h Drywell pressure, Emergency RPV Depressurization is required if Torus Water Level cannot be maintained below PSP (Pressure Suppression Pressure). Which one of the following is the basis for performing an Emergency RPV Depressurization if the Pressure Suppression Pressure Limit is exceeded? To ensure that the vacuum breakers will not become submerged and fail to functio To ensure adequate free volume (airspace) of the Torus for steam suppressio To prevent damaging the Toru To prevent steam from the Drywell bypassing the Suppression Pool.


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EXAMINATION SUMMARY Examination Report 50-333/97-09 (OL)
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Initial exams were administered to four senior reactor operator (SRO) instant applicants and four reactor operator (RO) applicants during the period of November 4-7,1997, at the James A. FitzPatrick (JAF) Nuclear Power Plant.


  ..
OPERATIONS All eight applicants passed the exam. All applicants were well prepared for the examination. The JAF training staff and a contractor developed the examination. The quality of the initial submittal was not at the level that met NRC expectations as defir.ed in NUREG 1021. However the JAF training staff responded to the NRC comments on the proposed examination and developed a final examination that was acceptable.
SENIOR REACTOR OPERATOR EXAMINATION-Question 9 Which one of the following would give positive indication that SRV 'C' la open when its control switch is taken to OPEN? SRV red light is o SRV white light is o SRV tailpiece temperature rises and stabilizes at 285 ' Epic alarm ' SONIC DET RV-C' RESFT is receive Question 10 The following conditions exist:
. A plant transient raised RPV pressure to 1150 psi . The SRVs have opene . RPV levelis 150 inche Assuming no operator action, which one of the following describes when the SRVs are expected to close? Before RPV pressure decreases below approximately 1050 psi seconds after the initial transien After RPV pressure decreases below approximately 50 psi d, When both RIIR and Core Spray pumps are secure Page 5 of 50
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An unresolver' item was identified related to a change made to the Emergency Operating Procedures regarding initiation of isolations that should have occurred but did not.
SEN1OR REACTOR OPERATOR EXAMINATION ~
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        !
. Questionil1 A reactor scram occurred but many control rods failed to insert due to a high water level in  r the Scram Discharge Volume. The APRMs read 9 %EWhich one of the following actions--
will be most effective in inserting control rods? :
- Manually initiate ARl,      , De-energize scram solenoid Manually insert control rod . Close the CRD Flow Control valve.


Question 12
On the operating test, the examiners noted very good performance regarding team work, use of prints, communication, procedure use, and peer checking. Also, the examiners noted weak performance related to an alternate path task related to the refueling interlock test.


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Following the trip of one Recire. Pump with the reactor at power, the operators have closed the discharge valve of the tripped pump. Which one of the following is the reason that this is done?-
a.~ Stops reverse rotation of the tripped pum Prevents backflow through the idle Jet Pumps, Prevents runout of the operating Recire. Pum ' Lowers the probability of entering the instability region of the power / flow ma ,
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Reoort Details 05.1 Operator initial Exams a. Scone The examiners administered initial examinations to four RO and four SRO instant applicants in accordance with NUREG-1021, " Examiner Standards," Interim Revision 8. The examinations were prepared by James A. FitzPatrick (JAF) staff and were approved by the NRC. JAF staff administered and graded the written examination. The NRC administered and graded the operating test and concurred with the JAF staff grading of the written examination.
    .,        ,
 
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b. Observations and Findinas The results of the initial examinations are summarized below:
I SRO  RO  Pass / Fail Written  4/O  4/O  8/O
' Operating  4/0  4/O  8/0 l Overall  4/O  4/0  8/O The examinations were prepared by JAF staff. The JAF staff involved with the development of these examinations signed security agreements to ensure the integrity of the initial examination process.


SENIOR RNA'CTOR OPERATOR NX MINATION)
JAF staff submitted their proposed sample plan on August 27,1997. The NRC Chief examiner made minor changes to the submitted sample plan which were made by the JAF staff.
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UQue'stion? 13-I
  ,  { The following conditions ~ exist: - __        'l
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  # * a Condenser vacuum is 25.1 inches Hgi
  ? e 1 Turbine load is 170 MWe.-      ~
1 J AOP 11 (Loss of Condenser Vacuum) has been entere q
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j c  - Which one of the following actions, by itself, will make it MORE LIKELY that a manual
  -          j
  - - Turbine Trip will be required? -        l I
L ai: . Starting the Mechanical Vacuum pump ) L Increase load to 255 MWe.


,
The JAF proposed SRO and RO written examinations were submitted for NRC !
            ]
approval on September 25,1997, and the operating tests the following week as agreed by the Chief Examiner. The JAF initial submitted examination was not an examination capable of discriminating between acceptable and unacceptable license candidates and required modification to meet NRC Examiner Standards. The ,
:>      - .
following is a summary of the problems noted with the proposed examination. I
c. - Decrease load to 85 MWe,       l
- Simplistic written, JPM and admin questions
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Poor written question distractors which were easily eliminated
    'd. . Placing the spare Air Ejector sets in senic .
- Written questions which did not correlate with the assigned K/A
            ;
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  -
Awkwardly worded written and JPM questions
- Written and JPM questions that did not solicit the answer in the answer key
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E Question '14 -          '
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. With the plant shutdown, an Emergency Diesel Generator is running and is tied to its bus for load testing. Which one of the following describes the response to a complete loss of offsite power?          ,
a. ' . The Tie Breakers will trip and the diesel will maintain the bus loads. .
Ib, The Diesel Output breaker will trip and the diesel will switch to isochronous
  -
    - mode, then the Diesel Output breaker reclose l
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  " The Diesel Output breaker will trip and the diesel will switch to droop mode, then
+
the Diesel Output breaker recloses,      r
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. l d.- 1 The Tie 'oreakers and the diesel will tri +  ,
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    , , , . . . J .4 , - , . , .. ~ , _ . , _ . . - . - . . ~ . . . ... SENIOR REACTOR OPERATOR EXAMINATION Question 15 Ilus 10400 is powered by the Main Generator via breaker 10402. Which one of the following ways of opening this breaker will not allow closing the Station Reserve breaker 104127
      . Manually opened locally, Manually opened from the control roo Automatically opened on o /ercurren Automatically opened on undervoltage.


,
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Question 16 Which one of the followi.ig describes the loads in the 24 VDC Power System? Each Icad breaker is connected to 48 VDC potential (input) from its associated 9. VDC charger, Italf the loads on a 124 VDC distribution bus are powered from +24 VDC, The other half are powered from -24 VD Each load breaker is connected to 24 VDC potential (input) from its associated 112 VDC charger, IIalf the loads on a 148 VDC distribution bus are powered from +48 VDC. The other half are powered from -48 VD ,
Double jeopardy questions
Page 8 of 50
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Lack of balance in the written distractors
l
      .
-
More than one correct answer
- Inadequate cues for in-plant JPMs
-
JPM and admin questions not writt'en at the SRO level
-
JPM questions written as direct look up rather than "open reference" use
-
Inadequate operator actions in the proposed simulator scenarios
- Specification of scenario critical tasks
-
Inadequate malfunctions to assess each operator in the competency evaluation    ,
The NRC examination team held an examination preparation visit the week of September 20,1997. As a result of the NRC and JAF staff interaction, an acceptable examination was developed and administered.


__
JAF staff administered the written examinations on November 3,1997. The NRC examiners administered the operating examinations in the period of November 4-7,1997.


_ ~ _  . _. _  _ ,~ . . ., _ ._ . . .. _ - _, . _ . - -
By letter, dated Nover%r 12,1997, JAF staff provided the grading of. o written examination and identh.1: comments on five questions. A copy of the JAF letter is contained in Attachment 3. The NRC accepted the JAF comments on the written examination as described in Attachment 4. The examiners reviewed the grading of the written examinations and concurred with the grading by JAF staff.


F
During the walkthrough portion of the operating test, the SRO instant applicants performed poorly in the following task:   -
_
Alternate path task related to the refueling interlock test.
    - SENIOR REACTOR OPERATOR EXAMINATION-i
            -
Qdestion4174 L'Ihe follo(ing Narrow Range RPV level conditions exist:      l
  '
  *: - A' indicates 215 inches and is rising slowlyt
  -
            ;
  *:- - 'B' in/4icates 185 inches and is lowering slowly.


L -
During the operating test, the following items were significant and consistent positive observations.
  -e ,'C' it,dicates 214 inches and is rising slowly,       :
:  :* Feedwater control is selected to the 'A' Column -      ]
Selecting the 'B' RPV Level Column will result in which one of the following effects on levell
  - trends?:
  - a, 'A' and 'C' will continue to rise. 'B' will lower.


.
P&lD, electrical, and logic prints were effectively used by the applicants.
bi 'A' and 'C' will continue to rise. 'B' will rise. -      ;
q
, "A' and 'C' will lower 'B' will lower.


' 'A' and 'C' will lower. 'B' will rise. -      ;
Toimwork within the crews was very good.
,
Question 18 In which one of the following ways does a loss of 125 VDC Bus 'A' affect the ADS /SRV system?
, Loss of'A' logic, ADS remains functional.


* None of the ADS /SRV valves can b opened.
Communication within the crews was very good. Crew briefings were concise, timely, and appropriate. The applicants were very poised.


*
. . -
,
.. . .... - . . . .
c, The ADS /SRV valves cannot be opened from the remote pane :
  .
Only valves F, J, K & L remain fully functiona !
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g + , + - -, , y - -, ,, + + , + . - , , , - - - ~ . ---r-+ ~N+,


_ ~ _ . .  . _ .; , _ _ . . _ . _.--_ ._-_ . _ __ _ ,. - _ . - - . - . _ _ _ _ _ _ _
Procedures, including alarm response procedures, were effectively used during the scenarios.
          :
s
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SENIOR REACTOR OPERATOR EXAMINATION .
          :
e
. Question'19;
_
i AOP43 (Shutdown From Outside the Control Room) requires the operators to remove RiiR    ;
  : pumps 'A' and 'C' from service. Which one of the following' describes the reason that this  ,
,
step is necessary?
          ' : Prevent water hammer in the event of a LOCA signsl.


-
Effective use of peer checking.
  . Prevent inadvertent Drywell spra ; Prevent inadvertent LPCI injectio [
 
,.
c. Conclusions The applicants were well prepared for the examination, and as a result,8 of 8 applicants passed the examinations and were subsequently issued licenses.
d.- Prevent draining the RP_V to the. Torus.
:          .
          .
p Question- 20 The following events occur:
  . - The plant is at 20% power.


'
JAF staff did not have a complete understanding of the NRC expectations in the development of their proposed initial examination. Significant interactions between the NRC and JAF staff were required to develop an examination that was consistent with the NRC Examiner Standards, in the end, JAF staff were successful in developing an acceptable examination.    !
  . liigh radiation in the Off Gas system starts the OITGas Timer.
03.1 Emeraency Operatina Procedures (EOPs)
a. Scope The examiner reviewed the change to EOPs which changed the Emergency Procedure Guideline (EPG) step RC/L-1 from " Initiate each of the following which should have initiated but did not" to " Verify initiation of".


   . No operator action is taken.
b. Observations and Findinas During the examination the examiners noted that the applicants did not always
   " Verify initiation of" during the execution of the EOPs. The examiners noted that the EOPs were revised to change the step as a concurrent step rather than a series step and also " Initiate" was changed to " Verify initiations".


[  Which one of the following will be the most likely cause of an automatic reactor scram?. liigh Reactor Powe t'
At JAF, in accordance with AP-02.01 " verify initiation" meant "to observe that the associated activities have been performed or that the expected conditions or characteristics exist." This was not the same as " Initiate each of the following which should have but did not". AT JAF " verify" was performed on a concurrent, when available basis by the ROs informing the SRO what actions should have initiated but did not. The SRO was allowed to decide as to whether to initiate those actions. At JAF " ensure" was used to mean initiate each of the following which should have initiated but did not.
l ._ Low RPV Level.-
. MSIV closur ,
  . 'lligh RPV Pressure.
:
i-
,
.
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SENIOR REACTOR OPERATOR EXAMINATION
The EOP pr.aedure change, dated December 6,1996, which made the change and the resulting plant specific technical guide (PSTG) indicated that this was plant specific terminology and did not specifically identify whether the wording change was meant to be identical in interpretation. In addition,the change from series to concurrent execution of initiate isolations was not specifically addressed.
. Question 21
,
Which one of the following describes the use of ESW for Drywell cooling during a LOCA7 It is the preferred metho It may be used only on loss of RBCL c, it may be used only if directed by EOP- It is prohibite Question 22 On a Loss ofinstrument Air pressure during normal plant operation, whicii one of the following describes if and when the MSIVs will go closed? Inboards remain open; outboards close immediately, Inboards and outboards close inunediately, Inboards close eventually; outboards close immediately, Inboards remain open; outboards close eventuall Page11of50
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c. Conclusion An unresolved item was identified for JAF to provide an assessment of whether
SENIOR REACTOR OPERATOR EXAMINATION Question 23 The following conditions exist:
" Verify isolations" was meant to be equivalent to " Initiate each of the following -
. A valid Reactor Scram has occuned on low RPV leve . The EDGs have auto started in response to high Drywell pressur . The Recire, pumps anc running at minimum speed as expecte Which one of the following describes the status of the containment isolations? Group 1 isolated; Group 11 isolate Group 1 not isolated; Group 11 not isolate Group I isolated; Group 11 not isolate Group i not isolated; Group 11 isolate l
which should have but did not". If this was not the case, then the procedure j change documentation should be reassessed for completeness and adequacy. In 1 addition the adequacy of the change from series to concurrent, when available execution should be documented. This is unresolved item (50 333/97-09-01)
       !
l'
      -l Question 24 During a plant startup RPV pressure is 900 psig. Loss of CRD flow will have which one of the fo'.iowing efTects on control rod motion and scram times? Normal rod motion is unafTected and scram times will be within acceptable limit Normal rod motion is lost and scram times will not meet c.cceptable limit Normal rod motion is unafTected but scram time; will not meet acceptable limit Normal rod motion is lost but scram times will be within acceptable limit Page 12 of 50
E.8 Review of UFSAR Commitments    j A recent discovery of a licensee operating their facility in a mentar contrary to the updated final safety analysis report (UFSAR) description highlighted the need for a i special focused review that compares plant practices, procedures and/or parameters )
  "*** EXAMINATION CONTINUED ON NEXT PAGE ***"
to the UFSAR descriptions. While performing the examination activities discussed l in this report, the examiner reviewed portions of the UFSAR that related to a main j steam line break accident examination question. The selected examination question -(
reviewed was consistent with the UFSAR.  .
l V. Manaaement Meetings l
X1 Exit Meeting Summary    j
       )
At the conclusion of the examination, the examiners discussed their observations of the examination process with members of JAF management. The examinations noted that no simulator fidelity concerns had been observed or identified. JAF management acknowledged the examiner observations.


  - _
The JAF personnel present at the exit included the following:
    -
P. Brozenich,' Operations Manager R. Locey, Training Manager    !
SENIOR REACTOR OPERATOR EXAMINATION
J. Morris, Initial Program Administrator J. Romanowski, Operations Training Supervisor D. Topley, General Manager, Maintenance Attachments:
-
1. SRO Examination and Answer Key 2. RO Examination and Answer Key 3. JAF Comments on the Written Examination 4. NRC Resolution of JAF Comments on the Written Examination
Question 25 During power operation with RilR pump 'A' in Torus Cooling, an operator misttkenly manually opens R11R pump 'A' Shutdown Cooling Suction valve (10MOV-15A) locally at the valve, Which one of the following describes the expected automatic actions, if any? There will be no automatic action When 10MOV-15A reaches 10% open, it will automatically close the 'A' RilR Pump Suction Torus Isolation Valve (10MOV-13A). When 10MOV-15A reaches full open, the RilR Torus Cooling / Torus Spray outboard valve (10MOV-39A) will auto clos d.' The ' A' RliR pump will trip on low suction pressure.
      .


Questic.i 26 Which one of the following describes the consequences of spraying the Drywell if Drywell conditions are not in the permissible region of the Drywell Spray Initiation Curve? Water sprayed into the Drywell will turn to steam raising pressure even furthe The cold water will put excessive thermal stress on the Drywell which may lead to its failure, The efTect is unpredictable and would result in putting the plant in an unanalyzed conditio Drywell pressure would drop more rapidly than could be handled by the vacuum breaker Page 13 of 50
- ATTACHMENT 1 SRO EXAMINATION AND ANSWER KEY l
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SENIOR REACTOR OPERATOR EXAMINATION Quustion 27
      .
  %e Reactor Dailding Ventilation system is in operation when the exhaust plenum radiation levels exceed 10' cpm. Which one of the following describes the expected response of the Reactor Building Ventilation and SBGT systems to this esent? Reactor Building Ventilatien w;11 isolate and neither train of SBGT will start, Reactor Building Ventilation will isolate and both trains of SBGT will ctart, Reactor Building Ventilation will not isolate and neither train of SBGT will star Reactor Building Ventilation will not isolate and both trains of SBGT will star Question 28 The following conditions exist:
NEW YORK POWER AUTHOR!TY    EXAMINATION /QUlZ JAME3 A. FITZPATRICK NUCLEAR POWER PLANT  COVER SHEET Examination Title: USNRC SENIOR REACTOR OPERATOR EXAMINATION Examination Submitte By:) Mder  Date: 11/03/97
  . A fuel element failure has occurre . 01-107AOV-100 (OITGas Outlet Isolation Valve) is ope . The Off Gas timer has starte . The Stack Low Range monitors are reading full upscal . The Stack High Range monitors are reading 110 mR/h . Reactor Building Exhaust radiation is reading 22,000 cp These conditions require entry ''to which one of the following combinations of Emergency Plan EALs and EOPs? Unusual Event and EOP- Unusual Event and EOP- Alert and EOP- Alert and EOP- Page 14 of 50
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Supervisor Approval: .1.6. Mc EEIS  Date: to lt5 97 Authorized Reft:rence 1: ATTACHED Minimum Acceptable Grade: 80  Total Exam Points: 100  )
i
Grade: Graded By:  Time Limit: 4 hours STUDENT DATA Name: -   S.S.#:
Last First  M.l.


  . . , -- . .- .. - . .-. -.- - .. - - . - - . . - -
Employer: NEW YORK POWER AUTHORITY Date:
  '
Department:
SENIOR REACTOR OPERATOR EXAMINATION
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          ;
GUIDELINES
          ;
      ,
        "
1. Remain quiet during the exam. If you have any questions during the exam, raise l your hand. Your instructor will provide clarification wherever possible. i 2. You are expected to do your own work and not to help anyone else.
Question '29
          '
        '
  'In the event that normal shutdown cooling capability has been lost, which one of the
_
. following states the minimum shutdown time before Fuel Pool Cooling Assist will provide -
          -
adequate cooling? -
-
  .       a Ida ' .4 days.


>
3. Use only the authorized reference material.
  . ' 7 days.


, ~ 9 days.-
4. At the completion of this examination, you are to sign the following certification.
          :
.


.
I certify all answers contained in this examination are my own. In addition, I have not received nor given any unauthorized assistance, nor have used any unauthorized references.
Question 30 Which one of the following describes why it is important to establish forced Recire, flow during a Loss of Shutdown Cooling event? Coolant stratification may mislead the operators into azuming bulk water
. temperature is below 212'F,
"
  - Cooling of the recire. loop will produce a reactivity effect when the first recire.


E  pump is starte Unstable transition boiling at low pressure may cause clad damag ,
Student Signature:    Date:
d.~ Steam build up in the RHR suction piping will lead to waterhammer when RHR flow is restored, t
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SENIOR REACTOR OPERATOR EXAMINATION Question 1 With the plant operating at 50% power, which one of the following Main Generator faults will cause an automatic reactor scram?   ,
SENIOR REACTOR OPERATOR EXAMINATION Question 31-Which one of the followit.g limits takes precedence during the operation of the SBGT system with the Reactor Building isolated? Maintain RB AP more negative than -0.25 inches of water, Maintain charcoal filter temperatures less than 170 ' Limit SBGT flow to a maximum of 6000 scf Maintain Reactor Building Ventilation exhaust radiation levels less than 10' cpm.
a. High Stator Winding Temperature.
 
;
~
Question 32 Following a reactor scrara the pressure in the Scram Discharge Volume (SDV) rises to RPV pressure. Which one of the following describes the most likely reason for this condition? One or more CRDM seals have faile The scram has not been reset, The SDV vent valves have failed close The CRDil flow control valve has failed ope Page 16 of 50
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c


  - -. -... . .. . . . - - - - . . . . - . . . . . .
b. High Differential Current.
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      ~  "J r
          - .
    . SENIOR REACTOR OPERATOR EXAMINATION '


_. Questionf 33i c Which one of the fo.lowing RWM conditions,;f any, will prevent insertion of a selected rod !  !
c. Loss ofIsolated Phase Bus Duct Cooling.
using the Emergency In' switch?
          ,


L Non ;
d. Low Hydrogen Pressure.
2 Select Error.;
_
          .l : Withdraw block.


,
d. ' E - Insert bloc !
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$
          .
I  :
Question 34
.
.
The following' conditions exist:
Question 2 Which one of the following is the reason that the Reactor Mode Switch should be taken out of the RUN position immediately after a Reactor Scram?
L. - The plant is shut down.
a. Enable SRM and IRM rodblocks.


"  1 The 'A' RilR loop is in Shutdown Coolin _
I b. Prevent MSIV isolation.
L. . A LPCI initiation signal on low RPV level occur "
Which one''of the following describes the operator actii.ns, if any, which must be taken i " order for LPCI 'A' to start injecting?
. : None.


. Reset the Group 2 isolation,' manually start the pump and reset the injection valve isolation signa Manually lign the suction path for the' desired pump and reset IS LPCI initiation
c. Enable the SDIV high level bypass circuitry, d. Lower the APRM scram setpoint to 15%.
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signal; -
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Page1of50
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   . Manually align the suction path for the desired pump, manually start the pump,' -
and reset the injection valve isolation signal.


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SENIOR REACTOR OPERATOR EXAMINATION Question 3 A reactor scram has just occurred followed by a Residual Transfer. Which one of the following describes the operators' concerns regarding the MSIVs under these conditions?
,
a. Ensure the MSIVs close to minimize the possibility of Main Turbine overspeed.
  .
m
. -  --  --


__  .. _ .. _ _  _ _ _ . _ . _ . _ _ . . . _ . _ . _ . _ _ . _ _ . . . _ _ . _ _ . _ .
b. Ensure the MSIVs close to minimize the possibility of Turbine Building contamination.
              :
i i
    - ' SENIOR REACTOR OPERATOR EXAMINATION      !
t
              -!
I Question 35 n            ;
              !
The following sequence of events has occurre . A LOCA has occurred resulting in LPCI injectio . - OfTsite power is then los .
              :
  . EDGs 'B', 'C', & 'D' start and load normall j
  . EDG 'A' falls to star ,
              ,
              !
              !
Under these conditions wh':ch of the following RilR pumps will be running two minutes after the loss of power? -          ,
i              ;
.L , All four          <
jl
  ; b. . ~ 'B' 'C' & 'D'
    , ,          [
              > 'A', 'C', & 'D' - -
              .
' 'B'A'D'          t
              ,
i
              :
              .
              :
Question 36
;
The follow events occuri
  . A low RPV level causes llPCI to start and injec . ;lPCI is the only available injection syste . RPV level starts to increas ;
;  . The liPCI Aux. Oil Pump breaker trips,        j
              ,
  - Assuming no operator action, which one of the following describes the expected response o l'
,,  lil'Cl?    . , _ , , , -
      .
- IIPCI will trip when the Aux. Oil Pump breaker trips and can not restar " b. . IIPCI will trip on ll!gh Level and can not restart. -
_
  - IIPCI will trip on liigh Level and can restart on low level,
,
E IIPCI will continue running until manually tripped.'      ,
.
i'


              +
c. Ensure the MSIVs remain open to minimize Toms heat laad.
  ,
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    .
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, e --E - -hy. . ---e .E mh , , h[ :. %,- .-s, .--6-4.,,+.p--nviu-e-v .,-+--, ,..qm ..w,%,,, , v.,.,w,r.,we-.-, ,,._w. . , , ,.~,,,,r.m---eve,.-e-ye,--w,y,-mmw+


i SENIOR REACTOR OPERATOR EXAMINATION Question 37 The following events have occurred:
d. Ensure the MSIVs remain open to maintain availability of Turbine Sealing steam.
. A LOCA has occurre . The Core Spray pumps auto started on low leve . RPV level subsequently recovered to 180 inche . 'the operators took both Core Spray Pump switches to STO . Drywell pressur:is 2.3 psi Which one of the following describes the expected response of the Core Spray pumps to ,
these events? After auto starting they remain on until the initiation logie is tex They stop when switched to STOP but restart if Drywc!! pressure increases above their auto start setpoin They stop when switched to STOP but restart iflevel decreases below tl.eir auto-start setpoldt, They stop when switched to STOP and remain off.


Question 38 Which one of the following describes the effect of a loss of 600 VAC power on the Core Spray system? Core Spray pumps will not auto start when required. They can be started manually, Core Spray pumps cannot be started either automatically or manually,
Question 4 Following an automatic HPCI initiation, the operators note that HPCI trips and then later restarts with no operator action. Which one of the following was the cause of the trip?
      ' Core Spray pumps will start nonnally but their discharge valves will not 'open automaticall Core Spray pumps will start nonnally but will trip on low P.o Page 19 of 50
a. High turbine exhaust diaphragm pressure.
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SENIOR REACTOR OPERATOR INAMINATION
b. High steam flow rate.
      .
Question 39 1he operator takes the SLC keylock switch to START SYS A. Pump 'A' receives a start signal but fails to start due to mechanical binding ofits W.aw contactor. Which one of the following describes the expected response of the Squib Valves and RWCU system isolation valves to these events? Neither Squib valve will fire; RWCU wi." not isolat Only the 'N Squib valve will fire; RWCU will isolate, Both Squib valves will fire: RWCU will isolate, Iloth Squib valves will fire; RWCU will not isolat Question 40 Following a Residual Transfer and prior to the operator taking any actions, which one of the following describes the ability to start the SLC pumps and fire the squib valves? The pumps can be started and the squib valves will fire, The pumps cannot be started and the squib valves will fir The pumps can be started and the squib valves will not fir The pumps cannot be started and the squib valves will not fir Page 20 of 50
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  ._ .. _ _ __
c. High RPV level.
    ,
SENIOR REACTOR OPl!RATOR EXAhilNATION Question 41 l
The plant is operating at 100% power when a Generator Load Reject occurs. Which one of the following describes the RPS input that generates the first expected scram signal? l liigh RPV Pressure, Illgh Neutron Flux, Turbine Control Valve Fast Closur Turbine Stop Valve Closure.


-
d. High HPCI area temperature.
Question 42 The reactor is operating at 25% power. Which one of the following describes the response, if any, of RPS if the 'A' inboard and 'D' outboard htSIVs are closed? Full Scra Italf Scram in Channel 'A'. Italf Scram in Channel'I No elTec Page 21 of 50
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_ _ _ _ _ _ _ _ - _ - _ - _ _ _ _ _ _ _ _ _ _ _ -
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SENIOR REACTOR OPERATOR EXAhilNATION
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        :
SENIOR REACTOR OPERATOR EXAMINATION
Question 43
        ,i
      '
A normal plant startup is in progress and the following conditions exist:  l
. The Reactor hiode Switch is in STARTU '
. All the IRhi range switches are on RANGE .


. No IRhts are bypasse (AV Which one of the following describes the effect on half scrams or rod blocks, if any, that will occur if the IRh1 W hiode Switch is placed in the STANDilY position? None, as long as its companion APRh1 is not downscal Rod Withdrawal Block onl RPS Italf Scram onl Rod Withdrawal Block and RPS llalf Scra Question 44 The following conditions exist:
Question 5 A power ascene on is in progress with the follow.!ng conditions:
  . All IRhi Range switches are on RANGE . The SRhl detectors are partially withdraw . SRhi'A' reads 80 cp Which one of the ibliowing dascribes the ability to witlidraw SRh1 'A' and the status of rod blocks? The detector can be further withdrawn and a rod block exist The detector can be further withdrawn and no rod block exists, The detector cannot be further withdrawn and a rod block exists, The detector cannot be further withdrawn and no rod block exist Page 22 of 50
  . Power le el is 70%.
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. Load lir.e is 100%.
. Two Feedwater pumps are operating.


_  - _ _  ._. _ - _ _ _ . _
Which one of the following describes when and how the Recire. Pumps will runback if one Feed Pump trips?
_
a. Immediately runback to minimum speed.
SENIOR REACTOR OPERATOR EXAMINAT10N
 
,
b. When RPV level lowers to 1%.5 inches; runback to minimum speed.
Question 45 A Recirculation Flow Summer fails resulting in zero output. Which one of the following is the highest power level at which the APRM will generate a rod block but not a scram signal? % %      ,
 
t % %
c. Immediately runback to 44% speed.
Question 46 Assuming no change in vessel inventory, starting the Recire pumps will affect Fuel Zone and Wide Range RPV level indication in which one of the following ways? Fuel Zone rises; Wide Range rises, Fuel Zone rises; Wide Range lower Fuel Zone lowers; Wide Range rise Fuel Zone lowers: Wide Range lower Page 23 of 50
 
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d. When RPV level lowers to 196.5 inches; runback to 44% speed.
- . - . . --    - . . .- - - _
        . - . - -.


      )
Question 6
i i
I SENIOR REACTOR OPERATOlt EXAhilNATION Question 47      j
      !
RCIC is in operation due to a small LOCA. Which one of the folloi , describes the expected position of the RCIC Turbine Govemor Valve (13110V 2): . De RCIC Turbine Steam Inlet Isolation Valve (13h10V 131)if RPV level rises to 222.5 h.. . s7
      .
       .
       .
l Turbine Governor Valve open; Turbine Steam Inlet Isolation Valve closed, Turbine Governor Valve closed; Turbine Steam Inlet Isolation Valve ope Turbine Governor Vahe open; Turbine Steam inlet isolation Valve ekwed ope Turbine Governor Vi;lve closed; Turbine Steam inlet isolation Valve close Question 48 1he following events have occurred:
The following conditions exist:
  . An Automatic Depressurization System (ADS) initiation has occurre . The initiation signals are still presen . A blowdown is ir. progres Taking the ADS Nonnal/ Override switches to OVERRIDE and back to NORh1AL will have which one of the following effects on the ADS Valves 7 ADS Valves will close and remain closed, ADS Valves will close then reopen immediately, ADS Valves will close then reopen aller 120 second ADS Valves will remain ope Page 24 of 50
  . A Group 11 isolation has occurred due to high Daywell pressure.
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t
. Present Drywell pressure is 5 psig.


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. The EMERG OVERR DRYWELL HI PRESS keylock switch on the PCP panel has been taken to its OVERRIDE position.
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SENIOR REACTOR OPERATOR EXAMINATION l
                ,
l Question 4 i The following conditions exist:            f
  . Drywell pressure has risen from 1.8 to 2.5 psi j
  * Torus pressure has risen from 0 to 2.5 psi !
'
These conditions are symptonatic of which one of the following?
' SRV cycled to control pressure and an SRV tailpiece failure inside the Toru [
l Small break LOCA in the Drywell and a Downcomer failure inside the Toru ,
., Small break LOCA in the Drywell and a Torus to Drywell vacuum breaker failed
'
to ope ;
; SRV cycled to control pressure and an SRV tallpiece vacuum breaker stuck ope '


r
. No other operator actions have been taken.
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i Question 50              ,
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With the Mode Switch in STARTUP, which one of the following conditions will result in the        >
automatic closure of the MSIVs? RPV Level is 50 inche Steam'' , pressure is 750 psi . Main Condenser Vacuum is 10 inches li ;
di  Turbine Stop valves not fully close .
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'i--- gi f tve,=u r'ei-,y pw 1(eTw9.-y- e yru-W--g--w n gg zvev-_ry-grw-- s .--wwee nygmg-afw v+ m---m4mw w m e'9av mw r-w snwe ,e-- t- ,w.sw ew-e-mm - w wer ewe e-e re m -w


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Which one of the following describes the CAD isolation valves that can be opened at this -
SENIOR REACTOR OPERATOR EXAhilNA'llON Question $1 The plant is in shutdown cooling when a relay failure results in a spurious ADS logic Channel 'A' low low low level signal. No other level trips have occurred. Which one of the I
time?
following describes the effect that this event will have on ADS? ADS will initiat ADS will not initiate because the RilR or Core Spray pump running interlock is bypassed in shutdown coolin ADS will not initiate because both channels are needed for ADS initiatio ADS will not initiate because there is no low level trip.
a. All CAD isolation valves.


Question 52 RFP 'A' hasjust tripped on high reactor vessel level. Which one of the following conditions must be satisfied before the RFP 'A' hydraulic coupling automatically disengages? IIP and 1.P stop valves close RFP turbine tripped signal sense Turbine speed less than 4 RPh htGU and htSC on low speed stop Page 26 of 50
b. All CAD isolation valves exupt 27AOV-111 through 118 (CAD vent valves).
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c. All CAD isolation valves except 27MOV-113,117,122,123 (CAD purge valves).
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I SENIOR REACT 0F, OPERATOR EXAMINATION  I Question 53 The following events occu . The plant is operating at full power with the MGUs and Master Controller balanced.-
. The Master Controller outpi.t slowly falls downscal . RPV level lowers to 185 Ir.ches at which point the operator takes both MOUs to manua !
. No further operator actior, is take Which one of the followinr, describes the response of feed flow and RPV level aner the ;
MGUs have been shined to manual?    l Flow will increase to 100%; Levcl will increase to 200 inche Flow will increase to 100%; Level will remain at 185 inche , Flow will increase to greater than 100%; Level will increase to 200 inche Flow will remain less than 100%; Level will continue to trend down.


Question -54 The SBGT system has failed to auto start in response to a IIPCI start signal Which one of the following will occur as a result of the failure of SBGT to start?
d. All CAD isolation valves except 27AOV 131 A/B,132A/B (CAD make-up valves).
a, llPCI start up sequence will not complete and the llPCI turbine will not start, The llPCI turbine will start but may trip on liigh Exhaust Pressure,
      ' The llPCI turbine will start but may trip on liigh IIPCI Area Temperatur IIPCI flow rate will be limited due to decreased condenser eflicienc l l
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Question 55 Which one of the following is the reason that operation of an EDG at loads near 2000 KW is to be avoided? Excessive wear on turbocharger drive gears, Main bearing degradation due to inadequate lube oil coolin Potential Lube oil sump fire due to increased piston blow b Overheating of exhaust syste f'
Question 56 Following a LOCA with concurrent Loss of OfTsite Power, which one of the following will be the first to be reenergized when the 'A' and 'C' EDO breakers close? 'A' ESW Pum 'A' RilR Pum 'C' RilR Pum 'A' Core Spray Pum Page 28 of 50
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SENIOR REACTOR OPERATOR EXAMINATION Question 57 The operator withdraws a control rod one notch but the rod position indications show that the rod is withdrawing continuously until it reaches full out position. Which one of the following : ,uld be the cause of this? Stuck collet piston, liigh CRDil pressur Uncoupled ro Leaking IICU Scram inlet valve (03AOV-126).
SENIOR REACTOR OPERATOR EXAMINATION   -
Question 7 The plant is operating at full power when the following occur:
. Generated MWe starts to decrease.
 
. Reactor power starts to decrease.


.
Which one of the following could have caused these symptoms?
Question 58 Reactor power is 5%. The RWM is fully operational and has generated a Withdraw Bloc Under these conditions, which one of the following is the maximum number of rods with insert errors that could possibly be moved in the withdraw direction? Non On Two, d, Thre Page 29 of 50
a. Decrease in grid frequency.
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SENIOR REACTOR OPERATOR EXAMINATION Question 59 The plant is operating at full power when the following Recire. Pump Seal readings are noted:
b. Jet Pump malfunction.
. #1 (inner) Seal Cavity pressure is 1000 psi . #2 (outer) Seal Cavity pressure is 150 psi Which one of the following will cause these conditions? Normal operation of both seal Failure of both seal Partial failure of the #1 sea Partial failure of the #2 seal.


Question 60 During tha startup of the 'A' Recire. Pump the following conditions exist:
c. Loss of feedwater heating.
. The 'A' Recire. Pump Discharge valve is 85% ope . The 'II' Recire. Pump Discharge valve is fully ope . Total Feed Flow is 30%.
. Feedwater Pump 'A' is running; Feedwater Pump 'I3' is secure . RPV level is 195 inche Which one of the following describes the most restrictive Recire. Pump speed limitt.tions currentiy in efTect? Iloth pumps are limited to 30%. Iloth pumps are limited to 44%. Pump 'A' is limited to 30%; '13' is not limite ' Pump 'A' is limited to 30%; '13' is limited to 44%.
Page 30 of 50
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d. Inadvertent SRV opening.
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SENIOR REACTOR OPERATOR EXAhilNATION Question 61 The drive mechanism of a fully withdrawn control rod is uncoupled. Which one of the  .
following indications during the coupling check indicates that the rod is uncoupled?  l
      . Individual Rod Drill Alar Individual Rod Ovenravel Alarm, '49' will be displayed in the rod position windo Individual Rod Full Out light remains energized.


Question 62 Three of the eight 1.PRhi detectors supplying an RBhi channel have failed downscal Which one of the following describes the response, if any, of the RBhi to these failures? There will be no functional efTect since the RBht still has sufficient 1.PRh1 inputs to function, The rod block setpoint will be automatically adjusted downward to compensate for the lost inputs, An inop. Rod Block will be generated until one detector is bypasse A Rod Block will be generated until the PUSil TO SETUP pushbutton has been depresse Page 31 of 50
Question 8 With a high Drywell pressure, Emergency RPV Depressurization is required if Torus Water Level cannot be maintained below PSP (Pressure Suppression Pressure). Which one of the following is the basis for performing an Emergency RPV Depressurization if the Pressure Suppression Pressure Limit is exceeded?
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a. To ensure that the vacuum breakers will not become submerged and fail to function.


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b. To ensure adequate free volume (airspace) of the Torus for steam suppression, c. To prevent damaging the Torus.
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SENIOR REACTOR OPERATOR EXAhilNATION i
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Question 63      l Which one of the following describes the e&ct of spraying the Drywell during a LOCA
      '
when Drywell pressure is below 2.7 prig? Unnecessary damage to equipment in the Drywell, Pvtial de inerting of the Primary Containment,  ; Inability to vent the Primary Containmen hiechanical 4 'ure of the Torus to Drywell vacuum breaker i Question 64 The operators are unatle to reset an inadvertent Group 1 isolation signal. Which one of the following conditions, ifit existed, would cause this problem?  , A control switch for one of the htSIVs is in the OPEN positio The Reactor hiode Switch is in RU The control switches for the hiain Steam Line Drain valves are in the OPEN positio The AP across the htSIVs is 125 psi :
Page 32 of 50
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SENIOR REACTOR OPERATOR EXAMINATION
d. To prevent steam from the Drywell bypassing the Suppression Pool.
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Question 65 During plant operation it is noted that 345 kV bus voltage is 380 kV. Which one of the - .;
following is the appropriate response, if any, to this condition?  i i No response require j ' Reduce generator output voltage to restore 345 kV bus voltage to nonna Contact the Load Dispatch Center and request that 345 kV bus voltage be ;
reduce Increar.c Generator Isolated Phase Cooling to maximu ;
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Question 66      l The following sequence of events occurs:
Page 4 of 50
-. 600 VAC power is lost for 3 minute . After 600 VAC power is restored,125 VDC power is briefly los j
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. - 125 VDC power is then restore Afler restoration of 125 VDC power, which one of the following will be the source, if any, of ,
- 120 VAC UPS Instrumer.t Power? Nothing,120 VAC will be deenergize ;
- VAC via the UPS MO Se l
        ! VAC via the 600/120 VAC transfomic l E VDC via the UPS MO Set. -    i a
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SENIOR REACTOR OPERATOR EXAMINATION   ,
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SENIOR REACTOR OPERATOR EXAMINATION Question 9 l
Question 67      i i
Which one of the following would give positive indication that SRV 'C' is open when its control switch is taken to OPEN?   .
Loss of all 12$ VDC power would have which one of the following effects on the Emergency Diesel Generators?
a. SRV red light is on, b. SRV white light is on.
      '
t Diesels would auto start and load,
, Diesels would auto start, but would not auto loa Diesels would not start and could not be started at the Engine Control Panel, Diesels would not auto start but could be started at the Engine Control Pane Question 68 Which one of the following describes the efret of the Control Room Inlet Radiation Monitor channel failing upscale? Alann onl , The intake and Exhaust dampers close and the Recire, damper open The Control Room Supply fans trip and the Exhaust Damper closes, The Emergency Supply fan starts and the inlet filter system is placed in servic Page 34 of 50
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I SRV tailpiece temperature rises and stabilizes at 285 *F.
SENIOR RItACTOR OPERATOR EXAMINATION Question 69 Which one of the following describes a potential path for radioactive contamination to tir discharge canal during nonnal power operation?
l
      ' Drywell Air Cooler tube lea RilCl,C lleat Exchanger tube leak.


, Recombiner condenser tube leak, Main Condenser tube lea Question 70 Which one of the following describes the response of any TIP ictector not in its shield when a Group I and Group 11 Containment isoletion Signal occurs? A Group I isolation will cause the TIP to withdraw to the Lead Shield position. A Group 11 has no further efTect, A Group i isolation will cause the TIP to withdraw to the Lead Shield position. A Group 11 will activate the shear valve if the TIP is still inserted, A Group I Isolation will have no effect. A Group 11 Isolation will actuate the
c.
,
shear valve if the TIP is not withdrawn within 10 minute A Group 1 Isolation will have no clTect. A Group 11 Isolation will cause the TIP to be withdrawn to the Lead Shield positio Page 35 of 50
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1        I Question 71      !
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The crew is conducting EOP 5 (Secondary Containment Control) when Reactor Building  [
ventilation isolates on high radiation. The radiation level is subsequently seen to decrease  !
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below the isolation setpoint. Which one of the follrwing describes under what condition, if
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any, it is perMssible to override the high radiation isolation to restart the Reactor Building i ventilation system?      .
d. EPIC alarm ' SONIC DET RV-C' RESET is received.
t It is not pennissible.


; Two Reactor 11uilding area temperatures are above maximum norma After it is confinned that no primary system is discharging into the Reactor  (
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Building,      j i If Reactor llulldirg AP cannot be maintained at a negative pressure with SBO l
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1-Question 10
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The following conditions exist:
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Question 72 While conducting EOP-2 the operators discover that a required action cannot be  ;
. A plant transient raised RPV pressure to 1150 psig.
accomplished. Which one of the following is the appropriate response to thie event?  i Continue to the next step irrespective of the type of step it wa , Wait until the step can be accomplished before continuin Continue to the next step only ifit was a concurrent action ste I The decision to continue or wait is only at the discretion of the S !
 
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. The SRVs have opened.
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;    SENIOR REACTOR OPERATOR EXAMINATION      l
. RPV levelis 150 inches.
, Question 73 The reactor is operating at full power wtan the following events occur:      i
            '
e The Turbine Control Valves close.


[  $ Tne Turbine Bypass Valves fully ope . The Reactor Scrams,         i
Assuming no operator action, which one of the following describes when the SRVs are expected to close?
            '
  . The SRVs open briefl l Whkh one of the following could have caused this chain of events?     !
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, Tusbine Load Reference signal has failed downscal The MSIVs have closed.
a. Before RPV pressure decreases below approximately 1050 psig.


,-  - The luckup (B) Pressure Regulator has failed low,      [
b. 120 seconds after the initial transient.
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            ' The Maximum Combined Flcw Limiter has failed downscal :
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c. After RPV pressure decreases below approximately 50 psig. j d. When both RHR and Core Spray pumps are secured. l l
t Question 74 The reactor has recently scrammed and the MSIVs are closed, llPCI is maintaining RPV
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level and pressure. Torus Cooling is not available and Primary Containment Pressure is rising. Which one of the following describes the appropriate considerations if Primary Containment venting becomes necessary?        ! Venting via the Torus will not keep up with decay heat production but will    x minimize the rate of radioactivity release,
Page 5 of 50
, Venting via the Torus will keep up with decay heat production and will minimize the rate of radioactivity release, Venting via the Drywell will not keep up with decay heat but will minimize the
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rate of radioactivity release, d- Venting via the Drywell will keep up with decay heat production and will
  - minimize the rate of radioactivity release.-
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9- y --y 'y--,e-- - <vw- y y 9awy-fer' '***d'' CWfv F'''Wwrdr 'w'''vervP9""TrvW r -~~T-- -+w-'--- + =-?-7- ve 3- + -
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e'T*'-
r * 7


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SENIOR REACTOR OPERATOR EXAMINATION Question 11 A reactor scram occurred but many control rods failed to insert due to a high water level in the Scram Discharge Volume. The APRMs read 9 %. Which one of the following actiuns will be most effective in inserting control rods?
I SENIOR REACTOR OPERATOR EXAMINATION       l
a. Manually initiate ARI.
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Question 75
,
A scram has occurred due to a transient resulting from a loss of UPS. Not all rods have fully      ;
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inserted. Which one of the following should be used to evaluate reactor power to detennine if entry into EOP 2 (RPV Control) is required?
i            : APRM chart recorder [ SPDS displa ,
i Steam Flo ;
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I Number ofopen SRV l
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j Question 76 t
!  The following conditions exist:          ,
'
  . A LOCA has occurre !
  . The 'A' RilR is the only low pressure ECCS pump available and is injecting in LPCI      ;
mod ,
  . RPV level -90 inches and is trending down slowl . Drywell temperature is 350 'F
  . Drywell pressure is 65 psi . Torus pressure is 64 psi . Torus level is 21 fee ;
Which one the following describes the correct decision regarding Drywell and Torus spray?
            . Spray the Drywell. Do not the spray Torus, t
' Do not the spray Drywell. Spray the Toru e,  Spray the Drywi;11. Spray the Torus, Do not spray the Drywell. Do not spray the Torus, i
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SIINIOR REACTOR OPERATOR EXAhilNATION Question 77 A plant transient has caused a reactor scram followed by a prolonged SRV actuation. Current conditions are:
b. De-energize scram solenoids.
* All control rods are : ally inserte * Reactor pressure 900 psig and risin * All SRVs are close * Torus temperature is 160 * * lorus level is 11 fee Under these conditions, RPV pressure must be reduced to no more than which one of the following? psi , psi psig, psig.


Question 78 A 1.OCA has occurred and the following conditions exist:
c. Manually insert control rods.
. Drywell 112 concentration is 7%.
. Torus 11, concentration is 4%.
. Drywell 0; concentration is 4%.
* Torus 0, concentration is 6%.
Which one of the following describes the Torus and Drywell flammability limits? Iloth the Torus and the Drywell are below the flammable limit, The Torus is above the flammable limit and the Drywell is below the flammable limi The Drywell is above the flammable limit and the Torus is below the flammable limi Iloth the Torus and the Drywell are above the flammable limi Page 39 of 50
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d. Close the CRD Flow Control valve.
SENIOR REACTOR OPERATOR EXAhilNATION Question 79 A large LOCA has occurred and the following conditions exist:
 
* RPV pressure is 50 psi Drywell temperature is 350 'F,
Question 12 Following the trip of one Recire. Pump with the reactor at power, the operators have closed the discharge valve of the tripped pump. Which one of the following is the reason that this is done?
. Nanow Range RPV level indicates 175 inche . Refuel Zone level indicates 215 inche . Wide Range RPV level indicates 40 inche Which one of the following is the correct RPV level? inche inches, inche RPV level is unknown.
a. Stops reverse rotation of the tripped pump.


Question 80 The Appendix R llypass Switch for 23MOV 15 (llPCI Inboard Containment Isolation)is in the llYPASS position. Which one of the following describes the effect that this will have on llPCI operation? h10V-15 will not close on low steam pressure, MOV 15 will not operate from panel 09 IIPCI will not trip on high RPV water leve IIPCI will not auto restart on low RPV leve Page 40 of 50
b. Prevents backflow through the idle Jet Pumps.
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SENIOR REACTOR OPERATOR EXAMINATION Question 81 During refueling operations, irradiated components may be lined with an auxiliary hois Which one of the following describes the required method to assure adequate water shielding for personnel involved in this operation? Tape markers on the hoist cable to inform the operator when to stop linin A jamming device on the cable to prevent hoist movement above the safe level, A Reactor Engineer must participate in all such operation A second SRO must be present on the Refueling Drldge.
c. Prevents runout of the operating Recire. Pump.


Question 82 EOP 5 (Secondary Containment Control), has been entered due to high area temperature Other Secondary Containment parameters also have been increasing. No primary system is currently discharging into the Secondary Containment. Which one of the following combinations of area temperatures and radiation levels require a reactor shutdoc.? SLC Pump Area - 140 *F and RWCU llX room radiation level of 1600 mIW RWCU Pump Area radiation level of 800 mlWr and RWCU llX Roem radiation level of 1200 mR/h RWCU llX Room temperature of 205 'F and RCIC Room Temperature is 120 ' IIPCI Room temperature of 150 'F and RCIC Room temperature of 150 ' Page 41 of 50
d. Lowers the probability of entering the instability region of the power / flow map.
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SENIOR REACTOR OPERATOR EXAMINATION i
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Question 83        ;
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i During normal plant operation, the SNO is injured and contaminated. The only on shin  .
SENIOR REACTOR OPERATOR EXAMINATION Question 13 -
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The following conditions exist:
Radiation technician and the SNO both leave site in the ambulance. The CRS is not qualified as fire brigade leader, Which one of the following describes the allowable times to restore  ;
* Condenser vacuum is 25.1 inches Hg.
the full shift complement? SNO within two hours; Rad Tech by end of shl j
          ' SNO within two hours; Rad Tech within two hour * SNO by end of shin; Rad Tech within two hour . SNO by end of shift; Rad Tech by end of shif L
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Question 84        4 You are the SM and it is brought to your attention that present thermal power is 2560 MWt ,
Which one of the following actions, if any, is required as a result of this situation? No action required, this is within tolerance for full powe Adjust power if necessary to assure that the 8 hour average is 2536 MWth or les Immediately reduce power to 2536 MWth or less and assure that the 8 hour average is 2536 MWth or les . Commence a plant shutdown and issue a verbal report to the NRC within I hour of the discovery of the situatio l t
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SENIOR REACTOR OPERATOR EXAMINATION Question 85 Reactor power level is 6% and personnel are in the Drywell. Which one of the following describes the current restrictions on control rod motion? No rod motion is permitted until personnel are clear of the Drywel b No planned rod motion la permitted but rods may be inserted as needed to terminate unplanned events.


, There are no restrictions on rod insertion. Withdrawal is prohibite There are no restrictions on rod motion as long as personnel are not working above elevation 292 fl. in the Drywel Question 86 The plant is at full power when Chemistry reports the following SLC parameters:
* Turbine load is 170 MWe.
. Weight % Sodium Pentaborate is l'' *%.
. Net Volume of Solution is 2500 g . Solution temperature is 60 ' Which one of the following changes will bring the St.C system into compliance with Tech Specs? Increase solution temperature to 70 ' Raise the Weight % to 11.2%. Raise the Weight % to 11.2% and the Net Volume to 2550 gallon Raise the Net Volume to 3000 gallon Page 43 of 50
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* AOP-31 (Loss of Condenser Vacuum) has been entered.'
SENIOR REACTOR OPERATOR EXAMINATION Question 87 3 is day 90 of a continuous full power run when Chemistry reports that the following sample readings have been verified:
Which one of the following actions, by itself, will make it MORE LIKELY that a manual Turbine Trip will be required?
. Conductivity is I pmh . Chloride ion is 0.4 pp Which one of the following actions, if any, is required by Tech Specs? Readings are within specifications, power operation may continu Reduce steam flow to less than 100,000 lb/hr. within 24 hour lle in the cold condition within 24 hours after reaching a steam flow rate of 100,000 lb/h Be in the cold condition within 24 hour Question 88
a. Starting the Mechanical Vacuum pumps.
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A temporary change to a procedure has been approved by an SRO and implemented. Afler the changed procedure had been used, the RPO (Responsible Procedere Owner) disapproved the change. Which one of the ibilowing describes the need for a Deviation and Event Report (DER) and whether the change must be withdrawn? DER is requited; PORC decides if the change must be withdrawn, DER is required; the change must be withdraw DER is not required; PORC decides if the change must be withdraw DER is not required; the change must be withdraw Page 44 cf 50
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b. Increase load to 255 MWe.


SENIOR REACTOR OPERATOR !!XAMINATION Question 89 IJse of a Temporary Mod is prohibited for which one of the following applications? To correct a design deficiency while a permanent solution is pendin . Allow testing of plant equipmen To temporarily compensate for a procedural deficienc To allow continued operation of essential equipmen Question 90 Today is November 3 and the time is 0800. 'A' RilR is inoperable for a planned LCO that began on November 1 at 0800. It is determined that the work cannot be completed before November 12. Which one of the following describes the actions that are required for this condition?
c. Decrease load to 85 MWe.
Place the plant in the cold condition no later than 0800 on: November November Novembe: November 1 Page 45 of 50
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d. Placing the spare Air Ejector sets in service.
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  [ SENIOR REACTOR OPERATOR EXAMINATION!
fQuestion 91i
- During an outage the plant is in Risk Condition Green. Work is planned which will result in -
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; a degradation to Risk Condition Yellow. In addition to the Shift Manager which one of the
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. following lists all of the approvals required, if any, before this work can start? No additional approval .
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[  >b? General Manager of Op rations and Planning Manage Operations Manager and General Manager of Maintenanc ,
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:  ' Operations Manger and Planning Manage ;
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- Question 92?        ;
You are the Core Alteration SRO during fuel offload. An irradiated fuel bundle is being transferred to the Spent Fuel pool when you are required to leave the Reactor Building for a  >
, random drug test. Tht. anly other SRO on shift is the SM. Which cne of the following actions is permitted under these conditions? The bridge operator may complete the move but may not pick up another bundle until your retu b.' As long as an RO is stationed in the control room, the SM may temporarily  .
assume your functio ' If qualified, you may turnover and exchange shift positions with the SM. Fuel handling ~ operations may continue, The NYPA Refuel Floor Supenisor may assume your duties. Fuel handling operations may continuei Page 46 of 50
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Ques' ion 14 With the plant shutdown, an Emergency Diesel Generator is running and is tied to its bus for load testing. Which one of the following describes the response to a complete loss of offsite power?
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a. The Tie Breakers will trip and the diesel will maintain the bus loads. 1 b, The Diesel Output breaker will trip and the diesel will switch to isochronous ,
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mode, then the Diesel Output breaker recloses.
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    - SENIOR REACTOR OPERATOR EXAMINATION '     ;
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Which one of the following meets ALARA for performing ajob? 2
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  - 1 man accomplishing the job in I hour in a 60 mR/hr field, .
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a.' man installing shielding for 30 minutes in a 60 mR/hr field and then    -
  . accomplishing thejob in I hour in a 6 mR/hr fiel _3 men accomplish!ng the job in 25 minutes in a 60 mR/hr fiel men installing shielding for 15 minutes in a 60 mR/hr field and then-accomplishing thejob in 25 minutes in a 6 mR/hr fiel >
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$  - . Question 94
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Which one of the following describes the JAF administrative limit for thS maximum TEDE k  .-which a radiation worker may accumulate in one year with the maximum dose extensions approved?
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a.- 2 Re Re ..
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c. ~ 4 Rem.


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c. The Diesel Output breaker will trip and the diesel will switch to droop mode, then the Diesel Output breaker recloses.


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d. The Tie breakers and the diesel will trip.
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-h W  b y e ' ' 4 m1 e e 3 +1~e --W w-p 4 r r cf q y-p r m yyw r ,i ) y y


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  ~ SENIOR REACTOR OPERATOR EXAMINATION '    ,
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- Questio'n 95 Routine makeup nitrogen supplied to the Drywell to maintain an inerted state should be :
supplied by which one of the following train configurations?. Train .'A' is preferre b.' Train 'B' is preferre ;
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e' LTrains 'A' & 'B'should be alternated for each makeup operatio' ~ Trains 'A' & 'B'should be operated while cross-connecte !
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- Question 96 -
You are the Shill Manager / Emergency Director and'the following conditions exist:
A non isolable steam leak is discharging into the Turbine Building. A ground-level release is  ,
in progress. Radiological hazards exist outside the plant, A Site Area Emergency has been declared. You have decided to evacuate the site.
 
, - Which one of the following describes where you will send non-essential personnel? Nine Mile Training Center,
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          ' State Fairground : c, Emergency Operating Facilit ; d.- Niagara Mohawk Service Center, i _  _
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SENIOR IGACTOR OPERATOR EXAMINATION Question 97 Foam must not be used for fighting fires in the vicinity of new fuel for which one of the following reasons 7 Voiding of fuel warrant Conosive effect on claddin Danger of criticalit Fouling of heat transfer surface Question 98 An Unusual Event has been declared. Which one of the following describes the time limits 3 for notifying off site agencies?
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SENIOR REACTOR OPERATOR EXAMINATION   -
~- USNRC within 15 minutes, state and county within I hou USNRC within 15 minutes, state and county within 15 minute USNRC within I hour, state and county within 15 minutes, USNRC within I hour, state and county within I hour.
Question 15 Bus 10400 is powered by the Main Generator via breaker 10402. Which one of the following ways of opening this breaker will not allow closing the Station Reserve breaker 104127 a. Manually opened locally.


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b. Manually opened from the control room.
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c. Automatically opened on overcurrent.
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    ' SENIOR REACTOR OPERATOR EXAMINATION '    ;
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1 uestion"99 I-      _
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d. Automatically opened on undervoltage.
  ~ The following conditions exist: -
J. = !An ATWS is in progress.. ._    .
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  . 1 1The operators have reduced RPV level to -10 inches in accordance with EP 5 -  1 L(Termination and Prevention of RPV injection)?
  . SLC is injecting.-      1 e L Reactor power is 1%
  . : - Torus temperature is 157 ' !
  .Which one of the following Emergency Plan EALs must be declared and which evacuation  .
_ must be performed?      -
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  ; Site Area Emergency; Radiologically Controlled Area Evacuatio .
s b.- : General Emergency; Radiologically Controlled Area Evacuatio ' . Site Area Emergency; Protected Area Evacuatio General Emergency; Protected Area Evacuation.-
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  ' Question 100L
Question 16 Which one of the following describes the loads in the 24 VDC Power System?
  * EOP-4, ' Primary Containment Control,' Torus Level Control leg, directs the operator to
a. Each load breaker is connected to 48 VDC potential (input) from its associated 124 VDC charger.
  ' Terminate and prevent IIPCI operation irrespective of whether adequate core cooling is e.ssured' ifTorus level cannot be maintained above 10.75 fee Which of the following describes the effect of continued operation of the llPCI system?
. Continued operation will: = damage the HPCI turbine by' supplying high temperature cooling water to the oil system.


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b. Half the loads on a124 VDC distribution bus are powered from +24 VDC. The other half are powered from -24 VDC.
  ; reduce Torus water level below the safety relief valve T-quenchers.


. ic, result in a direct discharge of steam into the Torus air spac g
c. Each load breaker is connected to 24 VDC potential (input; from its associated 12 VDC charger.
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7d.' result in a loss of the last high pressure injection system on high exhaust -
i    backpressure.
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d. Half the loads on a 148 VDC distribution bus are powered from +48 VDC. The other half are powered from -48 VDC.
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LOSS OF SHUTDOWN COOLING *    AOP-30 ATTACHMENT 2 Page 1 of 1
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SENIOR REACTOR OPERATOR EXAMINATION Question 17 The following Narrow Range RPV level conditions exist:
* 'A' indicates 215 inches and is rising slowly.   .
  * 'B' indicates 185 inches and is lowering slowly.


CORE DECAY HEAT VS. TIME AFTER SHUTDOWN
e 'C' indicates 214 inches and is rising slowly.
., Days after BTU /hr Days after  BTU /hr shutdown  shutdown 0 6.28E8  21  1.48E7 1 4.79E7 l 22  1.44E7 2 3.92E7 l 23  1.42E7 3 3.36E7 l 21  1.39E7 4 2.97E7 l 25  1.36E7 5 2.69E7 l 26  1.33E7
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6 2.48E7 l 27  1.31E7 7 2.32E7 l 28  1.28E7 8 2.19E7 l 29  1.26E7 9 2.08E7 l 30  1.24E7 10 2.00E7 l 31  1.22E7 11 1.92E7 l 32  1.20E7 12 1.86E7 l 33  1.18E7
.: 13 1.80E7 l 34  1.16E7
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14 1.75E7 l 35  1.14E7 15 1.70E7 l 36  1.12E7 16 1.66E7 l 37  1.10E7 17 1.62E7 l 38  1.09E7 18 1.58E7 l 39  1.07E7 19 1.54E7 l 40  1.06E7 20 1.51E7  730  9.13E5 (
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e Feedwater control is selected to the 'A' Column.
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LOSS OF SHUTDOWN COOLING 0        AOP-30 ATTACHMENT 3      Page 1 of 1 ALTERNATE COOLING METHODS METHOD APPROXIMATE HEAT    LIMITATIONS REMOVAL CAPACITY (BTU /hr)
Decay Heat Removal  3.00E7  * Gates removed between cavity end spent fuel pool Fuel Pool Cooling  3.30E6  * Gates removed between cavity and spent fuel pool e RBC must be available
    * SW must be available
. Fuel Pool Cooling  2.40E7  * RHR must be available Assist
    * RHRSW must be available a Gates removed between cavity and spent fuel pool RWCU Blowdown Mode  2.06E6  * No isolation signal present
* 1 pump running  * Makeup source must be
* 125 gpm blowdown flow    available (see list below)
* 125 gpm makeup flow
    * Main Condenser.or Radwaste must be available RWCU Recirc Mode  1.70E6  No isolation signal present RWCU Blowdown Mode  1.00E6  * No isolation signal present
* gravity drain    * Makeup source must be
* 50 gpm blowdown flow    available (see list below)
* 50 gpm makeup flow
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    * Main Condenser or Radwaste must be available Makeup Source * Condensate transfer keep-full using Core Spray or RHR
* Control Rod Drive System
*
Condensate /Feedwater
* Condensate transfer to skimmer surge tanks (gates removed)
* Condensate transfer to fuel pool using DHR (gates removed)
* Condensate *.ransfer using service box connections on the refuel floor (gates removed)
* Fire Protection System water from local fire hose stations or outside sources
* RHR service water cross-tie
* Fire Water Crosstie Rev. N Page  19 of 19 L    _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - . _ _ _-._________  ______ o


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Selecting the 'B' RPV Level Column will result in which one of the following effects on level trends?
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a. 'A' and 'C' will continue to rise. 'B' will lower.
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FIGURE I CONDENSER VACUUM VS. TURBINE LOAD ca 27. z 26.50 U      NORMAL DPERATING REGION j lllll!!!!!! NIbE  I'n l':
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b l ji llllll
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0 25.50!l!i!yll lll
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    'jIj !)lb i
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  !! l j
25.00 '-
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  "^*  bld hlh5--IlE
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o n-r to m
0R"EEOm
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m cu m n n N
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      ",o to l2 in S $
b. 'A' and 'C' will continue to rise. 'B' will rise.
in e 8 N $ $ 0 $
e i- r- e e e TURBINE LOAD (MWe)
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c. 'A' and 'C' will lower. 'B' will lower.
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SRO ANSWER KEY 1) B - 26)- D  51) D 76) B


2); - B- - 27)T _ B  52) C- . 77) - B --.
' 3) : B _ 28)- A- 53) B- 17_8) . A-
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4) _C . 29) ~C _ 54) .C 79)- D 5)- D 30)- A 55) A _80) A=
6) D - 31) DELETED 56) A 81) .B 17) -
. ) _- B - 57) -- 'A' 82). D
- 8) C- 33) D- -58) D- 83)' _ B
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9) ._- DB 34) lD- 59) D 84) -C 10) -A -
35) C- 60) D 85) -B_ ,
11) ~- - C 36) B 61) - A OR B 86) D 12) - A' - 37)- D 62) A 87) A-13) B- 38) C 63) B 88) -B
?14)- :A  39) C -64) A- 89) C
:;15) -C 40) A 65) C 90) -A
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16) ) ) C 91). ' D
d. 'A' and 'C' will lower. 'B' will rise.
 
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17) -B 42) -D 67) C 92) C 18) 'A L 43) - D_ 68)_ A 93) D 19) B - 44) 9 AL 69) ) _C 20) _B 45) D_ 70) D 95) A 21) D 46) B _ _71) A 96) D-
i Question 18
; 22) D 47) A6 A 72) A 97) C 23) - D- 48) G -A- C 73) A 98) C ,
) In which one of the following ways does a loss of 125 VDC Bus 'A' affect the ADS /SRV system?
a. Loss of'A' logic, ADS remains functional.


24) D 49) B 74) B 99) C 25) -A 50) A 75) B 100) C
b. None of the ADS /SRV valves can be opened.
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c. The ADS /SRV valves cannot be opened from the remote panel.
NEW YORK POWER AUTHORITY    EXAMINATION / QUIZ JAMES A. FITZPATRICK NUCLEAR POWER PLANT  COVER SHEET Examination Title: USNRC REACTOR OPERATOR EXAMINATION Examination Submitte y: i M A {  Date: 11/03/97
' Supervisor Approval:  '
A,5.Moecis- Date: to/ss/97 Authorized Reference . ATTACHED Minimum Acceptable Grade: 80  Total Exam Points: 100 Grade:  Graded By:  Time Limit: 4 hours STUDENT DATA Name:    S.S.#:
Last First  M.I.


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d. Only valves F, J, K & L remain fully functional.
Employer: NEW YORK POWER AUTHORITY  Date:
 
Department:
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GUIDELINES Remain quiet during the exam. If you have any questions during the exam, raise your hand. Your instructor will provide clarification wherever possibl . - You are expected to do your own work and not to help anyone els . Use only the authorized reference material.
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SENIOR REACTOR OPERATOR EXAMINATION Question 19 AOP-43 (Shutdown From Outside the Control Room) requires the operators to remove RHR pumps 'A' and 'C' from service. Which one of the following describes the reason tha this .
step is necessary?
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l a. Prevent water hammer in the event of a LOCA signal.
 
b. Prevent inadvertent Drywell spray.


' At the completion of this examination, you are to sign the following certificatio I certify all answers contained in this examination are my own. In addition, I have not received nor given any unauthorized assistance, nor have used any unauthorized reference Student Signature:    Date:
c. Prevent inadvertent LPCI injection.


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d. Prevent draining the RPV to the Torus.
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Question 20 The following events occur:
REACTOR OPERATOR EXAMINATION
  . The plant is at 20% power.
- Question 1 With the plant operating at 50% power, which one of the following Main Generator faults -
will cause an automatic reactor scram? High Stator Winding Temperatur High Differential Currc
          " Loss ofIsolated Pimse bw elb Low Ilydrogen Pressur Question 2 An instrument failure has resulted in a reactor scram from 20% power. The following conditions exist:
  . Minimum RPV level reached was 195 inche . Maximum RPV pressure reached was 1005 psi . Drywell pressure is 0 psi . All APRMs are downscal . Two control rods have failed to inser Under these conditions, the control rods will be inserted in accordance with which one of the following procedures? AOP-Oi (Reactor Scram).


. .EOP-02 (RPV Control). EOP-03 (Failure to Scram). EP-3 (Backup Control Rod Insertion).
. High radiation in the Off Gas system starts the Off Gas Timer.


Page 1 of 50
. No operator action is taken.
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; Which one of the following will be the most likely cause of an automatic reactor scram?
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l a. High Reactor Power.
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REACTOR OPERATOR EXAMINATION
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QuestionL 35
b. Low RPV Level.
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Which one f the following is the reason that the Reactor Mode Switch should bs taken out;  l
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  . : of the RUN position immediately after a Reactor Scram?    --
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L ; Enable SRM and IRM rodblocks.'  -
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  " b., Prevent MSIV isolatio c;
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  : Enable the SDIV high level bypass circuitr '
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  ~ ~ d. ' Lower the APRM scram setooint to 15%.
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  - Question 4
  : A reactor scram hasjust occurred followed by a Residual Transfer. Which one of the following describes the operators' concerns regarding the MSIVs under these conditions? Ensure the MSIVs close to minimize the possibility of' ~ '- Turbine overspeed.- Ensure the MSIVs close to minimize the possibility of Turbine Building
    - contaminatio .,
  - Ensure the MSIVs remain open to minimize Torus heat loa : Ensure the MSIVs remain open to maintain availability of Turbine Scaling stea _
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c. MSIV closure.
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      ._  g IA power ascension is in progress with the following conditions:
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s ei Powerlevelis 70%; ^
U.-- t Load line is 100%.
w  L.) TTwo Feedwater pumps are operatin %
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t Which one of the following describes when and how the Recirc. Pumps will runback if one
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  - Feed Pump trips??
n.- 'Immediately runback to minimum spee ~
    ' b~. : ! When RPV level lowers to 196.5 inches, rur.back to' minimum speedt
    ~ c/- Immediately runback to 44% spee Whch RPV level lowers to 196.5 inches, runback to 44% speed.


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  (Question 6-i The following conditions exist:
.  . . A Group II isolation has occurred due to high Drywell pressure. . - Present Drywell pressure is 5 psi >-  -.: The EMERG OVERR DRYWELL lil_ PRESS keylock switch on the PCP panel has been
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SENIOR REACTOR OPERATOR EXAMINATION Question 21 Which one of the following describes the use of ESW for Drywell cooling during a LOCA?
    (taken to its OVERRIDE positio . - No other operator actions have been take Which one of the following describes the CAD isolation valves that can be opened at this
a. It is the preferred method.
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time?
b. It may be used only on loss of RBCLC.
y-     . All CAD _ isolation valves, b.' All CAD isolation valves except 27AOV-111 through 118 (CAD vent valves).
 
c. It may be used only if directed by EOP-4.
 
d. It is prohibited.


1 L All' CAD isolation valves except 27MOV-113,117,122,123 (CAD purge valves).
Question 22 On a Loss ofInstrument Air pressure during normal plant operation, which one of the following describes if and when the MSIVs will go closed?  .
a. Inboards remain open; outboards close immediately.


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b. Inboards and outboards close immediately.
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    ? d.' LAll CAD isoletion valves except 27AOV 131 A/B,132A/B (CAD make-up
    - valves).


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c. Inboards close eventually; outboards close immediately.
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d. Inboards remain open; outboards close eventually, a
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*  REACTOR OPERATOR EXAMINATION
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SENIOR REACTOR OPERATOR EXAMINATION Question 23 The following conditions exist:
  '
  . A valid Reactor Scram has occurred on low RPV level.
Tim plant koperating at full power when the following occur:
 
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.' The EDGs have auto started in response to high Drywell pressure.
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  . - 1 Generated MWe starts to decreas . : Reactor power starts to' decrease. -
. The Recire. pumps are running at minimum speed as expected.
Which one of the following could have caused these symptoms?
 
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Which one of the following descri' es the status of the containment isolations?
1 Decrease in grid frequenc b- - Jet Pump malSctio Loss of feedwater heating. - Inadvertent SRV openin Questioit 8 With a high Drywell pressure, Emergency RPV Depressurization is required if Torus Water Level cannot be maintained below PSP (Pressure Suppression Pressure) Which one of the following is the basis for performing an Emergency RPV Depressurization if the Pressure- ;
a. Group I isolated; Group I1 isolated.
Suppression Pressure Limit is exceeded?: To ensure that the vacuum breakers will not become su'omerged and fail to functio To ensure adequate free volume (airspace) of the Torus for steam suppressio To prevent damaging the Toru To prevent steam from the' Drywell bypassing the Suppression Poo I
 
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b. Group I not isolated; Group II not isolated.
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c. Group I isolated; Group II not isolated.
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    ' REACTOR OPERATOR EXAMINATION -
d. Group I not isolated; Group II isolated.
Question 9J Which one of the following would give positive indication that SRV 'C' ;s open when its
  - ' control switch is taken to OPEN?J '
_  . a.- SP.V red light is o : SRV white light is o c.; SRV tailpiece temperature rises and stabilizes at 285 * > EPIC alarm ' SONIC DET RV-C' RESET is received.


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Question 24 During a plant startup RPV pressure is 900 psig. Loss of CRD flow will have which one of the following effects on control rod motion and scram times?
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a. Normal rod motion is unaffected and scram times will be within acceptable limits.
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QuestionL1 The following conditions exist:
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  . ' A plant transient raised RPV pressure to 1150 psi . The SRVs have opened. _
  . RPV level is 150 inche Assuming no operator action, which one of the following describes when the SRVs are
  - expected to close? Before RPV pressure decreases below approximately 1050 psi : b.' 120 seconds aner the initial transien c 'ADer RPV pressure decreases below approximately 50 psi ; ; When both RHR and Core Spray pumps are secure t i
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.. '' REACTOR OPERATOR EXAMINATION Question 11
' A reactor scram occurred but many control rods failed to insen due to a high water level in -
the Scram Discharge Volume. The APRMs read 9 %. Which one of the following actions will be most effective in inserting control rods? Manually initiate AR De-energize scram solenoids, Manually insert control rod Close the CRD Flow Control v6e.


_ Question 12 Following the trip of one Recire. Pump with the reactor at power, the operators have closed the discharge valve of the tripped pump. Which one of the following is the reason that this is done? Stops reverse rotation of the tripped pump, Prevents backflow through the idlejet pumps, Prevents runou: of the operating recire, pum Lowers the probability of entering the instability region of the power / flow ma Page 6 of 50
b. Normal rod motion is lost and scram times will not meet acceptable limits.
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c. Nennal rod motion is unaffected but scram times will not meet acceptable limits.


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d. Normal rod motion is lost but scram times will be within acceptable limits.
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cREACTOR OPERATOR EXAMINATION -    j-t
 
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SENIOR REACTOR OPERATOR EXAMINATION Question 25 During power operation with RHR pump 'A' in Torus Cooling, an operator mistakenly manually opens RHR pump 'A' Shutdown Cooling Suction valve (10MOV-15A) locally at -
c- _' Question!!31        i
the valve. Which one of the following describes the expected automatic actions, if any?
;  cO,e follo' wing conditions exist: . .
a. There will be no automatic actions.
.
"
  'e = lCor. denser vacuum is 25.1 inches Hg.'
_
      -
      -
          :j-e z. Turbine load is 170 MWei      - /-
'
e iAOP 31 (Loss of Condenser Vacuum) has been enteredc-     1
          ::;
;  , Which one of the following' actions, bi itself, will make it MORE LIKELY that a manual:  _l LTurbine Trip will be required? -      l
          :
          ,
t
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a'. Starting the Mechanical Vacuum pumps.-
,  <
6.- Increase load to'2SS MWe,
          -
j
          * Decrease load to 85 MW >
    '
'
c
-
  . _ Placing the spare Air Ejector sets in sersic ,
.
i


Question 14
b. When 10MOV-15A reaches 10% open, it will automatically close the 'A' RHR Pump Suction Torus Isolation Valve (10MOV-13A).
          '
With the plant shutdown, an Emergency Diesel Generator is rurming and is tied to its bus for
,
_ load testing. Which one of the following describes the response to a complete loss of offsite power?
.-
l The Tie Breakers will trip and the diesel will maintain the bus !oad The Diesel Output breaker will tdp and the diesel will switch to isochronous
,
mode, then the Diesel Output breaker reclose The Diescl_Outpu: breaker will trip and the diesel will switch to droop mode, then :
'
  ^ ?he Diesel Output breaker rector,e :
  : d.: The Tie breakers and the diesel will tri !
"
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    .+-  Page 7 ot$50


,
c. When 10MOV-15A reaches full open, the RHR Torus Cooling / Torus Spray outboard valve (10MOV-39A) will auto close.
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  ._-->r-  ,  ,wg*  n- 4 w ar , .yr,wm_- . ,a , , ,- .e i y , o y


. . .  -. ..... . - . - . - . - . , . . .= .. . -. . .- - .. ~ -.-
d. The %' RHR pump will trip on low suction pressae.
_ i;-


    '
t REdCTOR OPERATOR EXAMINATION -    '
_
          .;
Question 15        i Bus 10400 is powered by the Main Generator via breaker 10402. Which one of the following _
      -
tways'of orening this breaker will not allow closing the Station Reserve breaker 104127 -
t Manually _ opened locall , Manually opened from the control roo ,
:  c. . Automatically opened on overcurren Automatically opened on undervoltag ,
,
.
.
'
Question 26 Which one of the following describes the consequences of spraying the Drywell if Drywell conditions are not in the permissible region of the Drywell Spray Initiation Curve?
i
a. Water sprayed into the Drywell will turn to steam raising pressure even further.
 
b. The cold water will put excessive thermal stress on the Drywell which may lead to its failure.


.
c. The effect is unpredictable and would result in putting the plant in an unanalyzed condition.
I F-
 
. Question 16
d. Drywell pressure would drop more rapidly than could be handled by the vacuum breakers.
,
  - Which one of the following describes the loads in the 24 VDC Power System?
:
. Each load breaker is connected to 48 VDC potential (input) from its associated
  .i24 VDC charger, Italf the loads on a124 VDC distribution bus are powered from +24 VDC. The  -i other half are powered from -24 VD . Each load breaker is conn'ected to 24 VDC potential (input) from its associated
  - l2 VDC charge _
-
          . Italf the loads on a 148 VDC distribution bus are powered from +48 VDC. The other half are powered from _-48_VDC.


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M r w --c y9  % e e 4. - , , ,--s- , , s.-5 -.,- + . , , -- +- ,-r- r t-
SENIOR REACTOR OPERATOR EXAMINATION  *
l Question 27 l The Reactor Building "entilation system is in operation when the exhaust plenum radiation


_, . ..  . . . _ . _. . __ _ , . ~  . _ . _ _ . . . . . _ _ . . _ . . _ . . .
l levels exceed 10 cpm. Which one of the following describes the expected response of the Reactor Building Ventilation and SBGT systems to this event?
  ~
            :
REACTOR OPERATOR EXAMINATION -      i
.
.
  (Question - 17 '.~        1 XThe following Narmw Range RPV level conditions exist:        ,
  . L'A' indicates 215 inches and is rising slowl '
  .- 'B' indicates 185 inches and is lowering slowl '
  '
t  . C' indicates 214 inches and is rising slowl ;
  . Feedwater control is selected to the 'A' Column.-        ,
            ,
iSelecting the 'B' RPV Level Column will result in which one of the following elTects on level
  ~ trends?          .
            .
  . A' and 'C' will continue to rise. 'B' will lowe '
l
l
    '
      >
b.-  A' and 'C' will continue to rise. 'B' will ris :
a. Reactor Building Ventilation will isolate and neither train of SBGT will start, b. Reactor Building Ventilation will isolate and both trains of SBGT will start. I c. Reactor Building Ventilrti 3n will not isolate and neither train of SBGT will start.
u ~'A' and 'C' will lower. 'B' will lowe :
 
.
d. Reactor Building Ventilation will not isolate and both trains of SBGT will str -
  - 'A' and 'C' will lower. 'B' will rise,
l i
            ,
Question 28 The following conditions exist:
t
. A fuel element failure has occurred.
  ' Question 18 -
In which one of the following ways does a loss of 125 VDC Bus 'A' affect the ADS /SRV
  : system?
i Loss of'A' logic, ADS remains ftinctional.


.
. 01-107AOV-100 (Off Gas Outlet Isolation Valve) is open.
  . b.' . 'None of the ADS /SRV valves can be opene The ADS /SRV valves cannot be opened from the remote pane b L Only valves F, J, K & L remain fully functiona Page 9 of 50
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L-- +s 6 4e  .,--,..v.w-'-  +4 u-. -- -,-,,g~..- - - , -
        - , - , - - . , - , - , --<s.e,--, + ~:r--+-


,
. The Off Gas timer has started.
REACTOR OPERATOR EXAMINATION Question 19
. AOP-43 (Shutdown From Outside the Control Room) requires the operators to remove RilR pumps 'A' and 'C' from service. Which on; cf Ge following der.:ribes the reason that this step is necessary?
. Pr; vent water hammer in the even; of a LOCA signh Prevent inadvertent Drywell spra , Prevent inadvettent LPCI injectio Prevent draining the RPV to the Toru Question 20 The following events occur:
. The plant is at 20% powe . liigh radiation in the Off Gas system starts the Off Gas Time . No operator action is take Which one of the following will be the most likely cause of an uutomatic reactor scram?
' liigh Reactor Powe l.ow RPV Leve MSIV closure, liigh RPV Pressur Page 10 of 50
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I i
_________.__m___ _ _ _ _ _ _ _ _


,
. The Stack Low Range monitors are reading full upscale.
.,y- . ~ - .- . . - . -- . ~. . . . . - ,... - ...- .- . -
q
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4: - REACTOR OPEP $ TOR EXAMINATION:  1 d
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  -
        !
  ,
P >
  ; Quest!on 211      ;
        '
1 Whleh one of the following describes the use of ESW for Drywell cooling duririg a LOCA?
        .+
-


-
. The Stack High Range monitors are reading 110 mR/hr.
. La, 'It is the preferred method. -    _
    . .
        ;
-
bf h may be used only on loss of RBCLC. .    ;
        ,
c.- ; it may be used only iidirected by EOP- j
  ;        ;
      '
  ; It is prohibite :
        +
I


        .
. Reactor Building Exhaust radiation is reading 22,000 cpm.
_
i
-        +
t
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Question 22-4-On a Loss ofInstrument Air pressutv during normal plant operation, which one of the following describes if and when the MSIVs v.ill go closed?
I _ Inboards remain open: outboards close immediatel ,
,  . Inboards and outboards close immediatel Inboards close eventually; outboards close immediatel .
        ,
a- Inboards remain open; outboards close eventually.


.
These conditions require entry into which one of the following combinations of Emergency Plan EALs and EOPs?     l a. Unusual Event and EOP-5.
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i b. Unusual Event and EOP-6. I
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c. Alert and EOP-5.    ;
d. Alert and EOP-6.


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I REACTOR OPERATOR EXAMINATION-   j j
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  ; Question 23i The following conditions exist:      .
          '
   . EA valid Reactor Scram has occurred on low RPVlevel.'
23 The EDGs have auto started in response to high Drywell pressure,    ,
  . : The Recirc. pumps are running at minimum speed as expecte t
'
          ;
Which one of the following describes the status of the containment isolations?
          ,
  : Group I isolated; Group 11 isolated.-
l
' Group 1 not isolated; Group 11 not isolate ;
          ;
    '
          '
[ Group 1 isolated; Group 11 not isolate ,
' Group i not isolated; Group 11 isolated.-
Question _24 During a plant startup RPV pressure is 900 psig. Loss of CRD flow will have which one of the following effects on control rod motion and scram times?
' Normal rod moticn is unafrected and scram times will be within acceptable limits, Normal rod motion is lost and scram times will not meet acceptable limits.


;    . .
SENIOR REACTOR OPERATOR EXAMINATION  )
;:  . . Normal rod motion is unaffected but scram times will not meet acceptable lim;t U
Question 29 In the event that normal shutdown cooling capability has been lost, which one of the -
,- Normal rod motion is lost but scram times will be within acceptable limits.
following states the minimum shutdown time before Fuel Pool Cooling Assist will provide adequate cooling?
a. Iday, b. 4 days.


.
c. 7 davs.
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4 v.--- .y-4 ,s .g ye .W-- y .- -q.- - - ,e em-g -44' r .i w g zi y &
d. 9 days.


REACTOR OPERATOR EXAMINATION
Question 30 Which one of the following describes why it is important to establish forced Recire, flow during a Loss of Shutdown Cooling event?
      ,
a. Coolant stratification may mislead the operators into assuming bulk water temperature is below 212*F.
Question 25 During power operation with RIIR pump 'N in Torus Cooling, an operator mistakenly manually opens RilR pump 'A' Shutdown Cooling Suction valve (10MOV-15A) locally at the valve. Which one of the following describes the expected automatic actions, if any? There will be no automatic action When 10MOV 15 A reaches 10% open, it will automatically close the 'A' RilR Pump Suction Torus Isolation Valve (10MOV 13A).   , When 10MOV-15A reaches full open, the RllR Torus Cooling / Torus Spray outboard valve (10MOV-39A) will auto clos The ' A' R11R pump will trip on low suction pressur Question 26 Which one of the following describes the consequences of spraying the Drywell if Drywell conditions are not in the permissible region of the Drywell Spray Initiation Curve? Water sprayed into the Drywell will tum to steam raising pressure even further.


. The ecid water will put excessive thermal stress on the Drywell which may lead to its failur The effect is unpredictable and would result in putting the plant in an unanalyzed condition, Drywell pressure would drop more rapidly than could be handled by the vacuum breaker Page 13 of 50
b. Cooling of the recire loop will produce a reactivity effect when the first recire.
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_-_ ____ - _ _ _- -
pump is started.
\
 
ev N<~
c. Unstable transition boiling at low pressure may cause clad damage.
"    ~
      :! REACTOR OPERATOR EXAMINATION"
  -
*  .       -
? -.
  "  '
Question i 27  -
  '
>
5The following conditions existp:    _
W:Tioperators are conducting EOP- :. . iiPCI and RCIC are inj6ctin .e  s . iTorus level is 10.9 ft. and decreasing rapidl Which one of the following actions, if any; must be taken regarding liPCI and RCIC if Torus level cannbt be maintained above 10.75 feet? -
a.- iTrip both IIPCI and RCIC, i b. . Trip IIPCI, RCIC may remain runnin _ Trip RCIC,llPCI may remain runnin Both IIPCI and RCIC 'may remain runnin Question 28
'
  -The Reactor Building Ventilation system is in operation when the exhaust plenum radiation


  : levels exceed 1.0 cpm. Which one of the following describes the expected response of the Reactor Building Ventilation and SBGT systems to this event? Reactor Building Ventilation will isolate and neither train of SBGT will star b. . Reactor Building Ventilation will isolate and both trains of SBGT will star , .
d. Steam build up in the RHR suction piping will lead to waterhammer when RHR flow is restored.
  ~ : Reactor Building Ventilation will not isolate and neither train of SBGT will star .
  ? d, f Reactor Building Ventilation will not isolate and both trains of SBGT will star ;  -
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'Y''
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l r- .;j= - . .. .
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  -.~ . .  .  . - . - . -
        ~ . , . - ..- .- - -. .-
Y v
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^
<
    - REACTOR OPERATOR EXAMINATION:
          .:
          ,
'
          *
Question 29 l-in the event that normal shutdown cooling capability has been lost, which one of the'
    ^
          .
fol. lowing states the minimum shutdown time before Fuel Pool Cooling Assist will provide -  >!
  : adequate cooling?-
-
a/- 1 day.-      ,
b, - 4 days      ,
c.; _7 days. -      ,
  '        '
d.- 9 day !
~ T Question -30-
"
          .
Which one of the following describes why it is important to establish forced Recire, flow during a Loss of Shutdown Cooling event?      *
          *
a Coolant stratification may mislead the operators into assuming bulk water temperature is below 212 'F,
  . Cooling of the recire, loop will produce a reactivity effect when the first recir m  . pump is starte : c,- - Unstable transition boiling at low pressure may cause clad damag Steam build up in the RHR suction piping will lead to waterhammer when RHR flow is restore .
          ,
-
._
Page 15 of 50
Page 15 of 50
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SENIOR REACTOR OPERATOR EXAMINATION Question 31 Which one of the following limits takes precedence during the operation of the SBGT system with the Reactor Building isolated?
, e, %v' ~
a. Maintain RB AP more negative than -0.25 inches of water.
  . - . - + . , _ - - , ,, -= /r s-, , y-  , ,u.--
 
b. Maintain charcoal filter temperatures less than 170 'F.
 
c. Limit SBGT flow to a maximum of 6000 scfm.
 
d. . Maintain Reactor Building Ventilation exhaust radiation levels less than 10' cpm.


  -  .  .. - - . . . .
l Question 32 Following a reactor scram the pressure in the Scram Discharge Volume (SDV) rises to RPV pressure. Which one of the following describes the most likely reason for this condition? )
        !
a. One or more CRDM seals have failed.
      ,  ,
 
REACTOR OPERATOR EXAMINATION-    ,
b. The scram has not been reset.
' Question 31 LWhich _one of the following liniits takes precedence during the operation of the SBGT system -
 
. with the Reactor Building isolated?    -
c. The SDV vent valves have failed closed, d. The CRDH flow control valve has failed open.
  : Maintain RB AP more negative than -0.25 inches of water. :
 
t b.- Maintain charcoal filter temperatures _less than 170 ' ' . Limit SBGT flow to a maximum of 6000 scf _ Maintain Reactor Building Ventilation exhaust radiation levels less than 10 cp f
I i
.
      !
. Question 32
Page 16 of 50
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Following a reactor scram the pressure in the Scram Discharge Volume (SDV) rises to RPV pressure. Which one of the following describes the most likely reason for this condition? One or more CRDM seals have faile The scram has not been reset, The SDV vent valves have failed close The CRDil flow control valve has fitiled ope Page 16 of' 50.-
 
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SENIOR REACTOR OPERATOR EXAMINATION Question 33 Which one of the following RWM conditions, if any, will prevent insertion of a selected rod using the Emergency In switch?    -
  -
a. None, b. Select Error, c. Withdraw block.
y,       1
 
d. Insert block.


.  .. - ..  ~ -
      . .- ,, . ~ .- . -. . - . . - . -
-3
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REA0 TOR OPERATOR EXAMINATION ~    j
          . ,
k
      - -
_
          ;;
-
LQuestionL33
          '
  - Which one of the following RWM conditions,'if any, will prevent insenion of a selected ro'd'-
        ~
t using the Emergency in switch?/  -
        -
          -
  :
a'. - Non ,
  .      +
b. - Select Erro i
'
  -
i Withdraw bloc f . Insert bloc !
'
il p
          ..;
          '
.
.
*
Question 34 The following conditions exist:
Question 34 -        .
. The plant is shut down.
The following conditions exist:
 
'
. The 'A' RHR loop is in Shutdown Cooling.


  . The plant is shut dow . .The 'A' RIIR loop is in Shutdown Coolin ,
. A LPCI initiation signal on low RPV level occurs.
t-  e _ A LPCI initiation signal on low RPV level occurs, j
      '
Which one of the following describes the operator actions, if any, which must be taken in order for LPCI 'A' to start injecting? Non : Reset the Group 2 isolation, manually start the pump and reset the injection valve  .1 n    isolation signal.


'
Which one of the following describes the operator actions, if any, which must be taken in order for LPCI 'A' to start injecting?
c. . . Manually align the suction path for the desired pump and reset the LPCI initiation
a. None.
      '
          -
signa <
    . .     :
1 Manually align the suction path for the desired pump, manually Mart the pump, -
and reset the injection valve isolation signal.


  "
b. Reset the Group 2 isolation, manually start the pump and reset the injection valve isolatioa signal.
      ]


Page 17 00:50 -
c. Mniually align the suction path for the desired pump and reset the LPCI initiation signal d. Manually align the su , tion path for the desired pump, manually start the pump, and reset the injection valve isolvion signal.
' 9; ,
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r- t r g,..--' + * Ts - - + + - E -, y E ,a ~ , ,* m..-~ s
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'-k_,- ,  (.['
SENIOR REACTOR OPERATOR EXAMINATION
.    -
' Question 35'
      -
The following sequence of events has occurred.
=  "
 
-
. A LOCA has occurred resulting in LPCI injection.
    ,
EREACTOR OPERATOR EXAMINATION :
      .
          <
            .
              ;
          - - _
            *    ;
t Question 135
  ~
_  t
  ..
    '
:  (The folloding sequence of events has occurre ?
,
  ' A LOCA has occurred resulting in LPCI injectio ~
'
  '
  -.; - Offsite power is then lost.'          :
  'c
  .
      . .
,
1 .. EDGs 'B', 'C', & 'D' start and load normall ,
c  -.' EDG 'A' fails to star =
              .
'
  . Udder these conditions, which of the following RHR pumps will be running two minutes t      1
  .- fta er hl t e oss of power?l          t


~
. Offsite power is then lost.
,
  /La.' LAll four          .
b. - ' 'B', 'C', & 'D'          4j


  -
.- EDGs 'B', 'C', & 'D' start and load normally.
  - 'A', 'C', & 'D'
'
              >
1 d.' o 'B' & 'D'.
.
: :
1 Question 36'
              !
,
,
  ; The follo'w events occur:          ,
  . A low RPV level causes IIPCI to start and inject.


.   . , llPCI is the only available injection systeta.
. EDG 'A' fails to start.


l'  .. ' RPV level starts to increas . - The HPCI Aux, Oil Pump breaker trip Assuming no operator action, which one of the following describes the expected response of-IIPCl?
Under these conditions, which of the following RHR pumps will be running two minutes after the loss of power?
d
a. All four b. 'B', 'C', & 'D'
< llPCI will trip when the Aux. Oil Pump breaker trips and can not restart, t.
c. 'A', 'C', & 'D'
d. 'B'&'D'
i I
. Question 36
      -
The follow events occur:
. A low RPV level causes HPCI to stan and inject.


-
. HPCI is the only available injection system.
b. - L llPCI will trip on High Level and can not restar .
cL IIPCI will trip on High Level and can restart on low leve ,
.
*
L IIPCI will continue running until manually trippe ? .
Page 18 of 50
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            ,.,h.-.'> ---f
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              . - -m&


REACTOP OPERATOR EXAMINATION Question 37 The following events have occurred:
. RPV level starts to increase.
. A ! OCA has occurre . The Core Spray pumps auto started on low leve . RPV level subsequent!y recovered to 180 inche . The operators took both Core Spray Pump Switches to STO . Drywell pressure is 2.3 psi Which one of the following describes the expected response of the Core Spray pumps to these events? After auto-starting they remain on until the initiation logic is rese They stop when switched io STOP but restan if Drywell pressure increases above their auto start setpoin They stop when switched to STOP but restad iflevel decreases below their auto-start setpoin They stop when switched to STOP and remain off.


Question 38 Which one of the following describes the effect of a loss of 600 VAC power on the Core Spray rystem? Core Spray pumps will not auto-rart w' en required. They can be started manuall Core Spray pumps cannot be started either automatically er manuall Core Spray pumps will start normally but their discharge valves will not open automatically, Core Spray pumps will start normally but will trip on low flow
. The HPCI Aux. Oil Pump breaker trips.    )
  .
Assuming no operator action, which one of the following describes the expected response of HPCl?
Page 19 of 50
a. HPCI will trip when the Aux. Oil Pump breaker trips and can rat restart.
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    - . .- .-_ _- -- ._-.
b. HPCI will trip on High Level and can not restart.
REACTOR OPERATOR EXAMINATION Question 39
'the operator takes the St.C keylock switch to START SYS A. Pump 'A' receives a stad signal but fails to start due to mechanical binding ofits hde: contactor. Which one of the following describes the expected response of the Squib Valves and RWCU system isolation valves to these events?
I Neither Sq2ib valve will fire: RWCU will not isolat Only the 'A' Squib valve will fire; RWCU will isolat Ibth Squib valves will fire; RWCU will isolat Iloth Squib valves will fire; RWCU will not isolat Question 40 Following a Residual Transfer and prior to the operator taking any actions, which one of the foDowing describes the ability to start the St.C pumps and fire the squib valves? The pumps can be started and the squib valves will fir The pumps cannot be started and the squib valves will tir e, The pumps can be started and the squib valves will not fire, The pumps cannot be started and the squib valves will not fire.


. Page 20 of 50
c. HPCI will trip on High Level and can restart on low level. l d. HPCI will continue rurming until manually tripped.
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Y REACTOR OPERATOR EXAMINATION-Question 41-The plant is operating at 100% power when a Genemtor Load Reject occurs. Which one~of
Page 18 of 50
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  - the following describes the RPS input that generates the first expected scram signal?
l l
.  . a. - - liigh RPV Pressure, liigh Neutron Flu : c. _ Tu,bine Control Valve Fast Closur d. _ Turbine Stop Valve Closur h
: :
Question 42-The reactor is operating at 25% power. Which one of the following describes the response, if l
,
any, of RPS if the 'A' inboard and 'D' outboard MSIVs are closed?  l
  - Full Scram, Italf Scram in Channel'A'.
*
c.- IIalf Scram in Chanr.el 'll'.' No effect. .
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w
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s s, zc
%-
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REACTOR OPERATOR EXAMINATION      !
f
 
Question 43
          :
A normal plant startup is in progress and the following conditions exist:
          [
. The Reactor Mode Switch is in STARTU ,
. . All the IRM range switches are on RANGE j
. No IRMs are bypasse i i
          '
Which one of the following describes the effect on half scrams or rod blocks, if any, that will occur if the IRM 'A' Mode Switch is placed in the STANDilY position?      ;
i
          ' None. as long as its companion APRM is not downscal Rod Withdrawal 131ock onl .
1 RPS llalf Scram onl ;
          > Rod Withdrawal lilock and RPS llalf Ecra !
l i
i Question 44 The following conditions exist:
. ' All IRM Range switches are on RANGE . The SRM detectors are partially withdraw . SRM 'A' reads 80 rp .,
          '
Which one of the following describes the ability to withdraw SRM 'A' and the status of rod blocks?- The detector can be further withdrawn and a rod block exist ' The detector can be further withdrawn and no rod block exist : The detector cannot be further withdrawn and a rod block exists, The detector cannot be further withdrawn and no rod block exists, f
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57e.,-,4---.--,,y e e rvvy +in-t--*.- .-e---,,- ,,,-,-x- - m r, . c ~,. - ,-- - +- - -~-,-
 
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l REACTOR OPERATOR EXAMINATION    i I
Question 45 A Recirculation Flow Summer falls resulting in zero output. _ Which one o .he following is .
the highest power level at which the APRM will generate a rod block but not a scram signal? ! %      l
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- % .
      : Ye P %
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Question 46 Assuming no change in vessel inventory, starting the Recire, pumps will affect Fuel Zone !
and Wide Range RPV level indication in which one of the following ways? Fuel Zone rises; Wide Range rises, Fuel Zone rises; Wide Range lower : Fuel Zone lowers; Wide Range rise d.' Fuel Zone lowers; Wide Range lower :
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REACTOR OPERATOlt EXAMINATION Questiori 47 RCIC is in operation due to a small LOCA. Which one of the following describ:s the expected position of the RCIC Turbine Governor Valve (13110V 2) and the RCIC Turbine Steam Inlet isolation Valve (13MOV-131) if RPV level rises to 222.5 inches? Turbine Governor Valve open; Turbine Steam inlet isolation Valve ope Turbine Governor Valve closed; Turbine Steam Inlet Isolation Valve ope Turbine Governor Valve open; Turbine Steam inlet Isolation Valve closed, Turbine Governor Valve closed; Turbine Steam inlet isolation Valve closed.
__ _
SENIOR REACTOR OPERATOR EXAMINATION Question 37 The following events have occurred:
. A LOCA has occurred.


Question 48 The following events have occurred:
. The Core Spray pumps auto started on low level.
. An Automatic Depressurization System (ADS) initiation has occurre . The initiation signals are still presen . A blowdown is in progres Taking the ADS Normal / Override switches to OVERRIDE and back to NORMAL will have which one of the following efTects on the ADS Valves? ADS Valves will close and remain close ADS Valves will close then reopen immediately, ADS Valves will close then reopen after 120 seconds, ADS Valves will remain ope '
Page 24 of 50
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REACTOR OPERATOR EXAMINATION Question 49
. RPV level subsequently recovered to 180 inches.
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The following conditions exist:
. The operators tock both Core Spray Pump switches to STOP.
. Drywell pressure has risen from 1.8 to 2.5 psi . Torus pressure has risen from 0 to 2.5 psi nese conditions are symptomatic of which one of the following? SRV cycled to control pressure and an SRV tailpiece failure inside the Toru Small break LOCA in the Drywell and a Downcomer failure inside the Toru Small break LOCA in the Drywell and a Torus to Drywell vacuum breaker failed to ope SRV eycled to control pressure and an SRV tailpiece vacuum breaker stuck ope Question 50 With the Mode Switch in STARTUP, which one of the following conditions will result in the automatic closure of the MSIVr? RPV Level is 50 inche Steamline pressure is 750 psi Main Condenser Vacuum is 10 inches lig, Turbine Stop valves not fully close Page 25 of 50
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_ _ _ _ _ . _ _ _ ._ _ .. __ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . . _ - _ .
. Drywell pressure is 2.3 psig.
t
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REACTOR OPERATOR EXAMINATION      !
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Question 51 1hc plant is in shutdown cooling when a relay failure results in a spurious ADS logic    l
            '
Channel'A' low low low level signal. No other level trips have occurred. Which one of the
            * '
following describes the effect that this event will have on ADS? ADS willinitiat :
            ' ADS will not initiate because the RilR or Core Spray pump running interlock is bypassed in shutdown coolin t
- ADS will not initiate because both channels are needed for ADS initiatio .
' ' ADS will not initiate because there is no low level tri .
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:-
t t
[  Question $2_
RFP 'A' hasjust tripped on high reactor vessel level. Which one of the following conditions must be satisfied before the RFP 'A' hydraulic coupling automatically disengage 37    - IIP and 1.P stop valves close RFP turbine tripped signal sense Turbine speed less than 4 RPM, MGU and MSC on low speed stops,      ;
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,-+r ,-,.m-,  ..,,-.-,-,-_.-.__.,_,-.m,m.,  _ , - , . _.. , . . _ . . . . , . , ,, , , . . . ...,,,,,,...-.,-m- --


    - _ . . .
Which one of the following describes the expected response of the Core Spray pumps to these events?
REACTOR OPERATOR EXAhi! NATION Question $3 The following events occur,
a. After auto-starting they remain on until the initiation logic is reset.
. The plant is operating at full power with the hiGUs and hiaster Controller balance . The Master Controller output slowly fails downscal . RPV level lowers to 185 inche: at which point the operator takes both h10Us to manua . No further operator action is take Which one of the following describes the response of Fred Flow and RPV level afler the MGUs have been shilled to manual? Flow will increase to 100%; Level will increase to 200 inche Flow will increase to 100%; Level will remain at 185 inche Flow will increase to greater than 100%; Level will increase to 200 inche Flow will remain less than 100%; Level will continue to trend down.


Question 54 The SilGT system has failed to auto start in response to a llPCI start signal. Which one of the following will occur as a result of the failure of SBOT to start?
b. They stop when switched to STOP but restart if Drywell pressure increases above their auto-start setpoint.
a, llPCI start up sequence will not complete and the llPCI turbine will not start, The llPCI turbine will start but may trip on liigh Exhaust Pressur The llPCI turbine will start but may trip on liigh IIPCI Area Temperature, IIPCI flow rate will be limited due to decreased condenser eflicienc Page 27 of 50
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REACTOR OPERATOR EXAMINATION Question 55 Which one of the following is the reason that operation of an EDO at loads near 2000 KW is to be avoided? Excessive wear on turbocharger drive gears, Main bearing degradation due to inadequau lube oil coolin Potential Lube oil sump fire due tr increased piston blow by, Overheating of exhaust syste Question 56 Following a 1.OCA with concurrent Loss of OITsite Power, which one of the following will be the first to be reenergized when the 'A' and 'C' EDO breakers close?
c. They stop when switched to STOP but restart iflevel decreases below their auto-start setpoint.
a, 'A' ESW Pump, 'A' RI1R Pump, 'C' RilR Pump, 'A' Core Spray Pum Page 28 of 50
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REACTOR OPERATOR EXAMINA110N Question 57 The operator withdraws a control rod one notch but the rod position indications show that the rod is withdrawing continuously until it reaches full out position. Which one of the following could be the cause of this? Stuck collet pisto liigh CRDil pressur Uncoupled ro Leaking IICU Scram inlet valve (03 AOW126).
d. They stop when switched to STOP and remain off.


-
Question 38 Which ( ie of the following describes the effect of a loss of 600 VAC power on the Core Spray system?
Question 58 Reactor power is 5%. The RWM is fully operational and has generated a Withdraw Illoc Under these conditions, which one of the following is the maximum number of rods with insert errors that could possibly be moved in the withdraw direction? Non On , Tw Thre Page 29 of 50
a. Core Spray pumps will not auto-start when required. They can be started manually.
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b. Core Spray pumps cannot be started either automatically or manually.
REACTOR OPERATOR EXAMINATION Question 59
'Ihe plant is operating at full power when the following Recire. Pump Seal readings are noted:
. #1 (~ inner) Seal Cavity pressure is 1000 psi . #2 (outer) Seal Cavity pressure is 150 psi Which one of the following will cause these conditions? Normal operation of both seals, Failure of both seal Partial failure of the #1 sea Partial failure of the #2 seal, Question 60 During the stanup of the 'A' Recire. Pump the following conditions exist:
. The 'A' Recire. Pump Discharge valve is 85% ope . The 'II' Recire. Pump Discharge valve is fully ope . Total Feed Flow is 30%.
. Feedwater pump 'N is running; Feedwater pump 'll' is secure . RPV level is 195 inche Which one of the following describes the most restrictive Recire. Pump speed limitations currently in effect? Iloth pumps ac limited to 30%. Iloth pumps are limited to 44%. Pump 'A' is limited to 30%; 'B' is not limite Pump 'N is limited to 30%; 'B' is limited to 44%.
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c. Core Spray pumps will start normally but their discharge valves will not open automa:ically.


REACTOR OPERATOR EXAMINATION l
d. Core Spray pumps will start normally but will trip on low flow.
I Question 61
'Ihe drive mechanism of a fully withdrawn control rod is uncoupled. Which one of the following indications during the coupling check indicates that the rod is uncoupled? Individual Rod Drift Alann, Individual Rod Overtravel Alar c '49' will be displayed in the rod position window, Individual Rod Full Out light remains energize l l
Question 62 Three of the eight LPRM detectors supplying an RilM channel have failed downscal Which one of the following describes the response, if any, of the RBM to these failures? There will be no functional effect since the RIIM still has sumcient LPRM inputs to functio The rod block setpoint will be automatically adjusted downward to compensate .
      '
Ibr the lost input An Inop, Rod Illock will be generated until one detector is bypasse A Rod Illo:k will be generated until the PUSil TO SETUP pushbutton has been dep:esse Page 31 of 50
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REACTOR OPERATOR EXAhilNATION Question 61 Which one of the following describes the effect of spraying the Drywell during a LOCA when Drywc!! pretisure is below 2.7 psig? Unnecesnry damage to equipment in the Drywell, Partial de inertir.g of the Primary Containmen Inability to vent the Primary Containmen Mechanical failure of the Torus to Drywell vacuum breaker i Question 64
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The operators are unable to reset an inadvertent Group i isolation signal. Which one of the following conditions, ifit existed, would cause this problem?
3 A control switch for one of the MSIVs is in the OPEN positio The Reactor Mode Switch is in RU >
- The control switches for the Main Steam Line Drain valves are in the OPEN positio The AP across the MSIVs is 125 psi Page 32 of 50
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,  .-,,  .  . . . REACTOR OPERATOR EXAMINATION Question 65 During plant operation it is noted that 345 KV bus voltage is 380 KV. Which one of the following is the appropriate response, if any, to this condition? No response require Reduce generator output voltage to restore 345 KV bus voltage to norma Contact the Load Dispatch Center and request that 345 KV bus voltage be reduce Increase Generator Isolated Phase Cooling to maximum.


Question 66 The ibliowing sequence of events occurs:
      ~
. 600 VAC power is lost for 3 minute . Afier 600 VAC power is restored,125 VDC power is briefly los . 125 VDC power is then restore Aller restoration of 125 VDC power, which one of the following will be the source, if any, of 120 VAC UPS Instrument Power? Nothing,120 VAC will be deenergize b, 600 VAC via the UPS MG Se VAC via the 600/120 VAC transformer, VDC sia the UPS MG S I Page 33 of 50  ;
S~aiOR REACTOR OPERATOR EXAMINATION Question 39 The operator takes the SLC keylock switch to START SYS-A. Pump 'A' receives a start signal but fails to start due to mechanical binding ofits breaker contactor. Which one of the following describes the expected response of the Squib Valves and RWCU system isolation valves to these events?
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a. Neither Squib valve will fire; RWCU will not isolate.


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b. Only the 'A' Squib valve will fire; RWCU will isolate.
REACTOR OPERATOR EXAMINATION
      !
Question 67 l.oss of all 125 VDC power would have which one of the 1ollowing effects on the Emergency Diesel Generators? Diesels would auto start and load, Diesels would auto start, but would not auto loa Diesels would not start and could not be started at the Engine Control Pane Diesels would not auto start but could be stan, at the Engine Control Pane ,
      ,
Question 68 Which one of the following describes the effect of the Control l loom inlet Radiation Monitor channel failing upscale?
a. . Alarm only,
      ' ' 1he intake and Exhaust dampers close and the Recire, damper opem The Control Room Supply fans trip and the Exhaust Damper closes, d, The Emergency Supply fan starts and the inlet filter system is placed in acryic .
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c. Both Squib valves will fire; RWCU will isolate, d. Both Squib valves will fire; RWCU will not isolate.
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REACTOR OPERATOR EXAMINATION
        ,
Question 69
      .  .
        '
Which one of the following describes a potential path for radioactive contamination to the discharge canal during normal power operation?    I Drywell Air Cooler tube lea l RilCLC lleat Exchanger tube lea , Recombiner condenser tube leak, Main Condenser tube leak, i
Question 70 Which one of the following describes the response of any TIP detector not in its shield when a Group I and Group 11 Containment isolation Signal occurs? A Group i isolation will cause the TIP to withdraw to the Lead Shield position. A Group 11 has no further effec A Group 1 isolation will cause the TIP to withdraw to the Lead Shield position. A Group 11 will activate the shear valve if the TIP is still inserte A Group 1 Isolation will have no effect. A Group 11 Isolation will actuate the shear valve if the TIP is not withdrawn within 10 minutes, A Group 1 Isolation will have no effect. A Group 11 Iso lation will cause the TIP to be withdrawn to the Lead Shleid positio Page 35 of 50
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Question 40 Following a Residual Transfer and prior to the operator taking any actions, which one of the following describes the ability to start the SLC pumps and fire the squib valves?
Rl! ACTOR OPlillATOR !!XAMINATION Question 71
a. The pumps can be started and the squib valves will fire.
'lhe crew is conducting EOP 5 (Secondary Containment Control) when Reactor llul!d'ng ventilation isolates on high radiation. The radiation level is subsequently seen to deercase below the isolation setpoint. Which one of the following describes under what condition, if any, it is pennissible to override the high radiation isolation to restan the Reactor 13uilding ventilation system 7 It is not pennissible, Two iteactor lluilding area temperatures are above maximum nonna Aller it is confirmed that no priniary systun is discharging into the P.cactor limiding, If Reactor lluilding AP cannot be maintained at a negative pressure with S110 t Question 72 Inadvenent closure of which one of the following CRD llCU valves will result in the inability to scram the afrected rod? Scram inlet Valve 12 i Insert licader Isolation 101, Exhaust Waterlleader Isolation 10 l 1 Withdraw Ileader Isolation - 10 l


Page 36 of 50
b. The pumps cannot be staned and the squib valves will fire.
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c. The pumps can be started and the squib valves will not fire.
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I Question 73        .,
d. The pumps cannot be started and the squib valves will not fire.
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The plant is operating at $0% power with RCIC testing in progress. Under these conditions, Tech Specs .Tquire an immediate reactor scram if Torus temperature reaches which one of the following temperatures? 'l? 'F Il0 *F I20 *1
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Question 74 Fuel handling operations are in progress when a Fuel Pool leak is discovered. Which one of the following states the initial point at which immediate evacuation of the Refuel Floor becomes mandatory?       , When the presence of the leak is verifie Wh:n level decreases below its Tech Spec limit (33 feet). When uncovering of spent fuel is imminen , When uncovering of spent fuel has ocenrre Pace 37 of 50
SENIOR REACTOR OPERATOR EXAMINATION Question 41 The plant is operating at 100% power when a Generator Load Reject occurs. Which one of the following describes the RPS input that generates the first expected scram signal? -
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a. High RPV Pressure.-
      ,-y--- , , m..-- -- , . - g-
b. High Neutron Flux.
 
c. Turbine Control Valve Fast Closure, d. Turbine Stop Valve Closure.


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i REACTOR OPERA' LOR EXAMINATION    'l, i
i Question '75        It
:  A plant startup is in progress and Recire, pump speed is 30%. APRM readings are as listed below:
          ; Channel A 2.3 t
  . Channel B ' 4.0%        !
  : . Channel C  5,0%      ;
-  e Channel D 4.7%      !
l  e Channel E '2.4%      l e Channel F  5.1%      i
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.
  . If the Reactor Mode Switch is plu:ed in RUN, w hich one of the following des.cribes the    i
  . ability to raise power with control rods and/or recire, flow?    j a.' The power can be raised using rods or recire. flo .
    .
          .
.  . Power can be raised using rods onl J i
          . Power can be raised using recire. onl >
.    - Power cannot be raised;      l t
r s
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Question 42 The reactor is operating at 25% power. Which one of the following describes the response, if any, of RPS if the 'A' inboard and 'D' outboard MSIVs are closed?
          !
a. Full Scram.
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l Question 76
          :
The plant is operating at full power when the pressure compensation for the in service RPV    .
          '
i  - level column is lost. Which one of the following describes the effect that this will have on actual RPV water level?
          !
  - . RPV level will lower until a reactor scram occurs.


,  b.- RPV level will lower (by about 12 inches) and stabilize, ci RPV level will rise until a reactor scram occurs.
b. Half Scram in Channel 'A'.
c. Half Scram in Channel 'B'.
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d. No effect.


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          ! 'RPV level will rise (by about 12 inches) and stabiliz j i
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  ~- . T - . i i _ ,, .  ._,,-.,-,a,._.,, ..., ,, ..- .-,  ,, . , . - . - . -
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SENIOR REACTOR OPERATOR EXAMINATION Quesdon 43 A normal plant startup is in progress and the following conditions exist:
  . The Reactor Mode Switch is in STARTUP.


. . ..  . . - - . -  ~ - . . - - -. .- . . . - - .  - - - -
. All the IRM range switches are on RANGE 2.
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REACTOR OPERATOR EXAMINATION i
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Question 77-            l
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The plant is at full power and the 'A' Pressuir Regulator is in control. Failure of wNeh one      l of the following inputs to the EllC Pressure Regulators will have the smallest impact on RPV      q pressure? .
; W Pressure Regulator throttle pressure fails hig ;
4 'A' Pressure Regulator throttle pressure fails lo i 4 'll' Pressure Regulator throttle pressure fails hig j
            ;
            ~ 'll' Pressure Regulator thmitle pressure fails low. .
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Question 78 The plant is operating at full power when RiiCl.C flow to the RWCU system is lost. Which      l one of the following is the expected response of the system isolation and the llolding pumps      ;
to this event?          .;
e The system will i ot isolate; The lloiding pumps will star j
            , The system will isolate; The llolding pumps will tri .
. . The system will not isolate; The liolding pumps will tri The system will isolate; The flolding pumps will start.


~
. No IRMs are bypassed.
            .


-            i
Which one of the following describes the effect on half scrams or rod blocks, if any, that will occur if the IRM 'A' Mode Switch is placed in the STANDBY position?
,            i
a. None, as long as its companion APRM is not downscale, b. Rod Withdrawal Block only.
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,n ., , ..-m -
  .,a w a w , . . - -,.. , , , - - , , , , , - , , , . --,,,,.~,-e,-. . - - - . - ...~., .-....s.,c ,. --


_ __- .- ..  ..
c. RPS Half Scram only.
. REACTOR OPERATOR EXAMINATION  ,
E Question 79 The plant is at 70% power with all Condensate, Conden, ate llooster, and Feed pumps running. Which one of the following describes the expected plant response to the trip of one Condensate pump? The remaining pumps will remain in service and RpV level will not be affecte One Feed pump will trip on low suction pressure but RPV level will not be affecte One Fred pump will trip on low suction pressure and RPV level will decreas i One Condensate flooster pump will trip but RpV level will not be affecte Question 80 Which one of the following describes the purpose of the Reactor Steam supply to the Off Gas llydrogen Recombiner? Dilutes hydrogen to below the explosive limi Increase temperature which improves efficiency of recombinatio Improves removal of radioactive lodines from gas stream, Improves cooling of the charcoal filters during accident conditions.


C Page 40 of 50
d. Rod Withdrawal Block and RPS Half Scram.
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REACTOR OPEllATOR EXAMINATION Question 81 Fire Main use during a fire on site caused its pressure to lower to 90 psig for 30 second Pressure subsequently recovered to 120 psig where it has remained for the past 10 minute Assumirg no operator action concerning the Fire Pumps, which one of the following identifies the Fire pumps that should be running at this time? Makeup Pump only, Makeup Pump and Motor Driven Fire Pump onl Makeup Pump, Motor Driven Fire Pump and One Diesel Driven Fire Pump onl Makeup Pump, Motor Driven Fire Pump and Both Diesel Driven Fire Pump Question 82
Question 44 The following conditions exist:     i
'
  . AllIRM Range switches are on RANGE 2.
The following air pressures exist in the Instrument and Service Air headers:
  . Instrument Airis 100 psi . Service Air is 90 psi Under these conditions, which one of the following describes the expected position of the Instrument to Service Air Isolation valve (39FCV-110) and the 13reathing Air Isolation valve (39FCV 111)? Iloth will be ope FCV 110 will be open. FCV-111 will be closed, FCV-110 will be closed. FCV 111 will be open, Iloth will be close Page 41 of 50
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REACTOR OPERATOR EXAMINATION Question 83 An RilCLC Makeup Tank Level annunciator is alarming dee to a high level. Which one of the following is the most likely cause of this condition? Tube leak in the RBCLC heat exchanger, Tube leak in the RWCU NRil , RBCLC low low pressure, d, RilR pump seal cooler lea Question 84 During normal power operation, which one of the following sources can be used for emergency makeup to the Spent Fuel Pool? CRD, Condensate Transfer, Core Spray, RilR Service Wate Page 42 of 50
. The SRM detectors are partially withdrawn. j
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. SRM 'A' reads 80 cps. 4 Which one of the following describes the ability to withdraw SRM 'A' and the status of rod blocks?
a. The detector can be further withdrawn and a rod block exists. j b. The detector can be funher withdrawn and no rod block exists, c. The detector cannot be further withdrawn and a rod block exists.


. --.  . - . . - . . - - - - - - . . - - -  -.- . - . - - - -
d. The detector cannot be further withdrawn and no rod block exists.
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i REACTOR OPERATOR EXAMINATION   [
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Question 85      :;
          ;
'  '
  . Ihe Reactor Mode switch is in the REFUEL position, and the Refueling Platfonn (bridge) is =  [
over the Reactor Vessel.- Which one of the following would cause a Rod Block under these  i conditions?      i i
  '      * lhe Auxiliary 11011,1is loade !
, 'Ihe Fuel Orapple is in the FULL UP positio ;
.      . .
          !
  ~
I
  . ll.: Service Platform floist is unloaded and not FULL U ;
i di All rods are Full In, except for a selected rod at position 0 {
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I Question 86        i i
in accordance with AP-02.04, which one of the following activities requires an ' instruction or  !
''
procedure to perfomW
'
          : Checking a relay energized or deenergize ,
i Changing a fish basket, Checking an oil sump level.


.
  - d. - - Opening drain valves within a PTR boundar .
c        .;
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SENIOR REACTOR OPERATOR EXAMNATION
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Question 45
          ,
  'A Recirculation Flow Summer fails resulting in zero output. Which one of the following is the highest power level at which the APRM will generate a rod block but not a scram signal?
  '
a. 100 %
  >        !
b. 75 %
- . ,._.,T-..,...  .-  . . . ~ - . - - _ - - - - . .
<
_ .-.  .  . . - .. . . . REACTOR OPERATOR EXAh11 NATION  ,
c. 60 %
.
d. 50%
Question 87 During normal plant operations, you have been assigned to perform a routine task that is governed by a Reference Use procedure without step signofTs. Which one of the following describes the requirements for procedure review and reference? No prior review of the p.ocedure is reanired. Reference to the procedure during the task is not require Review the procedure prior to performing the task. Reference to the procedure during the task is not require Review the procedure prior to performing the tt k. Refer to the procedure prior to performing each ste No prior review of the procedure is required. Refer to the procedure prior to perforrning each step.
Question 46 Assuming no change in vessel inventory, starting the Recire. pumps will affect Fuel Zone and Wide Range RPV level indication in which one of the following ways?
a. Fuel Zone rises; Wide Range rises, b. Fue1 Zone rises; Wide Range lowers.


Question 88 The plant is at full power when ST-5D (APRhi Calibration) shows that the AGAF for an APRM is 1.02. Which one of the following describes the significance of this reading? There is no significance if FRP is greater than hiFLP The reactor will ceram at a higher power than allowe The reactor will scram at a lower power than require The APRh1 has too few input i Page 44 of 50
c. Fuel Zone lowers; Wide Range rises.
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REACTOR OPERATOR EXAMINATION Question 89 Operation with a high hotwell level (>l 12 inches) is likely to have which one of the following consequences?
d. Fuel Zone lowers; Wide Range lowers.
      ,
o Condenser tube damage due to high tube vibratio Condenser Air Removal pump damage due to high moisture ir:tak T Unmenitored release to the lake via the Cire. Water syste Condensate pump damage due to runout.


Question 90 You are hanging a PTR on a circuit breaker and the PTR form has a slash through the first check block (' Initials first') for that component. Which of the following describes the meaning of the slash on the PTR form? This is a replacement for a lost tag, No independent verification is require Dual concurrent verification is require The position of the circuit breaker is not being change Page 45 of 50
Page 23 of 50
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t Rl! ACTOR OPERATOR EXAMINATION 1-Question 91 The scram times of 136 control rods have been measured and average 3.50 seconds to position 04. What is the slowest scram time that the remaining control rod can have and still satisfy the requirements of Tech Specs? .554 se t .764 se .000 se ,
      .
I .900 sec.
SENIOR REACTOR OPERATOR EXAMINATION Question 47 RCIC is in operation due to a small LOCA. Which one of the following describes the expected position of the RCIC Turbine Governor Valve (13HOV-2) and the RCIC Turbine Steam Inlet Isolation Valve (13MOV-131) if RPV level rises to 222.5 inches?
a. Turbine Governor Valve open; Turbine Steam Inlet Isolation Valve closed, b. Turbine Governor Valve closed; Turbine Steam Inlet Isolation Valve open.
 
c. Turbine Governor Valve open; Turbine Steam Inlet Isolation Valve elesed open.


Question 92 During fuel handling operations the operator in the control room notes that the SRhis are reading below 3 eps. Under which one of the following conditions, if any, may fuel handling continue? - The plant has been shadown for more than 90 days, A core spiral ofiload is in progress, A control rou olade replacement is in progres None. Fuel handling must always be terminated if SRhis fall below 3 cp Page 46 of 50
d. Turbine Govemor Valve closed; Turbine Steam Inlet Isoleion Valve closed.
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i Question 48      1 The following events have occurred:
. An Automatic Depressurization System (ADS) initiation has occurred.


REACTOR OPERATOR EXAMINATION Question 93 A fask in the RCA requires that you enter a Very liigh Radiation Area during normal plant operations. Which one of the following describes the minimum key (s) and RWP coverage requirements necessary to enter the area? Single key from radiation Protection; Non-routine RWP Single key from Shift Manager; Operations standing R One key from Radiation Protection and one key from Shift Manager; Non-routine RW One key from Radiation Protection and one hey froin Shill Manager; Operations standing RW Question 94 You are wearing single PCs while working in the Reactor Building when immediate evacuation of the Reactor Building is directed over the Gaitronics. You should remove your PCs at which one of tb. following places? Your currun location when you hear the announcemen Area Normal Step oft Pa P6er !" .:ntering the Reactor Building Airloc Admin Building RCA Access Poin Page 47 of 50  .
. The initiation signals are still present.
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- - . . - , . .  . - . . . . . . - . -- _ -.-. ..-...., . , -  - -.
. A blowdown is in progress.
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REACTOR OPERATOR EXAMINATION:
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  : Question _95 )
You are NCol performing a shutdown from outside the Control Room; When you arrive ~ at
          *
  ; Panel 25RSP you report successful completion of all actions you we . required to perform at other locations. Which one of the following actions remains to be aci >mplished?:
    ..
a.: Tripping the Main Turbine.-
i j
  - , Closing the MSIV ~'
'- Closing the llPCI outboard steam suppl d.- Tripping the Recirc. pumps, i
          '
i
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          :
:
:
  - Question 96
:  An Alert has been declared and the operaters are conducting EOP-6 (Radioactivity Release r  _ Control). Which one of the following is a type of accident that this EOP is designed to
[  mitigate?


a. - Dropped fuel bundle in the Spent Fuel Pool, . Radwaste spill in the Radwaste Building.
Taking the ADS Normal / Override switches to OVERRIDE and back to NORMAL will have which one of the following effects on the ADS Valves?
a. ADS Valves will close and remain closed.


;
b. ADS Valves will close then reopen immediately.
L Main Steam leak in the Turbine Buildin .
  ~
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  - . Fire in the SBGT filters.


.
c. ADS Valves will close then reopen after 120 seconds.
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d. ADS Valves will remain open.
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REACTOR OPERATOR EXAMINATION
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LQuestion 97-
  - Following a failure to scram an operator has been directed to implement EP-3 (Backup 3 :;
,  Control Rod Insertion) at Panels 09-15 and 0917 to remove and replace fuses. Which one of the following describes the desired outcome of this evolutlo 37
,
a. ' Opest the scram inlet and outlet valve b.- Deenergize the RPS power supply buses.


, Vent and Drain the Scram Discharge Volum , Reset RP ,
Page 24 of 50
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e Question 98 The reactor is operating at ful! power when the following events occur:
SENIOR REACTOR OPERATOR EXAMINATION Question 49 The following conditions exist:     )'
  . The Turbine Control Valves clos . The Turbine Bypass Valves fully ope . - The Reactor Scram . The SRVs open briefly.
. Drywell pressure has risen from 1.8 to 2.5 psig.


.
. Torus pressure has risen from 0 to 2.5 psig.
Which one of the following could have caused this chain of eveats? Turbine Load Reference signal has failed downscal The MSIVs have closed, The_ Backup (B) Pressure Regulator has failed low.


'
'
  .d ' The Maximum Combined Flow Limiter has failed downscale.
These conditions are symptomatic of which one of the following?  I a. SRV cycled to control pressure and an SRV tailpiece failure inside the Torus.
 
b. Small break LOCA in the Drywell and a Downcomer failure inside the Torus.
 
c. Small break LOCA in the Drywell and a Torus to Drywell vacuum breaker failed to open.
 
d. SRV cycled to control pressure and an SRV tailpiece vacuum breaker stuck open.


.
.
. .
Question 50 With the Mode Switch in STARTUP, which one of the following conditions will result in the automatic closure of the MSIVs?
,
a. RPV Levelis 50 inches.
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Page 49 of 50
b. Steamline pressure is 750 psig.
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c. Main Condenser Vacuum is 10 inches Hg.
 
d. Turbine Stop valves not fully closed.
 
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Page 25 of 50
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SENIOR REACTOR OPERATOR EXAMINATION Question 51 The plant is in shutdown cooling when a relay failure results in a spurious ADS logic Channel 'A' low-low-low level signal. No other level trips have occurred. Which one of the following describes the effect that this event will have on ADS?
a. ADS willinitiate.


  - ,.- - . _ -  _- . . - . . - - - . _. - . - . ~
b. ADS will not initiate because the RHR or Core Spray pump running interlock is bypassed in shutdown cooling.
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REACTOR OPERATOR EXAMINATION -  j
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Question 99
        '
w - A scram has occurred due to a transient resulting from a loss of UPS. Not all rods have fully-inserted. Which one of the following should be used to evaluate reactor power to determine ' -
if entry into EOP 2 (RPV Control)is required?.    '
  . APRM chart recorder '
  ' SPDS displa ! Steam Flow.


d.' Number of open SRV .
c. ADS will not initiate because both channels are needed for ADS initiation. '
T Question 100 The following conditions exist:
d. ADS will not initiate because there is no low-level trip.
. : A LOCA has occurred at 100% power. -
. '' EPIC is not availabl . 16TI 107 and 108 both indicate 256 ' . Drywell pressure on panel 09 3 indicates 40 psi . - RPV 09-5 Wide Range indicates 40 inches.


,
,
. - RPV 09-3 Fuel Zone Recorder indicates -130 inche .Which one of the following describes the use of the Fuel Zone Recorder and the Wide Range Instruments?
      )
NOTE: Figures 4.7 and 4.8 of EOP-4 are provide a . Neither the Fuel Zone Recorder nor the Wide Range is usabl Fuel Zone Recorder is usable; Wide Range is not usable.
l


- Fuel Zone Recorder is not usable; Wide Range is usable, c Both the Fuel Zone Recorder and the Wide Range are usable,
Question 52
_ _    Page 50 of 50
      -
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RFP 'A' hasjust tripped on high reactor vessel level. Which one of the following conditions must be satisfied before the RFP 'A' hydraulic coupling automatically disengages.'
    *""5NO OF EXAMINATION ""*
      )
- . . . _ _
      ;
_ . . _ . _ _ _ _ . . - . _ _
      )
a. HP and LP stop valves closed. j b. RFP turbine tripped signal sensed.


. . .- . _ . . - . _ - . _ .-
j c. Turbine speed less than 4 RPM.   .
d. MOU and MSC on low speed stops.


LOSS OF 51R7TDOWN COOLINGO    AOP-30
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      -
      !
i ATTACHMENT 2  Page 1 of 1 CORE DECAY HEAT VS. TIME AFTER SHUTDOWN l
Page 26 of 50
I Days after  DTU/hr Days after BTU /hr shutdown   shutdown 0 6.28E8  21 1.48E7 1.44E7 1 4.79E7 l  22 1.42E7 2 3.92E7 l  23 1.39E7 3 3.36E7 l  24 1.36E7 4 2.97E7 l  25 5 2.69E7 l  26 1.33E7 l
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6 2.48E7  27 1.31E7 1.28E7 7 2.32E7 l  28 1.26E7 8 2.19E7 l 29


9 2.08E7 .24E7 1.22E7 10 2.00E7 l 31 1.20E7 11 1.92E7 l 32 12 1.86E7 l 33 1.18E7 13 1.80E7 l 34 1.16E7 14 1.75E7 l 35 1.14E7 15 1.70E7 l 36 1.12E7 16 1.66E7 l 37 1.10E7 17 1.62E7 l 38 1.09E7 18 1.58E7 l 39 1.07E7 19 1.54E7 l 40 1.06E7 20 1.51E7 l 730  9.13E5 Rev. N Page 18 of 19
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SENIOR REACTOR OPERATOR EXAMINATION Question 53 The following events occur.


      'i .
. The plant is operating at full power with the MGUs and Master Controller balanced.
LOSS OF SHUTDOWN COOLING 0    AOP-30
 
'
. The Master Controller output slowly fails downscale.
ATTACHMENT 3  Page 1 of 1 ALTERNATE COOLING METHODS METHOD APPROXIMATE HEAT LIMITATIONS REMOVAL CAPACITY (BTU /hr)
Decay Heat Removal  3.00E7 * Gates removed between cavity and spent fuel pool
    ,
Fuel Pool Cooling  3.30E6 * Cates removed between cavity and spent fuel pool
    * RBC must be available
    * SW must be available
.Ftel Pool Cooling  2.40E7 * RHR must be available Assist
    * RHRSW must be available
    * Gates removed between cavity and spent fuel pool RWCU Blowdown Mode  2.06E6 * No isolation signal present
* 1 pump running  * Makeup source must be
* 125 gpm blowdown flow  available (see list below)
* 125 gpm makeup flow
    * Main Condenser-or Radwaste must be available RWCU Recirc Mode  1.70E6 No isolation signal present RWCU Blowdown Mode  1.00E6 * No isolation signal present
* gravity drain  * Makeup source must be
* 50 gpm blowdown flow  available (see list below)
* 50 gpm makeup flow    .
    * Main Condenser or Radwaste must be available Makeup Sources
* Condensate transfer keep-full using Core Spray or RHR
* Control Rod Drive System
*
Condensate /Feedwater
* Condensate transfer to skimmer surge tanks (gates removed)
* Condensate transfer to fuel pool using DHR (gates removed)
* Condensate transfer using service box connections on the refuel floor (gates removed)
* Fire Protection System water from local fire hose stations or outside sources
* RHR service water cross-tie
* Fire Water Crosstie
; Rev. N Page 19 of 19


' ^
. RPV level lowers to 185 inches at which point the operator takes both MGUs to manual.
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          .
JAFNPP
,
33 (cont'd)    43 (cont'd)    .
l Scram insertion Times Scraminsertion Tar.cs The average scram inserton time, based on the de- After each refueling outage, all operable rods shall be ,
  -energ'zation of the scram pilot valve solenoids as time  scram time tested from the fully vnthdrawn position with zero, of all operable control rods in the reactor power  the nuclear system pressure above 950 poig (with operation cordtica shall be no greater thart  saturation temperature). This testing shall be completed l Control Flod  Average Scram  W to exW M m. NW d mam tirne-Notch Position Insertion Time  test % W M m.h M N k wh -  l l  Observed  (Seconds)
46  0.338 38  0.923 24  1.992      *
04  3.554
  .
        .
Amendment No.df .155


          ;
. No further operator action is taken.
      .


      .  .      -.  .        _. _ . - _ _ .
Which one of the following describes the response of feed flow and RPV level after the MGUs have been shifted to manual?
                      '
a. Flow will increase to 100%; Level will increase to 200 inches.
                        .
      .
JAFNPP 4.3.0 (cont'd)
                      '
3.3.C icont'd)
    ' The average of the scram insertion times for the three At 16iweek intervals.10 percent of the operable control -
fastest operable control rods of all groups of four control rod drives shot be scram timed above 950 peig. The some rods in a two-by-two array sheH be no greater than:  control rod dnves should not be tested each intervs i Whenever such scram time measurements are mode, an Control Rod Average Scram  evolustion she' be made to provide rossonable assurance Notch Position Insertion Time  that proper control rod drive performance is ipeang Observed (Secondal  maintaine .361 38  0.977 24  2.112 04  3.764 The maximurn scram insartion time for 90 percent All control rods shou be determned operable once every insertion of any operable control rod shall not exceed  24 months by demonstrating the scram discharge volume 7.00 se drain and vent volves operable when the scram test initiated by placing the modo switch in the SHUTDOWN position is performed as required by Table 4.1-1 and by verifying that the drain and vent volves: Close in less than 30 seconds af ter receipt of a signal for control rods to screm, and
                        , Open when the scram segnal is rese ;
  -
                    .
Amendment No. 49rG2r75, SS,165, 203; 232 on
- -___-- _ __-____ -__ . - _ - - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ - - - _ _ - - _ _ _ _ - - - _ _ _ _ - - _ - - _ _ _ _ . _ _ _ _ _      _ _ _ _ . - _ _ - - _ _ . - - _ _ _ _ . - - - _ _ . - _ _ _ _ - - . _ _ - - -


_ _ . _
b. Flow will increase to 100%; Level will remain at 185 inches.
_ _ - .  .
        . .__ . _ . . _ _ _ _
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-
E69
  .
ssss: +:+ =- -- ogg BOB
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E
      -
i: . 994
      .


c-
c. Flow will increase to greater than 100%; Level will increase to 200 inches.
      :
EEL i  z  e t  o g  Sg 009 O  w  c
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d. Flow will remain less than 100%; Level will continue to trend down.
      .c Z  g  Sm Egg S
 
f9    olG 5  d MEE8M w" E  E
Question 54     .
  ~
The SBGT system has failed to auto-start in response to a HPCI start signal. Which one of the fol! wing will occur as a result of the failure of SBGT to start?
H  s C 097 -
a. HPCI start up sequence will not complete and the HPCI turbine will not start.
  * S  $ :
 
gav @
b. The HPCI turbine will start but may trip on High Exhaust Pressure.
wW  w $$w-:: _
 
x : a 3>
c. The HPCI turbine will start but may trip on High HPCI Area Temperature.
g,
 
    #skM&-
d. HPCI flow rate will be limited due to decreased condenser efficiency.
    =- -:+,:+>: o o -
EBE J
m-  . . . :=:--. w u.d-  g g  z---. OPE $
U      0
  <  #35 51  963 g
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      -
c=:9 6 +  H
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cr  _.:. :: : -: sss:--
    -
w  n:- :- :+:+:.
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m    EI3 Z  #8Ms5sii8 m: ^~-m
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ES${5i3il!39    o o o o o o o o a o a o a o o.' . .  . . . .
b W W D L7 T T
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        ,
j (SH 'NI) HnnDVA 63SN30NO3 i


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l t
OPERATORAID NUMBER 722      0
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SENIOR REACTOR OPERATOR EXAMINATION l
    .':. .
Question 55 Which one of the following is the reason that operation of an EDG at loads near 2000 KW is to be avoided?
  . . . . .  .
 
, . v v. ... ..  *
a. Excessive wear on turbocharger drive gears.
    **l<  .. . .. . . . ::*:.  .'* .* .. . *:.
 
        *" *
b. Main bearing degradation due to inadequate lube oil cooling.
9~
 
*: . * . . . :..  . :: . :*
c. Potential Lube oil sump fire due to increased pi. ton blow by.
      *
 
      .. . *..*  *
d. O :rheating ofexhaust system.
    *
 
    .......  .. ,
Question 56 Following a LOCA with concurrent Loss of Offsite Power, which one of the following will be the first to be reenergized when the 'A' and 'C' EDG breakers close?
      *
a. 'A' ESW Pump.
        . . . .: . ::: ::::
 
,. . . ... y '...
b. 'A' RHR Pump.
  .
 
    ..
c. 'C' RHR Pump, d. 'A' Core Spray Pump.
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Page 28 of 50
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SENIOR REACTOR OPERATOR EXAMINATION
O
 
      .
Question 57 The operator withdraws a control rod one notch but the rod position indications show that the !
N,
rod is withdrawing continuously until it reaches full out position. Which one of the ,
        . .
following could be the cause of this?
  .    .
a. Stuck collet piston.
  ..  . ..
 
.
b. High CRDH pressure.
, , . , .,,..., , . ., . , .  ... .
 
        *, ., f
c. Uncoupled rod.
        ..
 
  **   * .j ." . :  l
d. Leaking HCU Scram Inlet valve (03AOV-126).
  ..
 
  . . , ,.. ..
.
    .
Question 58 Reactor power is 5%. The RWM is fully operational and has generated a Withdraw Bleck.
    *. . .. :. . . ..
 
      .
Under these conditions, which one of the following is the maximum number of rods with insert errors that could possibly be moved in the withdraw direction?
. '.
a. None.
.
 
  .,
)
  ...
b. One.
    . ,,. .
 
      .
c. Two.      .
      .
d. Three.
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  :            1 rO  ;
      '
              .
SENIOR REACTOR OPERATOR EXAMH3ATION -
CD  C  4  N  O  CD (O v,- N N  N  N  N  N  ,-  v- v-Ml3A37 US1VM SnUO1          j;
Question 59 -
The plant is operating at full power when the following Recire. Pump Seal readings are noted:'
  . #1 (inner) Seal Cavity pressure is 1000 psig.


1
. #2 (outer) Seal Cavity pressure is 150 psig.


4
Which one of the following will cause these conditions?
a. Nonnal operation of both seals.


    , . . . .  .t+=      -. % * . s., w n-
b. Failure of both seals.


ry b An RPV water levelinstrument may not be used # either of th)
.
fo#owing conditions exists:
c. Partial failure of the #1 seal.
+ An instrurnent run terrporature is at or above the RPV Saturation Temperature (Fig 4.7)
 
+ The instrument reads at or below its Meirnum Usable indcat'ng r Level (Fig 4.8)
d. Partial failure of the #2 seal.
FIGURE RPV SATURATION TEMPERATURE 800
  '
li E l!!!!
    '
    ,
      -
l C 550 -
@ , !b  -
    '
I B fij!; P*$ IIi:. !"'if Ji ' 7
  !$ [!!!!!,
$ kll!h! ! !!!ih
- ,- l n-w ;f u
  <
  ,
u s h u)
3 250 200 , , .   .
0 100 200 300 400 500 600 700 000 900 10001100 RPV PRESSURE (psig)
      .
      '
FIGURE MINIMUM USABLE INDICATING LEVELS (in.)


8- Es n E& ~.'.&
Question 60 During the startup of the 'A' Recire. Pump the following conditions exist:
q $S ad 38
  . The 'A' Recire. Pump Discharge valve is 85% open.
      $3 m:
ZC
  .8 KN E d5 WE
  }-~}- n-
  -  -
a a E SM E  180 250 B  u o 5 400  o a g
g  171 225
-  u o 46 di
.a 200 43 -145 134
$
5  - - -- -- -- -- -
5 200 b
c  16 y IN  JL 175


U _ ." _ _f _ _" _ - _ " _ _ "_
. The 'B' Recire. Pump Discharge valve is fully open.


__ . _ . _ . - ~ ._ _ .~.
. Total Feed Flow is 30%.
      .
  . Feedwater Pump 'A' is running; Feedwater Pump 'B' is secured.
      -
      .,4
=
RO ANSWER KEY
  .1): . B - 26) D 151)- D 76) D
..
2); ~A- 27) B 52) -C- 77) - D 3)- B 28)- B 53) B_ 78)_ D 4)- B- 29)- 'C 54) C- 79) -A '
5) -D 30) -A 55) A 80) -A 6)' D 31) DELETED 56) _A 81) C 7): B 32) B 57)_ A- 82) C 8): C 33) D 58) D 83) B 9) DB 34) D 59)- D 84) B 10)- A 35) C 60) D 85)- A 11)- -C 36) B 61) A OR B 86) D 12) -A 37) ) A'- 87) B 13) _B 38) C 63) B 88) B 14) A 39) C 64) A 89) C 15) 'C 40) A 65) C 90) C 16). A 41) C 66)- C 91) C 17) B 42) D 67) C 92) B 18) A 43)_ D 68). A 93) C 19)- B 44) DA 69) B 94) D 20) B- 45) D 70) D 95) C 21) D 46) B 71) A 96) C- t 22) D 47) C 72) D 97) A 23) D 48) C 73) C 98) A 24) D 49) B 74) C 99) B
"
25) A 50) A 75) D 100) B
.
.


ATTACHMENT 2 RO EXAMINATION AND ANSWER KEY
. RPV level is 195 inches.


ATTACHMENT 3 JAF COMMEftrS ON WRITTEN EXAMINATION
Which one of the following describes the most restrictive Recire. Pump speed limitations currently in effect?
a. Both pumps are limited to 30%.
b. Both pumps are limited to 44%.
c. Pump 'A' is limited to 30%; 'B' is not limited.


l l
d. Pump 'A' is limited to 30%; 'B' is limited to 44%.
Page 30 of 50
  * * * * * EXAMINATION CONTINUED ON NEXT PAGE * * * * *


    - -  -. - . .~ .
SENIOR REACTOR OPERATOR EXAMINATION Question 61 The drive mechanism of a fully withdrawn control rod is uncoupled. Which one of the following indications during the coupling check indicates thu the rod is uncoupled?
w ,- ,.
a. Individual Rod Drift Alarm.
        :
~
RO 009
  -:SRO 909 During the post-examination review, it was discovered that the key contained an incorrect
  - answer, D vice the correct answer, B. This was a typographical error that occurred while -  t
        *
balancing the examination distractors. The first submittal (attached) indicated the answer  '
correctly. -
  .
        :
        '
Distractor A is incorrect because the red light on indicates that the pilot solenoid is energized, not that the main valve is ope ;
    '
Distractor C is incorrect because the SRV. tailpiece would rise to approximately 380
  - degrees if the valve were ope 'i Distractor D is incorrect because the EPIC alarm RESET condition indicates that the high noise level condition associated with an open SRV has cleared.-    !
The key was changed from D to B to correct this error.


,.
b. Individual Rod Overtravel Alarm.
        .
k b
i
.A ~
y- y eew-+ y - p y- y -,..e , .-- sg .,m4ee 3 , . ei--- .' m g    .
      ,
      . . ~ ,- . .nw _
          +- -
S .*  [O r
  \f +
  ,
    '
      ,
      .r'  i
          '
010h iTIER I?  LOROUP 1/1 LICENSE LEVEL RST KNOWLEDGE LEVEL Li LANSWER A i
.
Which one of the following would give pusitive indication that an SRV is currently open as a result of sn a~utomatie :
_
          :
  . actuation caused byhigh RPV pressure?/      1
    , .
      ~
4 a.: [ White acoustic monitor light is o . _  .
          ,
_ ,;  ,
      ,
          '
T '  ib? i Tailpiece temperature is 235 'F, ;    i
  : cc Tailpiece temperature is ? 10 *F. .    .
*
.j idp red valve open light is on.-      ,
  , 295025'  HIGH REACTOR PRESSUR A.03
  " Ability 1o identify postfaccident instrumentatio ~
          .
IMPORTANCE 3.5/3.8 !  ;10CFR55.4l(6)/()--  10CFR55.43()/()~ SOURCE


  '10CFR$$ REASON
c. '49' will be displayed in the rod position window.
          ,
 
REFERENCE:  SDLP-168, Page 40; ATTACHMENTl  *'
d. Individual Rod Full Out light remains energized.
          .
 
        '-
Question 62 Three of the eight LPRM detectors supplying an RBM channel have failed downscale. ~
SDLP16B    OBJECTIVE- 1.01
Which one of the following describes the response, if any, of the RBM to these failures?
,
a. There will be no functional effect since the RBM still has sufficient LPRM inputs to function.
  [l LESSON PLAN e
 
,
b. The' rod block setpoint will be automatically adjusted downward to compensate for the lost inputs.
" 6  3    ' NOTES
'


CHANGES FROM ORIGINAL OUTLINE
c. An Inop. Rod Block will be generated until one detector is bypassed.
_ .
ORIGINAL SYSTE61/ EVENT #    ORIGINAL K/A#
REASON FOR CHANGE        ,
          ,'
  '
, - KNOW1. EDGE LEVE' - t,= Lower (Recall) - H= Higher - LICENSE LEVEL R=RO S=SRO RS=Both
  : SOURCE N=New Quesnon -, B-Exam Bank (Not seen before) . S-Bank (Seen in training program) M-Modified
  ; 10CF'R55 listings are the sub-paragraph numbers under t 0CFR 55.4! (for ROs) or 55.43 (for SROs) addressed by this question, y  10CFR55 reference is listed as (Assigned by K/A Manual) / (Assigned by question author)
  : Group and imponance are listed as RO/SRO values
'. :-
    *
  ,-_  ,
      ..
g.'. .
<
s zg .- 1. #  ..
    .-
a
    ~~
y .
L2 ~ - 1


o- .
d. A Rod Block will be generated until the PUSH TO SETUP pushbutton has been depressed.
RO 031 SRO O31 This question was deleted from the examination. During the post-examination review it was determined that the question had no correct answer. The limits stated form an envelope that bounds the operation of the system and no direction exists to violate one limit at the expense of another, a. OP 20, STANDBY GAS TREATMENT SYSTEM, directs: IF reactor building difTerential pressure is less negative than -0.25 inches water, TIIEN ensure that SGT Train A (B) is in service per Subsection D.l(2).' No direction is given allowing this limit to be violated to meet other limits, b. OP-20, STANDBY GAS TREATMENT SYSTEM, directs if the high temperature annunciator is received then the affected train is shutdown and cooling flow for the charcoal filters established using the other train.2 No direction is given allowing this limit to be violated to meet other limits, c. OP-20, STANDBY GAS TREATMENT SYSTEM, directs: Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01 125FI 106A(B).3 No direction is given allowing this limit to be violated to meet other limit '
OP-20, STANDBY GAS TREATMENT SYSTEM, revision 22, steps D.I.6 on pg. I 1, D.2.6 on pg.13, G.5.2 on pg. 28 and G.6.2 on pg. 2 #
OP-20, STANDBY G AS TREATMENT SYSTEM, revision 22, steps G.I.4 on pg. 20 and 0.2.4 on p ,


OP-20, STANDBY G AS TREATMENT SYSTEM, revision 22, steps D.I.S.b on pg.11, D.2.5.b on p , G 5.3 on pg. 28 and G.6.3 on pg. 2 . .    '
I Page 31 of 50
    .
  *"" EXAMINATION CONTINUED ON NEXT PAGE "*"


..
ARP 09-75 2-16
,
ANNUNCIATOR SGT SYS B ucENo .CT CaiR' .,
TEMP-CONTROLLED COPY
      =
SENSOR / 01 125TS 128 SGT FILTER TRAIN "B" CHARC0AL FILTER TEMP !
       '
       '
TRIP POINT- SWITCH (170*F)
SENIOR REACTOR OPERATOR EXAMINATION Question 63 Which one of the following describes the effect of spraying the Dywell during a LOCA when Drywell pressure is below 2.7 psig?
a. Unnecessary damage to equipment in the Drywell.
 
b. Partial de-inerting of the Primary Containment.


CAUSE Heat from decay of fission products adsorbed by charcoal-filter AUTOMATIC None ACTION
c. Inability to vent the Primary Containment.
        ,
OPERATOR Refer to OP 20, Standby Cas Treatment System,
. ACTION  section G for actione to be take I
_
b
:
i
        !
Rev N PORC Meeting No, 90-088
:- Date 08/29/90  Page 1 of 1 A


m  . .-.
d. Mechanical failure of the Torus to Drywell vacuum breakers.
j' '


B
Question 64 The operators are unable to reset an inadvertent Group I isolation signa). Which one of the following conditions, ifit existed, would cause this problem?
  . _ .
a. A control switch for one of the MSIVs is in the OPEN position.
cj "
.
ARP 09-75-1-16 i
        ,
t ANNUNCIATOR > SCT SYS A'
  . LEGEND'  ACT CHAR TEMP    l HI
        .t r
SENSOR /  01-125TS 12A SGT FILTER TRAIN "A" CHARCOAL FILTER TEMP -
TRIP POINT SWITCH (170'F)
Cyron1 ID COPY cal'SE  Heat from decay of fission products adsorbed by charcoal filter _,
        {
s AUTOMATIC- -None ACTION :
        ;
_
OPERATOR Refer to OP 20, Standby Gas Treats.ent System, ;
; -ACTION  section G for actions.to be take ;
l
-
        ,
:
-
t


        ,
b. The Reactor Mode Switch is in RUN.   ;
  :i
c. The control switches for the Main Steam Line Drain valves are in the OPEN position.
..
Rev. No.- 'A'  PORC Meeting No. 90-088-I Date 08/29/90    Page 1 of 1
-
    - i
  .~
r


..,, .
d. The AP across the MSIVs is 125 psid. l i
.
Page 32 of 50
.
  '"" EXAMINATION CONTINUED ON NEXT PAGE "*"
NEW YORK POWER. AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLMIT OPERATING PROCEDURE STANDBY GAS TREATHENT SYSTEM *
 
OP-20 REVISION 22 REVIEWED BY: PLANT OPERATING REVIEW COMMITTEE NA  DATE NA MEETING N APPROVED BY:  -  DATE /2[h RESPON$.)BLE P'ROCE OWNER APPROVED BY: k  -  DATE 1Vb
    .
      '[
SENIOR REACTOR OPEl% TOR EXAMINATION Question 65 During plant operation it is noted that 345 kV bus voltage is 380 kV. Which one of the following is the appropriate response, if any, to this condition? .
P % MANAGER
a. No response required.
'
 
EFFECTIVE DATE: Decanber 4,1996 FIRST ISSUE D  FULL REVISION O LIMITED REVISION E
b. Reduce generator output voltage to restore 345 kV bus voltage to normal.
*************************, *************************
 
  * * *
c. Contact the Load Dispatch Center and request that 345 kV bus voltage be reduced.
*
  * *
* REFERENCE USE
  .
tyN G O L,TS OLLED.*
*  *
**.*******.*.***.**.. ...  .
    "
COPY * g. * * * * * . * * *
*************************  CHANGES
*  *
* TECHNICAL * NOT UpOATED gjyH TEMPORAR USE ONLY
  *
*  REFERENC
*************************
l PERIODIC REVIEW DUE DATE 2/13/98
  .
i i


  ,  - . .  . . .
d. Increase Naerator Isolated Phase Cooling to maximum.
_-. - -.
        *
        .
        -4 STANDBY GAS TREATMENT SYSTEM *  -OP-20  *
    .
        '
REVISION fiUMMARY SHEET'
REV. N CHANGE AND REASON FOR CHANGE 22 Added Precaution C.2.1 to require Reactor Building Ventilation be isolated before performing any of the following-activities. This action is necessary (  -to comply with the requirements of safety evaluation JAF-SE-96-071:
-
  * Fuel handling
  * Core alterations
        '
  * Movement of heavy loads over the spent fuel pool or open reactor cavity
  * Placing RX MODE switch in START & HOT STBY, witb.out Primary Containment Integrity in effect
"
21 1. Added Subsections G.8 and G.9 to provide guidance for operativn of the Standby Gas
,  Treatment System during filter testin .
.
2. Added subsection G 10 to provide guidance for operation of the Standby Gas Treatment System during filter samplin (PCR dated 3/26/96)
20 1. Added Subsection G.7, to provide steps for operating SBGT when secondary containment penetrations are opened or degraded per PCR #10 dated 10/25/9 . Changed description of activated charcoal in


Section B, System Description per PCR #9 dated 7/10/9 ... Revised Precaution C.2.2 to include time limits per PCR #8 dated 7/10/95 and J. Dunha ,
.
    *
Question 66 The following sequence of events occurs:
.         :
. 600 VAC power is lost for 3 minutes.
        )
 
,
. After 600 VAC power is restored,125 VDC power is briefly lost.
    ,   ( !
 
  ,     !
. 125 VDC power is then restored.
l Rev. No. - 22  Page 2 of 45
 
_ - _ _ _ - . _ _ -. _ . , . . _ _
After restoration of 125 VDC power, which one of the following will be the source, if any, of 120 VAC UPS Instrument Power?
a. Nothing,120 VAC will be deenergized. j l
b. 600 VAC via the UPS MG Set. I c. 600 VAC via the 600/120 VAC transformer. j d. 125 VDC via the UPS MG Set.


      ,    -, .. .
?, ;- ,
  ,
  -
          ,
F i
.$'
*
  . STANDBY, GAS TREATMENT SYSTEM *f      OP- 2 0 --
          '
          ,
I- 4 :-  .
TABLE'OF CONTENTS-
          '
SECTION'      PAGE A.- . REQUIREMENTS . . . - . '. . . .- . .. . ..: . - . . . - . . - . .- . . = . - -:- . 4 SYSTEM DESCRIPTIONz,  . . . . .:=.. . . . .. . .. . .
        -
        .=, . . 5
  :C.; PLANT-OPERATING REQUIREMENTS .  . . .. . . .- . . ... .  .7'
' STARTUP-      ..' '
  . - . _ . . - . _ . . . .. . .. .. . . .' . . . . . .
_ NO'RMAL OPERATION .  -
    . . . . - . . . -. . . . . . - . . . . . . .
    -
14 _ SHUTDOW .- -. . . . . . = . . . , , . . .  .c... -
        . . . . . . .. 16 _
  [Gl SPECIAL. PROCEDURES . . . . .. . . . . . _. . . . . . _ . . . 19-
          ,
  ' ATTACitMENTS . _ . _ . . .-'. . .. . . . .. : .. . . . . .' . . . 36 1.- REFERENCES . . . . . .:. . . . . . . . . . . . . . .  -37
  - TABLE 1 - VALVE LINEUP  . - . . . . . . . . . . . . . . 38 .
          -y
, TABLE 2 - MAJOR COMPONENT POWER SUPPLIES  . . . . . . . 4 !
. t:-
,
          ,
          -f
:
.
.
:
Page 33 of 50
          .
  ***** EXAMINATION CONTINUED ON NEXT PAGE *****
  .
 
F
      .
SENIOR REACTOR OPERATOR EXAMINATION ~
Question 67 Loss of all 125 VDC power would have which one of the following effects on the Emergen;y Diesel Generators?
a. Diesels would auto-start and load.


.g^
b. Diesels would auto-start, but would not auto load.
>
z - -      -
  .
I-Rev. N :    Page =3 _ of _ 45 . >


    . . ~ . . .-  . .. . - . . . . - - . . -
c. Diesels would not start and could not be started at the Engine Control Panel.
, .. - .-  .. .  . .
--l p;. : . s
        ,
T r.,
      '
        ,!
3  :1:      ,
      ~
N-- 1
  ,
STANDBYcGASJTREATMENT--SYSTEM *-  OP-20 ,
      -
  ..        !
.
,-
-{~
  ,
Al : REQUIREMENTS    a
        :}
  ' A.1:. -- Technica1L Specifications
  -
        ,
t t
  ' Volume-1A Sections.3,7.B, 3.7,C and 4.7.C-:
    .
        .
  -Volume 1B Section'3.O'-    :
s


  - A .- 2 ' Comunitments ' -
d. Diesels would not auto-start but could be staned at the Engine Control Panel.
        ,
Non .


"'
Question 68 Which one of the following describes the effect of the Control Room Inlet Radiation Monitor channel failing upscale?
  '
a. Alarm only.
A.31. Validation i
yValidated:per ODSO-35,    ,
        !
,        ,
        *
a V
s. l
        !
      ,
'
.
,
        ,
,
  .:
  ,
        %
>
        ,
b T
t
:
3 -' 4
.
- - -s .
;
        ,
  ' Rev. ;,No ., 22  Page 4 of- 45~
.  .. . . .. .  . . .


,  - - .- -  -. . _ _ . . - .. --
b. The Intake and Exhaust dampers close and the Recire, damper opens.
-STANDBY GAS TREATMENT SYSTEM * -    OP-20
, _ SYSTEM DESCRIPTION-
    -
The Standby: Gas Treatment 1 System. includes two identical-filter trains. Each filter train is a full _ capacity system thet has the ability to maintain reactor building to atmosphere differential' pressure more negative than negative 0.25 inches water gaug ~Each filter train includes the following:-
  -* Decister: Removes entrained moisture, and in conjunction with the air heater, maintains humidity less than 70% at the inlet to the charcoal filte ;
  * 39 KW Electric Air Heater: Maintains humidity less than 70% at the inlet to the charcoal-filte '
  * Prefilter: Removes particle * High Efficiency Particulate Absolute Pre-Filter (HEPA) :
Designed to be capable of removing at least 99.97% of the O'.3 micron particles which impinge on the filter, however i
credit is only taken for 90% removal capabilit e Activated Charcoal Filter: Removes in excess of 95% of the iodine in the air stream, with 10% of the iodine in the form of methyl iodide, with air entering the charcoal
-  filter at less than 70% humidity. Charcoal filter material is iodide or TEDA impregnated activated carbo * High Efficiency Particulate Absolute After-Filter (HEPA) :
Designed to be capable of removing at least 99.97% of the 0.3 micron particles which impinge on the filter, however credit is only taken for 90% removal capability.
:  * Fan: Provides the differential pressure to draw gases through-the train for treatment. The fan discharges to the stac :
    .
i
_R e v .J N o .1 '22  Page 5 of- 45 l-
- _ , .- _
  ,


.
c. The Control Room Supply fans trip and the Exhaust Damper closes.
      *
      .
      -.
STANDBY EJsS' TREATMENT SYSTEM *  OF-20 Each filter; train can take suction from one or more of the
'following suction supplies:
  -
-* Reactor BuildingLabove-369' elevation
*-Reactor Building'below 369' elevation
*LDrywell vent connections
* Torus vent connections
  '
'
* HPCI gland seal exhauster
* Main Steam Leakage Collection. System
* Auxiliary Gas Treatment System  t Standby gas treatment trains are cross-tied at the fan suctions to allow drawing cool air over the charcoal-filter-of the inactive train to remove decay hea The Standby Gas Treatment System auto-in:tiates when any of the following conditions occur:
*LReactor Building Ventilation above 369' elevation exhaust duct radiation high-high .PCIS logic A sensors start A train; PCIS logic B sensors start B train
,
* Reactor Building Ventilation below 369' elevation exhaust duct radiation nigh-high: PCIS logic A sensors start A train; PCIS logic B sensors stTrt B train
* Drywell pressure high (2.7 psig increasing) : Both trains star * RPV water level low (177 inches decreasing) : PCIS logic A sensors start'A train; PCIS logic.B sensors-start B train
#
-* HPCI auto-initiation: Both trains start The Standby Gas Treatment' system can-be manually placed in service from panel 09-75 in the Control' Roo .


      !
d. The Emergency Supply fan starts and the Inlet filter system is placed in sen' ice.
  .
  .
Rev. N ,
Page 6 of 45 ,
    ~ . - - .  .


-- _ . __ _ _ _ _ _ _ _. _ _  _. __
_
'
Page 34 of 50
,
  "*** EXAMINATION CONTINUED ON NEXT PAGE *****
STANDBY: GAS TREATMENT SYSTEM *   OP-20- PLANT OPERATING REQUIREMENTS C.1- Prerequisites-C.1.1- Syetem valves are lined up per Attachment 2, with  .
 
exceptions approved by the Shift Manage ;
SENIOR REACTOR OPERATOR EX AMINATION Question 69 Which one of the following describes a potential path for radioactive contamination to the discharge canal during nonnal power operation?
C.1.2- System power supplies are lined up per .
a. Drywell Air Cooler tube leak.
        ,
Attachment 3, with exceptions approved by the Shift- -
Manage The following systems are in operation per their
'
C. respective operating procedure, with exceptions-
.
approved by the Shift Manager
  * 4160 V and 600 V Normal And Emergency AC Power  ..-
Distribution per OP-46A
  * Process Radiation Monitoring System per OP-31  ,
  * Fire Protection System per OP-?. ,
.
.:


    .
b. . RBCL C Heat Exchanger tube leak.
  .
'Rev.'' Page 7 of 45
-    . - . _ - _ _ _ _ _ _


  -- .-. . -. .. _. ._ . .
c. Recombiner condenser tube leak.
      '
      .
    .
STANDBY GAS TREATMENT SYSTEM *  OP-20 Precautions C.2.1- Reactor-building ventilation _shall be isolated before performing any of-the following activitie This action is necessary to comply with the requirements of safetyLevaluation JAF-SE-96-071:
  * Puel handling
  * Core alterations
  * Movement of heavy loads over the spent fuel pool or open reactor cavity
  * Placing RX MODE switch in START & HOT STBY, without Primary Containment Integrity in effect C. During normal operation, 27MOV-120 (containment exhaust to standby gas treatment isol valve) shall remain closed when primary containment is required per Tech Spec 4.7. C. Operating a SGT train with the charcoal filters installed to vent paint fumes, welding fumes, or smoke could damage the charcoal filter. Guidelines to prevent possible charcoal filter damage from paint fumes are as follows:
  * Painting shall stop during periods of SGT operatio * Painting shall stop whenever Reactor Building Ventilation is isolated, unless SGT will not be required for 24 hours following the completion of paintin * SGT should not be run for at least 30 minutes following the completion of paintin * :If a SGT run is desired within 8 hours following
  . painting, Reactor Building Ventilation should not be isolated until the end of the SGT ru * SGT runs are kept as short as possible within 8 hours following paintin C. To prevent plugging of the spray nozzles from debrir caused by rust or corrosion, the fire protection water supply spray header between 76FCV-107A/B and the spray nozzles shall be drained following-system actuatio ,
.Rev..N Page 8 of 45


  . _ . _ .  ._  . . . . .
d. Main Condenser tube leak.
T 4
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  : STANDBY GASJTREATMENT: SYSTEM *  * -
          ; OP-20:  --
          -,,
      ,
          '
  '
! y 0. '''. ._ ..STARTUP:        .
s TABLE OF CONTENTS
  < SHPSECTION  _
PAgg D ; 1'- Train:A Startup'- .- .- -. :. . ._ . .. . ..' . _ . .-.--:.- . . . . 10;
          '
  - D.2- Train 3"Startup  . . . _ . . . . . . . -. .. ,_ . . . .. . .
        -


_
l Question 70 Which one of the following describes the response of any TIP detector not in its shield when a Group I and Group 11 Containment Isolation Signal occurs?
            ,
a. A Group I Isolation will cause the TIP to withdraw to th: Lead Shield position. A Group II has no further effect.
w
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Rev . E No .~ . -22-    Page 9 of 45 L
          --


. . _ . - - _ . _. __._. . . _ . _ _ _ _ . . _ . _ . _ . _ _ _ _ . _ . _ _ _ _ _ . _ _
b. A Group I Isolation will cause the TIP to withdraw to the Lead Shield position. A Group II will activate the shear valve if the TIP is still inserted. j
      !
c. A Group I Isolation will have no effect. A Group II Isolation will actuate the shear valve if the TIP is not withdrawn within 10 minutes.


t STANDBY GAC TREATMENT SYSTEM *      OP-20 l
d. A Group I Isolation will have no effect. A Group II Isolation will cause the TIP to ;
          !
be withdrawn to the Lead Shield position. l l
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Page 35 of 50
D1 Train A Startup        *
   ""* EXAMINATION CONTINUED ON NEXT PAGE ""*
          -
 
i CAUTION operating a standby gas treatment train with-the charcoal    ,
    .
;  filters installed to vent paint fumes, welding fumes, or smoke    '
      '
could damage the charcoal filter. See Precaution C. !
SENIOR REACTOR OPERATOR EXAMINATION
!          !
_ Question 71 The crew is conducting EOP-5 (Secondary Containment Control) when Reactor Building ventilation isolates on high radiation. The radiation level is subsequently seen tc decrease below the isolation setpoint. Which one of the following describes under what condition, if any, it is permissible to override the high radiation isolation to restart the Reactor Building ventilation system?
D. Ensure open at least one of the following valves    l
a. It is not permissible.
,
 
;   * ABOVE EL 369' SUCT 01-125MOV-11 J  * BELOW EL 363' SUCT 01-125MOV-12      ;
b. Two Reactor Building area temperatures are above maximum normal.
t
 
. D. Ensure open TRAIN A INLET t -125MOV-14 l D. Verify the following:      .
c. After it is confirmed that no primary system is discharging into the Reactor Building.
          '
CommentDt    Status
  * TRAIN A FN 01-125FN-1A    Running l
;
  * FN DISCH 01-125MOV-15A    Open
  * TRAIN A CLG VLV 01-125MOV-100A    Closed
  * Red light for AIR HTR 01-125E-5A    On i
D. F standby gas treatment is being placed in r,ervice to support any of the following:      i
*
  * Torus venting
          *
,
  * Drywell venting
  * HPCI operation
  ?
  * Main Steam Leakage Collection System operation
,
  * Auxiliary Gas Treatment System operation THEN ensure required standby gas treatment suction
,
"
valves are lined up per the applicable procedure prior to proceeding to Step D. i-i
          !
  .
Rev. N Page 10 of 45
      , _ - - - - - . - - - - .. . -,--.. -- -.-


STANDBY GAS TREATMENT SYSTEM 8  OP-20 D.1.5- IF SGT Train B is shutdown, TMEN perform the followings a. Verif> open TRAIN B CLG VLV 01-125MOV-100 NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2A (SGT f an A suct isol valve) .
d. If Reactor Building AP cannot be maintained at a negative pressure with SBGT.
b. Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125F1-106 D. IF RB DIFF PRESS 01-125DPI-100A or B indicates-less negative than.- 0.25 inches water, TMEN ensure SGT Train-B is in service per Subsection a
.
  . _
Rev. No. _ L
. Pag of' 45


STANDBY GAS TREATMENT SYSTEM *  OP-20 Train D Startup CAUTIO:4 operating a standby gas treatment train with the charcoal filters installed to vent paint fumes, welding fumes, or smoke could damage the charcoal filter. See Precaution c. D. Ensure open at ler.st one ot the following valves:
Question 72 While conducting EOP-2 the operators discover that a required action cannot be accomplished. Which one of the following is the appropriate response to this event?
  * ABOVE EL 369' SUCT 01-125MOV-11
a. Continue to the next step irrespective of the type of step it was.
  * BELOW EL 369' SUCT 01-125MOV-12 D. Ensure open TRAIN B INLET 01-125MOV-14 D. Verify the follt) wing:
Comoonent  Status
* TRAIN B FN 01-125FN-1B  Running
* FN DISCH 01-125MOV-15B  Open
* TRAIN B CLG VLV 01-125MOV-100B Closed
* Red light for AIR HTR 01-125E-5B On D. IF standby gas treatment is being placed in service to support any of the following:
* Torus venting
* Drywell venting
* HPCI operation
* Main Steam Leakage Collection System operation
* Auxiliary Gas Treatment System operation THEN ensure required standby gas treatment suction valves are lined up per the applicable procedure pri1r to proceeding to Step D. '
  .
  .
Rev. N Page 12 of 45


i
b. Wait until the step can be accomplished before continuing.
.             !
 
              ;
c. Continue to the next step only ifit was a concurrent action step. I d. The decision to continue or wait is only at the discretion of the SM.
    -
 
i
Page 36 of 50
              !
  ***** EXAMINATION CONTINUED ON NEXT PAGE *****
STANDBY GAS TREA1HENT SYSTEM *         OP-20_  j
 
              ;
SENIOR REACTOR OPERATOR EXAMINATION Q .;stion 73 The reactor is operating at full power when the following events occur:
            ..  ,
. The Turbine Control Valves close.   .
  --
  . The Turbine Bypass Valves fully open.
      .
 
              !
. The Reactor Scrams.
,
 
D. IF SGT Train A is shutdown,          l
. The SRVs open briefly.
"
 
TREN perform the following:-          l
Which one of the following could have caused this chain of events?
  - .           i a.= Verify open TRAIN A CLG VLV 01-125MOV-100A, NOTE: SGT flow rate is adjusted by throttling        '
a. Turbine Load Reference signal has failed downscale.
              ,
 
01-125SGT-2B (SGT fan B suct isol valve).
b. The MSIVs have closed.
 
c. The Backup (B) Pressure Regulator has failed low.
 
d. The Maximum Combined Flow Limiter has failed downscale.


b.. Ensure flow rate is 3000 to 6000 scfm        i on SGT FLOW 01-125FI-106 l
              :
D. IF RB DIFF PRESS 01-125DPI-100A or_B indicates        l
              '
1ess negative than - 0.25 inches water,-        ;
TEEN. ensure SGT Train A is in service per        l Subsection }
f t
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Rev'. N ,
Page - 13  of  -45
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9- e -7,= y w- *p--r > w wa ,e W-Twr gmq v--w-s ivm y - tg - p t wry m -e, ,(v9+- y y- g r, p ?w e t-g tve g i PHy- gg wa-atr N *e-+zT *t mey tw W <- "v We1
Question 74 The reactor has recently scrammed and the MSIVs are closed. HPCI is maintaining RPV level and pressure. Torus Cooling is not available and Primary Containment Pressure is rising. Which one of the following describes the appropriate considerations if Primary Containment venting becomes necessary?
a. Venting via the Torus will not keep up with decay heat production but will minimize the rate of radioactivity release.


'
]
      .
b. Venting via the Torus will keep up with decay heat production and will minimize the rate of radioactivity release.
l STANDBY GAS TREATMENT SYSTEM *    OP-20 i i
 
      !
c. Venting via the Drywell will not keep up with decsy heat but will minimize the rate of radioactivity release.
      , NORMAL OPERATION    l l The Standby Gas Treatment = System is normally maintained in  i the following standby lineup    l
* Valves lined up per Attachment 2 -
i
* Component power supplies lined up per Attachment 3  i
* Panel 09-75 indications and controls as follows:
Valves Common To Both SGT Trains Component    Status ABOVE EL 369' SUCT 01-125MOV-11 . . . . . . . . . Closed BELOW EL 369' SUCT 01-125MOV-12 . . . . . . . . . Closed Train A Standby Lineurg Component    S.L41.uA AIR HTR 01-12SE-5A . . . . . White light on, red light off HPCI GLMiD SEAL SUCT 01-125MOV-13A .  . . . . . . . Closed
;.
TRAIN A CLG VLV 01-125MOV-100A . . . . . . . . . . . Open TRAIN A INLET 01-125MOV-14A . . . . . . . . . . . Closed FN DISCH 01-125MOV-15A . . . . . . .. . . . . . . Closed TRAIN A-FN 01-125FN-1A . . . . . . . . . . . . . Shutdown Train B Standby Lineun J Comoonent    Statug AIR HTR 01-125E-5B . . . . . White light on, red-light off HPCI GLAND SEAL CUCT 01-125MOV-13B .  . . . . . . . Closed-TRAIN B CLG:VLV 01-125MOV-100B . . . . . . . . . . . . -Open TRAIN B' INLET 01-125MOV-14B- '
    . . . .- . . . . . . . Closed FN DISCH 01-125MOV-15B . . . . . . . . . . . . . . . Closed
-
.
TRAIN B FN 01-12bFN-1B . . . . . . . . .. . _ . . Shutdown
  ,Section ( E continued on next page)
Rev. Nos 22  Page- 14 'of 4 5__


      '
d. Venring via the Drywell will keep up with decay heat production and will j minimize the rate of radioactivity release. l
      .
      !
STANDBY GAS TREATMENT SYSTEM * *
J Page 37 of 50
OP-20 (Cont) Whenever standby gas treatment is in service, monitor the following parameters per ODSo-17:
  ***** EXAMINATION CONTINUED ON NEXT PAGE * ****
* Profilter differential pressures maximum 0.75 inches water gauge on 01-125DPIS-1A(B)
l l
* HEPA filter differential pressures maximum 1.5 inches water gauge on 01-125DPIS-2A(B)  ,
      ,
* Carbon filter differential pressures n.aximum 1.5 inches water gauge on 01-125DPIS-3A(B)
* After filter differential pressures maximum 1.5 inches water gauge'on 01-125DPIS-4A(B)
* SGT flow on 01-125FI-106B: 3000 to 6000 scfm
.
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Rev. No.- 22  Page is of' 45


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SENIOR REACTOR OPERATOR EXAMINATION Question 75 A scram has occurred due to a transient resulting from a loss of UPS. Not all rods have fully inserted. Which one of the folicwmg should be used to evaluate reactor power to determine if entry into EOP-2 (RPV Cor. trol) is required?    !
*A      j
a. APRM chart recorders.
  ; - -;
    .
(l. <      j STANDBY GASLTREATMENT SYSTEM 4  OP-20 '
        - SNUTDOWN TABLE OF CONTENTS SUBBECTION    g F.1- Train A Shutdown . . . . . . . - . . . . . . . . . . . . . . . . 17 F.2' Train BLShutdown . . . . . . . . . . . . ... . . . .. . is
        .


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b. SPDS display. I c. Steam Flow.
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  :'. R e v. M N o .: 22-  Page 16 of+ 4s-


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d. Number of open SRVs.
b'.


STANDBY GAS TREATMPNT SYSTEM 0  OP-20
l l
  .. Train A Shutdown F. Ensure SGT Train A operation is not require F. IF SGT Train B is shutdown, THEN ensure closed the following valves:
Question 76 The following conditions exist:
  * DW TORUS EXH TO SGT IDCL VLV 27MOV-121 (at panel 27PCP)
. A LOCA has occurred.
  *
DW/ TORUS EXH TO SGT ISOL VLV 27MOV-120 (at panel 27PCP)
  * HPCI GLAND SEAL SUCT 01-125MOV-13A
  * HPCI GLAND SEAL SUCT 01-125MOV-13B
  * ABOVE EL 369' SUCT 01-125MOV-11
  * DELOW EL 369' SUCT 01-125MOV-12 F. Close TRAIN A INLET 01-125MOV-14 F. Verify the following:
comoonent  Status
.  * TRAIN A FN 01-125FN-1A  Shutdown
  * FN DISCH 01-125MOV-15A  Closed
  *
TRAIN A CLG VLV 01-125MOV-100A Open
  * Red light for AIR HTR 01-125E-5A Off a White light for AIR HTR 01-125E-5A On F. IF SGT Train B is in service,
-
THEN ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106 NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2B (SGT fan B suct isol valve).


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t
The 'A' RHR is the only low pressure ECCS pump available and is injecting in LPCI mode.
  .
 
Rev. N Page 17 of __iE__
. RPV level -90 inches and is trending down slowly.


i
. Drywell temperature is 350 'F
      !
  . Drywell pressure is 65 psig.
STANDBY GAS TREATMENT SYSTEM *  OP-20 Train 3 Shutdown  *
      'l
      !
F . 2 .1' Ensure SGT Train B operation is not require j l
      '
F. IF SGT Train A is shutdown, THEN ensure closed the following valves  i
  * DW TORUS EXH TO SGT ISOL VLV 27MOV-121 1 (at panel 27PCP)
  * DW/ TORUS EXH TO SGT ISOL VLV 27MOV-120 (at panel 27PCP)
      !
  * HPCI GLAND SEAL SUCT 01-125MOV-13A
  * HPCI GLAND SEAL SUCT 01-125MOV-13B  ,
  * ABOVE EL 369' SUCT 01-125MOV-11
  * BELOW EL 369' SUCT 01-125MOV-12 F. Close TRAIN B INLET 01-125MOV-14 F. Verify the following:
ComDonent  Status !
-  * TRAIN B FN 01-125FN-1B  Shutdown i
  * FN DISCH 01-125MOV-15B  Closed
  * TRAIN B CLG VLV 01-125MOV-100B Open
  * Red light for AIR HTR 01-125E-5B Off
  * White light for AIR HTR 01-125E-5B On F. IF SGT Train A is in service,
-
TREN ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106 t NOTE: SGT flow rate is adjusted by throttling 01-125SGT*2A (SGT fan A suct isol valve) .
.
i
  .
Rev..N ,
Page 18 of 45
      .i


      *
. Torus pressure is 64 psig.
  .
STANDBY GAS TREATMENT SYSTEM *    OP-20 SPECIAL PROCEDURES    j
      '
TABLE OF CONTENTS l
SUBSECTION    PAGE j Train A Charcoal Filter Cooling . . . . . . . . . . . . 20 Train B charcoal Filter Cooling . . . . . . . . . . . . 21 i Train A Charcoal Filter Fire Protection Water Spray  . . 22 [
r Train B charcoal Filter Fire Protection Water Spray  .. . 25 G. 5' Train A Auto-Initiation Verification . . . . . . . . . . 28 ,
a Train'B Auto-Initiation Verification . . . . . . . . . . 29 Maintenance of Secondary Containment Integrity with a Degraded or Open Reactor Building Penetration . . . . 30 - SGT Train A Operation During Filter Testing . . . . . . 31 * SGT Tre.in B Operation During Filter Testing . . . . . . 33 G.10 SG'.' Train Operation During Filter Sampling . .. . . . . 35 ;
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      *
e Rev. : N ~  Page 19 of 45


      .
. Torus levelis 21 feet.
STANDBY GAS TREATMENT SYSTEM *  OPr20 Train A Charcoal Filter Cooling G. IP amber SBGT A WTR SPRAY SYS HI TEMP light is on at panel FPP, TMEN exit Subsection G.1 and proceed to Subsection G. WHILE performing the following steps, periodically monitor annunciator 09-75-1-16 SGT SYS A ACT CHAR TEMP H G. Ensure SGT Train B is in service per Subsection G .1. 4 ' IF SGT Train A is in service, TREN shutdown SGT Train A as follows:
 
a. Close TRAIN A INLET 01-125MOV-14 b. Verify the following Comoonent  SD Lyg
Which one the following dercribes the correct decision regarding Drywell and Torus spray? l l
  * TRAIN A FN-01-125FN-1A  Shutdown
a. Spray the Drywell. Do not the spray Torus.   :
  * FN DISCH.01-125MOV-15A  Closed
      !
-  * TRAIN A'CLG VLV 01-125MOV-100A Open
b. Do not the spray Drywell. Spray the Torus.
  * Red light for AIR HTR 01-125E-5A Off
 
  * White light for AIR HTR 01-125E-SA On G. Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-12SFI-106 NOTE: SGT flow rate is adjusted by throttling
c. Spray the Drywell. Spray the Torus.
,
01-125SGT-2B-(SGT fan B suct isol vs.:,ve).


  .
d. Do not spray the Drywell. Do not spray the Torus.
Rev. . No'. 22  Page 20 of 45


STANDBY GAS TREATMENT SYSTEM *  OP-20 Train B-Charcoal Filter Cooling G. IF amber SBGT B WTR SPRAY SYS HI TEMP light is on at panel FPP, THEN exit Subsection G.2 and proceed to Subsection G. WHILE performing the following steps, periodically monitor annunciator 09-75-2-16 SGT SYS B ACT CHAR TEMP H G. Ensure SGT Train A is in service per Subsection G. IF SGT Train B is in service, TREN shutdown SGT Train B as follows:
Page 38 of 50
a. Close TRAIN B INLET 01-125MOV-14 b. Verify'the following:
   ***** EXAMINATION CONTINUED ON NEXT PAGE *****
Component  Status
   * TRAIN B FN 01-125FN-1B Shutdown
  * FN DISCH 01-125MOV-158 Closed
!  * TRAIN B CLG VLV 01-125MOV-100B Open
  * Red light for AIR HTR 01-125E-5B Off
  * White light for AIR HTR 01-125E-5B On G. Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106 NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2A (SGT fan A suct isol valve).
:
  .
Rev._N Page 21 of .45


_ - _ . _ . _ _ _ _ _ _ _ _ _ _ _ . _ __ _ . _ . _ _ _ _    _ .~ _ _ . _ . . . . _ _ _ . . _ .
          .
STANDBY GAS TREATMENT SYSTEM 0      OP .10 NOTE: The amber SBGT'A WTR SPRAY _SYS HI TEMP light will come on and an alarm bell will ring at panel FPP when the temperature setpoint of the charcoal filter heat detector is reached. SGT Train A charcoal filter water spray is 4 manually actuated syste !
i G3 Train A Charcoal Filter Fire Protection Water Spray G. Shutdown SGT Train A as follows:
a. Close TRAIN A INLET 01-125MOV-14 b. Verify the following:
ComDonent    Status,
    * TRAIN A FN-01-125FN-1A  Shutdown
.
    * FN DISCH 01-125MOV-15A  Closed  ,
    * TRAIN A CLG VLV 01-12 MOV-100A  Open
    * Red light AIR HTR 01-125E-5A  Off l  G. Initiate water spray per Step a, b, or c a. To initiate water spray from panel FPP in 4    Control Room, perform the following l    1) Depress 6BGT A Spray System INIT pushbutto .
2) Verify red SBGT A WTR SPRAY SYS VLV OPEN
'
light is o b. To initiate water spray from local breakglass station, break glass or remove retainer ring from SGT Train A breakglass station and verify
,
button pops ou ..
c; To initiate water spray from flow control valv emergency release station, pull down SGT Train A    >
emergency release leve .
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Page 22- of -45
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SENIOR REACTOR OPERATOR EXAMINATION Question 77 A plant transient has caused a reactor scram followed by a prolonged SRV actuation. Current conditions are:
STANDBY GAS TREATMENT SYSTEM *     OP-20
  * All control rods are fully inserted.
 
* Reactor pressure 900 psig and rising.
 
* All SRVs are closed.
 
* Torus temperature is 160 'F.


CAUTION    4 i
* Torus levelis 1I feet.
To prevent plugging of the spray nozzles from debris caused by
  .
          ;
rust-or corrosion, the water spre" beader between 76FCV-107A    ;
and the spray nozzles shall be druined following system actuatio . NEEN train A water spray is no longer required,    j perform the following:      !
'
a. Close 76 FPS-123 (west SGT sprinkler supply gate valve).      ;
i
  -
          '
b. Drain fire protection supply header in SGT Room as follows:      ,
1) Connect hose to fire protection supply header low point drain located by charcoal filter side panel,      i
'
2) Route hose to nearest floor drai ) Open fire protection supply header drain valv t c. Drain 76FCV-107A flow control station header as
-  follows:
1) Connect hose to drain header located under flow control valv ) Route hose to nearest floor drain or suitable containe .
;  3) Open MAIN DRAIN and AUXILIARY DRAIN valve '
NOTE la Scaffolding may be necessary to reach overhead supply header drain plu NOTE 2: Supply header drain plug is located
;    approximately 20 feet above and north of-71MCC-142 and panel 66HV-3 .
d. Drain. fire, protection supply header as follows:
  '1) - Connect funnel and hose under supply header drain plu ) Route hose to nearest floor drain or suitable containe ,- 3 ) Remove,sup' ply header drain plu . _ R e v . 1N o .- 22    Page 23 of 45
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_ _ _ - - - _ . . _ . .


._ . - _ . _ . - ._ _ _ _ _ _ . . - _ _ _ _ _ _ _ . . .
Under these conditions, RPV pressure must be reduced to no more than which one of the following?
__
a. 800 psig.
      -
_ __ _ _ _
        -
        .
        .
it STANDBY GAS TREATMENT SYSTEM *  *
OP-20
  '
          !
          '
e. WREN supply header is drained, perform the following:
1) Clone SGT Room supply header drain valve and  l disconnect hos i
          ,
2) Close MAIN DRAIN and AUXILIARY DRAIN valves    i for 76FCV-107A (flow control valve) and    i disconnect hos ) Install overhead supply header drain plug    !
and disconnect funnel and hos f. Ensure _ WEST SGT TRAIN A SPRINKLER BREAK GLASS    ,
STATION 76BGS-19 retaining ring and glass cover are installe ,
g. Ensure closed emergency release lever fcr 76FCV-107 h. Depress plunger on drip check valve for 76PS-107A located by funnel to depressurize    '
  -
pressure switc ,
          ,
i. Depress RESET pushbutton at panel 76CP-107 I j. Open the priming valve for 76FCV-107A and verify
-
pressure rises on 76PI-107A i
          ,
k. WHEN pressure on 76PI-107AB is stable, close priming valve for 76FCV-107 . Crack open 76 FPS-123 and verify pressure rises on 76PI-107A m. WHEN pressure is stable on 76PI-107AA, fully open 76 FPS-12 #
n. Verify the following at panel 76CP-107At    ;
  * Red-FLOW CONTROL VALVE OPEN light is off    .
  * Red GATE VALVE OPEN light.is on o. Verify the following at panel FPP:
  * Green HDR VLV TROUBLE light is off -
  * Red VLV OPEN light is on
  * Amber SBGT A WTR SPRAY SYS HI TEMP light is of .
Rev. N Page 24' of 45
        .
< y- ,  $ - ,, . -
      --t- - - - - - - -


    .
b. 700 psig.
l OP-20
    '
STANDBY GAS TREATMENT SYSTEM *
I NOTE: The amber SBGT D WTR SPRAY SYS HI TEMP light will come on and an alarm bell will ring at panel FPP when the temperature setpoint of the charcoal filter heat detector is reached. SGT Train B charcoal filter water spray is a manually actuated syste Train B Charcoal Filter Fire Protection Water Spray G. Shutdown SGT Train B as follows:
a. Close TRAIN B INLET 01-125MOV-14 b. Verify the following:
ComDonent  Status
  * TRAIN B FN 01-125FN-1D Shutdown
  * FN DISCH 01-125MOV-15B Closed
  * TRAIN D CLG \4N 01-125MOV-100B Open
  * Red light AIR HTR 01-125E-5B Off G. Initiate water spray per Step a, b, or c:
a. To initiate water spray from panel FPP in
-  Control Room, perform the following:
1) Depress SBGT B INIT pushbutto ) Verify red SBGT B WTR SPRAY SYS VLV OPEN light is on, b. To initiate water spray from local breakglass station, break glass or remove retainer ring from SGT arain B breakglass station and verify
,
button pops out, c. To initiate water spray from flow control valve
  . emergency release station, pull down SGT Train B emergency release leve .
Rev. N Page 25 of 45


      .
c. 600 psig, d. 400 psig.
STANDDY GAS TREATMENT SYSTEM *  OP-20 CAUTION To prevent plugging of the spray nozzles from debris caused by rust or corrosion, the water spray header between 76FCV-107D and the spray nozzles shall be drained following system
-
actuatio G. WHKH train B water spray is no longer required, perform the followings a. Close 76 FPS-122 (east SGT sprinkler supply gate valve).


b. Drain fire protection suppl *, header in SGT Room as follows:
Question 'R A LOCA has occurred and the following conditions exist:
1) Connect hose to fire protection supply header low point drain located by charcoal filter side pane ) Route hose to nearest ficor drai ) Open fire protection supply header drain valv c. Drain 76FCV-107B flow control station header as
o Drywell H 2concentration is 7%.
-
. Torus H2concentration is 4%.
follows:
. Drywell 0. 2concentration is 4%.
1) Connect hose to drain header located under flow control valv ) Route hose to nearest floor drain or suitable containe ) Open MAIN DRAIN and AUXILIARY DRAIN valve ,
  . Torus 0 2concentration is 6%.
NOTE 1: Scaffolding may be necessary to reach
Which one of the following describes the Torus and Drywell flammability limits?
  -
a. Both the Torus and the Drywell are below the flammable limit. I b. The Torus is above the flammable limit and the Drywell is below the flammable limit.
overhead supply header drain plu NOTE 2: Supply header drain plug is located approximately 20 feet above and north of 71MCC-142 and panel 66HV-3 d. Drain fire protection supply header as follows:
1) Conne:t funnel and hose under supply header drain plu ) Route hose to nearest floor drain or suitable containe ,
  , 3) Remove supply header drain plu Rev. N Page 26 of 45


      -
c. The Drywell is above the flammable limit and the Torus is below the flammable limit.
STANDBY GAS TREATMENT SYSTEM *  OP-20 e. WHEN supply header is drained, perform the following:
1) Close SGT Room supply header drain valve and disconnect hos ) Close MAIN DRAIN and AUXILIARY DRAIN valves for 76FCV-107B (flow control valve) and disconnect hos ) Install overhead supply header drain plug and disconnect funnel and hos f. Ensure EAST SGT TRAIN B SPRINKLER BREAK GLASS STATION 76BGS-20 retaining ring and glass cover are installe g. Ensure closed emergency release lever for 76FCV-107 h. Depress plunger cnt drip check valve for 76PS-107E located by funnel to depressurize pressure switch, i. Depress RESET pushbutton at panel 76CP-107 j. Open the priming valve for 76FCV-107B and verify
-
pressure rises on 76PI-107B k. WHEN pressure on 76PI-107BB is stable, close priming valve for 76FCV-107 . Crack open 76 FPS-122 end verify pressure rises on 76PI-107B m. WHEN pressure is stable on 76PI-107BA, fully open 76 FPS-12 n. Verify the following at panel 76CP-107B:
  * Red FLOW CONTROL VALVE OPEN light is off
  * Red GATE VALVE OPEN light is on
      '
o. Verify the following at panel FPP: -
  *- Green HDR VLV TROUBLE light is off
  * Red VLV OPEN light is on
  * Amber SBGT B WTR SPRAY SYS HI TEMP l'ght is off
  .
R e v ... N o . 22  Page 27 of- 45
    . - . - a


. . . - -  .- . ... - . - - . . - _ - . - . - . - . - .
d. Both the Torus and the Drywell are above the flammable limit.
        - - . . . - . . . , .
 
          . t STANDBY GAS TREATMENT SYSTEM *    OP-20  t t
Page 39 of 50  l
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      '
i G:5 Train A Auto-Initiation Verification--     f
  ***** EXAMINATION CONTINUED ON NEXT PAGE *****
      .
     .
          )
      ,
G. Verify the followings    j i
i I
Comoonent    Status
    * AIR HTR 01-125E-5A  Nhite-light is on,  !
red light is.on l
    * ABOVE EL 369' SUCT 01-125MOV-11  Open f f
    * TRAIN A CLG VLV 01-125MOV-100A  Closed


    * TRAIN A INLET 01-125MOV-14A  Open
.    * FN DISCH 01-125MOV-15A    Open j
    * TRMN A FN 01-125FN-1A  Running
.
G. IF reactor building differential pressure    f is less-negative than --0.25 inches water,-    :
,
TREN ensure SGT Train B is in service per    .
Subsection !
          ,
          '
G. IF SGT Train B is shutdown, TREN ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A.
:
          '
NOTE: SGT flow rate is adjusted by throttling  l 01-125SGT-2A (SGT f an A suct isol valve) .  ,
-
-
G. IF both SGT trains are in service,
      ,
,
l
  '
      )
THEN one SGT train may be shutdown per subsection    +
      .
F.-1 or F.2, at the Shift Manager's discretion.
SENIOR REACTOR OPERATOR EXAMINATION l
Question 79      _
A large LOCA has occurred and the following conditions exist:
  . RPV pressure is 50 psig.
 
. Drywell temperature is 350 'F.
 
. Narrow Range RPV level indicates 175 inches.
 
. Refuel Zone level indicates 215 inches.


          [
. Wide Range RPV level indicates 40 inches.
  .:        I
          '!
t
          ,
          *
  .


          ;
Which one of the following is the correct RPV level?
    .
a. 215 inches.
          -
.
-
R
          !
          :
          '
.
i-          .i
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          !
  -Rev.-N Page 28 of- 45
          ;
. . . . . . . - . - - - , . a, , . . . .
        -
        . .--._--.-,;]


,
b, 175 inches.
,        !
 
        !
c. 40 inches.
l
 
<        l
d. RPV level is unknown.
'
 
STANDBY GAS TREATMENT SYSTEH*    OP-20 l
Question 80 The Appendix R Bypass Switch for 23MOV-15 (HPCI Inboard Containment Isolation) is in the BYPASS position. Which one of the following describes the effect that this will have on HPCI operation?
        *
a. 23MOV-15 will not close on low steam pressure.
        .
 
      ..
b. 23MOV-15 will not operate from panel 09-3.
l Train 3 Auto-Initiation Verification    !
 
        !
c. HPCI will not trip on high RPV water level.
G. Verify the following     l Comoonent    Status
 
    * AIR HTR 01-12SE-5B  White light is on,
d. HPCI will not auto-restart on low RPV level.
  ,    red light is on
 
    * BELOW EL 369' SUCT 01-125MOV-12  Open l
Page 40 of 50
    * TRAIN B CLG VLV 01-125MOV-100B  Closed  l
   **"* EXAMINATION CONTINUED ON NEXT PAGE ***"
    * TRAIN B INLET 01-125MOV-14B  Open ;
 
    * FN DISCH 01-125MOV-15B  Open
SENIOR REACTOR OPERATOR EXAMINATION Question 81 During refueling operations, irradiated components may be lifted with an auxiliary hoist.
    * TRAIN B FN 01-125FN-1B  Running G IF reactor building differential pressure is less negative than - 0.25 inches water,  !
 
TEEN ensure SGT Train A is in service per  ,
Which one of the following describes the required method to assure adequate water shielding -
Subsection j G. IF SGT Train A is shutdown, TEEN ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106 .
for personnel involved in this operation?
NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2B (SGT fan B suct isol valve).   ,
a. Tape markers on the hoist cable to inform the operator when to stop lifting.
G IF both SGT trains are in service, THEN one SGT train may be shutdown per Subsection F.1 or F.2, at the Shift Manager's discretio L f
 
:        !
b. A jamming device on the cable to prevent hoist movement above the safe level.
  .
        ,
    .
I-
  ~
Rev.?N Page 29 of 45
  . . - ,,-, a. .. -, . - - - - . - . .. -.-_- - -.-. . -- .----,. .'


_ _ . _ _ .___ _ _ _ _ _.-- ._ - ____ . _ .
c. A Reactor Engineer must participate in all such operations.
I J
STANDBY GAS TREATMENT SYSTEM *  OP 20 Maintenance of Secondary Containment Integrity with a
      '
Degraded or Open Reactor Building Penetration G. Place SBGT train in service per Section :
G. Isolate reactor building ventilation as follows:
a. Depress she following pushbuttons at  ['
panel 09-75:
  * RB VENT ISOL A    ,
  * RB VENT ISOL B
.
b. Verify isolation per Section G of OP-51 G. Prior to opening a secondary containment  ,
penetration notify the SM and Fire Protection Supervisor of the following:
  * Penetration identification number
  * Penetration area and elevation  I G. Establish communications between work site and control roo G. WHEN secondary containment penetration is open,  ,
verify ths following:
  * Flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A (B)
      :
  * RB DIFF PRESS 01-125DPI-100A(B) indicates  ,
GREATER THAN negative 0.25 inches water G. IF reactor building differential pressure cannot be maintained GREATER THAN negative 0.25 inches water,
?
THEN reseal secondary containment penetratio G. IF reactor building differential pressure can be maintained GREATER TRAN negative 0.25 inches water,  *
THEN restore from reactor building isolation per Section G of OP-51 G.7.8- WHEN secondary containment _ penetration is closed and maintenance is complete, restore from reactor building isolation per Section G of OP-51 n-
      \
  .
l Rev. N Page 30 of 45 3 l
  . - - , - - -  , -- .


    - -
d. A secotid SRO must be present on the Refueling Bridge.
_-
-
,
  .
          ;
        .-
          ;
*
i STANDBY GAS TREATMENT SYSTEM *    -
OP-20 ;
i SGT Train A Operation During Filter Testing      !
.          l G. Ensure open the following valves:    ,
          !
,
    * ABOVE EL 369' SUCT 01-125MOV-11    ;
    * BELOW EL 369' SUCT 01-125MOV-12    !
          (
G. Open TRAIN A INLET 01-125MOV-14 ,
0. Verify the following:      !
-
    * TRAIN A FN 01-125FN-1A is running
    * FN DISCH 01-125MOV-15A is open    l
    * TRAIN A CLG VLV 01-125MOV-100A    !
is closed      :
;.          >
,    * Red light for AIR HTR 01-125E-5A is on
          '
'
G. 'IF flow rate is not 6000 to 6100 scfm on.SGT FLOW 01-125FI-106A,    ;
THEN throttle 01-125SGT-2A to establish 6000 to 6100 scfm on SGT FLOW 01-125FI-106 . G. WHEN testing is complete, perform the followings a. Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A by throttling 01-125SGT-2 b. Close TRAIN A INLET 01-125MOV-14 ,
          ,
0. Verify the following:
3  * TRAIN A FN 01-125FN-1A is stopped
    * FN DISCH 01-125MOV-15A is closed
    * TRAIN A CLG VLV 01-125MOV-100A is open


    * - Red light for AIR-HTR 01-125E-5A is off
    * White light for AIR HTR 01-12SE-1A is on
.
.
    .
Question 82 EOP-5 (Secondary Containment Control), has been entered due to high area temperatures.
Rev. No, ,22      Page 31 of 45
- , , ,- , _ , . _ . . , . _ , _ _ , . _ _ _ - . . _ _ - . - . _ _ . _ . . _ . , -~ _.- _ , z. .. _ _ _ . - . _ _


~
Other Secondary Containment parameters also have been increasing. No primary system is currently discharging into the Secondary Containment. Which one of the following combinations of area temperatures and radiation levels require a reacter shutdown?
    .
a. SLC Pump Area - 140 *F and RWCU HX room radiation level of 1600 mR/hr.
    ,
      . l
      .
STANDBY GAS TREATMENT SYSTEM *  OP-20 G. IF testing of SGT trains is complete, THEN close the following valves:
  * ABOVE EL 369' SUCT 01-125MOV-11
  * BELOW EL 369' SUCT 01-125MOV-12
.
:
,
    \
  .
Rev. N Page 32 of 45


- . _ _ - .. . _ _ . - - . . . . - - . -  ~ . . . . .--.. . _ . _ _ . - - - . - .
b. RWCU Pump Area radiation level of 800 mR/hr and RWCU HX Room radiation level of 1200 mR/hr.
'
.
.
STANDBY GAS TREATMENT SYSTEM *      OP-20 P- sGT Train.3 Operation During Filter-Testing G. Ensure open the following valves:
ABOVE EL 369' SUCT 01-125MOV-11
'
  *
            -
            ,
  * BELOW EL 369' SUCT 01-125MOV-12 0. Open TRAIN B INLET 01-125MOV-14 l G. Vorify the following:        ,
  * TRAIN B FN 01-125FN-1B is running
  * FN DISCH 01-125MOV-15B is open
  * TRAIN B CLG VLV 01-125MOV-100B      .
is closed        ,
  * Red light for AIR HTR 01-125E-5B 1s on l
G. IF flow rate ,is not 6000 to 6100 scfm on SGT FLOW 01-125FI-106A, THEN throttle 01-125SGT-2B to establish 6000 to
. 6100 scfm on SGT FLOW 01-125FI-106 G. WHEN' testing is complete, perform the following:
a. Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A by throttling 01-125SGT-2 ;
b. Close TRAIN B INLET 01-125MOV-14 :
G. Verify the following:
  * TRAIN B FN 01-125FN-1B is stopped
  * FN DISCH 01-125MOV-15B is closed      ,
  * TRAIN B CLG VLV 01-125MOV-100B is ope .
  * Red light-for AIR HTR 01-125E-5B is off
  * White light for AIR HTR 01-125E-5B is on
  .
Rev. N . Page 33 of_ 45
.
  =  ,-..+w r -, e . . - - -.- iw... ..ww.v. -- we- -v<. ., ~,,,~-. ,m, - , ~ . -,w ~. .w,


    - _
c. RWCU HX Room temperature of 205 'F and RCIC Room Temperature is 120 'F. -
    *
d. HPCI Room temperature of 150 'F and RCIC Room temperature of 150 'F.
    .
      .
STANDDY GAS TREATMENT SYSTEM *  OP-20 G. IF testing of SGT traino is complete, THEN close the following valves:
  * ABOVE EL 369' SUCT 01-125MOV-11
  * BELOW EL 369' SUCT 01-125MOV-12
.
.
    (
  .
Rev. N Page 34 of 45


  - . . . -  - - . . - . - --- -.- .-..- -. - - - - -~.--._-._._.-.-. ~
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      :
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l
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i Page 41 of 50  j
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  "*" EXAMINATION CONTINUED ON NEXT PAGE "*"
  . STANDBY GAS TREATMENT SYSTEM *      OP-20 i l
j
G.10 NGT Train Operation During Filter Sampling      ;
 
G.1 IF SGT Train A will be sampled, THEN perform the followings
      '
          [
SENIOR REACTOR OPERATOR EXAMINATION Question 83 During normal plant operation, the SNO is injured and contaminated. The only on-shin Radiation technician and the SNO both leave site in the ambulance. The CRS is not qualified as fire brigade leader. Which one of the following describes the allowable times to restore the full shift complement?
a. Declaro SGT Train A inoperable per ODSO-3 b. Ensure SGT Train A is shutdown per Section ;
a. SNO within two hour.,; Rad Tech by end of shift.
c. Close 01-125SGT-3A (SGT train A fan 1A suct cross-tie isol-valve)..     .
 
          '
b. SNO within two hours; Rad Tech within two hours.
d. WHEN sampling of SGT Train A is complete,
 
c. SNO by end of shift; Rad Tech within two hours.   ;
d. SNO by end of shift; Rad Tech by end of shift.
 
Question 84 You are the SM and it is brought to your attention that present thermal power is 2560 MWth.
 
Which one of the following actions, if any, is required as a result of this situation?
a. No action required, this is within tolerance for full power.
 
b. Adjust power if necessary to assure that the 8-hour average is 2536 MWth or less.


perform the following:
c. Immediately reduce power to 2536 MWth or less and assure that the 8-hour average is 2536 MWth or less.
1) Open-01-125SGT-3A.-
2) IF it is desired to operate SGT Train A, THEN startup SGT Train A per Section !
          '
l    3) Consider declaring SGT Train A operable per ODSO-3 ,
G.1 IF SGT Train B will be sampled, THEN perform the following      ,
a. Declare SGT Train B inoperable per ODSO-3 l
_
b. Ensure SGT Train B is shutdown-per Section c, Close 01-125SGT-3B (SGT train B fan 1B suct cross-tie isol valve).


d. W6df sampling of SG. Train B is complete,    .
d. Commence a plant shutdown and issue a verbal report to the NRC within I hour of the discovery of the situation.
perform the.following:      i 1) Open 01-125SGT 3 ) . IF it is desired to operate'SGT Train B,
<
THEN startup_SGT Train B per Section ,
          *
,.
l    -3) Consider declaring SGT Train B operable per ODSO-3 .
          :
.l:+
      .
    .
-
Rev. No,- 22- ,
Page  35 - of 45
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    . __ __
l
o .
RO 044 SHO O44 During the post examination review,it was discovered that the key contained an incorrect answer, D vice the correct answer Distractor 11 is incorrect because an SRM reading less than 100 eps whose detector is not full in will generate a rod withdrawal bloc Distractors C arid D are incorrect because detector motion is never blocke The key was changed from D to A to correct this erro . . .
   .
   .
        --
Page 42 of 50
' *       !
  ****' EXAMINATION CONTINUED ON NEXT PAGE *****
SDLPo075    KEY AIDS
        ;
        !
l a) : Purpose - to allow the operator to    i
-'
swap recorder indication from IRH    !
to AFRH/RBH on startups or back to  ,
IRH on shutdown [
        ;
b) Positions - IRN-OFF-APRH (RBH)    ;
    (1) PBH A(B)/IRH G(D)    {
        :
    (2) All other APRH/1RH
        !
3) Bypass Switches  ,
a) Allows operator-to bypass an Inop  LOR 1.05.a. ,
        '
IRH channe LOR 1.11.b.10
-
b) . Joystick type
        ,
c) Allow bypassing only one IRH per RPS channel at a tim .,
d) One switch for Channels A. C. E    !
and G    ;
e) One switch for Channels B. D. F    i and H
        !
6. Interlocks      ;
' SRH 1) Retract Periaissive Interlock for    ;
detector withdrawa *
a) Interlock between (1) SRH Log Count-Rate (2) SRM Detector Positio .:
    (3) 1RH Range Switches    ;
  'b)71nt'orlockidoesnotstop: detector-
      <- *
jmovement. 3 c) In'terlock will cause a rod block if the following conditions are
        '
met:
        *
    (1) SRM. detector not full in And
    '(2) SRM. count rate <100 cp k  d) Interlock.is bypassed when: . . ~ -  . , _ . _ . . _ , - _ - . _ - __...~.c_ . . - -


,    . . . . . - -
SENIOR REACTOR OPERATOR EXAMINATION   j
_
. .. ; W ,-
,  ANNUNCIATOR- ROD    ARP 09-5-2-2
:; = LEGEND- WITHDRAWAL z
BLOCK
        ;
'['
es
  . DEVIC NA-    4
  .SETPOINTL NA-      ;
        >
ggferencer ESK-10P, l'.84-101 CAUSES
        ,
elAny Reactor Mode Switch positions-APRM high' flux
  - APRM inoperative-
        '
  - :RBM high: flux (if reactor. power is above 30%)
    -
  - RBM inoperative (if reactor power is above 30%)  .
-
t-Recirc-Flow Comparator trip
  - Recirc Flow Converter upscale or inoperative  .
d
  -- CRD Hydraulic System SDIV level high
~
.
.c
;_  RPIS malfunction
  - RWM withdraw block (below 201, reactor power)
  - SDIV high water level trip bypassed   j e Reactor Mode Switch in Run:
  - APRM downscale
  - APRM upscale :(flow biased)    l
  - ;RBM downscale (if reactor power is greater than 30%)
e-Reactor Mode Switch in Startup/ Hot Standby:
  - AFRM. upscale >(12%)    I
  - Refuel platform,over core    -
  - Service: platform-hoist loaded-nn- e n"< mm l \ l 4
      ' "
  --(Continued on.next page)
    -
      " ""
iRev. N PORC Meeting No, NA Date 6/23/95    Page 1 of 3 h


A = A L 1- -s -- ==. m- r--
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Question 85 Reactor power level is 6% and personnel are in the Drywell. Which one of the following describes the current restrictions on control rod motion?
        ,
a. No rod motion is permitted until personnel are clear of the Drywell. )
. ANNUNCIATOR-  ROD    ARP 09-5-2-2 y' . LEGEND  WITHDRAWAL  .
b. No planned rod motion is permitted but rods may be inserted as needed to terminate unplanned events.
BLOCK
'
        .,
        --
.;
  ~CAUSES? - (Cont )-
e Reactor Mode Switch in Startup/ Hot Standby or Refuel:
    ~
7lhj SRMldet'ectors A$tIfUlly TnsArtieFih the / core, wit (count ]
    ~
,  irate l below' 100D cpsy"and :assodiated :IRM .rangeLawitch on , ,
    ' '  ~
1 range 12~orlbelo ,
  . - - SRM high flux
  -
Refueling interlocks
        .
  - SRP, inoperative
  - IRM'downscale (bypassed on range 1)
  - IRM high flux
  -
IRM detector not full in
  -
IRM inoperative    ,
e Reactor Mode Switch in Refuel
  - Refueling platform near or over the core with a load on the refuel platform hoist, or fuel grapple not full up
  -
Service platform hoist loaded
  - Selection of a second control rod with any other rod not
    *
full in


  -
c. There are no restrictions on rod insertion. Withdrawal is prohibited.
SDIV high water level trip bypassed
  -
Rod select power turned off or no rod selected
.:
  -
Refuel platform power turned off e Reactor Mode Switch in Shutdown:
  -
Reactor Mode switch-in shutdown-
-
AUTOMATIC ACTIONS Rod withdrawal block
.  (Continued on next page)
  =Rev. N PORC Meeting No. _ NA Date-- -6/23/95'  page 2 of 3
        <
  -


    .
d. There are no restrictions on rod motion as long as personnel are not working above elevation 292 ft. in the Drywell.
,. , ; 4 .4
~
f . .. ANNUNb1ATO ROD,  ARP 09-5-2-2-
,: g-  . LEGEND:  1 WITHDRAWAL
  '
4  -:- BLOCK .
        '
      ,
.; .  -: .
  > PROCEDURE-.
J ;Determinefcause'of rod. block at' panel 09- .
  ..,
  . 2.- ' Correct catise of alarm prior to attempting'.to_
withdraw control rod ,,
          .
  ,
          *
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k
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  : Rev. .' No.- '3  - PORC Meeting-No.- NA-6/23/95'
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Question 86 The plant is at full power when Chemistry reports the following SLC parameters:
            ,
  . Weight % Sodium Pentaborate is 10.5%.
r   1-1
  . Net Volume of Solution is 2500 gal.
_
 
'
. Solution temperature is 60 'F.
            .-
 
J SRO 0471 l During the administration of the examination, a typographical errorfwas note 41 in that -    ,
Which one of the following changes will bring the SLC system into compliance with Tech Specs?
l  ' distractors A and C were the identical.' Disanctor C was changed from:
a. Increase solution temperature to 70 'F.
y  -Turbine Governor Valve open; Turbine Steam lnlet Isolation Valve closed,
 
  -
b. Raise the Weight % to 11.2%.
r to:
c. Raise the Weight % to 11.2% and the Net Volume to 2550 gallons.
  , Turbine Governor Valve open; Turbine Steam Inlet Isolation Valve ope .
 
,
d. Raise the Net Volume to 3000 gallons.
This corrected the typographical error but necessitated a key change for the SRO exam from C to A. The determination to change distrac'or C vice distractor A was based on the    .
 
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Page 43 of 50
  - fact that some candidates had already recognized A to be a correct answer and marked
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  -their answer sheets to reflect their choice.
      .
SENIOR REACTOR OPERATOR EXAMINATION Question 87 It is day 90 of a continuous full power run when Chemistry reports that the following sample readings have been verified:
. Conductivity is 1 pmho.
 
. Chloride ion is 0.4 ppm.
 
Which one of the following actions, if any, is required by Tech Specs?
a. Readings are within specifications, power operation may continue, b. Reduce steam flow to less than 100,000 lb/hr. within 24 hours.


-
c. Be in the cold condition within 24 hours after reaching a steam flow rate of 100,000 lb/hr.
            : i e
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d. Be in the cold condition within 24 hours.
        -,
. . .. .
        ,


        !
Question 88 A temporary change to a procedure has been approved by an SRO and implemented. After l
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      '
        !
< the changed procedure had been used, the RPO (Responsible Procedure Owner) disapproved the change. Which one of the following describes the need for a Deviation and Event Report (DER) and whether the change must be withdrawn?
RO 061 SRO 061 -
a. DER is required; PORC decides if the change must be withdrawn.
        '
During the post-examination review, it was discovered that there were two correct
. answers given for the questio '
The rod drifl indication however is not referenced as a symptom of an uncoupled control rod ~ in the applicable procedure,. AOP-25, UNCOUPLED CONTROL RO That - ,
procedure states the symptom: -
An overtravel alarm is received during a coupling check of control rod.'
        ,
        ;
. Both the ROD . DRIFT and ROD OVERTRAVEL annunciators will alarm if the respective condition exists for any of the 137 control rods. Each of the control rods also  '
has an individual rod drift light on the full core display. There is actually no " Individual"


Rod Overtravel alarm as the question asks nor is there an " individual" Rod Drift alarm (there are however, individual rod drift lights). This ambiguity apparently led the candidates to associate individual in the sense of "an alarm caused by moving an individual rod." That perspective, coupled with the procedural symptom makes B also a correct answe The answer key was changed to reflect either A or B as a correct answe .
b. DER is required; the change must be withdrawn.


.
c. DER is not required; PORC decides if the change must be withdravm.
f
' ' AOP-25, UNCOUPLFO ONTROL ROD, revision 4, Section A., pg. 4.


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d. DER is not required; the change must be withdrawn.
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Page 44 of 50
  -r A30fDNCIATOR ROD DRIFT'-  ARP'09-5-2-3-LEGEND-    ,
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DES'TE Not applicable SETPOINT Not applicable
SENIOR REACTOR OPERATOR EXAMINATION Question 89 Use of a Temporary Mod is prohibited for which one of the following applications? l
+
      .
CAUSES A control' rod that is not selected moves off a
a. To correct a design deficiency while a permanent solution is pending.
   . latched even1 numbered position.- A control rod that is selected moves off an even numbered positior. or past an odd numbered position after rod sequence timer has stoppe AUTOMATIC ACTIONS-None
 
.
b. Allow testing of plant equipment.
  '
 
PROCEDURE
c. To temporarily compensate for a procedural deficiency.
  ,
 
Enter AOP-27, Cont.'01 Rod Drift *,
d. To allow continued operation of essential equipment.
     -  .
 
     =
.
Question 90 Today is November 3 and the time is 0800. 'A' RHR is inoperable for a planned LCO that began on November 1 at 0800. It is determined that the work cannot be completed before November 12. Which one of the following describes the actions that are required for this condition?
Place the plant in the cold condition no later than 0800 on; a. November 4.
 
l b. November 8.    )
      .
c. November 9.
 
d. November 10.
 
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Page 45 of 50
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SENIOR REACTOR OPERATOR EXAMINATION Question 91-During an outage the plant is in Risk Condition Green. Work is planned which will result in a degradation to Risk Condition Yellow. In addition to the Shift Manager which one of the following lists all of the approvals required, if any, before this work can start?
a. No additional approvals.
 
b. General Manager of Operations and Planning Manager.
 
c. Operations Manager and General Manager of Maintenance.
 
d. ~ Operations Manager and Planning Manager.
 
Question 92 You are the Core Alteration SRO during fuel offload. An irradiated fuel bundle is being transferred to the Spent Fuel pool when you are required to leave the Reactor Building for a random drug test. The only other SRO on shift is the SM. Which one of the following actions is permitted under these conditions?
a. The bridge operator may complete the move but may not pick up another bundle until your retum.
 
b. As long as an RO is stationed in the control room, the SM may temporarily assume your function.
 
c. If qualified, you may tumover and exchange shift positions with the SM. Fuel handling operations may continue.
 
d. The NYPA Refuel Floor Supervisor may assume your duties. Fuel handling operations may continue.
 
Page 46 of 50
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SENIOR REACTOR OPERATOR EXAMINATION Question 93 Which one of the following meets ALARA for performing ajob? ,
a. 1 man accomplishing the job in I hour in a 60 mR/hr field.
 
b. I man installing shielding for 30 minutes in a 60 mR/hr field and then accomplishing the job in 1 hour in a 6 mR/hr field.
 
c. 2 men accomplishing the job in 25 minutes in a 60 mR/hr field.
 
d. 2 men installing shielding for 15 minutes in a 60 mR/hr field and then accomplishing the job in 25 minutes in a 6 mR/hr field.
 
Question 94 Which one of the following describes the JAF administrative limit for the maximum TEDE which a radiation worker may accumulate in one year with the maximum dose extensions approved?
a. 2 Rem.
 
b. 3 Rem.
 
c. 4 Rem.
 
d. 5 Rem. j i
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SENIOR REACTOR OPERATOR EXAMINATION Question 95 Routine makeup nitrogen cupplied to the Drywell to mainiain an inerted state should be supplied by which one of the following train configurations?
a. Train 'A'is preferred.
 
b. Train 'B' is preferred.
 
c. Trains 'A' & 'B'should be alternated for each makeup operation.
 
d. Trains 'A' & 'B'should be operated while cross-connected.
 
Question 96 You are the Shift Manager / Emergency Director and the following conditions exist:
A non-isolable steam leak is discharging into the Turbine Building. A ground-level release is in progress. Radiological hazards exist outside the plant. A Site Area Emergency has been declared. You have decided to evacuate the site.
 
Which one of the following describes where you will send non-essential personnel?
a. Nine Mile Training Center.
 
]
b. State Fairgrounds.
 
c. Emergency Operating Facility.
 
d. Niagara Mohawk Service Center.
 
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SENIOR REACTOR OPERATOR EXAMINATION Question 97 Foam must not be used for fighting fires in the vicinity of new fuel for which one of the following reasons?    ,
a. Voiding of fuel warranty.
 
b. Corrosive effect on cladding.
 
c. Danger of criticality.
 
d. Fouling of heat transfer surfaces.
 
.
Question 98 An Unusual Event has been declared. Which one of the following describes the time limits for notifying off site agencies?
a. USNRC within 15 minutes, state and county within I hour.
 
*'
b. USNRC within 15 minutes, state and county within 15 minutes.
 
c. USNRC within 1 hour, state and county within 15 minutes.  .
  ~ d. USNRC within 1 hour, state and county within I hour.
 
.
Page 49 of 50
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SENIOR REACTOR OPERATOR EXAMINATION Question 99 The following conditions exist:
. An ATWS is in progress.
 
. The operators have reduced RPV level to -10 inches in accordance with EP-5 (Termination and Prevention of RPV Injection).
 
. SLC is injecting.
 
. Reactor power is 1%.
  . Torus temperature is 157 'F.
 
Which one of the following Emergency Plan EALs must be declared and which evacuation must be performed?
a. Site Area Emergency; Radiologically Controlled Area Evacuation, b. General Emergency; Radiologically Controlled Area Evacuation.
 
c. Site Area Emergency; Protected Area Evacuation.
 
d. General Emergency; Protected Area Evacuation.
 
Question 100 EOP-4, ' Primary Containment Control,' Torus Level Control leg, directs the operator to
' Terminate and prevent HPCI operation irrespective of whether adequate core cooling is assured' if Torus level cannot be maintained above 10.75 feet.
 
Which of the following describes the effect of continued operation of the HPCI system?
Continued operation will:
a. damage the HPCI turbine by supplying high temperature cooling water to the oil system.
 
b. reduce Torus water level below the safety relief valve T-quenchers.
 
c. result in a direct discharge of steam into the Torus air space.
 
d. result in a loss of the last high pressure injection system on high exhaust backpressure.
 
""* END OF EXAMINATION "*"
 
LOSS OF SHUTDOWN COOLING *  AOP-30 ATTACHMENT 2  Page 1 of 1 CORE DECAY HEAT VS. TIME AFTER SHUTDOWN I
Days after BTU /hr Days after BTU /hr shutdown  shutdown 0 6.28E8 21 1.48E7 1 4.79E7 l 22 1.44E7 l 2 3.92E7 l 23 1.42E7 3 3.36E7 l 24 1.39E7 4 2.97E7 l 25 1.36E7 5 2.69E7 l 26 1.33E7 6 2.48E7 l 27 1.31E7 7 2.32E7 l 28 1.28E7 8 2.19E7 l 29 1.26E7 9 2.08E7 l 30 1.24E7 10 2.00E7 l 31 1.22E7 11 1.92E7 l 32 1.20E7 12 1.86E7 l 33 1.18E7 13 1.80E7 l 34 1.16E7 14 1.75E7 l 35 1.14E7 15 1.70E7 l 36 1.12E7 16 1.66E7 l 37 1.10E7 17 1.62E7 l 38 1.09E7 ,
18 1.58E7 l 39 1.07E7 19 1.54E7 l 40 1.06E7 20 1.51E7 l 730 9.13E5 I l
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LOSS OF SHUTDOWN COOLING *    AOP-30 ATTACHMENT 3  Page 1 of 1 ALTERNATE COOLING METHODS METHOD APPROXIMATE HEAT LIMITATIONS REMOVAL CAPACITY (BTU /hr)
Decay Heat Removal  3.00E7 * Gates removed between cavity and spent fuel pool Puel Pool Cooling  3.30E6 * Gates removed between cavity and spent fuel pool e RBC must be available
    * SW must be available Fuel Pool Cooling  2.40E7 * RHR must be available Assist
    * RHRSW must be available o Gates removed between cavity and spent fuel pool RWCU Blowdown Mode  2.06E6 * No isolation signal present
* 1 pump running  * Makeup source must be
* 125 gpm blowde,wn flow  available (see list below)
* 125 gpm makeup flow
    * Main Condenser-or Radwaste must be available RWCU Recire Mode  1.70E6 No isolation signal present RWCU Blowdown Mode  1.00E6 * No isolation signal present
* gravity drain  * Makeup source must be
* 50 gpm blowdown flow  available (see list below)
* 50 gpm makeup flow
    * Main Condenser or Radwaste.
 
must be available Makeup Sources
*
Condensate transfer keep-full using Core Spray or RHR
* Control Rod Drive System
* Condensate /Feedwater
*
Condensate transfer to skimmer surge tanks (gates removed)
*
Condensate transfer to fuel pool using DHR (gates removed)
*
Condensate transfer using service box connections on the refuel floor (gates removed)
* Fire Protection System water from local fire hose stations or outside sources
*
*
RHR service water cross-tie Fire Water Crosstie Rev. No. 10  Page . 19 of 19
 
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NEW YORK POWER AUTHORITY    EXAMINATION / QUIZ JAMES A. FITZPATRICK NUCLEAR POWER PLANT  COVER SHEET Examination Title: USNRC REACTOR OPERATOR EXAMINATION Examination Submitte y:sAAr  Date: 11/03/97 Supervisor Approval: a
    '
A .E. mocci.5 Date: roles /97 Authorized Reference . ATTACHED Minimum Acceptable Grade: 80  Total Exam Points: 100 Grade:  Graded By:  Time Limit: 4 hours STUDENT DATA Name:    S.S.#:
Last First M.I.
 
Employer: NEW YORK POWER AUTHORITY  Date:
Department:
GUIDFLINES 1. Remain quiet during the exam. If you have any questions during the exam, raise your hand. Your instructor wii! provide clarification wherever possible.
 
2. You are expected to do your own work and not to help anyone else.
 
3. Use only the authorized reference material.    .
4. At the completion of this examination, you are to sign the following certification.
 
I certify all answers contained in this examination are my own. In addition, I have not received nor given any unauthorized assistance, nor have used any unauthorized references.
 
Student Signature:    Date:
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              .
REACTOR OPERATOR EXAMINATION
' Question 1
-
With the plant operating at 50% power, which one of the following Main Generator faults will cause an automatic reactor scram?
a. High Stator Winding Temperature.
 
b. High Differential Current, c. i.ou ofIsolated Phase Bus Duct Cooling.
 
d. Low Hydrogen Pressure.
 
Question 2 An instrument failure has resulte'. , w ator scram from 20% power. The following conditions exist:
  . Minimum RPV level react >    u of <ches.
 
. Maximum RPV pressu.    ,
          '
v 1005 psig.
 
. _Drywell pressure is 0 psig.
 
. All APRMs are downscale.
 
. Two control rods have failed to insert.
 
Under these conditions, the control rods will be inserted in accordance with which one of the following procedures?
a. AOP-01 (Reactor Scram).
 
b. EOP-02 (RPV Control).
 
c. EOP-03 (Failure to Scram).
 
d. EP-3 (Backup Control Rod Inse tia).
 
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              .
 
i REACTOR OPERATOR EXAMINATION Question 3 Which one of the following is the reason that the Reactor Mode Switch should be taken out of the RUN position immediately after a Reactor Sciam?  ,
a. Enable SRM and IRM rodblocks.
 
b. Prevent MSIV isolation.
 
c. Enable the SDIV high-level bypass circuitry.
 
d. Lower the APRM scram setpoint to 15%.
      .
Question 4 A reactor scram has just occurred followed by a Residual Transfer. Which one of the following describes the operators' concems regarding the MSIVs under these conditions?
a. Ensure the MSIVs close to minimize the possibility of Main Turbine overspeed.
 
b. Ensure the MSIVs close to minimize the possibility of Turbine Building contamination, c. Ensure the MSIVs remain open to minimize Torus heat load.
 
d. Ensure the MSIVs remain open to maintain availability of Turbine Scaling steam.
 
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REACTOR OPERATOR EXAMINATION  *
Question 5 A power ascension is in progress with the following conditions:
. Power levelis 70%.
. Load line is 100%.
. Two Feedwater pumps are operating.
 
Which one of the following describes when and how the Recire. Pumps will runback if one Feed Pump trips?
a. Immediately runback to minimum speed.
 
b. When RPV level lowers to 196.5 inches, runback to minimum speed.
 
c. Immediately runback to 44% speed.
 
d. When RPV level lowers to 196.5 inches, runback to 44% speed.
 
Question 6 The following conditions exist:
. A Group 11 isolation has occurred due to high Drywell pressure.
 
. Present Drywell pressure is 5 psig.
 
.
The EMERG OVERR DRYWELL HI PRESS keylock switch on the PCP panel has been taken to its OVERRIDE position.
 
. No other operator actions have been taken.
 
Which one of the following describes the CAD isolation valves that can be opened at this time?
a. All CAD isolation valves.
 
b. All CAD isolation valves except 27AOV-111 through 118 (CAD vent valves).
 
c. All CAD isolation valves except 27MOV-113,117,122,123 (CAD purge valves).
 
d. All CAD isolation valves except 27AOV 131 A/B,132A/B (CAD make-up valves).
 
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REACTOR OPERATOR EXAMINATION Question 7 The plant is operating at full power when the following occur:
. Generated MWe starts to decrease.
 
. Reactor power starts to decrease.
 
Which one of the following could have caused these symptoms?
a. Decrease in grid frequency.
 
b. Jet Pump malfunction.
 
c. Loss of feedwater heating.
 
d. Inadvertent SRV opening.
 
Que: tion 8 With a high Drywell pressure, Emergency RPV Depressurization is required if Torus Water Level cannot be maintained below PSP (Pressure Suppression Pressure). Which one of the following is the basis for performing an Emergency RPV Depressurization if'the Pressure Suppression Pressure Limit is exceeded?
a. To ensure that the vacuum breakers will not become submerged and fail to function.
 
b. To ensure adequate free volume (airspace) of the Torus for steam suppression.
 
i c. To prevent damaging the Torus. l l
d. To prevent steam from the Drywell bypassing the Suppression Pool. !
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REACTOR OPERATOR EXAMINATION Question 9 Which one of the following would give positive indication that SRV 'C' is opot when its h control switch is taken to OPEN7 l
a.~ SRV red light is on.
 
, b. SRV white light is on.
 
c. SRV tailpiece temperature rises and stabilizes at 285 *F.
 
d. EPIC alarm ' SONIC DET RV-C' RESET is received.
 
Question 10 The following conditions exist:
. A plant transient raised RPV pressure to 1150 psig.
 
. The SRVs have opened.
 
. RPV level is 150 inches.
 
Assuming no operator action, which one of the following describes when the SRVs are expected to close?
a. Before RPV pressure decreases below approximately 1050 psig, b. 120 seconds after the initial transient.
 
c. After RPV pressure decreases below approximately 50 psig.
 
d. When both RHR and Core Spray pumps are secured.  !
,
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l'  REACTOR OPERATOR EXAMINATION
!
Question 11 l A reactor scram occurred but many control rods failed to insert due to a high water level in the Scram Discharge Volume. The APRMs read 9 %. Which one of the following actions -
will be most effective in inserting control rods?
a. Manuallyinitiate ARI.
 
b. De-energize scram solenoids.
 
c. Manually insert control rods.
 
d. Close the CRD Flow Control valve.
 
.
Question 12 Following the trip of one Recirc. Pump with the reactor at power, the operators have closed the discharge valve of the tripped pump. Which one of the following is the reason that this is l done?
!
a. Stops reverse rotation of the tripped pump.
 
b. Prevents backflow through the idlejet pumps.
 
-
c. Prevents runout of the operating recirc. pump.
 
i d. Lowers the probability of entering the instability region of the power / flow map.
 
l
 
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REACTOR OPERATOR EXAMINATION  -
Question 13 The following conditions exist:
. Condenser vacuum is 25.1 inches Hg.
 
. Turbine load is 170 MWe.
 
.
AOP-31 (Loss of Condenser Vacuum) has been entered.
 
Which one of the following actions, by itself, will make it MORE LIKELY that a manual Turbine Trip will be required?
a. Starting the Mechanical Vacuum pumps.
 
b. Increase load to 255 MWe.
 
c. Decrease load to 85 MWe, d. Placing the spare Air Ejector sets in service.
 
Question.14 With the plant shutdown, an Emergency Diesel Generator is running and is tied to its bus for load testing. Which one of the following describes the response to a complete loss of offsite power?
a. The Tie Breakers will trip and the diesel will maintain the bus loads.
 
b. The Diesel Output breaker will trip and the diesel will switch to isochronous mode, then the Diesel Output breaker recloses, c. The Diesel Output breaker will trip and the diesel will switch to droop mode, then the Diesel Output breaker recloses. f l
d. The Tie breakers and the diesel will trip.
 
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REACTOR OPERATOR EXAMINATION Question 15 Bus 10400 is powered by the Main Generator via breaker 10402. Which one of the following ways of opening this breaker will not allow closing the Station Reserve breaker 10412?
a. Manually opened locally.
 
b. Manually opened from the control room, c. Automatically opened on overcurrent.
 
d. Automatically opened on undervoltage.
 
Question 16 Which one of the following describes the loads in the 24 VDC Power System?
a. Each load breaker is connected to 48 VDC potential (input) from its associated
  !24 VDC charger.
 
b. Half the loads on a 24 VDC distribution bus are powered from +24 VDC. The other half are powered from -24 VDC.
 
c. Each load breaker is connected to 24 VDC potential (input) from its associated 112 VDC charger, d. Half the loads on a 48 VDC distribution bus are powered from +48 VDC. The other half are powered from -48 VDC.
 
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REACTOR OPERATOR EXAMINATION Question 17 The following Narrow Range RPV level conditions exist:
. 'A' indicates 215 inches and is rising slowly.
 
'
. B'' indicates 185 inches and is lowering slowly.
 
. 'C' indicates 214 inches and is rising slowly.
 
. Feedwater control is selected to the 'A' Column.
 
Selecting the 'B' RPV Level Column will result in which one of the following effects on level trends?
l a. 'A' and 'C' will continue to rise. 'B' will lower.
 
b. 'A' and 'C' will continue to rise. 'B' will rise.
 
c. 'A' and 'C' will lower. 'B' will lower.
 
d. 'A' and 'C' will lower. 'B' will rise.
 
Question 18 in which one of the following ways does a loss of 125 VDC Bus 'A' affect the ADS /SRV system?
a. Loss of'A' logic, ADS remains functional.
 
b. None of the ADS /SRV valves can be opened, c. The ADS /SRV valves cannot be opened from the remote panel.
 
d. Only valves F, J, K & L remain fully functional.
 
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REACTOR OPERATOR EXAMINATION  l Question 19 AOP-43 (Shutdown From Outside the Control Room) requires the operators to remove RHR pumps 'A' and 'C' from service. Which one of the following describes the reason that bis .
step is necessary?
a. Prevent water hammer in the event of a LOCA signal.
 
b. Prevent inadvertent Drywell spray.
 
c. Prevent inadvertent LPCI injection.
 
d. Prevent draining the RPV to the Torus.
 
.
Question 20 The following events occur:
. The plant is at 20% power.
 
. High radiation in the Off Gas system starts the Off Gas Timer.
 
. No operator action is taken.
 
Which one of the following will be the most likely cause of an automatic reactor scram?
a. High Reactor Power, b. Low RPV Level.
 
c. MSIV closure.
 
d. High RPV Pressure.
 
.
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REACTOR OPERATOR EXAMINATION  '
Question 21 Which one of the following describes the use of ESW for Drywell cooling during a LOCA?
a.- It is the preferred method.-
b. It may be used only on loss of RBCLC.
 
c. It may be used only if directed by EOP-4.
 
d. It is prohibited.
 
Question 22 On a Loss ofInstrument Air pressure during normal plant operation, which one of the following describes if and when the MSIVs will go closed?
a. Inboards remain open; outboards close immediately.
 
{
i b. Inboards and outboards close immediately. I c. Inboards close eventually; outboards close immediately.
 
d. Inboards remain open; outboards close eventually.
 
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REACTOR OPERATOR EXAMINATION
. Question 23 The following conditions exist:-
. A valid Reactor Scram has occurred on low RPV level.
 
. The EDGs have auto started in response to high Drywell pressure.  ,
. The Recire. pumps are running at minimum speed as expected.
 
i Which one of the following describes the status of the containment isolations?
a. Group I isolated; Group 11 isolated.
 
b. Group I not isolated; Group 11 not isolated.
 
\
c. Group I isolated; Group II not isolated.
 
d. Group I not isolated; Group II isolated.
 
Question 24 During a plant startup RPV pressure is 900 psig. Loss of CRD flow will have which one of the following effects on control rod motion and scram times?  .
a. Normal rod motion is unaffect.; and scram times will be within acceptable limits.
 
b. Normal rod motion is lost and scram times will not meet acceptable limits.
 
c. Normal rod motion is unaffected but scram times will not meet acceptable limits.
 
d. Normal rod motion is lost but scram times will be within acceptable limits.
 
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  - REACTOR OPERATOR EXAMINATION  -
i Question 25 During power operation with RHR pump 'A' in Torus Cooling, an operator mistakenly manually opens RHR pump 'A' Shutdown Cooling Suction valve (10MOV-15A) locally at the valve. Which one of the following describes the expected automatic actions, if any?
a. There will be no automatic actions.
 
b. When 10MOV-15A reaches 10% open, it will automatically close the 'A' RHR Pump Suction Torus Isolation Valve (10MOV-13A).
 
c. When 10MOV-15A reaches full open, the RHR Torus Cooling / Torus Spray outboard valve (10MOV-39A) will auto close.
 
d. The 'A' RHR pump will trip on low suction pressure.
 
Question 26 Which one orthe following describes the consequences of spraying the Drywell if Drywell conditions are not in the pemtissible region of the Drywell Spray Initiation Curve?
a. Water sprayed into the Drywell will turn to steam raising pressure even further.
 
b. The cold water will put excessive thermal stress on the Drywell which may lead to its failure.
 
c. The effect is unpredictable and would result in putting the plant in an unanalyzed condition.
 
d. Drywell pressure would drop more rapidly than could be handled by the vacuum breakers.
 
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REACTOR OPERATOR EXAMINATION
 
Question 27 The following conditions exist:
l . The operators are conducting EOP-4.    ,
l . HPCI and RCIC are injecting.
 
l . Torus level is 10.9 ft. and decreasing rapidly.
 
l Which one of the following actions,if any, must be.taken regarding HPCI and RCIC if Torus level cannot be maintained above 10.75 feet? -
a. Trip both HPCI and RCIC.
 
b. Trip HPCI, RCIC may remain running.
 
c. Trip RCIC, HPCI may remain running.
 
d. Both HPCI and RCIC may remain running.
 
.
Qaestion 28 The Reactor Building Ventilation system is in operation when the exhaust plenum radiation levels exceed 10' cpm. Which one of the following d: scribes the expected response of the Reactor Building Ventilation and SBGT systems to this event?
a. Reactor Building Ventilation will isolate and neither train of SBGT will start.
 
b. Reactor Building Ventilation will isolate and both trains of SBGT will start.
 
c. Reactor Building Ventilation will not isolate and neither train of SBGT will start.
 
d. Reactor Building Ventilation will not isolate and both trains of SBGT will start.
 
.
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REACTOR OPERATOR EXAMINATION Question 29
. In the event that normal shutdown cooling capability has been lost, which one of the following states the minimum shutdown time before Fuel Pool Cooling Assist will provide adequate cooling?
a. Iday.
 
b. 4 days.
 
c. 7 days.
 
d. 9 days.
 
I Question 30 Which one of the following describes why it is important to establish forced Recire. flow during a Loss of Shutdown Cooling event?
a. Coolant stratification may mislead the operators into assuming bulk water temperature is below 212 'F.
 
b. Cooling of the recire. loop will produce a reactivity effect when the first recire.
 
pump is started.
 
c. Unstable transition boisia;; at low pressure may cause clad dam age. l I
d. Steam build up in the RHR s'uction piping will lead to waterhammer when RHR l flow is restored.
 
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REACTOR OPERATOR EXAMINATION Question 31 l
Which one of the following limits takes precedence during the operation of the SBGT system I with the Reactor Building isolated?
a. Maintain RB AP more negative than -0.25 inches of water.
 
b. Maintain charcoal filter temperatures less than 170 'F.
 
c. Limit SBGT flow to a maximum of 6000 scfm.
 
d. Maintain Reactor Building Ventilation exhaust radiation levels less than 10 cpm.
 
Question 32 Following a reactor scram the pressure in the Scram Discharge Volume (SDV) rises to RPV'
pressure. Which one of the following describes the most likely reason for this condition?
a. One or more CRDM seals have failed.
 
b. The scram nas not been reset.
 
c. The SDV vent valves have failed closed.
 
d. The CRDH flow control valve has failed open.
 
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REACTOR OPERATOR EXAMINATION Question 33 Which one of the following RWM conditions, if any, will prevent inseition of a selected rod using the Emergency In Svitch?
a. None.
 
b. Select Error.
 
c. Withdraw block.
 
d. Insert block.
 
'
Question 34
      !
The following conditions exist:
l
. The plant is shut down.
 
l
. The 'A' RHR loop is in Shutdown Cooling.    ,
. A LPCI initiation signal on low RPV level occurs. i Which one of the following describes the operator actions, if any, which must be taken in order for LPCI 'A' to start injecting?
a. None.
 
b. Reset the Group 2 isolation, manually start the pump and reset the injection valve isolation signal.
 
c. Manually align the suction path for the desired pump and reset the LPCI initiation signal.      ;
d. Manually align the suction path for the desired pump, manually start the pump, and reset the injection valve isolation signal.
 
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REACTOR OPERATOR EXAMINATION I
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- Question 35      i l
The following sequence of events has occurred.
 
. A LOCA has occurred resulting in LPCI injection.  -
. Offsite power is then lost.    ,
. EDGs 'B', 'C', & 'D' start and load normally.
 
. EDG 'A' fails to start.    .
Under these conditions, which of the following RHR pumps will be running two minutes after the loss of power?    l a. All four b. 'B', 'C', & 'D'
c. 'A', 'C', & 'D'
      .
d. 'B' & 'D'
Question 36
- The follow events occur:
. A low RPV level causes HPCI to start and inject.
 
. HPCI is the only available injection system.
 
. RPV level starts to increase.
 
. The HPCI Aux. Oil Pump breaker trips.
 
Assuming no operator action, which one of the following describes the expected response of HPCI?
a. HPCI will trip when the Aux. Oil Pump breaker trips and can not restart.
 
b. HPCI will trip on High Level and can not restart.
 
.
c. HPCI will trip on High Level and can restart on low level.
 
d. HPCI will continue mnning until manually tripped.
 
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REACTOR OPERATOR EXAMINATION Question 37 The following events have occurred:
  . A LOCA has occurred.
 
. The Core Spray pumps auto staned on low level.
 
. RPV level subsequently recovered to 180 inches.
 
. The operators took both Core Spray Ptunp Switches to STOP.
 
. Drywell pressure is 2.3 psig.
 
Which one of the following describes the expected response of the Core Spray pumps to these events?
a. After auto-starting they remain on until the initiation logic is reset. l I
b. They stop when switched to STOP but restart if Drywell pressure increases above their auto-start setpoint.
 
c. They stop when switched to STOP but restart iflevel decreases below their auto-start setpoint.
 
d. They stop when switched to STOP and remain off.
 
I i
Question 38 l
Which one of the following describes the effect of a loss of 600 VAC power on the Core l 1. Spray system?
a. Core Spray pumps will not auto-start when required. They can be staned
.
manually.
 
l l
b. Core Spray pumps cannot be started either automatically or manually.
 
l c. Core Spray pumps will start normally but their discharge valves will not open l automatically. l l
d. Core Spray pumps will stan normally but will trip on low flow. j l        i
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REACTOR OPERATOR EXAMINATION Question 39 The operator takes the SLC keylock switch to START SYS-A. Pump 'A' receives a start signal but fails to start due to mechanical binding ofits bmake contactor. Which one of the following describes the expected response of the Squib Valves and RWCU system isolation valves to these events?
a. Neither Squib valve will fire; RWCU will not isolate.
 
b. Only the 'A' Squib valve will fire; RWCU will isolate.
 
c. Both Squib valves will fire; RWCU will isolate.
 
d. Both Squib valves will fire; RWCU will not isolate.
 
Question 40 Following a Residual Transfer and prior to the operator taking any actions, which one of the following describes the ability to start the SLC pumps and fire the squib valves?
a. The. pumps can be started and the squib valves will fire.
 
b. The pumps cannot be started and the squib valves will fire.
 
c. The pumps can be started and the squib valves will not fire. 1 d. The pumps cannot be started and the squib valves will not fire.
 
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REACTOR OPERATOR EXAMINATION Question 41 The plant is operating at 100% power when a Generator Load Reject occurs. Which one of the following describes the RPS input that generates the first expected scram signal?
a. High RPV Pressure, b. High Neutron Flux, c. Turbine Control Valve Fast Closure.
 
d. Turbine Stop Valve Closure.
 
Question 42 The reactor is operating at 25% power. Which one of the following describes the response,if any, of RPS if the 'A' inboard and 'D' outboard MSIVs are closed?
a. Full Scram.
 
b. Half Scram in Channel 'A'.
c. Half Scram in Channel 'B'.
d. No effect.
 
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REACTOR OPERATOR EXAMINATION l
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Question 43 l
l A normal plant startup is in progress and the following conditions exist:
;
. The Reactor Mode Switch is in STARTUP.    -
i
. All the IRM range switches are on RANGE 2.
 
. No IRMs are bypassed.
 
Which one f the following describes the efTect on half scrams or rod blocks, if any, that will
! occur if the lxM 'A' Mode Switch is placed in the STANDBY position?
a. None, as long as its companion APRM is not downscale.  !
!
,
b. Rod Withdrawal Block only.
 
!
c. RPS Half Scram only.
 
d. Rod Withdrawal Block and RPS Half Scram.  .
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Question 44 The following conditions exist:
. AllIRM Range switches are on RANGE 2.
 
. The SRM detectors are partially withdrawn. i l . SRM 'A' reads 80 cps.
 
Which one of the following describes the ability to withdraw SRM 'A' and the status of rod blocks?
      .
l a. The detector can be further withdrawn and a rod block exists.
 
b. The detector can be further withdrawn and no rod block exists.
 
c. The detector cannot be further withdrawn and a rod block exists.
 
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d. The detector cannot be further withdrawn and no rod block exists.
 
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REACTOR OPERATOR EXAMINATION
_ Question 45 A Recirculation Flow Sununer fails resulting in zero output. Which one of the following is the highest power level at which the APRM will generate a rod block but not a scram signal?
a. 100 %
b. 75 %
c. 60%
d. 50 %
Question 46 Assuming no change in vessel inventory, starting the Recire pumps will affect Fuel Zone and Wide Range RPV level indication in which one of the following ways?
a. Fuel Zone rises; Wide Range rises.
 
b. Fuel Zone rises; Wide Range lowers.
 
c. Fuel Zone lowers; Wide Range rises.
 
d. Fuel Zone lowers; Wide Range lowers.
 
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REACTOR OPERATOR EXAMINATION Question 47 RCIC is in operation due to a small LOCA. Which one of the following describes the expected position of the RCIC Turbine Governor Valve (13HOV-2) and the RCIC Turbine Steam inlet Isolation Valve (13MOV-131) if RPV level rises to 222.5 inches?
a. Turbine Govemor Valve open; Turbine Steam Inlet Isolation Valve open.
 
b. Turbine Govemor Valve closed; Turbine Steam Inlet Isolation Valve open.
 
c. Turb.6- Governor Valve open; Turbine Steam Inlet Isolation Valve closed.
 
d. Turbine Governor Valve closed; Turbine Steam Inlet Isolation Valve closed.
 
Question 48 The following events have occurred:
. An Automatic Depressurization System (ADS) initiation has occurred. '
. The initiation signals are still present.
 
. A blowdown is in progress.
 
Taking the AD'S Normal / Override switches to OVERRIDE and back to NORMAL will have which one of the following effects on the ADS Valves?
a. ADS Valves will close and remain closed.
 
b. ADS Valves will close then reopen immediately.
 
c. ADS Valves will close then reopen after 120 seconds.
 
d. ADS Valves will remain open.
 
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REACTOR OPERATOR EXAMINATION  .
 
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Question 49 The following conditions exist:
. Drywell pressure has risen from 1.810 2.5 psig.
 
. Torus pressure has risen from 0 to 2.5 psig.
 
These conditions are symptomatic of which one of the follow'mg?  )
a. SRV cycled to control pressure and an SRV tailpiece failure inside the Torus.
 
b. Small break LOCA in the Drywell and a Downcomer failure inside the Torus.
 
c. Small break LOoA in the Drywell and a Torus to Drywell vacuum breaker failed -
to open.
 
d. SRV cycled to control pressure and an SRV tailpiece vacumn breaker stuck open.
 
Question 50 With the Mode Switch in STARTUP, which one of the following conditions will result in the automatic closure of the MSIVs?
a. RPV Level is 50 inches.
 
b. Steamline pressure is 750 psig.
 
c. Main Condenser Vacuum is 10 inches Hg.
 
d. Turbine Stop valves not fully closed.
 
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REACTOR OPERATOR EXAMINATION Question 51 The plant is in shutdown cooling when a relay failure results in a spurious ADS logic Channel 'A' low-low-low level signal. No other level trips have occurred. Which one of the .
      -
following describes the effect that this event will have on ADS?
a. ADS willinitiate.
 
b.- ADS will not initiate because the RHR or Core Spray pump running interlock is bypassed in shutdown cooling.
 
c. ADS will not initiate because both channels are needed for ADS initiation.
 
,
d. ADS will not initiate because there is no low-level trip.
 
.
Question 52 RFP 'A' has just tripped on high reactor vessel level. Which one of the following conditions must be satisfied before the RFP 'A' hydraulic coupling automatically disengages?
a. HP and LP stop valves closed.
 
b. RFP turbine tripped signal sensed.
 
c. Turbine speed less than 4 RPM.
 
d. MGU and MSC on low speed stops.
 
.
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REACTOR OPERATOR EXAMINATION  '
-Question 53-
, The following events occur.
 
. The plant is operating at full power with the MGUs and Master Controller balanced. - ..
. The Master Controller output slowly fails downscale. l
. RPV level lowers to 185 inches at which point the operator takes both MGUs to manual.
 
. No further operator action is taken.
 
Which one'of the following describes the response of Feed Flow and RPV level after the MGUs have been shifted to manual?
a. Flow will increase to 100%; Level will increase to 200 inches.
 
b. Flow will increase to 100%; Level will remain at 185 inches.
 
c.- Flow will increase to greater than 100%; Level will increase to 200 inches.
 
d. Flow will remain less than 100%; Level will continue to trend down.
 
!
Question 54 The SBGT system has failed to auto start in response to a HPCI start signal. Which one of I the following will occur as a result of the failure of SBGT to start?  ;
I a. HPCI start up sequence will not complete and the HPCI turbine will not start.
 
;
i b. The HPCI turbine will start but may trip on High Exhaust Pressure.
 
. c. The HPCI turbine will start but may trip on High HPCI Area Temperature.
 
d. HPCI flow rate will be limited due to decreased condenser efficiency.
 
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REACTOR OPERATOR EXAMINATION Question 55 Which one of the following is the reason that operation of an EDO at loads near 2000 KW is to be avoided?
a. Excessive wear on turbocharger drive gears.
 
b. Main bearing degradation due to inadequate lube oil cooling.
 
c. ' Potential Lube oil sump fire due to increased piston blow by.
 
d. Overheating of exhaust system.
 
Question 56 Following a LOCA with concurrent Loss of Offsite Power, which one of the Eollowing will be the first to be reenergized when the 'A' and 'C' EDG breakers close?
a. 'A' ESW Pump.    -
I b. 'A' RHR Pump.
 
c. 'C' RHR Pump.
 
d. 'A' Core Spray Pump.
 
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REACTOR OPERATOR EXAMINATION Question 57 The operator withdraws a control rod one notch but the rod position indications show that the rod is withdrawing continuously until it reaches full out position. Which one of the following could be the cause of this?
a. Stuck collet piston.
 
,
b. High CRDH pressure.
 
c. Uncoupled rod.
 
d. Leaking HCU Scram Inlet valve (03AOV-126).
 
Question 58 Reactor power is 5%. The RWM is fully operational and has generated a Withdraw Block.
 
Under these conditions, which one of the following is the maximum number of rods with insert errors that could possibly be moved in the withdraw direction?
a. None.
 
'
b. One.
 
c. Two.
 
d. Three.
 
<
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REACTOR OPERATOR EXAMINATION Question 59 The plant is operating at full power when the following Recire. Pump Seal readings are noted:      .
. #1 (inner) Seal Cavity pressure is 1000 psig.
 
. #2 (outer) Seal Cavity pressure is 150 psig.
 
Which one of the following will cause these conditions?
a. Normal operation ofboth seals.
 
b. Failure of both seals.
 
c. Partial failure of the #1 seal.
 
d. Partial failure of the #2 seal.
 
.
Question 60 During the startup of the 'A' Recire. Pump the following conditions exist:
. The 'A' Recire. Pump Discharge valve is 85% open.
 
. The 'B' Recire. Pump Discharge valve is fully open.
 
. Total Feed Flow is 30%.
. Feedwater pump 'A' is running; Feedwater pump 'B' is secured.
 
. RPV levelis 195 inches.
 
Which one of the following describes the most restrictive Recire. Pump speed limitations currently in effect?
a. Both pumps are limited to 30%.
b. Both pumps are limited to 44%.
c. Pump 'A' is limited to 30%; 'B' is not limited.
 
d. Pump 'A' is limited to 30%; 'B' is limited to 44%.
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REACTOR OPERATOR EXAMINATION  -
Question 61.
 
The drive mechanism of a fully withdrawn control rod is uncoupled. Which one of the
. following indications during the coupling check indicates that the rod is uncoupled?
a. Individual Rod Drift Alarm.
 
b. Individual Rod Overtravel Alarm.
 
c. '49' will be displayed in the rod position window.
 
d. Individual Rod Full Out light remains energized.
 
Question 62 Three of the eight LPRM detectors supplying an RBM channel have failed downscale.
 
Which one of the following describes the response, if any, of the RBM to these failures?
a. There will be no functional effect since the RBM still has sufficient LPRM irputs to function.
 
b. The rod block setpoint will be automatically adjusted downward to compensate for the lost inputs.
 
c. An Inop. Rod Block will be generated until one detector is bypassed.
 
d. ' A Rod Block will be generated until the PUSH TO SETUP pushbutton has been depressed.
 
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r REACTOR OPERATOR EXAMINATION
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l l Question 63
! Which one of the following describes the effect of spraying the Drywell during a LOCA when Drywell pressure is below 2.7 psig?
a. Unnecessary damage to equipment in the Drywell.
 
b. Partial de-inerting of the Primary Containment.
 
l c. Inability to vent the Primary Containment.
 
L d. Mechanical failure of the Torus to Drywell vacuum breakers.
 
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l Question 64 i The operators are unable to reset an inadvertent Group I isolation signal. Which one of the l following conditions, ifit existed, would cause this problem?
!
l a. A control switch for one of the MSIVs is in the OPEN position.
 
b. The Reactor Mode Switch is in RUN.
 
l l c. The control switches for the Main Steam Line Drain valves are in the OPEN l position.
 
l d. The AP across the MSIVs is 125 psid.
 
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REACTOR OPERATOR EXAMINATION Question 65 During plant operation it is noted that 345 KV bus voltage is 380 KV. Which one of the following is the appropriate response, if any, to this condition?
a. No response required.
 
b. Reduce generator output voltage to restore 345 KV bus voltage to normal.
 
c. Cor. tact the Load Dispatch Center and request that 345 KV bus voltage be reduced.
 
d. Increase Generator Isolated Phase Cooling to maximum.
 
Question 66 The following sequence of events occurs:
. 600 VAC power is lost for 3 minutes.
 
. After 600 VAC power is restored,125 VDC power is briefly lost.
 
. 125 VDC power is then restored.
 
After restoration of 125 VDC power, which one of the following will be the source, if any, of 120 VAC UPS Instrument Power 7 a. Nothing,120 VAC will be deenergized.
 
b. 600 VAC via the UPS MG Set.
 
c. 600 VAC via the 600/120 VAC transformer.
 
d. 125 VDC via the UPS MG Set.
 
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REACTOR OPERATOR EXAMINATION Question 67 Loss of all 125 VDC power would have which one of the following effects on the Emergency Diesel Generators?      ,
a. Diesels would auto-start and load.
 
b. Diesels would auto-start, but would not auto load.
 
c. Diesels would not start and could not be started at the Engine Control Panel.
 
d. Diesels would not auto-start but could be started at the Engine Control Panel.
 
.
Question 68 Which one of the following describes the effect of the Control Room Inlet Radiation Monitor channel failing upscale?
a. Alarm only.
 
b. The intake and Exhaust dampers close and the Recire. damper opens.
 
c. The Control Room Supply fans trip and the Exhaust Damper closes.  .
d. The Emergency Supply fan starts and the Inlet filter system is placed in service.
 
.
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REACTOR OPERATOR EXAMINATION Question 69 Which one of the following describes a potential path for radioactive contamination to the discharge canal during normal power operation?
a. Drywell Air Cooler tube leak.
 
b. RBCLC Heat Exchanger tube leak.
 
c. Recombiner condenser tube leak.
 
d. Main Condenser tube leak.
 
l Question 70 Which one of the following describes the response of any TIP detector not in its shield when a Group I and Orc * 11 Containment Isolation Signal occurs?
a. A Group I Isolation will cause the TIP to withdraw to the Lead Shield position. A Group II has no further effect.
 
b. A Group I Isolation will cause the TIP to withdraw to the Lead Shield position. A Group II will activate the shear valve if the TIP is still inserted.
 
c. A Group I Isolation will have no effect. A Group II Isolation will actuate the shear valve if the TIP is not withdrawn within 10 minutes.
 
d. A Group I Isolation will have no effect. A Group II Isolation will cause the TIP to be withdrawn to the Lead Shield position.
 
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l i
      '
REACTOR OPERATOR EXAMINATION I
Question 71
      !
; The crew is conducting EOP-5 (Secondary Containment Control) when Reactor Building ventilation isolates on high radiation. The radiation level is subsequently seen to decrease below the isolation setpoint. Which one of the following describes under what condition, if any, it is permissible to override the high radiation isolation to restart the Reactor Building ventilation system?
a. It is not permissible.
 
b. Two Reactor Building area temperatures are above maximum normal.
 
c. After it is confirmed that no primary system is discharging into the Reactor Building.
 
d. If Reactor Building AP cannot be maintained at a negative pressure with SBGT.
 
Question 72 l
Inadvertent closure of which one of the following CRD HCU valves will result in the l
inability to scram the affected rod?
l n. Scram Inlet Valve - 126.
 
l
! b. '4nsert Header Isolation - 101.
 
l c. Exhaust Water Header Isolation - 105.
 
!
d. Withdraw Header Isolation - 102.
 
I Page 36 of 50
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REACTOR OPERATOR EXAMINATION Question 73 l
The plant is operating at 50% power with RCIC testing in progress. Under these conditions, Tech Specs require an immediate reactor scram if Torus temperature reaches which one of the following temperatures?
a. 95'F      ,
 
b. 105'F c. I10'F d. 120 'F Question 74 i
Fuel handling operations are in progress when a Fuel Pool leak is discovered. Which one of l
the following states the initial point at which immediate evacuation of the Refuel Floor i
becomes mandatory?      I a. When the presence of the leak is verified. j b. When level decreases below its Tech Spec limit (33 feet).
 
;
c. When uncovering of spent fuel is imminent.
 
d. When uncovering of spent fuel has occurred.
 
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l
 
REACTOR OPERATOR EXAMINATION l
Qucstion 75 A plant stettup is in progress and Recire. pump speed is 30%. APRM readings are as listed below:      .
. Channel A 2.3%
. Channel B 4.0%
. Channel C 5.0%
. Channel D 4.7%
. Channel E 2.4%
. Channel F 5.1%
If the Reactor Mode Switch is placed in RUN, which one of the following describes the ability to raise power with control rods and/or recire. flow?
a. The power can be raised using rods or recire flow.
 
b. Power can be raised using rods only.
 
.
c. Power can be raised using recire, only.
 
d. Power cannot be raised.
 
Question 76 The plant is operating at full pov.er when the pressure compensation for the in service RPV level column is lost. Which one of the following describes the effect that this will have on actual RPV water level?
a. RPV level will lower until a reactor scram occurs, b. RPV level will lower (by about 12 inches) and stabilize.
 
I c. RPV level will rise until a reactor scram occurs.
 
d. RPV level will rise (by about 12 inches) and stabilize.
 
.
Page 38 of 50
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      -
 
REACTOR OPERATOR EXAMINATION Question 77 The plant is at full power and the 'A' Pressure Regulator is in control. Failure of which one of the following inputs to the EHC Pressure Regulators will have the smallest impact on RPV pressure?
a. 'A' Pressure Regulator throttle pressure fails high.
 
b. 'A' Pressure Regulator throttle pressure fails low.
 
c. 'B' Pressure Regulator throttle pressure fails high.
 
d. 'B' Pressure Regulator throttle pressure fails low.
 
i
      )
Question 78 The plant is operating at full power when RBCLC flow to the RWCU system is lost. Which one of the following is the expected response of the system isolation and the Holding pumps to this event?
a. The system will not isolate; The Holding pumps will start.
 
b. The system will isolate; The Holding pumps will trip.
 
c. The system will not isolate; The Holding pumps will trip.
 
d. The system will isolate; The Holding pumps will start.
 
Pag,. 39 of 50  ,
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REACTOR OPERATOR EXAMINATION Question 79 The plant is at 70% power with all Condensate, Condensate Booster, and Feed pumps running. Which one of the following describes the expected plant response to the trip of one Condensate pump?
a. The remaining pumps will remain in service and RPV level will not be affected.
 
b. One Feed pump will trip on low suction pressure but RPV level will not be affected.
 
c. One Feed pump will trip on low suction pressure and RPV level will decrease.
 
d. One Condensate Booster pump will trip but RPV level will not be affected.
 
Question 80 Which one of the following describes the purpose of the Reactor Steam supply to the Off Gas Hydrogen Recombiner?
a. Dilutes hydrogen to below the explosive limit.  !
b. Increase temperature which improves efficiency of recombination.
 
c. Improves removal of radioactive iodines from gas stream.
 
d. Improves cooling of the charcoal filters during accident conditions.
 
Page 40 of 50
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REACTOR OPERATOR EXAMINATION  -
- Question 81 Fire Main use during a fire on site caused its pressure to lower to 90 psig for 30 seconds.
 
.
Pressure subsequently recovered to 120 psig where it has remained for the past 10 minutes.
 
Assuming no operator action concerning the Fire Pumps, which one of the following identifies the Fire pumps that should be running at this time?
a. Makeup Pump only.
 
b. Makeup Pump and Motor Driven Fire Pump only.
 
c. Makeup Pump, Motor Driven Fire Pump and One Diesel Driven Fire Pump only.
 
d. Makeup Pump, Motor Driven Fire Pump and Both Diesel Driven Fire Pumps.
 
Question 82 The following air pressures exist in the Instrument and Service Air headers:
. Instrument Air is 100 psig.
 
. Service Air is 90 psig.
 
Unoer these conditions, which one of the following describes the expected position of the Instrument to Service Air Isolation valve (39FCV-110) and the Breathing Air Isolation valve (39FCV-111)?
a. Both will be open.
 
b. FCV-110 will be open. FCV-11I will be closed.
 
c. FCV-110 will be closed. FCV-111 will be open.
 
d. Both will be closed.
 
Page 41 of 50
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REACTOR OPERATOR EXAMINATION Question 83 An RBCLC Makeup Tank Level annunciator is alarming due to a high level. Which one of
      -
the following is the most likely cause of this condition?
a. Tube leak in the RBCLC heat exchanger.
 
b. Tube leak in the RWCU NRHX.
 
c. RBCLC low-low pressure.
 
d. RHR pump seal cooler leak.
 
      *
J Question 84 During normal power operation, which one of the following sources can be used for emergency makeup to the Spent Fuel Pool?
a. CRD.
 
b. Condensate Transfer.
 
c. Core Spray.    .
d. RHR Service Water, i
      .
Page 42 of 50
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REACTOR OPERATOR EXAMINATION
      '
Question 85 t
The Reactor Mode switch is in the REFUEL position, and the Refueling Platform (bridge) is over the Reactor Vessel. Which one of the following would cause a Rod Block under these conditions?      I a. The Auxiliary Hoist is loaded.
 
b. The Fuel Grapple is in the FULL UP position.
 
c. The Service Platform Hoist is unloaded and not FULL UP.
 
d. All rods are Full-In, except for a selected rod at position 02.
 
Question 86 In accordance with AP-02.04, which one of the following activities requires an instruction or procedure to perform?
a. Checking a relay energized or deenergized.
 
b. Changing a fish basket.
 
c. Checking an oil sump level,    j d. Opening drain valves within a PTR boundary.
 
.
Page 43 of 50
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REACTOR OPERATOR EXAMINATION
,
Question 87 During normal plant operations, you have been assigned to perform a routine task that is govemed by a Reference Use procedure without step signoffs. .Which one of the following describes the requirements for procedure review and reference?
a. No prior review of the procedure is required. Reference to the procedure during the task is not required.
 
b. Review the procedure prior to performing the task. Reference to the procedure during the task is not required.
 
c. Review the procedure prior to performing the task. Refer to the procedure prior to performing each step.
 
d. No prior review of the procedure is required. Refer to the procedure prior to performing each step.
 
Question 88 The plant is at full power when ST-SD (APRM Calibration) shows that the AGAF for an APRM is 1.02. Which one of the following describes the significance of this reading?
a. There is no significance if FRP is greater than MFLPD.
 
b. The reactor will scram at a higher power than allowed.
 
'
c. The reactor will scram at a lower power than required.
 
d. The APRM has too few inputs.
 
Page 44 of 50
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RI ACTOROPERATOREXAMINATION  .
Question 89 Operation with a high hotwell level (>l 12 inches) is likely to have which one of the following consequences?
a. Condenser tube damage due to high tube vibration.
 
b. Condenser Air Removal pump damage due to high moisture intake.
 
c. Unmonitored release to the lake via the Cire. Water system.
 
d. Condensate pump damage due to runout.
 
Question 90 You are hanging a PTR on a circuit breaker and the PTR form has a slash through the first check block (' Initials first') for that component. Which of the following describes the meaning of the slash on the PTR form?
a. This is a replacement for a lost tag.
 
b. No independent verification is required.
 
c. Dual concurrent verification is required.
 
d. The position of the circuit breaker is not being changed.
 
Page 45 of 50
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REACTOR OPERATOR EXAMINATION Question 91 The scram times of 136 control rods have been measured and average 3.50 seconds to position 04. What is the slowest scram tirne that the remaining control rod can have and still -
satisfy the requirements of Tech Specs?
a. 3.554 sec.
 
b. 3.764 sec, c. 7.000 sec.
 
d. 10.900 sec.
 
.
Question 92 During fuel handling operations the operator in the control room notes that the SRMs are reading below 3 cps. Under which one of the following conditions, if any, may fuel handling continue?
a. The plant has been shutdown for more than 90 days.
 
b. A core spiral offload is in progress.    -
c. A control rod blade replacement is in progress.
 
d. None. Fuel handling must always be terminated if SRMs fall below 3 cps.
 
.
Page 46 of 50
  "*" EXAMINATION CONTINUED ON NEXT PAGE ""'
 
      '
REACTOR OPERATOR EXAMINATION Question 93 l
A task in the RCA requires that you enter a Very High Radiation Area during normal plant operations. Which one of the following describes the minimum key (s) and RWP coverage requirements necessary to enter the area?
a. Single key from radiation Protection; Non-routine RWP b. Single key from Shift Manager; Operations standing RWP.
 
c. One key from Radiation Protection and one key from Shift Manager; Non-routine RWP.
 
d. One key from Radiation Protection and one key from Shift Manager; Operations standing RWP.
 
Question 94 You are wearing single PCs while working in the Reactor Building when immediate evacuation of the Reactor Building is directed over the Gaitronics. You should remove your PCs at which one of the following places?
a. Your current location when you hear the announcement.
 
b. Area Normal Step Off Pad.
 
c. Prior to entering the Reactor Building Airlock.
 
d. Admin Building RCA Access Point.
 
Page 47 of 50
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      )
REACTOR OPERATOR EXAMINATION Question 95 You are NCOI performing a shutdown from outside the Control Room. When you arrive at Panel 25RSP you report successful completion of all actions you were required to perform at other lo.:ations. Which one of the following actions remains to be accomplished?
a. Tripping the Main Turbine.
 
b. Closing the MSIVs.
 
I c. Closing the HPCI outboard steam supply.
 
d. Tripping the Recire. pumps.
 
Question 96 An Alert has been declared and the operators are conducting EOP-6 (Radioactivity Release Control). Which one of the following is a type of accident that this EOP is designed to mitigate?
a. Dropped fuel bundle in the Spent Fuel Pool.
 
b. Radwaste spill in the Radwaste Building.
 
c. Main Steam leak in the Turbine Building.
 
.
d. Fire in the SBGT filters.
 
Page 48 of 50
  "*" EXAMINATION CONTINUED ON NEXT PAGE "*"
 
REACTOR OPERATOR EXAMINATION-Question 97 Following a failure to scram an operator has been directed to implement EP-3 (Backup Control Rod Insertion) at Panels 09-15 and 09-17 to remove and replace fuses. Which one of the following describes the desired outcome of this evolution?
a. Open the scram inlet and outlet valves.
 
b. Deenergize the RPS power supply buses.
 
c. Vent and Drain the Scram Discharge Volume.
 
d. Reset RPS.
 
Question 98 The reactor is operating at full power when the following events occur:
. The Turbine Control Valves close.
 
. The Turbine Bypass Valves fully open.
 
. The Reactor Scrams.
 
. The SRVs open briefly.
 
Which one of the following could have caused this chain of events?
a. Turbine Load Reference signal has failed downscale.
 
b. The MSIVs have closed.
 
c. The Backup (B) Pressure Regulator has failed low.
 
d. The Maximum Combined Flow Limiter has failed downscale.
 
Page 49 of 50
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m REACTOR OPERATOR EXAMINATION
 
!
!
Question 99 A scram has occurred due to a transient resulting from a loss of UPS. Not all rods have fully
      ~
inserted. Which one of the following should be used to evaluate reactor power to determine .
l if entry into EOP-2 (RPV Control) is required?
l a. APRM chart recorders.
 
b. SPDS display.
 
c. Steam Flow.
 
d. Number of open SRVs.
 
.
Question 100 The following conditions exist:
. A LOCA has occurred at 100% power.
 
. EPIC is not available.
 
. 16TI-107 and 108 both indicate 256 *F.
 
. Drywell pressure on panel 09-3 indicates 40 psig.
 
. RPV 09-5 Wide Range indicates 40 inches.
 
. RPV 09-3 Fuel Zone Recorder indicates -130 inches.
 
Which one of the following describes the use of the Fuel Zone Recorder and the Wide Range :
Instruments?
NOTE: Figures 4.7 and 4.8 of EOP-4 are provided.
 
.
a. Neither the Fuel Zone Recorder nor the Wide Range is usable.
 
b. Fuel Zone Recorder is usable; Wide Range is not usable.
 
c. Fuel Zone Recorder is not usable; Wide Range is usable.
 
d. Both the Fuel Zone Recorder and the Wide Range are usable.
 
Page 50 of 50 l  * *"* END OF EXAMINATION * * * * *
 
    ;
    .
LOSS OF SHUTDOWN COOLING *  AOP-30 ATTACHMENT 2  Page 1 of 1 CORE DECAY HEAT VS. TIME AFTER SHUTDOWN Days after BTU /hr Days after BTU /hr shutdown  shutdown 0 6.28E8  21 1.48E7 1 4.79E7 l 22 1.44E7 2 3.92E7 l 23 1.42E7 3 3.36E7 l 24 1.39E7 4 2.97E7 l 25 1.36E7 5 2.69E7 l 26 1.33E7 l
'
6 2.48E7  27 1.31E7 7 2.32E7 l 28 1.28E7 8 2.19E7 l 29 1.26E7 9 2.08E7 l . 30 1.24E7 10 2.00E7 l 31 1.22E7 11 1.92E7 l 32 1.20E7 12 1.86E7 l 33 1.18E7 13 1.80E7 l 34 1.16E7 14 1.75E7 l 35 1.14E7 15 1.70E7 l 36 1.12E7 16 1.66E7 l 37 1.10E7 17 1.62E7 l 38 1.09E7 18 1.58E7 l 39 1.07E7 19 1.54E7 l 40 1.06E7 20 1.51E7 l 730 9.13E5 Rev. No. 10  Page 18 of 19
 
    's ,
LOSS OF SHUTDOWN COOLING *    AOP-30 ATTACHMENT 3  Page 1 of 1 ALTERNATE COOLING METHODS METHOD -
APPROXIMATE HEAT LIMITATIONS i REMOVAL CAPACITY (BTU /hr)
 
Decay Heat Removal  3.00E7 * Gates removed between cavity and spent fuel pool Fuel Pool Cooling  3.30E6 * Gates removed between cavity and spent fuel pool i
    * RBC must be available
    * SW must be available
. Fuel Pool Cooling  2.40E7 * RHR must be available Assist
    * RNRSW must be available e Gates removed between cavity and spent fuel pool RWCU Blowdown Mode  2.06E6 * No isolation signal present-
* 1 pump running  * Makeup source must be
* 225 gpm blowdown flow  -
available (see list below)
* 125 gpm snakeup flow
    * Main Condenser.or Radwaste must be available RWCU Recirc Mode  1.70E6 No isolation signal present RWCU Blowdown Mode  1.00E6 * No isolation signal present
* gravity drain  * Makeup source must be
* 50 gpm blowdown flow  available (see list below)
* 50 gpm makeup flow    .
    * Main Condenser or Radwaste must be available Makeup sources
* Condensate transfer keep-full using Core Spray or RHR
* Control Rod Drive System
* Condensate /Feedwater
* Condensate transfer to skiauner surge tanks (gates removed)
* Condensate transfer to fuel pool using DHR (gates removed)
* Condensate transfer using service box connections on the refuel floor (gates r2 moved)
* Fire Protection System water from local fire hose stations or outside sources
* RHR service water cross-tie
* Fire Water Crosstie
      .
Rev. No. 10  Page 19 of 19
 
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b An R. v;er levelinstrument rnav not be used if either of th3 following conditions exists:
  + An instrurnent run terrporature is at or above the RPV Saturation Terrporature (Fig 4.7)
  . The instrurnent roads at or below its Minimum Usable indcating Level (Fig 4.8)
FIGURE 4.7 RPV SATURATION TEMPERATURE e00
    ! i ii!OE d!!!! ! ! !!!;e !!!ll; !!!!n c =
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  * h E 0 F 5 !!
g sw
    -
    ,
u; E a f
 
2m ,  .
0 100 200 300 400 500 em 700 000 90010001100 RPV PRESSURE (psig)
FIGURE 4.8 MINIMUM USABLE INDICATING LEVELS (in.)
 
e- Ez n E& i .' .& $$ $3 Eb $$ $$ $$
    "
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E sa  1-4a  a a E  180 250 l$ ,oo _
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g  171 225
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  $  200 43 -145 -134
 
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tt cc  164.5 u
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    ,
Nb  "
    .) _ _"_ _"_ _"_
t _ - - - - - - - - - - - - - - -
 
i
 
    .-
RO ANSWER KEY 1) B 26) D 51) D 76) D 2) A 27) B 52) C 77) D.
 
i 3) B 28) B 53) B 78) D -
4) B 29) C 54) C 79) A 5) D 30) A 55) A 80) A 6) D 31) DELETED 56) A 81) C 7) B 32) B 57) A 82) C 8) C 33) D 58) D 83) B 9) DB 34) D 59) D 84) B 10) A 35) C 60) D 85) A 11) C 36) B 61) OR B 86) D 12) A 37) D 62) *
  .. 87) B 13) B 38) C taj ti 88) B 14) A 39) C 64) A 89) C 15) C 40) A 65) C 90) C 16) A 41) C 66) C 91) C ,
17) B 42) D 67) C 92) B 18) A 43) D 68) A 93) C 19) B 44) DA 69) B 94) D 20) B 45) D 70) D 95) C 21)- D 46) B 71) A 96) C 22) D 47) C 72) D 97) A 23) D 48) C 73) C 98) A 24) D 49) B 74) C 99) B 25) A 50) A 75) D 100) B
,
e
 
ATTACHMENT 2
 
RO EXAMINATION AND ANSWER KEY l
,
 
ATTACHMENT 3 JAF COMMENTS ON WRITTEN EXAMINATION
 
      . r RO 009 SRO 009 During the post-examination review, it was discovered that the key contained an incorrect answer, D vice the correct answer, B. This was a typographical error that occurred while balancing the examination di. tractors. The first submittal (attached) indicated the answer correctly.
 
Distractor. A is incorrect because the red light on indicates that the pilot solenoid is energized, not that the main valve is open.
 
l Distractor C is incorrect because the SRV tailpiece would rise to approximately 380
!
degrees if the valve were open.
 
Distractor D is incorrect because the EPIC alarm RESET condition indicates that the high noise level condition associated with an open SRV has cleared.
 
I The key was changed from D to B to correct this error.
 
!
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010 TIER 1 GROUP 1/1 LICENSE LEVEL RS  KNOWLEDGE LEVEL L  ANSWER A
        -
Which one of the following would give positive indication that an SRV is currently open as a result of an automatic actuation caused by high RPV pressure?
a. White acoustic monitor light is on.
 
b. Tailpiece temperature is 235 *F.
 
c. Tailpiece temperature is 310 *F.
 
d. Red valve open light is on.
 
295025 HIGH REACTOR PbSSURE      2.4.03 l Ability to identify post-accident instrumentation.
 
IMPORTANCE 3.5/3.8  10CFR55.41(6)/()  10CFR55.43( )/()  SOURCE 10CFR55 REASON REFERENCE  SDLP-16B, Page 40      ,
ATTACHMENT
      -
LESSON PLAN SDLP-16B    OBJECTIVE 1.01 NOTES
_
CHANGES FROM ORIGINAL OUTLINE ORIGINAL SYSTEM / EVENT #    ORIGINAL K/A#
REASON FOR CHANGE KNOWLEDGE LEVEL L-Lower (Recall) H= Higher LICENSE LEVEL R=RO S=SRO RS=Both SOURCE N=New Question B= Exam Bank (Not seen before) S-Bank (Seen in training program) M= Modified 10CI'R55 listings are the sub-paragraph numbers under 10CFR 55 4 I (for ROs) or 55.43 (for SROs) addressed by this question.
 
10CFR$$ reference is listed as (Assigned by K/A Manual) / (Assigned by question author)
Group and imponance are listed as RO/SRO values
        .
 
RO 031 SRO031 This question was deleted from the examination. During the post-examination review it was determined that the question had no correct answer. The limits stated form an envelope that bounds the operation of the system and no direction exists to violate one limit at the expense of another.
 
a. _ OP-20, STANDBY GAS TREATMENT SYSTEM, directs: IF reactor building differential pressure is less negative than --0.25 inches water, THEN ensure that SGT Train A (B) is in service per Subsection D.l(2).' No direction is given allowing this limit to be violated to meet other limits.
 
b. OP-20, STANDBY GAS TREATMENT SYSTEM, directs if the high temperature annunciator is received then the affected train is shutdown and cooling flow for the charcoal filters established using the other train.2 No direction is given allowing this limit to be violated to meet other limits.
 
c. OP-20, STANDBY GAS TREATMENT SYSTEM, directs: Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125F1-106A(B).3 No direction is given allowing this limit to be violated to meet other limits.
 
ONO, STANDBY GAS TREATMENT SYSTEM, revision 22, steps D.I.6 on pg.1 I, D.2.6 on pg.13, G.5.2 on pg. 28 and G.6.2 on pg. 29,
 
OP-20, STANDBY GAS TREATMENT SYSTEM, revision 22, steps G.I .4 on pg. 20 and G.2.4 on pg.
 
21.
 
*
OP-20, STANDBY GAS TREATMENT SYSTEM, revision 22, steps D.1.5.b on pg.11, D.2.5.b on pg.
 
13, G.5.3 on pg. 28 and G.6.3 on pg. 29.
 
1 ARP 09-75 2-16 ANNUNCIATOR SGT SYS B LEGEND ACT CHAR ..
mP HI  CONTROLLED COPY SENSOR / 01-125TS-1*? SCT FILTEA TRAIN "B" CHARCOAL FILTER TEMP !
      '
TRIP POINT SWITCH (l' f)
CAUSE Heat from decay of fission products adsorbed by charcoal filters.
 
AUTOMATIC None ACTION OPERATOR 1. Refer to OP-20, Standby Cas Treatment System,
. ACTION  section C for actions to be taken.
 
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l Rev. No. 3  PORC Meeting No. 90-088 Date 08/29/90  Page 1 of 1 l
 
      !
ARP 09-75-1-16
      {
      !
ANNUNCIATOR SCT SYS A    l j
LEGEND ACT CHAR j
TEMP    i HI SENSOR / 01-125TS-12A SGT FILTER TRAIN "A" CHARCOAL FILTER TEMP TRIP POINT SWITCH (170*F)
c.- r-n ni t.ED COPY CAUSE Heat from decay of fission products adsorbed by charcoal filters. ,
AUTOMATIC None ACTION OPEFATOR 1. Refer to OP-20, Standby Gas Treatment System, ACTION  section C for actions to be taken.
 
Rev. No. 4  PORC Meeting No. 90-088 Date 08/29/90  Page 1 of 1
 
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATING PROCEDURE STANDBY GAS TREATMENT SYSTEM *  .
OP-20 REVISION 22  i REVIEWED BY: PLANT OPERATING REVIEW COMMITTEE MEETING NO. NA  DATE NA APPROVED BY:  - e  DATE /2[T[74 RESPON5)BLE P'ROCED OWNER APPROVED BY: km0 -- -  DATE 11 V f6
    '/
P % MAlfAGER
*
EFFECTIVE DATE: December 4, 1996 FIRST ISSUE D FULL REVISION D LIMITED REVISION 8
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* REFERENCE USE * * T  I
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  . * * OLLED **
: ********.**.**.**..****** yync COPY # g* *.* ***.* ES
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*  *
  *
WITH TEMPORARY CHA
* TECHNICAL
*
******.******************
  * NOT UPDATEDBEFERENCE USE i
PERIODIC REVIEW DUE DATE 2/13/98  .
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      .
STANDBY GAS TREATMENT SYSTEM *    CP-20
     .
REVISION SUMMARY SHEET REV. NO. CHANGE AND REASON FOR CHANGE 22  Added Precaution C.2.1 to require Reactor Building Ventilation be isolated before performing any of the following activitics. This action is necessary to comply with the requirements of safety evaluation JAF-SE-96-071:
  * Fuel hanuling
  * Core alterations
  * Movement of heavy loads over the spent fuel pool or open reactor cavity
  * Placing RX MODE switch in START & HOT STBY, without Primary Containment Integrity in effect 21  1. Added Subsections G.8 and G.9 to provide guidance for operation of the Standby Gas Treatment System during filter testing.
 
.
2. Added Subsection G.10 to provide guidance for operation cf the Standby Gas Treatment System during filter sampling. (PCR dated 3/26/96)
20  1. Added Subsection G.7, to provide steps for operating SBGT when secondary containment penetrations are opened or degraded per PCR #10 dated 10/25/95.
 
2.. Changed description of activated charcoal in
  :
  :
i e n' 1? T n' 'T9 f.,
Section-B, System Description per PCR #9 dated 7/10/95.
L,', , , , 6 <
 
J, J J. J
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  :Rev.-No.- 7-  PORC' Meeting N NA
  '
  :Datei 1/17/96  Page 1 of 1
  . Revised Precaution C.2.2 to ine'.ude time limits per PCR #8 dated 7/10/95 and J. Dunham.
 
 
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Rev. No. 22  Page 2 of 45
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I STANDBY GAS TREATMENT SYSTEM *    OP-20 l
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    .
l TABLE OF CONTENTS l SECTION      PAGE
 
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; A. REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . .  .4
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B. SYSTEM DESCRIPTION . . . . . . . . . . . . . . . . . . . . 5 C. PLANT OPERATING REQUIREMENTS  . . . .. . . . . . . . . . . 7 l D. STARTUP . . . . . . . . . . . . . . . . . . . . . . . . . 9 E. NORMAL OPERATION . . . . . . . . . . . . . . . . . . . . 14 F. SHUTDOWN . . . . . . . . . . . . . . . . . . . . . . . . 16 G. SPECIAL PROCEDURES . . . . . . . . . . . . . . . . . . . 19 H. ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . 36 1. REFERENCES . . . . . . . . . . . . . . . . . . . . . 37 2. TABLE 1 - VALVE LINEUP  . . . . . . . . . . . . . . . 38 3. TABLE 2 - MAJOR COMPONENT POWER SUPPLIES  . . . . . . 43
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STANDBY GAS TREATMENT SYSTEM *  OP-20 A. REQUIREMENTS A.1 Technical Specifications Volume 1A Sections 3.7.B, 3.7.C and 4.7.C Volume 1B Section 3.8 A.2 Commitments None A.3 Validation Validated per ODSO-35.
 
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Rev. No. 22  Page 4 of 45
 
l STANDBY GAS TREATMENT SYSTEM *  OP-20 i B. SYSTEM DESCRIPTION The Standby Gas Treatment System includes two identical filter tra',ns. Each filter train is a full capacity system -
that has the ability to maintain reactor building to i
    '
atmosphere differential pressure more negative than negative O.25 inches water gauge.
 
Each filter train includes the.following:
* Demister: Removes entrained moisture, and in conjunction with the air heater, maintains humiolty less than 70% at the inlet to the charcoal filter.
 
* 39 KW Electric Air Heater: Maintains humidity less than 70% at the inlet to the charcoal filter.
 
* Prefilter: Removes particles.
 
* High Ef ficiency Particulate Absolute Pre-Filter (HEPA) :
Designed to be capable of removing at least 99.97% of the 0.3 micron particles which impinge on the filter, however credit is only taken for 90% removal capability.
 
* Activated Charcoal Filter: Removes in excess of 95% of the iodine in the air stream, with 10% of the iodine in the form of methyl iodide, with air entering the charcoal
- filter at less than *iO% humidity. Charcoal filter material is iodide or T2DA impregnated activated carbon.
 
* High Efficiency Particulate Absciute Af^er-Filter (HEPA) :
Designed to be capable of removir.g at least 99.97% of the 0.3 micron particles which impinge on the filter, however credit is only taken for 90% removal capability.
 
* Fan: Provides the differential pressure to draw gases through the train for treatment. The fan discharges to the stack.
 
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Rev. No. 22  Page 5 of 45
 
STANDBY GAS TREATMENT SYSTEM *  OP-20 Each filter train can take suction from one or more of the following suction supplies:
* Reactor Building above 369' elevation
* Reactor Building below 369' elevation
* Drywell vent connections
* Torus vent connections
* HPCI gland seal exhauster
* Main Steam Leakage Collection System
* Auxiliary Gas Treatment System Standby gas treatment trains are cross-tied at the fan suctions to allow drawing cool air over the charcoal filter of the inactive train to remove decay heat.
 
T'he Standby Gas Treatment System auto-initiates when any of the following conditions occur:
* Reactor Building Ventilation above 369' elevation exhaust duct radiation high-high: PCIS logic A sensors start A train; PCIS logic B sensors start B train
.
* Reactor Building Ventilation below 369' elevation exhaust duct radiation high-high: PCIS logic A sensors start A train; PCIS logic B sensors start B train
* Drywell pressure high (2.7 psig increasing) : Both trains start
* RPV water level low (177 inches decreasing) : PCIS logic A sensors start A train; PCIS logic B sensors start B train
-
* HPCI auto-initiation: Both trains start The Standby Gas Treatment System can be manually placed in service from panel 09-75 in the Control Room.
 
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Rev. No. 22  Page 6 of 45 l
 
l STANDBY GAS TREATMENT SYSTEM *  OP-20 C. PLANT OPERATING REQUIREMENTS C.1 Prerequisites C.1.1 System valves are lined up per Attachment 2, with exceptions approved by the Shift Manager.
 
c.1.2 System power supplies are lined up per Attachment 3, with exceptions approved by the Shift Managen.
 
c.1.3 The following systems are in operation per their respective operating procedure, with exceptions approved by the shift Manager:
  * 4160 V and 600 V Normal And Emergency AC Power Distribution per OP-46A
  * Process Radiation Monitoring System per OP-31
  * Fire Protection System per OP-33.
 
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Fev. No. 22  Page 7 of 45
 
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STANDBY GAS TREATMENT SYSTEM *  OP-20 C.2 Precautions    I l
C.2.1    !
Reactor building ventilation shall be isolated before performing any of the following activities.
 
This action is necessary to comply with the requirements of safety evaluation JAF-SE-96-071:
  * Fuel handling I
e Core alterations
  * Movement of heavy loads over the spent fuel pool or open reactor cavity
  * Placing RX MODE switch in START & HOT STBY, without Primary Containment Integrity in effect C.2.2 During normal operation, 27MOV-120 (containment ;
exhaust to standby gas treatment isol valve) shall remain closed when primary containment is required per Tech Spec 4.7.B.4.
 
C.2.3 Operating a SGT train with the charcoal filters installed to vent paint fumes, welding fumes, or smoke could damage the charcoal filter. Guidelines to prevent possible charcoal filter damage from
-
paint fumes are as follows:
  * Painting shall stop during periods of SGT operation.
 
* Painting shall stop whenever Reactor Building ventilation is isolated, unless SGT will not be '
required for 24 hours following the completion of painting.
 
* SGT should not be run for at least 30 minutes following the completion of painting.
 
* If a SGT lun is desired within 8 hours following painting, Peactor Building Ventilation should not be isolated until the end of the SGT run.
 
* SGT runs are kept as short as possible within 8 hours following painting.
 
C.2.4 To prevent plugging of the spray nozzles from debris caused by rust or corrosion, the fire protection water supply spray header between  i 76FCV-107A/B and the spray nozzles shall be drained i following system actuation.
 
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Rev. !!c. 22  Page 8 of 45
 
      . 1 STANDBY GAS TREATMENT SYSTEM *    OP-20
    .
      ;
D.- STARTUP      i TABLE OF CONTENTS SUBSECTION    g D.1 Train A Startup . . . . . . . . . . . . , , . . . . . ,  lo D.2 Train B Startup . . . . . . . . . . . . . . , , . , , ,  12 l
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Rev. No. 22    Page 9 of 45
 
    .-
STANDBY GAS TREATMENT SYSTEM *  OP-20 D.1 Train A Startup CAUTION Operating a standby gas treatment train with the charcoal filters installed to vent paint fumes, welding fumes, or smoke could damage the charcoal filter. See Precaution C.2.2.
 
D.1.1 Ensure open at least one of the follcaing valves:
  * ABOVE EL 369' SUCT 01-125MOV-11
  * BELOW EL 369' SUCT 01-125MOV-12 D.1.2 Ensure open TRAIN A INLET 01-125MOV-14A.
 
D.1.3 Verify the 'ollowing:
Comoonent  Status ,
  * TRAIN A FN 01-125FN-1A  Running
  * FN DISCH 01-125MOV-15A  Open
  * TRAIN A CLG VLV 01-125MOV-100A Closed
  * Red light for AIR HTR 01-125E-5A On D.1.4 IF standby gas treatment is being placed in service to support any of the following:
  * Torus venting
  * Drywell venting
  * HPCI operation
-
  * Main Steam Leakage Collection System operation
  * Auxiliary Gas Treatment System operation THEN ensure required standby gas treatment suction valves are lined up.per the applicable procedure prior to proceeding to Step D.1.5.
 
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Rev. No. 22  Page 10 of 45 l
 
STANDBY GAS TREATMENT SYSTEM 0  OP-20 l
D.1.5 IF SGT Train B is shutdown,  I THEN perform the following:  l j
a. Verify open TRAIN B CLG VLV 01-125MOV-100B.
 
NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2A (SGT fan A suct isol valve).
 
b. Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A.
 
D.1.6 IF RB DIFF PRESS 01-125DPI-100A or B indicates less negative than - 0.25 inches water, TEEN ensure SGT Train B is in service per Subsection D.2.
 
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Rev. No. 22  Page 11 of 45
 
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STANDBY GAS TREA'.WENT SYSTEM *  OP-20 D.2 Train B Startup -
CAUTION Operating a standby gas treatment train with the charcoal filters installed to vent paint fumes, welding fumes, or smoke could damage the charcoal filter. See Precaution C.2.2.
 
D.2.1 Ensure open at least one of the following valves:
  * ABOVE EL 369' SUCT 01-125MOV-11
  * BELOW EL 369' SUCT 01-125MOV-12 D.2.2 Ensure open TRAIN B INLET 01-125MOV-14B.
 
D.2.3 Verify the following:
Comoonent  Status
  * TRAIN B FN 01-125FN-1B  Running
  * FN DISCH 01-125MOV-15B  Open
.
  * TRAIN B CLG VLV 01-125MOV-100B Closed
  * Red light for AIR HTR 01-125E-5B On D.2.4 IF standby gas treatment is being placed in service to support any of the following:
  * Torus venting
  * Drywell venting
  * HPCI operation
"  ~
  * Main Steam Leakage Collection System operation
  *
Auxiliary Gas Treatment System operation  I TREN ensure required standby gas treatment suction valves are lined up per the applicable procedure prior to proceeding to Step D.2.5.
 
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Rev. No. 22  Page 12 of 45
      ..
  .. .. .- . _ _ _ _ _ _ ..
 
I STANDBY GAS TREATMENT' SYSTEM *  OP-20 D.2.5 IF SGT Train A is shutdown, THEN perform the following:  ;
a. Verify open TRAIN A CLG VLV 01-125MOV-100A.
 
.
NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2B (SGT fan B suct isol valve). .
b. Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A.
 
D.2.6 IF RB DIFF PRESS 01-125DPI-100A or B indicates less negative than - 0.25 inches water, TEEN ensure SGT Train A is in service per Subsection D.1.
 
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Rev. No. 22  Page 13 of 45 I
 
      .
STANDBY GAS TREATMENT SYSTEM *    OP-20 E. NORMAL OPERATION E.1 The Standby Gas Treatment System is normally maintained in the following standby lineup:
* Valves lined up per Attachment 2 Component power supplies lined up per Attachment 3
    -
*
* Panel 09-75 indications and controls as follows:
Valves Common To Both SGT Trains Comoonent    Status ABOVE EL 369' SUCT 01-125MOV-11 . . . . . . . . . Closed BELOW EL 369' SUCT 01-125MOV-12 . . . . . . . . . Closed Train A Standbv Lineun Comoonent    Status AIR HTR 01-125E-5A . . . . . White light on, red light off HPCI GLAND SEAL SUCT 01-125MOV-13A . . . . . . . . Closed
.
TRAIN A CLG VLV 01-125MOV-100A . . . . . . . . . . . Open TRAIN A INLET 01-125MOV-14A . . . . . . . . . . . Closed 1 J
FN DISCH 01-125MOV-15A . . . . . . . . . . . . . . Closed TRAIN A FN 01-125FN-1A . . . . . . . . . . . . . Shutdown Train B Standbv Lineuo
#
Component    Status AIR HTR 01-125E-5B . . . . . White light on, red light off HPCI GLAND SEAL SUCT 01-125MOV-13B .  . . . . . . . Closed TRAIN B CLG VLV 01-125MOV-100B . . . . . . . . . . . Open TRAIN B INLET 01-125MOV-14B . . . . . . . . . . . Closed FN DISCH 01-125MOV-15B . . . . . . . . . . . . . . Closed TRAIN B FN 01-125FN-1B . . . . . . . . . . . . . Shutdown
  ,Section ( E continued on next page)
Rev. No. 22    Page 14 of 45 i
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    .
STANDBY GAS TREATMENT SYSTEM * *
OP-20 E. (Cont)
E.2 Whenever standby gas treatment is in service, monitor the following parameters per ODSo-17:
* Prefilter differential pressure: maximum 0.75 inches water gauge on 01-125DPIS-1A(B)
* HEPA filter differential pressure: maximum 1.5 inches water gauge on 01-125DPIS-2A(B)
* Carbon filter differential pressure: maximum 1.5 inches water' gauge on 01-125DPIS-3A(B)
* After filter differential pressure: maximum 1.5 inches water gauge'on 01-125DPIS-4A(B)
* SGT flow on 01-125FI-106B: 3000 to 6000 scfm
.
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,:
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Rev. No. 22  Page 15 of 45 q
 
      .
STANDBY GAS TREATMENT SYSTEM *  OP-20 F. SHUTDOWN TABLE OF CONTENTS SUBSECTION    PAGE F.1 Train A Shutdown . . . . . . . . . . . . . . . . . . . . 17 F.2 Train B Shutdown . . . . . . . . . . . . . . . . . . . . 18 l
.
 
  .
Rev. No. 22  Page 16 of 45 l
i
 
STANDBY GAS TREATMENT SYSTEM *  OP-20 F.1 Train A Shutdown *
F.1.1 Ensure SGT Train A operation is not required.
 
F.1.2 IF SGT Train B is shutdown,  . l THEN ensure closed the following valves:  J l
  * DW TORUS EXH TO SGT ISOL VLV 27MOV-121 (at panel 27PCP)
  * DW/ TORUS EXH TO SGT ISOL VLV 27MOV-120 (at panel 27PCP)
  * HPCI GLAND SEAL SUCT 01-125MOV-13A
  * HPCI GLAND SEAL SUCT 01-125MOV-13B
      !
  * ABOVE EL 369' SUCT 01-125MOV-11
  * BELOW EL 369' SUCT 01-125MOV-12
    .
F.1.3 Close TRAIN A INLET 01-125MOV-14A.
 
F.1.4 Verify the following:  !
Comoonent  $1gug
  * TRAIN A FN 01-125FN-1A  Shutdown !
  * FN DISCH 01-125MOV-15A  . Closed
  * TRAIN A CLG VLV 01-125MOV-100A Open
  * Red light for AIR HTR 01-125E-5A Off
  * White light for AIR HTR 01-125E-5A On F.1.5 IF SGT Train B is in service,  !
 
TEEN ensure flow rate is 3000 to 6000 scfm  i on SGT FLOW 01-125FI-106A.
 
NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2B (SGT fan B suct isol valve).
 
.
      !
    .
      .
  .
Rev. No. __ 22  Page 17 of 45
 
STANDBY GAS TREATMENT SYSTEM *  OP-20 F.2 Train B Shutdown -
F.2.1 Ensure SGT Train B operation is not required.
 
F.2.2 IF SGT Train A is shutdown, THEN ensure closed the following valves:
  * DW TORUS EXH TO SGT ISOL VLV 27MOV-121 (at panel 27PCP)
  * DW/ TORUS EXH TO SGT ISOL VLV 27MOV-120 (at panel 27PCP)
  * HPCI GLAND SEAL SUCT 01-125MOV-13A
  * HPCI GLAND SEAL SUCT 01-125MOV-13B e ABOVE EL 369' SUCT 01-125MOV-11
  * BELOW EL 369' SUCT 01-125MOV-12 F.2.3 Close TRAIN B INLET 01-125MOV-14B.
 
F.2.4 Verify the following:
Comoonent  Status
-  * TRAIN B FN 01-125FN-1B  Shutdown
  * FN DISCH 01-125MOV-15B  Closed
    !
  * TRAIN B CLG VLV 01-125MOV-100B Open 1
  * Red light for AIR HTR 01-125E-5B Off
  * White light for AIR HTR 01-125E-5B On F.2.5 IF SGT Train A is in service,
-
TEEN ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A.
 
NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2A (SGT fan A suct isol valve) .
  '    j Rev. No. 22  Page 18 of 45
 
      ,
      '
  .
 
STANDBY GAS TREATMENT SYSTEM 0    OP-20 G. SPECIAL PROCEDURES TABLE OF CONTENTS SUBSECTION      PAGE G.1 Train A Charcoal Filter Cooling . . . . . . . . . . . . 20 G.2 Train B Charcoal Filter Cooling . . . . . . . . . . . . 21 G.3 Train A Charcoal Filter Fire Protection Water Spray  . . 22 G.4 Train B Charcoal Filter Fire Protection Water Spray  . . 25 G.5 Train A Auto-Initiation Verification . . . . . . . . . . 28 G.6 Train B Auto-Initiation Verification . . . . . . . . . . 29 G.7 Maintenance of Secondary Containment Integrity with a Degraded or Open Reactor Building Penetration . . . . 30 G.8 SGT Train A Operation During Filter Testing  . . . . . . 31 G.9 SGT Train B Operation During Filter Testing  . . . . . . 33 G.10 SG'.' Train Operation During Filter Sampling . . . . . . . 35
  .
Rev. No. 22  Page 19 of 45
 
    ..
_
STANDBY GAS TREATMENT SYSTEM *    OP-20 G.1 Train A Charcoal Filter Cooling G.1.1  IF amber SBGT A WTR SPRAY SYS HI TEMP light is on at panel FPP, THEN exit Subsection G.1 and proceed to Subsection G.3.
 
G.1.2  WHILE performing the following steps, periodically monitor annunciator 09-75-1-16 SGT SYS A ACT CHAR TEMP HI.
 
G.1.3  Ensure SGT Train B is in service per Subsection D.2.
 
G.1.4  IF SGT Train A is in service, THEN shutdown SGT Train A as follows:
a. Close TRAIN A INLET 01-125MOV-14A.
 
b. Verify the following:
Comoonent  Status
  *
TRAIN A FN 01-125FN-1A  Shutdown
  * FN DISCH 01-125MOV-15A  Closed
  *
TRAIN A CLG VLV 01-125MOV-100A Open
  * Red light for AIR HTR 01-125E-5A Off
  * White light for AIR HTR 01-125E-5A On G.1.5  Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A.
 
NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2B (SGT fan B suct isol valve).
 
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Rev. No. 22 _  Page 20 of 45
. _ _ _ _ _ _ _ _ _ _ _ _ _ .
 
STANDBY GAS TREATMENT SYSTEM *  OP-20 G.2 Train B Charcoal Filter Cooling G.2.1 IF amber SBGT B WTR SPRAY SYS HI TEMP light is on at panel FPP, THEN exit Subsection G.2 and proceed to  .
Subsection G.4. 1 G.2.2 WHILE performing the following steps, periodically monitor annunciator 09-75-2-16 SGT SYS B ACT CHAR TEMP HI. 1 G.2.3 Ensure SGT Train A is in service per Subsection D.1.
 
G.2.4 IF SGT Train B is in service, THEN shutdown SGT Train B as follows:
a. Close TRAIN B INLET 01-125MOV-14B.
 
b. Verify'the following:
    .
Component  Status
  * TRAIN B FN 01-125FN-1B Shutdown
  * FN DISCH 01-125MOV-15B Closed
.  * TRAIN B CLG VLV 01-125MOV-1008 Open
  * Red light for AIR HTR 01-125E-5B Off
  * White light for AIR HTR 01-125E-5B On G.2.5 Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A.
 
NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2A (SGT fan A suct isol valve). -
:
  .
    .
  .
Rev. No. 22  Page 21 of ., 45
 
STANDBY GAS TREATMENT SYSTEM *  OP-20 NOTE: The amber SBGT A WTR SDRAY SYS HI TEMP light will come on and an alarm bell will ring at panel FPP when the temperature setpoint of the charcoal filter heat detector is reached. SGT Train A charcoal filter water spray is a manually actuated system.
 
G.3 Train A Charcoal Filter Fire Protection Water Spray G.3.1 Shutdown SGT Train A as follows:
a. Close TRAIN A INLET 01-125MOV-14A.
 
b. Verify the following:
Comoonent  Status
  * TRAIN A FN 01-125FN-1A Shutdown l
  * FN DISCH 01-125MOV-15A Closed
  * TRAIN A CLG VLV 01-125MOV-100A Open
  * Red light AIR HTR 01-125E-5A Off G.3.2 Initiate water spray per Step a, b, or c:
a. To initiate water spray from panel FPP in Control Room, perform the following:
1) Depress SBGT A Spray System INIT pushbutton, 2) Verify red SBGT A WTR SPRAY SYS VLV OPEN light is on.
 
b. To initiate water spray from local breakglass station, break glass or remove retainer ring from SGT Train A breakglass station and verify button pops out, c. To initiate water spray from flow control valve emergency release station, pull down SGT Train A emergency release lever.  ;
  .
Rev. No. 22  Page 22 of 45
 
_ _ _
STANDBY GAS TREATMENT SYSTEM *  OP-20 CAUTION To prevent plugging of the spray nozzles from debris caused by rust or corrosion, the water spray header between 76FCV-107A and the spray nozzles shall be drained following system actuation.
 
G.3.3 WHEN train A water spray is no longer required, perform the following:
a. Close 76 FPS-123 (west SGT sprinkler supply gate 3 vdivC).
 
b. Drain fire protection supply header in SGT Room as follows:
1) Connect hose to fire protection supply header low point drain located by charcoal filter side panel.
 
2) Route hose to nearest floor drain.
 
3) Open fire protection supply header drain valve.
 
c. Drain 76FCV-107A flow control station header as follows:
1) Connect hose to drain header located under flow control valve.
 
2) Route hose to nearest floor drain or suitable container.
 
3) Open MAIN DRAIN and AUXILIARY DRAIN valves.
 
NOTE 1: Scaffolding may be necessary to reach overhead supply header drain plug.
 
NOTE 2: Supply header drain plug is located approximately 20 feet above and north of 71MCC-142 and panel 66HV-3B.
 
d. Drain fire protection supply header as follows:
1) Connect funnel and hose under supply header drain plug.
 
2) Route hose to nearest floor drain or suitable container.
 
, 3) Remove. supply header drain plug.
 
l
  *
Rev. No. 22  Page 23 of 45 x  ,
 
      '
    .
 
STANDBY GAS TREATMENT SYSTEM *  OP-20 e. WHEN supply header is drained, perform the following:
1) Close SGT Room supply header drain valve and disconnect hose.
 
l
'
2) Close MAIN DRAIN and AUXILIARY DRAIN valves for 76FCV-107A (flow control valve) and disconnect hose.
 
3) Install overhead supply header drain plug and disconnect funnel and hose.
 
f. Ensure WEST SGT TRAIN A SPRINKLER 3REAK GLASS STATION 76BGS-19 retaining ring and glass cover are installed.
 
g. Ensure closed emergency release lever for 76FCV-107A.
 
h. Depress plunger on drip check valve for 76PS-107A located by funnel to depressurize pressure switch.
 
i. Depress RESET pushbutton at panel 76CP-107A.
 
a j. Open the priming valve for 76FCV-107A and verify pressure rises on 76PI-107AB.
 
k. WHEN pressure on 76PI-107AB is stable, close priming valve for 76FCV-107A.
 
1. Crack open 76 FPS-123 and verify pressure rises on 76PI-107AA.
 
m. WHEN pressure is stable on 76PI-107AA, fully open 76 FPS-123.
 
*
n. Verify the following at panel 76CP-107A:
  * Red FLOW CONTROL VALVE OPEN light is off
  * Red GATE VALVE OPEN light is on o. Verify the following at panel FPP:
  * Green HDR VLV TROUBLE light is off
  * Red VLV OPEN light is on
  * Amber SBGT A WTR SPRAY SYS HI TEMP light is off
    *
  .
Rev. No. 22  Page 24 of 45
 
    .
STANDBY GAS TREATMENT SYSTEM * *
OP-20 NOTE: The amber SBGT B WTR SPRAY SYS HI TEMP light will come on and an alarm bell will ring at panel FPP when the temperature setpoint of the charcoal filter heat detector is reached. S3T Train B charcoal filter water spray is'a manually actuated system.  .
G.4 Train B Charcoal Filter Fire Protection Water Spray G.4.1 Shutdown SGT Train B as follows:
a. Close TRAIN B INLET 01-125MOV-14B.
 
b. Verify the following:
Component  Status
  * TRAIN B FN 01-125FN-1B Shutdown
  * FN DISCH 01-125MOV-15B Closed
  * TRAIN B CLG VLV 01-125MOV-100B Open .
  * Red light AIR HTR 01-125E-5B Off G.4.2 Initiate water spray per Step a, b, or c:
a. To initiate water spray from panel FPP in
-  Control Room, perform the following:
1) Depress SBGT B INIT pushbutton.
 
2) Verify red SBGT B WTR SPRAY SYS VLV OPEN light is on.
 
b. To inir.iate water spray from local breakglass station, break glass or remove retainer ring from SGT Train B breakglass stution and verify
,
button pops out.
 
.      .
c. To initiate water spray from flow control valve emergency release station, pull down SGT Train B emergency release lever.
 
-
      )
      "
  .
Rev. No. 22  Page 25 of 45 I
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      !
 
.
STANDBY GAS TREATMENT SYSTEM *  OP-20 CAUTION To prevent plugging of the spray nozzles from debris caused by rust or corrosion, the water spray '.eader
    . between 76FCV-107B and the spray nozzles shall be drained following system actuation.
 
G.4.3 WHEN train B water spray is no longer required, perform the following:
a. Close 76 FPS-122 (east SGT sprinkler supply gate valve).
 
b. Drain fire protection supply header in SGT Room as follows:
1) Connect hose to fire protection supply header low point drain located by charcoal filter side panel.
 
2) Route hose to nearest floor drain.
 
3) Open fire protection supply header drain valve.
 
c. Drain 7GFCV-107B flow control station header as
-
follows:
1) Connect hose to drain header located under flow control valve.
 
2) Route hose to nearest floor drain or !
suitable container. I 3) Open MAIN DRAIN and AUXILIARY DRAIN valves.
 
NOTE 1: Scaffolding may be necessary to reach
*
overhead supply header drain plug. )
l NOTE 2: Supply header drain plug is located approximately 20 feet above and north of 71MCC-142 and panel 66HV-3B.
 
d. Drain fire protection supply header as follows:
1) Connect funnel and hose under supply header drain plug. l i
2) Route hose to nearest floor drain or suitable container.
 
<
  , 3) Remove supply header drain plug.
 
Rev. No. 22  Page 26 of 45
 
STANDBY GAS TREATMENT SYSTEM *  OP-20 e. WHEN supply header is drained, perform the following:
1) Close SGT Room supply header drain valve and j disconnect hose.  .
l 2) Close MAIN DRAIN and AUXILIARY DRAIN valves for 76FCV-107B (flow control valve) and disconnect hose.
 
3) Install overhead supply header drain plug and disconnect funnel and hose.
 
f. Ensure EAST SGT TRAIN B SPRINKLER BREAK GLASS STATION 76BGS-20 retaining ring and glass cover are installed.
 
g. Ensure closed emergency release lever for 76FCV-107B.
 
l h. Depress plunger on drip check valve for 76PS-107B located by funnel to depressurize pressure switch.
 
i. Depress RESET pushbutton at panel 76CP-107B.
 
j. Open the priming valve for 76FCV-107B and verify
-
pressure rises on 76PI-107BB.  <
k. WHEN pressure on 76PI-107BB is stable, close priming valve for 76FCV-107B.
 
1. Crack open 76 FPS-122 and verify pressure rises on 76PI-107BA.
 
m. WHEN pressure is stable on 76PI-107BA, fully i open 76 FPS-122.  !
-
n. Verify the following at panel 76CP-107B:
  * Red FLOW CONTROL VALVE OPEN light is off
  * Red GATE VALVE OPEN light is on o. Verify the following at panel FPP:
  * Green HDR VLV TROUBLE light is off
  * Red VLV OPEN light is on
  * Amber SBGT B WTR SPRAY SYS HI TEMP light is off
  .
Rev. No. 22  Page 27 of 45
 
      .~
STANDBY GAS TREATMENT SYSTEM *  OP-20 G.5 Train A Auto-Initiation Verification
!
G.5.1 Verify the following:
Comnonent  Status
  * AIR HTR 01-125E-5A White light is on, red light is on
  * ABOVE EL 369' SUCT 01-125MOV-11 Open
  * TRAIN A CLG VLV 01-125MOV-100A Closed
  * TRAIN A INLET 01-125MOV-14A  Open
      )
  * FN DISCH 01-125MOV-15A  Open
  * TRAIN A FN 01-125FN-1A  Running G.5.2 IF reactor building differential pressure is less negative than - 0.25 inches water, THEN ensure SGT Train B is in service per  i Subsection D.2.
 
G.5.3 IF SGT Train B is shutdown,  ,
THEN ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A.
 
A NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2A (SGT fan A suct isol valve) .
G.5.4 IF both SGT trains are in service, THEN one SGT train may be shutdown per Subsection F.1 or F.2, at the Shift Manager's discretion.
 
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l Rev. No. 22  Page 28 of 45 l
 
STANDBY GAS TREATMENT SYSTEM *  OP-20
    .
G.6 Train B Auto-Initiation Verification G.6.1 verify the following:
Comoonent  Status -
  * AIR HTR 01-125E-5B White light is on,
. red light is on
  * BELOW EL 369' SUCT'01-125MOV-12  Open
  * TRAIN B CLG VLV 01-125MOV-100B  Closed
  * TRAIN B INLET 01-125MOV-14B  Open
  * FN DISCH 01-125MOV-15B  Open
  * TRAIN B FN 01-125FN-1B  Running G.6.2 IF reactor building differential pressure ,
is less negative than - 0.25 inches water, TEEN ensure SGT Train A is in service per Subsection D.1.
 
G 6.3 IF SGT Train A is shutdown, TREN ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A.
 
'
NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2B (SGT fan B suct isol valve).
 
G.6.4 IF both SGT trains are in service, THEN one SGT train may be shutdown per Subsection F.1 or F.2, at the Shift Manager's discretion.
 
.
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Rev. No. 22  Page 29 of 45
_
 
      .
    .
STANDBY GAS TREATMENT SYSTEM *  OP-20 G.7 Maintenance of Secondary Containment Integrity with a Degraded or Open Reactor Building Penetration G.7.1 Place SBGT train in service per Section D.
 
G.7.2 Isolate reactor building ventilation as follows: j a. Depress the following pushbuttons at panel 09-75:
  * RB VENT ISOL A
  * RB VENT ISOL B b. Verify isolation per Section G of OP-51A.
 
G.7.3 Prior to opening a secondary containment penetration notify the SM and Fire Protection Supervisor of the following:
  *
Penetration identification number
  *
Penetration area and elevation G.7.4 Establish communications between work site and  j control room.
 
-
G.7.5 WHEN secondary containment penetration is open, verify the following:
  *
Flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A (B)
  *
RB DIFF PRESS 01-125DPI-100A(B) indicates GREATER THAN negative 0.25 inches water G.7.6 IF reactor building differential pressure cannot be
 
maintained GREATER TRAN negative 0.25 inches water, THEN reseal secondary containment penetration.
 
G.7.7 IF reactor building differential pressure can be maintained GREATER TRAN negative 0.25 inches water, THEN restore from reactor building isolation per Section G of OP-51A.
 
G.7.8 WHEN secondary containment penetration is closed and maintenance is complete, nstore from reactor
 
building isolation per Secti G of OP-51A.
 
\
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Rev. No. 22  Page 30 of 45
 
,
    .
.
STANDBY GAS TREATMENT SYSTEM 0  OP-20 G.8 SGT Train A Operation During Filter Testing b
G.8.1 Ensure open the following valves:
  * ABOVE EL 369' SUCT 01-125MOV-11
  * BELOW EL 369' SUCT 01-125MOV-12 G.8.2 Open TRAIN A INLET 01-125MOV-14A.
 
G.8.3 Verify the following:
  * TRAIN A FN 01-125FN-1A is running
  * FN DISCH 01-125MOV-15A is open
  * ' TRAIN A CLG VLV 01-125MOV-100A is c?osed
    ~
  * Red light for AIR HTR 01-125E-5A is on G.8.4 IF flow rate is n t 6000 to 6100 scfm on SGT FLOW 01-125FI-106A, THEN throttle 01-125SGT-2A to establish 6000 to 6100 scfm on SGT FLOW 01-125FI-10EA.
 
G.8.5 WHEN testing is complete, perform the following:
    ,
a. Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A by throttling 01-125SGT-2A.
 
b. Close TRAIN A INLET 01-125MOV-14A.
 
G.B.6 Verify the following:
  * TRAIN A FN 01-125FN-1A is stopped
  * FN DISCH 01-125MOV-15A is closed  I
  * TRAIN A CLG VLV 01-125MOV-100A  i is open  1
  * Red light for AIR HTR 01-125E-5A is off
      '
  * White light for AIR HTR 01-125E-5A is on
      *
  .
Rev. No. 22  Page 31 of 45
      )
 
    .
    .
STANDBY GAS TREATMENT SYSTEM *  OP-20 G.8.7 IF testing of SGT trains is complete, THEN close the following valves:
  * ABOVE EL 369' SUCT 01-125MOV-11
  * BELOW EL 369' SUCT 01-125MOV-12
    .
.
    !
 
    ',. >
  .
Rev. No. 22  Page 32 of 45 l
 
-,
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l STANDBY GAS TREATMENT SYSTEM *  OP-20 l
      !
G.9 SGT Train B Operation During Filter Testing G.9.1 Ensure open the following valves:
  * ABOVE EL 369' SUCT 01-125MOV-11
  * BELOW EL 369' SUCT 01-125MOV-12 G.9.2 Open TRAIN E INLET 01-125MOV-14B.
 
G.9.3 Verify the following:
  * TRAIN B FN 01-125FN-1B is running
  * FN DISCH 01-125MOV-15B is open
  * TRAIN B CLG VLV 01-125MOV-100B is closed
  * Red light for AIR HTR 01-125E-5B *
is on G.9.4 IF flow rate is not 6000 to 6100 scfm on SGT FLOW 01-125FI-106A, THEN throttle 01-125SGT-2B to establish 6000 to 6100 scfm on SGT FLOW 01-125FI-106A.
 
. G.9.5 WHEN testing is complete, perform the following:
a. Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A by throttling 01-125SGT-2B.
 
b. Close TRAIN B INLET 01-125MOV-14B.
 
G.9.6 Verify the following:
'
  * TRAIN B FN 01-125FN-1B is stopped
,
  * FN DISCH 01-125MOV-15B is closed
  * TRAIN B CLG VLV 01-125MOV-100B is open
  * Red light for AIR HTR 01-12SE-5B is off
  * White light for AIR HTR 01-125E-5B is on
    .
  .
Rev. No. 22  Page 33 of 45
 
      "
    .
      .
STANDBY GAS TREATMENT SYSTEM *  OP-20 G.9.7 IF testing of SGT trains is complete, THEN close the following valves:
  * ABOVE EL 369' SUCT 01-125MOV-11
  * BELOW EL 369' SUCT 01-125MOV-12
      \
.
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Rev. No. 22  Page 34 of 45 L.      )
 
STANDBY GAS TREATMENT SYSTEM *  OP-20 G.10 SGT Train Operation During Filter Sampling G.10.1 IF SGT Train A will be sampled, THEN perform the following:
a. Declare SGT Train A inoperable per ODSO-34.
 
b. Ensure SGT Train A is shutdown per Section F.
 
c. Close 01-125SGT-3A (SGT train A fan 1A suct cross-tie isol valve).
 
d. WHEN sampling of SGT Train A is complete, perform the following:
1) Open 01-125SGT-3A.
 
2) IF it is desired to operate SGT Train A, THEN startup SGT Train A per Section D.
 
3) Consider declaring SGT Train A operable per ODSO-34.
 
G.10.2 IF SGT Train B will be sampled, THEN perform the following:
a. Declare SGT Train B inoperable per ODSO-34.
 
b. Ensure SGT Train B is shutdown per Section F.
 
c. Close 01-125SGT-3B (SGT train B fan IB suct cross-tie isol valve).
 
d. WHEN sampling of SGT Train B is complete, perform the following:
1) Open 01-125SGT-3B.
 
2) IF it is desired to operate SGT Train B, THEN startup SGT Train B per Section D.
 
3) Consider declaring SGT Train B operable per ODSO-34.
 
.
  .
Rev. No. 22  Page 35 of 45
 
RO 044 SRO 944 During the post-examination review, it was discovered that the key contained an incorrect answer, D vice the correct answer, A.
 
Distractor B is incorrect because an SRM reading less than 100 cps whose detector is not full in will generate a rod withdrawal block.
 
Distractors C and D are incorrect because detector motion is never blocked.
 
The key was changed from D to A to correct this error.
 
t
 
-
SDLP-07B    KEY AIDS a) Purpose - to allow the operator to swap recorder indication from IRM  J to APP.M/RBM on startups or back to IRM on shutdowns.
 
b) Positions - IRM-OFF-APRM (RBM)  -
      !
  (1) RBM A(B)/IRM G(D)
  (2) All other APRM/IRM  i 3) Bypass Switches ,
a) Allows operator to bypass an Inop LOR 1.05.a.4.1 IRM channel. LOR 1.11.b.10 b) Joystick type c) Allow bypassing only one IRM per RPS channel at a time.
 
'
d) One switch for Channels A, C, E and G e) One switch for Channels B, D, F and H 6. Interlocks a. SRM 1) Retract Permissive Interlock for detector withdrawal.
 
a) Interlock between:
  (1) SRM Log Count Rate (2) SRM Detector Position
:
  (3) IRM Range Switches b) Interlock does not stop detector movement.
 
c) Interlock will cause a rod block if the following conditions are met:
  (1) SRM detector not full in And (2) SRM count rate <100 cps. l l
d) Interlock is bypassed when:
s.
 
-44-J
 
ANNUNCIATOR ROD  ARP 09-5-2-2 LEGEND WITHDRAWAL BLOCK DEVICE NA SETPOINT NA Reference: ESK-10P. 1.84-101 CAUSES e Any Reactor Mode Switch position:
- APRM high flux
- APRM inoperative
- RBM high flux (if reactor power is above 30%)
- RBM inoperative (if reactor power is above 30%)
- Recirc Flow Comparator trip
- Recirc Flow Converter upscale or inoperative
- CRD Hydraulic System SDIV level high l
- RPIS malfunction    1
- RWM withdraw block (below 20% reactor power)
- SDIV high water level trip bypassed j
e Reactor Mode Switch in Run
- APRM downscale
- APRM upscale (flow biased)  l
:
- RBM downscale (if reactor power is greater than 30%)  ;
      .
e Reactor Mode Switch in Startup/ Hot Standby:
- APRM upscale (12%)    l
- Refuel platform over core  )
- Service platform hoist loaded p r< < v m < <
    "r9n n ,
i g
      '
(Continued on next page)
i
  {" "' l ' '
Rev. No. 3  PORC Meeting No. NA Date 6/23/95  Page 1 of 3
 
U ANNUNCIATOR ROD  ARP 09-5-2-2 LEGEND WITHDRAWAL BLOCK CAUSES (Cont)
* Reactor Mode Switch in Startup/ Hot Standby or Refuel:
- SRM detectors not fully inserted in the core with count rate below 100 cps, and associated IRM range switch on ,
range 2 or below.  ,
. - SRM high flux
- Refueling interlocks
- SRM inoperative
- IRM downscale (bypassed on range 1)
- IRM high flux
- IRM detector not full in
- IRM inoperative e Reactor Mode Switch in Refuel:
.
  - Refueling platform near or over the core with a load on the 1, fuel platform hoist, or fuel grapple not full up
- Service platform hoist loaded
- Gelection of a second control rod with any other rod not
  '
full in
,
- SDIV high water level trip bypassed  f i
- Rod select power turned off or no rod selected
- Refuel platform power turned off e Reactor Mode Switch in Shutdown:
-
Reactor Mode switch in shutdown AUTOMATIC ACTIONS Rod withdrawal block i
i l
(Continued on next page)    j Rev. No. 3  PORC Meeting No. NA Date 6/23/95  Page 2 of 3 J
 
    ._
      .
.. * -
ANNUNCIATOR ROD  ARP O9-5-2-2 LEGEND WITHDRAWAL BLOCK PROCEDURE 1. Determine cause of rod block at panel 09-5.
 
2. Correct cause of alarm prior to attempting to withdraw control rods.  -
j
      !
      . 1 I
      ,
i
.
 
4 Rev. No. 3  PORC Meeting No. NA Date 6/23/95  Page 3 of 3 e
 
,
SRO 647 During the administration of the examination, a typographical error was noted in that distractors A and C were the identical. Distractor C was changed from:
      .
Turbine Govemor Valve open; Turbine Steam Inlet Isolation Valve closed.
 
to:
Turbine Governor Valve open; Turbine Steam Inlet Isolation Valve open.
 
This corrected the typographical error but necessitated a key change for the SRO exam from C to A. The determination to change distractor C vice distractor A was based on the fact that some candidates had already recognized A to be a conect answer and marked their answer sheets to reflect their choice.
 
.
    .
      .
 
RO 061 SRO O61 During the post-examination review, it was discovered that there were two correct answers given for the question.
 
The rod drift indication however is not referenced as a symptom of an uncoupled control rod in the applicable procedure, AOP-25, UNCOUPLED CONTROL ROD. 'Ihat procedure states the symptom:
An overtravel alarm is received during a coupling check of control rod."
 
Both the ROD DRIFT and ROD OVERTRAVEL' annunciators will alarm if the respective condition exists for any of the 137 control rods. Each of the control rods also has an individual rod drift light on the full core display. There is actually no " Individual" Rod Overtravel alarm as the question asks nor is there an " individual" Rod Drift alarm (there are however, individual rod drift lights). This ambiguity apparently led the
!
candidates to associate individual in the sense of "an alarm caused by moving an individual rod." That perspective, coupled with the procedural symptom makes B also a correct answer.
 
The answer key was changed to reflect either A or B as a correct answer.
 
.
* AOP-25, UNCOUPLED CONTROL ROD, revision 4, Section A., pg. 4.
 
N-      ,
 
. .. . . . .. . . .
    . . . __
ANNUNCIATOR ROD DRIFT  ARP 09-5-2-3 LEGEND
      .
DEVICE Not applicable SETPOINT Not applicable CAUSES 1. A control rod that is not selected moves off a latched even numbered position.
 
2. A control rod that is selected moves off an even numbered position or past an odd numbered position after rod sequence timer has stopped.
 
AUTOMATIC ACTIONS None PROCEDURE
  ,
Enter AOP-27, Control Rod Drift *.
033: 3  8 Rev. No. 7  PORC Meeting No. NA Date 1/17/96  Page 1 of 1
      >
 
I
      'ARP 09-5-2-4 ANNUNCIATOR ROD OVERTRAVEL'
LEGEND-
_
SENSOR / Reed switch S-50 located 3" past full out position TRIP POINT
 
'
.CAUSE' CRD and rod NOT coupled AUTOMATIC None ACTION
    .
P OPERATOR Refer to F-AOP-25, Uncoupled Control Rod  *
ACTION
__
I l
  *
 
l l.
 
.
Rev. No. 2  PORC Meeting No. ff7- // Z.
 
Date /2/h2 37  Page 1 of 1 t
 
.. .
UNCOUPLED CONTROL ROD *  AOP-25 A. SYMPTOMS    '
.
  * An overtravel alarm is received during a coupling check of control rod.
 
* Lack of a noticeable change in neutron monitoring
      -
indication during rod movement.
 
B. AUTOMATIC ACTIONS    :
None
.
r
    .
    .
Rev No. 4  Page 4 of 9 d
 
    .
ATTACHMENT 4 ^
NRC RESOLUTION OF JAF COMMENTS ON WRITTEN EXAMINATION RO-9, SRO-9 Accepted error in answer key. The key was changed from D to B.


M
i RO-31, SRO-31 Accepted comment. Question was deleted from the examination. i RO-44, SRO-44 Accepted error in answer key. The key was changed from D to A SRO 47 Accepted change in answer key to reflect change announced during examination administration to correct that A and C were the same answer. The key was changed from C to A RO-61,SRO-61 Accepted comment that there were two correct answers. The J4 answer key was changed to reflect either A or B as correct answers.
-
ANNUNCIATOR! ROD' OVERTRAVEL:
  ' LEGEND SENSOR / Reed switch S-50 located 3" past full out position TRIP POINT
  'CAUSE CRD and rod NOT coupled
        '
AUTOMATIC None ACTION t
OPERATOR Refer to F-AOP-25, Uncoupled Control Rod  *
ACTION


.
  :
      *
.
.
-.
\     )
        ,
  :
Rev. N ;  PORC' Meeting N bl~ // L Date - /2[22!8')  Page 1 -of 1
  .
 
     . . . _- .. . -. -
,.    .  . ..
{. _ . .
        !
UNCOUPLED: CONTROL' ROD *    AOP-25 s SYMPTONS--  .-
Y
,      ,.
  '
  * An?;overtravelialarETsJiecCived-'during"Jcouplinfcheck'of)
    '
  '. control) rod... '
      ' ' "
      '
      '
        *
  'e Lack.of a noticea'ble change in neutron monitoring  *
indication during rod movemen .
  . AUTOMATIC ACTIONS    *
*
None    ,
        .
        .
  .
 
4
:
      ,
        ,
L
        =m i
 
,
 
1
  - R e v .--- N o . - 4  Page 4 of 9
. , . _ - ;.  .
 
-. -    -  - . . -
ATTACHMENT 4 NRC RESOLUTION OF JAF COMMENTS ON WRITTEN EXAMINATION RO 9, SRO 9 Accepted error in answer key. The key was changed from D to RO 31, SRO 31 Accepted comment. Question was deleted from the examination.
 
- RO-44, SRO 44 - Accepted error in answer key. The key was changed from D to A SRO 47 Accepted change in answer key to reflect change announced during
  - examination administration to correct that A and C were the same answer. The key was changed from C to A RO 61,SRO-61 Ocepted comment that there were two correct answers. The answer key was changed to reflect either A or 8 as correct answers.
}}
}}

Latest revision as of 07:02, 18 December 2021

Forwards NRC Operator Licensing Exam Rept 50-333/97-09 for Exams Administered on 971103-07
ML20216B260
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 03/09/1998
From: Curley V
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
50-333-97-09, 50-333-97-9, NUDOCS 9803130022
Download: ML20216B260 (1)
v • d • e


Text

-i

March 9, 1998 l NOTE T0: NRC Document Control Desk Mail Stop 0-5-D-24

'

FROM: $c t I- oa fe n .L Opera';ing Licensi "BranchRpnsingAssistant SUBJECT:

OPERATOR llevendetr 3-7LICENSING 1997 . ATEXAMINATION ADMINJSIERED ON d. R. Fitz t'a7xich' .

' DOCKET #50.dja On vemlea A-7 n 97 Operator Licensing Examinations were administered at the referenced' facility. Attached. you will find the following information for processing through NUDOCS and distribution to the NRC staff, including the NRC PDR: j

)

Item #1 - a) Facility submitted outline and initial exam submittal.

designated for distribution under RIDS Code A070.

b) As given operating examination. designated for distribution under RIDS Code A070.

Item #2 - Examination Report with the as given written examination attached, designated for distribution under RIDS Code'IE42.

_

88 188!i 8188822a V PDR lllllllllllllll!,11Bll11

.

',_ '

December 15, 1997 h p_ (=, bC

.

, EFAm i '. LE

.

Mr. Michael Site Executive Officer New York Power Authority )

James A. FitzPatrick Nuclear Power Plant j Post Office Box 41 i Lycoming, NY 13093 l SUBJECT: FITZPATRICK EXAMINATION REPORT 50 333/97-09

Dear Mr. Colomb:

,

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During the period of November 4-7,1997, the NRC administered initial exams to eight employees of your company who had applied for licenses to operate the James A.

FitzPatrick Nuclear Power Plant. At the conclusion of the examinations, the prelimi, nary findings were discussed with Mr. Topley and members of your staff.

All eight applicants passed the exams. All applicants were well prepared for the examination.

Your staff developed the initial examinations. However, the quality of your staff's initial input did not meet our expectation. Based on the interaction between the chief examiner and your staff, an acceptable examination was eventually developed and subsequently administered. We hope that the lessons learned will be applied during future examination development efforts.

An unresolved item was identified related to a change made to your Emergency Operating Procedures.

In accordance with 10 CFR 2.700 of the NRC's " Rules of Practice," a copy of this letter and its enclosures will be placed in the NRC Public Document Room (PDR).

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a lh

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Mr. Michael Should you have any questions regarding this information, please contact Don Florek of my staff at (610) 337-5185 or me at (610) 337-5211.

Sincerely,

Glenn W. Meyer, Chief Operations and Human Performance Branch Division of Reactor Safety i

Docket No.: 50-333 License No.: DPR-59 Enclosures: Examination Report 50-333/97-09 s.g.w/ encl: w/o Attachments 1-4:

C. D. Rappleyea, Chairman and Chief Executive Officer )

E. Zeltmann, President and Chief Operating Officer R. Hiney, Executive Vice President for Project Operations J. Knubel, Chief Nuclear Officer and Senior Vice President

)

H. P. Salmon, Jr., Vice President of Nuclear Operations W. Josiger, Vice President - Engineering and Project Management J. Kelly, Director - Regulatory Affairs and Special Projects T. Dougherty, Vice President - Nuclear Engineering R. Deasy, Vice President - Appraisal and Compliance Services R. Patch, Director - Quality Assurance G. C. Goldstein, Assistant General Counsel C. D. Faison, Director, Nuclear Licensing, NYPA K. Peters, Licensing Manager ,

R. Locey, Trainira Manager l T. Morra, Executive Chair, Four County Nuclear Safety Committee Supervisor, Town of Scriba C. Donaldson, Esquire, Assistant Attorney General, New York Department of Law P. Eddy, Electric Division, Department of Public Service, State of New York G. T. Goering, Consultant, New York Power Authority J. E. Gagliardo, Consultant, New York Power Authority E. S. Beckjord, Consultant, New York Power Authority F. William Valentino, President, New York State Energy Research and Development Authority J. Spath, Program Director, New York State Energy Research and Development Authority

'

.

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Mr. Michael Distribution w/enci and Attachments 1-5:

DRS Master Exam File PUBLIC Nuclear Safety information Center (NSIC) *

Distribution w/ encl: w/o Attachments 1-5:

H. Miller, RA/W. Axelson, DRA (1)

J. Wiggins, DRS D. Screnci, PAO (2)

Nuclear Safety Information Center (NSIC)

PUBLIC NRC Resident inspector Region i Docket Room (with concurrences)

J. Rogge, DRP R. Barkley, DRP R. Junod, DRP D. Florek, Chief Examiner, DRS OL Facility File .

Distribution w/enet: w/o Attachments 1-5: (VIA E-MAIL)

M. Leach, R1 EDO Coordinator S. Bajwa, NRR K. Cotton, NRR W. Dean, OEDO (WMD)

D. Hood, NRR M. Campion, RI Inspection Program Branch, NRR (IPAS)

DOCDESK DOCUMENT NAME: A: FITZ9709.lNS

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

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m 2 .- ...c- - w- w-m OFFICE Rigg // l Rl/DRP/ l Rl/DRS [ Rl/ l Rl/

NAME l l D"'eff V JRogge GMeyer Qj [

DATE- 12/9597 12f /97 12/pf97

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9 12/ /97 12/ /97 l OFFICIAL RECORD COPY

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. j U.S. NUCLEAR REGULATORY COMMISSION '

REGION I

Docket No. 50-333 License No. DPR-59 Report No. 97-09 Licensee: New York Power Authority Post Office Box 41 Scriba, New York 13093 Facility Name: James A. FitzPatrick Nuclear Power Plant Examination Period: November 4-7, 1997 Examiners: D. Florek, Senior Operations Engineer S. Dennis, Operations Engineer C. Sisco, Operations Engineer Approved by: G. Meyer, Chief, Operations and Human Performance Branch Division of Reactor Safety iI

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EXAMINATION SUMMARY Examination Report 50-333/97-09 (OL)

Initial exams were administered to four senior reactor operator (SRO) instant applicants and four reactor operator (RO) applicants during the period of November 4-7,1997, at the James A. FitzPatrick (JAF) Nuclear Power Plant.

OPERATIONS All eight applicants passed the exam. All applicants were well prepared for the examination. The JAF training staff and a contractor developed the examination. The quality of the initial submittal was not at the level that met NRC expectations as defir.ed in NUREG 1021. However the JAF training staff responded to the NRC comments on the proposed examination and developed a final examination that was acceptable.

An unresolver' item was identified related to a change made to the Emergency Operating Procedures regarding initiation of isolations that should have occurred but did not.

On the operating test, the examiners noted very good performance regarding team work, use of prints, communication, procedure use, and peer checking. Also, the examiners noted weak performance related to an alternate path task related to the refueling interlock test.

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Reoort Details 05.1 Operator initial Exams a. Scone The examiners administered initial examinations to four RO and four SRO instant applicants in accordance with NUREG-1021, " Examiner Standards," Interim Revision 8. The examinations were prepared by James A. FitzPatrick (JAF) staff and were approved by the NRC. JAF staff administered and graded the written examination. The NRC administered and graded the operating test and concurred with the JAF staff grading of the written examination.

b. Observations and Findinas The results of the initial examinations are summarized below:

I SRO RO Pass / Fail Written 4/O 4/O 8/O

' Operating 4/0 4/O 8/0 l Overall 4/O 4/0 8/O The examinations were prepared by JAF staff. The JAF staff involved with the development of these examinations signed security agreements to ensure the integrity of the initial examination process.

JAF staff submitted their proposed sample plan on August 27,1997. The NRC Chief examiner made minor changes to the submitted sample plan which were made by the JAF staff.

The JAF proposed SRO and RO written examinations were submitted for NRC !

approval on September 25,1997, and the operating tests the following week as agreed by the Chief Examiner. The JAF initial submitted examination was not an examination capable of discriminating between acceptable and unacceptable license candidates and required modification to meet NRC Examiner Standards. The ,

following is a summary of the problems noted with the proposed examination. I

- Simplistic written, JPM and admin questions

-

Poor written question distractors which were easily eliminated

- Written questions which did not correlate with the assigned K/A

-

Awkwardly worded written and JPM questions

- Written and JPM questions that did not solicit the answer in the answer key

,

.

.

-

Double jeopardy questions

-

Lack of balance in the written distractors

.

-

More than one correct answer

- Inadequate cues for in-plant JPMs

-

JPM and admin questions not writt'en at the SRO level

-

JPM questions written as direct look up rather than "open reference" use

-

Inadequate operator actions in the proposed simulator scenarios

- Specification of scenario critical tasks

-

Inadequate malfunctions to assess each operator in the competency evaluation ,

The NRC examination team held an examination preparation visit the week of September 20,1997. As a result of the NRC and JAF staff interaction, an acceptable examination was developed and administered.

JAF staff administered the written examinations on November 3,1997. The NRC examiners administered the operating examinations in the period of November 4-7,1997.

By letter, dated Nover%r 12,1997, JAF staff provided the grading of. o written examination and identh.1: comments on five questions. A copy of the JAF letter is contained in Attachment 3. The NRC accepted the JAF comments on the written examination as described in Attachment 4. The examiners reviewed the grading of the written examinations and concurred with the grading by JAF staff.

During the walkthrough portion of the operating test, the SRO instant applicants performed poorly in the following task: -

Alternate path task related to the refueling interlock test.

During the operating test, the following items were significant and consistent positive observations.

P&lD, electrical, and logic prints were effectively used by the applicants.

Toimwork within the crews was very good.

Communication within the crews was very good. Crew briefings were concise, timely, and appropriate. The applicants were very poised.

. . -

.. . .... - . . . .

.

. . . .

.

l

Procedures, including alarm response procedures, were effectively used during the scenarios.

Effective use of peer checking.

c. Conclusions The applicants were well prepared for the examination, and as a result,8 of 8 applicants passed the examinations and were subsequently issued licenses.

JAF staff did not have a complete understanding of the NRC expectations in the development of their proposed initial examination. Significant interactions between the NRC and JAF staff were required to develop an examination that was consistent with the NRC Examiner Standards, in the end, JAF staff were successful in developing an acceptable examination.  !

03.1 Emeraency Operatina Procedures (EOPs)

a. Scope The examiner reviewed the change to EOPs which changed the Emergency Procedure Guideline (EPG) step RC/L-1 from " Initiate each of the following which should have initiated but did not" to " Verify initiation of".

b. Observations and Findinas During the examination the examiners noted that the applicants did not always

" Verify initiation of" during the execution of the EOPs. The examiners noted that the EOPs were revised to change the step as a concurrent step rather than a series step and also " Initiate" was changed to " Verify initiations".

At JAF, in accordance with AP-02.01 " verify initiation" meant "to observe that the associated activities have been performed or that the expected conditions or characteristics exist." This was not the same as " Initiate each of the following which should have but did not". AT JAF " verify" was performed on a concurrent, when available basis by the ROs informing the SRO what actions should have initiated but did not. The SRO was allowed to decide as to whether to initiate those actions. At JAF " ensure" was used to mean initiate each of the following which should have initiated but did not.

The EOP pr.aedure change, dated December 6,1996, which made the change and the resulting plant specific technical guide (PSTG) indicated that this was plant specific terminology and did not specifically identify whether the wording change was meant to be identical in interpretation. In addition,the change from series to concurrent execution of initiate isolations was not specifically addressed.

c. Conclusion An unresolved item was identified for JAF to provide an assessment of whether

" Verify isolations" was meant to be equivalent to " Initiate each of the following -

which should have but did not". If this was not the case, then the procedure j change documentation should be reassessed for completeness and adequacy. In 1 addition the adequacy of the change from series to concurrent, when available execution should be documented. This is unresolved item (50 333/97-09-01)

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E.8 Review of UFSAR Commitments j A recent discovery of a licensee operating their facility in a mentar contrary to the updated final safety analysis report (UFSAR) description highlighted the need for a i special focused review that compares plant practices, procedures and/or parameters )

to the UFSAR descriptions. While performing the examination activities discussed l in this report, the examiner reviewed portions of the UFSAR that related to a main j steam line break accident examination question. The selected examination question -(

reviewed was consistent with the UFSAR. .

l V. Manaaement Meetings l

X1 Exit Meeting Summary j

)

At the conclusion of the examination, the examiners discussed their observations of the examination process with members of JAF management. The examinations noted that no simulator fidelity concerns had been observed or identified. JAF management acknowledged the examiner observations.

The JAF personnel present at the exit included the following:

P. Brozenich,' Operations Manager R. Locey, Training Manager  !

J. Morris, Initial Program Administrator J. Romanowski, Operations Training Supervisor D. Topley, General Manager, Maintenance Attachments:

1. SRO Examination and Answer Key 2. RO Examination and Answer Key 3. JAF Comments on the Written Examination 4. NRC Resolution of JAF Comments on the Written Examination

.

- ATTACHMENT 1 SRO EXAMINATION AND ANSWER KEY l

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NEW YORK POWER AUTHOR!TY EXAMINATION /QUlZ JAME3 A. FITZPATRICK NUCLEAR POWER PLANT COVER SHEET Examination Title: USNRC SENIOR REACTOR OPERATOR EXAMINATION Examination Submitte By:) Mder Date: 11/03/97

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Supervisor Approval: .1.6. Mc EEIS Date: to lt5 97 Authorized Reft:rence 1: ATTACHED Minimum Acceptable Grade: 80 Total Exam Points: 100 )

Grade: Graded By: Time Limit: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> STUDENT DATA Name: - S.S.#:

Last First M.l.

Employer: NEW YORK POWER AUTHORITY Date:

Department:

-

GUIDELINES

,

1. Remain quiet during the exam. If you have any questions during the exam, raise l your hand. Your instructor will provide clarification wherever possible. i 2. You are expected to do your own work and not to help anyone else.

3. Use only the authorized reference material.

4. At the completion of this examination, you are to sign the following certification.

I certify all answers contained in this examination are my own. In addition, I have not received nor given any unauthorized assistance, nor have used any unauthorized references.

Student Signature: Date:

SENIOR REACTOR OPERATOR EXAMINATION Question 1 With the plant operating at 50% power, which one of the following Main Generator faults will cause an automatic reactor scram? ,

a. High Stator Winding Temperature.

b. High Differential Current.

c. Loss ofIsolated Phase Bus Duct Cooling.

d. Low Hydrogen Pressure.

.

Question 2 Which one of the following is the reason that the Reactor Mode Switch should be taken out of the RUN position immediately after a Reactor Scram?

a. Enable SRM and IRM rodblocks.

I b. Prevent MSIV isolation.

c. Enable the SDIV high level bypass circuitry, d. Lower the APRM scram setpoint to 15%.

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""* EXAMINATION CONTINUED ON NEXT PAGE *****

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SENIOR REACTOR OPERATOR EXAMINATION Question 3 A reactor scram has just occurred followed by a Residual Transfer. Which one of the following describes the operators' concerns regarding the MSIVs under these conditions?

a. Ensure the MSIVs close to minimize the possibility of Main Turbine overspeed.

b. Ensure the MSIVs close to minimize the possibility of Turbine Building contamination.

c. Ensure the MSIVs remain open to minimize Toms heat laad.

d. Ensure the MSIVs remain open to maintain availability of Turbine Sealing steam.

Question 4 Following an automatic HPCI initiation, the operators note that HPCI trips and then later restarts with no operator action. Which one of the following was the cause of the trip?

a. High turbine exhaust diaphragm pressure.

b. High steam flow rate.

c. High RPV level.

d. High HPCI area temperature.

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"*" EXAMINATION CONTINUED ON NEXT PAGE ""*

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SENIOR REACTOR OPERATOR EXAMINATION

Question 5 A power ascene on is in progress with the follow.!ng conditions:

. Power le el is 70%.

. Load lir.e is 100%.

. Two Feedwater pumps are operating.

Which one of the following describes when and how the Recire. Pumps will runback if one Feed Pump trips?

a. Immediately runback to minimum speed.

b. When RPV level lowers to 1%.5 inches; runback to minimum speed.

c. Immediately runback to 44% speed.

d. When RPV level lowers to 196.5 inches; runback to 44% speed.

Question 6

.

The following conditions exist:

. A Group 11 isolation has occurred due to high Daywell pressure.

. Present Drywell pressure is 5 psig.

. The EMERG OVERR DRYWELL HI PRESS keylock switch on the PCP panel has been taken to its OVERRIDE position.

. No other operator actions have been taken.

Which one of the following describes the CAD isolation valves that can be opened at this -

time?

a. All CAD isolation valves.

b. All CAD isolation valves exupt 27AOV-111 through 118 (CAD vent valves).

c. All CAD isolation valves except 27MOV-113,117,122,123 (CAD purge valves).

d. All CAD isolation valves except 27AOV 131 A/B,132A/B (CAD make-up valves).

!

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- ***** EXAMINATION CONTINUED AN NEXT PAGE *****

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SENIOR REACTOR OPERATOR EXAMINATION -

Question 7 The plant is operating at full power when the following occur:

. Generated MWe starts to decrease.

. Reactor power starts to decrease.

Which one of the following could have caused these symptoms?

a. Decrease in grid frequency.

b. Jet Pump malfunction.

c. Loss of feedwater heating.

d. Inadvertent SRV opening.

Question 8 With a high Drywell pressure, Emergency RPV Depressurization is required if Torus Water Level cannot be maintained below PSP (Pressure Suppression Pressure). Which one of the following is the basis for performing an Emergency RPV Depressurization if the Pressure Suppression Pressure Limit is exceeded?

a. To ensure that the vacuum breakers will not become submerged and fail to function.

b. To ensure adequate free volume (airspace) of the Torus for steam suppression, c. To prevent damaging the Torus.

d. To prevent steam from the Drywell bypassing the Suppression Pool.

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'"" EXAMINATION CONTINUED ON NEXT PAGE ""*

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SENIOR REACTOR OPERATOR EXAMINATION Question 9 l

Which one of the following would give positive indication that SRV 'C' is open when its control switch is taken to OPEN? .

a. SRV red light is on, b. SRV white light is on.

I SRV tailpiece temperature rises and stabilizes at 285 *F.

c.

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d. EPIC alarm ' SONIC DET RV-C' RESET is received.

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1-Question 10

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The following conditions exist:

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. A plant transient raised RPV pressure to 1150 psig.

. The SRVs have opened.

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. RPV levelis 150 inches.

Assuming no operator action, which one of the following describes when the SRVs are expected to close?

a. Before RPV pressure decreases below approximately 1050 psig.

b. 120 seconds after the initial transient.

c. After RPV pressure decreases below approximately 50 psig. j d. When both RHR and Core Spray pumps are secured. l l

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SENIOR REACTOR OPERATOR EXAMINATION Question 11 A reactor scram occurred but many control rods failed to insert due to a high water level in the Scram Discharge Volume. The APRMs read 9 %. Which one of the following actiuns will be most effective in inserting control rods?

a. Manually initiate ARI.

b. De-energize scram solenoids.

c. Manually insert control rods.

d. Close the CRD Flow Control valve.

Question 12 Following the trip of one Recire. Pump with the reactor at power, the operators have closed the discharge valve of the tripped pump. Which one of the following is the reason that this is done?

a. Stops reverse rotation of the tripped pump.

b. Prevents backflow through the idle Jet Pumps.

c. Prevents runout of the operating Recire. Pump.

d. Lowers the probability of entering the instability region of the power / flow map.

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SENIOR REACTOR OPERATOR EXAMINATION Question 13 -

The following conditions exist:

  • Condenser vacuum is 25.1 inches Hg.
  • Turbine load is 170 MWe.

Which one of the following actions, by itself, will make it MORE LIKELY that a manual Turbine Trip will be required?

a. Starting the Mechanical Vacuum pumps.

b. Increase load to 255 MWe.

c. Decrease load to 85 MWe.

d. Placing the spare Air Ejector sets in service.

Ques' ion 14 With the plant shutdown, an Emergency Diesel Generator is running and is tied to its bus for load testing. Which one of the following describes the response to a complete loss of offsite power?

a. The Tie Breakers will trip and the diesel will maintain the bus loads. 1 b, The Diesel Output breaker will trip and the diesel will switch to isochronous ,

mode, then the Diesel Output breaker recloses.

c. The Diesel Output breaker will trip and the diesel will switch to droop mode, then the Diesel Output breaker recloses.

d. The Tie breakers and the diesel will trip.

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Question 15 Bus 10400 is powered by the Main Generator via breaker 10402. Which one of the following ways of opening this breaker will not allow closing the Station Reserve breaker 104127 a. Manually opened locally.

b. Manually opened from the control room.

c. Automatically opened on overcurrent.

d. Automatically opened on undervoltage.

Question 16 Which one of the following describes the loads in the 24 VDC Power System?

a. Each load breaker is connected to 48 VDC potential (input) from its associated 124 VDC charger.

b. Half the loads on a124 VDC distribution bus are powered from +24 VDC. The other half are powered from -24 VDC.

c. Each load breaker is connected to 24 VDC potential (input; from its associated 12 VDC charger.

d. Half the loads on a 148 VDC distribution bus are powered from +48 VDC. The other half are powered from -48 VDC.

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SENIOR REACTOR OPERATOR EXAMINATION Question 17 The following Narrow Range RPV level conditions exist:

  • 'A' indicates 215 inches and is rising slowly. .
  • 'B' indicates 185 inches and is lowering slowly.

e 'C' indicates 214 inches and is rising slowly.

e Feedwater control is selected to the 'A' Column.

Selecting the 'B' RPV Level Column will result in which one of the following effects on level trends?

a. 'A' and 'C' will continue to rise. 'B' will lower.

b. 'A' and 'C' will continue to rise. 'B' will rise.

c. 'A' and 'C' will lower. 'B' will lower.

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d. 'A' and 'C' will lower. 'B' will rise.

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i Question 18

) In which one of the following ways does a loss of 125 VDC Bus 'A' affect the ADS /SRV system?

a. Loss of'A' logic, ADS remains functional.

b. None of the ADS /SRV valves can be opened.

c. The ADS /SRV valves cannot be opened from the remote panel.

d. Only valves F, J, K & L remain fully functional.

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SENIOR REACTOR OPERATOR EXAMINATION Question 19 AOP-43 (Shutdown From Outside the Control Room) requires the operators to remove RHR pumps 'A' and 'C' from service. Which one of the following describes the reason tha this .

step is necessary?

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l a. Prevent water hammer in the event of a LOCA signal.

b. Prevent inadvertent Drywell spray.

c. Prevent inadvertent LPCI injection.

d. Prevent draining the RPV to the Torus.

Question 20 The following events occur:

. The plant is at 20% power.

. High radiation in the Off Gas system starts the Off Gas Timer.

. No operator action is taken.

Which one of the following will be the most likely cause of an automatic reactor scram?

l a. High Reactor Power.

b. Low RPV Level.

c. MSIV closure.

j d. High RPV Pressure.

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SENIOR REACTOR OPERATOR EXAMINATION Question 21 Which one of the following describes the use of ESW for Drywell cooling during a LOCA?

a. It is the preferred method.

b. It may be used only on loss of RBCLC.

c. It may be used only if directed by EOP-4.

d. It is prohibited.

Question 22 On a Loss ofInstrument Air pressure during normal plant operation, which one of the following describes if and when the MSIVs will go closed? .

a. Inboards remain open; outboards close immediately.

b. Inboards and outboards close immediately.

c. Inboards close eventually; outboards close immediately.

d. Inboards remain open; outboards close eventually, a

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SENIOR REACTOR OPERATOR EXAMINATION Question 23 The following conditions exist:

. A valid Reactor Scram has occurred on low RPV level.

.' The EDGs have auto started in response to high Drywell pressure.

. The Recire. pumps are running at minimum speed as expected.

Which one of the following descri' es the status of the containment isolations?

a. Group I isolated; Group I1 isolated.

b. Group I not isolated; Group II not isolated.

c. Group I isolated; Group II not isolated.

d. Group I not isolated; Group II isolated.

Question 24 During a plant startup RPV pressure is 900 psig. Loss of CRD flow will have which one of the following effects on control rod motion and scram times?

a. Normal rod motion is unaffected and scram times will be within acceptable limits.

b. Normal rod motion is lost and scram times will not meet acceptable limits.

c. Nennal rod motion is unaffected but scram times will not meet acceptable limits.

d. Normal rod motion is lost but scram times will be within acceptable limits.

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SENIOR REACTOR OPERATOR EXAMINATION Question 25 During power operation with RHR pump 'A' in Torus Cooling, an operator mistakenly manually opens RHR pump 'A' Shutdown Cooling Suction valve (10MOV-15A) locally at -

the valve. Which one of the following describes the expected automatic actions, if any?

a. There will be no automatic actions.

b. When 10MOV-15A reaches 10% open, it will automatically close the 'A' RHR Pump Suction Torus Isolation Valve (10MOV-13A).

c. When 10MOV-15A reaches full open, the RHR Torus Cooling / Torus Spray outboard valve (10MOV-39A) will auto close.

d. The %' RHR pump will trip on low suction pressae.

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Question 26 Which one of the following describes the consequences of spraying the Drywell if Drywell conditions are not in the permissible region of the Drywell Spray Initiation Curve?

a. Water sprayed into the Drywell will turn to steam raising pressure even further.

b. The cold water will put excessive thermal stress on the Drywell which may lead to its failure.

c. The effect is unpredictable and would result in putting the plant in an unanalyzed condition.

d. Drywell pressure would drop more rapidly than could be handled by the vacuum breakers.

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l Question 27 l The Reactor Building "entilation system is in operation when the exhaust plenum radiation

l levels exceed 10 cpm. Which one of the following describes the expected response of the Reactor Building Ventilation and SBGT systems to this event?

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a. Reactor Building Ventilation will isolate and neither train of SBGT will start, b. Reactor Building Ventilation will isolate and both trains of SBGT will start. I c. Reactor Building Ventilrti 3n will not isolate and neither train of SBGT will start.

d. Reactor Building Ventilation will not isolate and both trains of SBGT will str -

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Question 28 The following conditions exist:

. A fuel element failure has occurred.

. 01-107AOV-100 (Off Gas Outlet Isolation Valve) is open.

. The Off Gas timer has started.

. The Stack Low Range monitors are reading full upscale.

. The Stack High Range monitors are reading 110 mR/hr.

. Reactor Building Exhaust radiation is reading 22,000 cpm.

These conditions require entry into which one of the following combinations of Emergency Plan EALs and EOPs? l a. Unusual Event and EOP-5.

i b. Unusual Event and EOP-6. I

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c. Alert and EOP-5.  ;

d. Alert and EOP-6.

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Question 29 In the event that normal shutdown cooling capability has been lost, which one of the -

following states the minimum shutdown time before Fuel Pool Cooling Assist will provide adequate cooling?

a. Iday, b. 4 days.

c. 7 davs.

d. 9 days.

Question 30 Which one of the following describes why it is important to establish forced Recire, flow during a Loss of Shutdown Cooling event?

a. Coolant stratification may mislead the operators into assuming bulk water temperature is below 212*F.

b. Cooling of the recire loop will produce a reactivity effect when the first recire.

pump is started.

c. Unstable transition boiling at low pressure may cause clad damage.

d. Steam build up in the RHR suction piping will lead to waterhammer when RHR flow is restored.

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SENIOR REACTOR OPERATOR EXAMINATION Question 31 Which one of the following limits takes precedence during the operation of the SBGT system with the Reactor Building isolated?

a. Maintain RB AP more negative than -0.25 inches of water.

b. Maintain charcoal filter temperatures less than 170 'F.

c. Limit SBGT flow to a maximum of 6000 scfm.

d. . Maintain Reactor Building Ventilation exhaust radiation levels less than 10' cpm.

l Question 32 Following a reactor scram the pressure in the Scram Discharge Volume (SDV) rises to RPV pressure. Which one of the following describes the most likely reason for this condition? )

a. One or more CRDM seals have failed.

b. The scram has not been reset.

c. The SDV vent valves have failed closed, d. The CRDH flow control valve has failed open.

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SENIOR REACTOR OPERATOR EXAMINATION Question 33 Which one of the following RWM conditions, if any, will prevent insertion of a selected rod using the Emergency In switch? -

a. None, b. Select Error, c. Withdraw block.

d. Insert block.

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Question 34 The following conditions exist:

. The plant is shut down.

. The 'A' RHR loop is in Shutdown Cooling.

. A LPCI initiation signal on low RPV level occurs.

Which one of the following describes the operator actions, if any, which must be taken in order for LPCI 'A' to start injecting?

a. None.

b. Reset the Group 2 isolation, manually start the pump and reset the injection valve isolatioa signal.

c. Mniually align the suction path for the desired pump and reset the LPCI initiation signal d. Manually align the su , tion path for the desired pump, manually start the pump, and reset the injection valve isolvion signal.

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' Question 35'

The following sequence of events has occurred.

. A LOCA has occurred resulting in LPCI injection.

. Offsite power is then lost.

.- EDGs 'B', 'C', & 'D' start and load normally.

. EDG 'A' fails to start.

Under these conditions, which of the following RHR pumps will be running two minutes after the loss of power?

a. All four b. 'B', 'C', & 'D'

c. 'A', 'C', & 'D'

d. 'B'&'D'

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The follow events occur:

. A low RPV level causes HPCI to stan and inject.

. HPCI is the only available injection system.

. RPV level starts to increase.

. The HPCI Aux. Oil Pump breaker trips. )

Assuming no operator action, which one of the following describes the expected response of HPCl?

a. HPCI will trip when the Aux. Oil Pump breaker trips and can rat restart.

b. HPCI will trip on High Level and can not restart.

c. HPCI will trip on High Level and can restart on low level. l d. HPCI will continue rurming until manually tripped.

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SENIOR REACTOR OPERATOR EXAMINATION Question 37 The following events have occurred:

. A LOCA has occurred.

. The Core Spray pumps auto started on low level.

. RPV level subsequently recovered to 180 inches.

. The operators tock both Core Spray Pump switches to STOP.

. Drywell pressure is 2.3 psig.

Which one of the following describes the expected response of the Core Spray pumps to these events?

a. After auto-starting they remain on until the initiation logic is reset.

b. They stop when switched to STOP but restart if Drywell pressure increases above their auto-start setpoint.

c. They stop when switched to STOP but restart iflevel decreases below their auto-start setpoint.

d. They stop when switched to STOP and remain off.

Question 38 Which ( ie of the following describes the effect of a loss of 600 VAC power on the Core Spray system?

a. Core Spray pumps will not auto-start when required. They can be started manually.

b. Core Spray pumps cannot be started either automatically or manually.

c. Core Spray pumps will start normally but their discharge valves will not open automa:ically.

d. Core Spray pumps will start normally but will trip on low flow.

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S~aiOR REACTOR OPERATOR EXAMINATION Question 39 The operator takes the SLC keylock switch to START SYS-A. Pump 'A' receives a start signal but fails to start due to mechanical binding ofits breaker contactor. Which one of the following describes the expected response of the Squib Valves and RWCU system isolation valves to these events?

a. Neither Squib valve will fire; RWCU will not isolate.

b. Only the 'A' Squib valve will fire; RWCU will isolate.

c. Both Squib valves will fire; RWCU will isolate, d. Both Squib valves will fire; RWCU will not isolate.

Question 40 Following a Residual Transfer and prior to the operator taking any actions, which one of the following describes the ability to start the SLC pumps and fire the squib valves?

a. The pumps can be started and the squib valves will fire.

b. The pumps cannot be staned and the squib valves will fire.

c. The pumps can be started and the squib valves will not fire.

d. The pumps cannot be started and the squib valves will not fire.

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SENIOR REACTOR OPERATOR EXAMINATION Question 41 The plant is operating at 100% power when a Generator Load Reject occurs. Which one of the following describes the RPS input that generates the first expected scram signal? -

a. High RPV Pressure.-

b. High Neutron Flux.

c. Turbine Control Valve Fast Closure, d. Turbine Stop Valve Closure.

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Question 42 The reactor is operating at 25% power. Which one of the following describes the response, if any, of RPS if the 'A' inboard and 'D' outboard MSIVs are closed?

a. Full Scram.

b. Half Scram in Channel 'A'.

c. Half Scram in Channel 'B'.

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d. No effect.

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SENIOR REACTOR OPERATOR EXAMINATION Quesdon 43 A normal plant startup is in progress and the following conditions exist:

. The Reactor Mode Switch is in STARTUP.

. All the IRM range switches are on RANGE 2.

. No IRMs are bypassed.

Which one of the following describes the effect on half scrams or rod blocks, if any, that will occur if the IRM 'A' Mode Switch is placed in the STANDBY position?

a. None, as long as its companion APRM is not downscale, b. Rod Withdrawal Block only.

c. RPS Half Scram only.

d. Rod Withdrawal Block and RPS Half Scram.

Question 44 The following conditions exist: i

. AllIRM Range switches are on RANGE 2.

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. The SRM detectors are partially withdrawn. j

. SRM 'A' reads 80 cps. 4 Which one of the following describes the ability to withdraw SRM 'A' and the status of rod blocks?

a. The detector can be further withdrawn and a rod block exists. j b. The detector can be funher withdrawn and no rod block exists, c. The detector cannot be further withdrawn and a rod block exists.

d. The detector cannot be further withdrawn and no rod block exists.

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Question 45

'A Recirculation Flow Summer fails resulting in zero output. Which one of the following is the highest power level at which the APRM will generate a rod block but not a scram signal?

a. 100 %

b. 75 %

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c. 60 %

d. 50%

Question 46 Assuming no change in vessel inventory, starting the Recire. pumps will affect Fuel Zone and Wide Range RPV level indication in which one of the following ways?

a. Fuel Zone rises; Wide Range rises, b. Fue1 Zone rises; Wide Range lowers.

c. Fuel Zone lowers; Wide Range rises.

d. Fuel Zone lowers; Wide Range lowers.

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SENIOR REACTOR OPERATOR EXAMINATION Question 47 RCIC is in operation due to a small LOCA. Which one of the following describes the expected position of the RCIC Turbine Governor Valve (13HOV-2) and the RCIC Turbine Steam Inlet Isolation Valve (13MOV-131) if RPV level rises to 222.5 inches?

a. Turbine Governor Valve open; Turbine Steam Inlet Isolation Valve closed, b. Turbine Governor Valve closed; Turbine Steam Inlet Isolation Valve open.

c. Turbine Governor Valve open; Turbine Steam Inlet Isolation Valve elesed open.

d. Turbine Govemor Valve closed; Turbine Steam Inlet Isoleion Valve closed.

i Question 48 1 The following events have occurred:

. An Automatic Depressurization System (ADS) initiation has occurred.

. The initiation signals are still present.

. A blowdown is in progress.

Taking the ADS Normal / Override switches to OVERRIDE and back to NORMAL will have which one of the following effects on the ADS Valves?

a. ADS Valves will close and remain closed.

b. ADS Valves will close then reopen immediately.

c. ADS Valves will close then reopen after 120 seconds.

d. ADS Valves will remain open.

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SENIOR REACTOR OPERATOR EXAMINATION Question 49 The following conditions exist: )'

. Drywell pressure has risen from 1.8 to 2.5 psig.

. Torus pressure has risen from 0 to 2.5 psig.

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These conditions are symptomatic of which one of the following? I a. SRV cycled to control pressure and an SRV tailpiece failure inside the Torus.

b. Small break LOCA in the Drywell and a Downcomer failure inside the Torus.

c. Small break LOCA in the Drywell and a Torus to Drywell vacuum breaker failed to open.

d. SRV cycled to control pressure and an SRV tailpiece vacuum breaker stuck open.

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Question 50 With the Mode Switch in STARTUP, which one of the following conditions will result in the automatic closure of the MSIVs?

a. RPV Levelis 50 inches.

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b. Steamline pressure is 750 psig.

c. Main Condenser Vacuum is 10 inches Hg.

d. Turbine Stop valves not fully closed.

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SENIOR REACTOR OPERATOR EXAMINATION Question 51 The plant is in shutdown cooling when a relay failure results in a spurious ADS logic Channel 'A' low-low-low level signal. No other level trips have occurred. Which one of the following describes the effect that this event will have on ADS?

a. ADS willinitiate.

b. ADS will not initiate because the RHR or Core Spray pump running interlock is bypassed in shutdown cooling.

c. ADS will not initiate because both channels are needed for ADS initiation. '

d. ADS will not initiate because there is no low-level trip.

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Question 52

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RFP 'A' hasjust tripped on high reactor vessel level. Which one of the following conditions must be satisfied before the RFP 'A' hydraulic coupling automatically disengages.'

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a. HP and LP stop valves closed. j b. RFP turbine tripped signal sensed.

j c. Turbine speed less than 4 RPM. .

d. MOU and MSC on low speed stops.

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SENIOR REACTOR OPERATOR EXAMINATION Question 53 The following events occur.

. The plant is operating at full power with the MGUs and Master Controller balanced.

. The Master Controller output slowly fails downscale.

. RPV level lowers to 185 inches at which point the operator takes both MGUs to manual.

. No further operator action is taken.

Which one of the following describes the response of feed flow and RPV level after the MGUs have been shifted to manual?

a. Flow will increase to 100%; Level will increase to 200 inches.

b. Flow will increase to 100%; Level will remain at 185 inches.

c. Flow will increase to greater than 100%; Level will increase to 200 inches.

d. Flow will remain less than 100%; Level will continue to trend down.

Question 54 .

The SBGT system has failed to auto-start in response to a HPCI start signal. Which one of the fol! wing will occur as a result of the failure of SBGT to start?

a. HPCI start up sequence will not complete and the HPCI turbine will not start.

b. The HPCI turbine will start but may trip on High Exhaust Pressure.

c. The HPCI turbine will start but may trip on High HPCI Area Temperature.

d. HPCI flow rate will be limited due to decreased condenser efficiency.

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Question 55 Which one of the following is the reason that operation of an EDG at loads near 2000 KW is to be avoided?

a. Excessive wear on turbocharger drive gears.

b. Main bearing degradation due to inadequate lube oil cooling.

c. Potential Lube oil sump fire due to increased pi. ton blow by.

d. O :rheating ofexhaust system.

Question 56 Following a LOCA with concurrent Loss of Offsite Power, which one of the following will be the first to be reenergized when the 'A' and 'C' EDG breakers close?

a. 'A' ESW Pump.

b. 'A' RHR Pump.

c. 'C' RHR Pump, d. 'A' Core Spray Pump.

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Question 57 The operator withdraws a control rod one notch but the rod position indications show that the !

rod is withdrawing continuously until it reaches full out position. Which one of the ,

following could be the cause of this?

a. Stuck collet piston.

b. High CRDH pressure.

c. Uncoupled rod.

d. Leaking HCU Scram Inlet valve (03AOV-126).

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Question 58 Reactor power is 5%. The RWM is fully operational and has generated a Withdraw Bleck.

Under these conditions, which one of the following is the maximum number of rods with insert errors that could possibly be moved in the withdraw direction?

a. None.

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b. One.

c. Two. .

d. Three.

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Question 59 -

The plant is operating at full power when the following Recire. Pump Seal readings are noted:'

. #1 (inner) Seal Cavity pressure is 1000 psig.

. #2 (outer) Seal Cavity pressure is 150 psig.

Which one of the following will cause these conditions?

a. Nonnal operation of both seals.

b. Failure of both seals.

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c. Partial failure of the #1 seal.

d. Partial failure of the #2 seal.

Question 60 During the startup of the 'A' Recire. Pump the following conditions exist:

. The 'A' Recire. Pump Discharge valve is 85% open.

. The 'B' Recire. Pump Discharge valve is fully open.

. Total Feed Flow is 30%.

. Feedwater Pump 'A' is running; Feedwater Pump 'B' is secured.

. RPV level is 195 inches.

Which one of the following describes the most restrictive Recire. Pump speed limitations currently in effect?

a. Both pumps are limited to 30%.

b. Both pumps are limited to 44%.

c. Pump 'A' is limited to 30%; 'B' is not limited.

d. Pump 'A' is limited to 30%; 'B' is limited to 44%.

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SENIOR REACTOR OPERATOR EXAMINATION Question 61 The drive mechanism of a fully withdrawn control rod is uncoupled. Which one of the following indications during the coupling check indicates thu the rod is uncoupled?

a. Individual Rod Drift Alarm.

b. Individual Rod Overtravel Alarm.

c. '49' will be displayed in the rod position window.

d. Individual Rod Full Out light remains energized.

Question 62 Three of the eight LPRM detectors supplying an RBM channel have failed downscale. ~

Which one of the following describes the response, if any, of the RBM to these failures?

a. There will be no functional effect since the RBM still has sufficient LPRM inputs to function.

b. The' rod block setpoint will be automatically adjusted downward to compensate for the lost inputs.

c. An Inop. Rod Block will be generated until one detector is bypassed.

d. A Rod Block will be generated until the PUSH TO SETUP pushbutton has been depressed.

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SENIOR REACTOR OPERATOR EXAMINATION Question 63 Which one of the following describes the effect of spraying the Dywell during a LOCA when Drywell pressure is below 2.7 psig?

a. Unnecessary damage to equipment in the Drywell.

b. Partial de-inerting of the Primary Containment.

c. Inability to vent the Primary Containment.

d. Mechanical failure of the Torus to Drywell vacuum breakers.

Question 64 The operators are unable to reset an inadvertent Group I isolation signa). Which one of the following conditions, ifit existed, would cause this problem?

a. A control switch for one of the MSIVs is in the OPEN position.

b. The Reactor Mode Switch is in RUN.  ;

c. The control switches for the Main Steam Line Drain valves are in the OPEN position.

d. The AP across the MSIVs is 125 psid. l i

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SENIOR REACTOR OPEl% TOR EXAMINATION Question 65 During plant operation it is noted that 345 kV bus voltage is 380 kV. Which one of the following is the appropriate response, if any, to this condition? .

a. No response required.

b. Reduce generator output voltage to restore 345 kV bus voltage to normal.

c. Contact the Load Dispatch Center and request that 345 kV bus voltage be reduced.

d. Increase Naerator Isolated Phase Cooling to maximum.

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Question 66 The following sequence of events occurs:

. 600 VAC power is lost for 3 minutes.

. After 600 VAC power is restored,125 VDC power is briefly lost.

. 125 VDC power is then restored.

After restoration of 125 VDC power, which one of the following will be the source, if any, of 120 VAC UPS Instrument Power?

a. Nothing,120 VAC will be deenergized. j l

b. 600 VAC via the UPS MG Set. I c. 600 VAC via the 600/120 VAC transformer. j d. 125 VDC via the UPS MG Set.

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Question 67 Loss of all 125 VDC power would have which one of the following effects on the Emergen;y Diesel Generators?

a. Diesels would auto-start and load.

b. Diesels would auto-start, but would not auto load.

c. Diesels would not start and could not be started at the Engine Control Panel.

d. Diesels would not auto-start but could be staned at the Engine Control Panel.

Question 68 Which one of the following describes the effect of the Control Room Inlet Radiation Monitor channel failing upscale?

a. Alarm only.

b. The Intake and Exhaust dampers close and the Recire, damper opens.

c. The Control Room Supply fans trip and the Exhaust Damper closes.

d. The Emergency Supply fan starts and the Inlet filter system is placed in sen' ice.

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SENIOR REACTOR OPERATOR EX AMINATION Question 69 Which one of the following describes a potential path for radioactive contamination to the discharge canal during nonnal power operation?

a. Drywell Air Cooler tube leak.

b. . RBCL C Heat Exchanger tube leak.

c. Recombiner condenser tube leak.

d. Main Condenser tube leak.

l Question 70 Which one of the following describes the response of any TIP detector not in its shield when a Group I and Group 11 Containment Isolation Signal occurs?

a. A Group I Isolation will cause the TIP to withdraw to th: Lead Shield position. A Group II has no further effect.

b. A Group I Isolation will cause the TIP to withdraw to the Lead Shield position. A Group II will activate the shear valve if the TIP is still inserted. j

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c. A Group I Isolation will have no effect. A Group II Isolation will actuate the shear valve if the TIP is not withdrawn within 10 minutes.

d. A Group I Isolation will have no effect. A Group II Isolation will cause the TIP to ;

be withdrawn to the Lead Shield position. l l

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_ Question 71 The crew is conducting EOP-5 (Secondary Containment Control) when Reactor Building ventilation isolates on high radiation. The radiation level is subsequently seen tc decrease below the isolation setpoint. Which one of the following describes under what condition, if any, it is permissible to override the high radiation isolation to restart the Reactor Building ventilation system?

a. It is not permissible.

b. Two Reactor Building area temperatures are above maximum normal.

c. After it is confirmed that no primary system is discharging into the Reactor Building.

d. If Reactor Building AP cannot be maintained at a negative pressure with SBGT.

Question 72 While conducting EOP-2 the operators discover that a required action cannot be accomplished. Which one of the following is the appropriate response to this event?

a. Continue to the next step irrespective of the type of step it was.

b. Wait until the step can be accomplished before continuing.

c. Continue to the next step only ifit was a concurrent action step. I d. The decision to continue or wait is only at the discretion of the SM.

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SENIOR REACTOR OPERATOR EXAMINATION Q .;stion 73 The reactor is operating at full power when the following events occur:

. The Turbine Control Valves close. .

. The Turbine Bypass Valves fully open.

. The Reactor Scrams.

. The SRVs open briefly.

Which one of the following could have caused this chain of events?

a. Turbine Load Reference signal has failed downscale.

b. The MSIVs have closed.

c. The Backup (B) Pressure Regulator has failed low.

d. The Maximum Combined Flow Limiter has failed downscale.

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Question 74 The reactor has recently scrammed and the MSIVs are closed. HPCI is maintaining RPV level and pressure. Torus Cooling is not available and Primary Containment Pressure is rising. Which one of the following describes the appropriate considerations if Primary Containment venting becomes necessary?

a. Venting via the Torus will not keep up with decay heat production but will minimize the rate of radioactivity release.

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b. Venting via the Torus will keep up with decay heat production and will minimize the rate of radioactivity release.

c. Venting via the Drywell will not keep up with decsy heat but will minimize the rate of radioactivity release.

d. Venring via the Drywell will keep up with decay heat production and will j minimize the rate of radioactivity release. l

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SENIOR REACTOR OPERATOR EXAMINATION Question 75 A scram has occurred due to a transient resulting from a loss of UPS. Not all rods have fully inserted. Which one of the folicwmg should be used to evaluate reactor power to determine if entry into EOP-2 (RPV Cor. trol) is required?  !

a. APRM chart recorders.

b. SPDS display. I c. Steam Flow.

d. Number of open SRVs.

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Question 76 The following conditions exist:

. A LOCA has occurred.

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The 'A' RHR is the only low pressure ECCS pump available and is injecting in LPCI mode.

. RPV level -90 inches and is trending down slowly.

. Drywell temperature is 350 'F

. Drywell pressure is 65 psig.

. Torus pressure is 64 psig.

. Torus levelis 21 feet.

Which one the following dercribes the correct decision regarding Drywell and Torus spray? l l

a. Spray the Drywell. Do not the spray Torus.  :

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b. Do not the spray Drywell. Spray the Torus.

c. Spray the Drywell. Spray the Torus.

d. Do not spray the Drywell. Do not spray the Torus.

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SENIOR REACTOR OPERATOR EXAMINATION Question 77 A plant transient has caused a reactor scram followed by a prolonged SRV actuation. Current conditions are:

  • Reactor pressure 900 psig and rising.
  • All SRVs are closed.
  • Torus temperature is 160 'F.
  • Torus levelis 1I feet.

Under these conditions, RPV pressure must be reduced to no more than which one of the following?

a. 800 psig.

b. 700 psig.

c. 600 psig, d. 400 psig.

Question 'R A LOCA has occurred and the following conditions exist:

o Drywell H 2concentration is 7%.

. Torus H2concentration is 4%.

. Drywell 0. 2concentration is 4%.

. Torus 0 2concentration is 6%.

Which one of the following describes the Torus and Drywell flammability limits?

a. Both the Torus and the Drywell are below the flammable limit. I b. The Torus is above the flammable limit and the Drywell is below the flammable limit.

c. The Drywell is above the flammable limit and the Torus is below the flammable limit.

d. Both the Torus and the Drywell are above the flammable limit.

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Question 79 _

A large LOCA has occurred and the following conditions exist:

. RPV pressure is 50 psig.

. Drywell temperature is 350 'F.

. Narrow Range RPV level indicates 175 inches.

. Refuel Zone level indicates 215 inches.

. Wide Range RPV level indicates 40 inches.

Which one of the following is the correct RPV level?

a. 215 inches.

b, 175 inches.

c. 40 inches.

d. RPV level is unknown.

Question 80 The Appendix R Bypass Switch for 23MOV-15 (HPCI Inboard Containment Isolation) is in the BYPASS position. Which one of the following describes the effect that this will have on HPCI operation?

a. 23MOV-15 will not close on low steam pressure.

b. 23MOV-15 will not operate from panel 09-3.

c. HPCI will not trip on high RPV water level.

d. HPCI will not auto-restart on low RPV level.

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SENIOR REACTOR OPERATOR EXAMINATION Question 81 During refueling operations, irradiated components may be lifted with an auxiliary hoist.

Which one of the following describes the required method to assure adequate water shielding -

for personnel involved in this operation?

a. Tape markers on the hoist cable to inform the operator when to stop lifting.

b. A jamming device on the cable to prevent hoist movement above the safe level.

c. A Reactor Engineer must participate in all such operations.

d. A secotid SRO must be present on the Refueling Bridge.

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Question 82 EOP-5 (Secondary Containment Control), has been entered due to high area temperatures.

Other Secondary Containment parameters also have been increasing. No primary system is currently discharging into the Secondary Containment. Which one of the following combinations of area temperatures and radiation levels require a reacter shutdown?

a. SLC Pump Area - 140 *F and RWCU HX room radiation level of 1600 mR/hr.

b. RWCU Pump Area radiation level of 800 mR/hr and RWCU HX Room radiation level of 1200 mR/hr.

c. RWCU HX Room temperature of 205 'F and RCIC Room Temperature is 120 'F. -

d. HPCI Room temperature of 150 'F and RCIC Room temperature of 150 'F.

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SENIOR REACTOR OPERATOR EXAMINATION Question 83 During normal plant operation, the SNO is injured and contaminated. The only on-shin Radiation technician and the SNO both leave site in the ambulance. The CRS is not qualified as fire brigade leader. Which one of the following describes the allowable times to restore the full shift complement?

a. SNO within two hour.,; Rad Tech by end of shift.

b. SNO within two hours; Rad Tech within two hours.

c. SNO by end of shift; Rad Tech within two hours.  ;

d. SNO by end of shift; Rad Tech by end of shift.

Question 84 You are the SM and it is brought to your attention that present thermal power is 2560 MWth.

Which one of the following actions, if any, is required as a result of this situation?

a. No action required, this is within tolerance for full power.

b. Adjust power if necessary to assure that the 8-hour average is 2536 MWth or less.

c. Immediately reduce power to 2536 MWth or less and assure that the 8-hour average is 2536 MWth or less.

d. Commence a plant shutdown and issue a verbal report to the NRC within I hour of the discovery of the situation.

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Question 85 Reactor power level is 6% and personnel are in the Drywell. Which one of the following describes the current restrictions on control rod motion?

a. No rod motion is permitted until personnel are clear of the Drywell. )

b. No planned rod motion is permitted but rods may be inserted as needed to terminate unplanned events.

c. There are no restrictions on rod insertion. Withdrawal is prohibited.

d. There are no restrictions on rod motion as long as personnel are not working above elevation 292 ft. in the Drywell.

Question 86 The plant is at full power when Chemistry reports the following SLC parameters:

. Weight % Sodium Pentaborate is 10.5%.

. Net Volume of Solution is 2500 gal.

. Solution temperature is 60 'F.

Which one of the following changes will bring the SLC system into compliance with Tech Specs?

a. Increase solution temperature to 70 'F.

b. Raise the Weight % to 11.2%.

c. Raise the Weight % to 11.2% and the Net Volume to 2550 gallons.

d. Raise the Net Volume to 3000 gallons.

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SENIOR REACTOR OPERATOR EXAMINATION Question 87 It is day 90 of a continuous full power run when Chemistry reports that the following sample readings have been verified:

. Conductivity is 1 pmho.

. Chloride ion is 0.4 ppm.

Which one of the following actions, if any, is required by Tech Specs?

a. Readings are within specifications, power operation may continue, b. Reduce steam flow to less than 100,000 lb/hr. within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. Be in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching a steam flow rate of 100,000 lb/hr.

d. Be in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Question 88 A temporary change to a procedure has been approved by an SRO and implemented. After l

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< the changed procedure had been used, the RPO (Responsible Procedure Owner) disapproved the change. Which one of the following describes the need for a Deviation and Event Report (DER) and whether the change must be withdrawn?

a. DER is required; PORC decides if the change must be withdrawn.

b. DER is required; the change must be withdrawn.

c. DER is not required; PORC decides if the change must be withdravm.

d. DER is not required; the change must be withdrawn.

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SENIOR REACTOR OPERATOR EXAMINATION Question 89 Use of a Temporary Mod is prohibited for which one of the following applications? l

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a. To correct a design deficiency while a permanent solution is pending.

b. Allow testing of plant equipment.

c. To temporarily compensate for a procedural deficiency.

d. To allow continued operation of essential equipment.

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Question 90 Today is November 3 and the time is 0800. 'A' RHR is inoperable for a planned LCO that began on November 1 at 0800. It is determined that the work cannot be completed before November 12. Which one of the following describes the actions that are required for this condition?

Place the plant in the cold condition no later than 0800 on; a. November 4.

l b. November 8. )

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c. November 9.

d. November 10.

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SENIOR REACTOR OPERATOR EXAMINATION Question 91-During an outage the plant is in Risk Condition Green. Work is planned which will result in a degradation to Risk Condition Yellow. In addition to the Shift Manager which one of the following lists all of the approvals required, if any, before this work can start?

a. No additional approvals.

b. General Manager of Operations and Planning Manager.

c. Operations Manager and General Manager of Maintenance.

d. ~ Operations Manager and Planning Manager.

Question 92 You are the Core Alteration SRO during fuel offload. An irradiated fuel bundle is being transferred to the Spent Fuel pool when you are required to leave the Reactor Building for a random drug test. The only other SRO on shift is the SM. Which one of the following actions is permitted under these conditions?

a. The bridge operator may complete the move but may not pick up another bundle until your retum.

b. As long as an RO is stationed in the control room, the SM may temporarily assume your function.

c. If qualified, you may tumover and exchange shift positions with the SM. Fuel handling operations may continue.

d. The NYPA Refuel Floor Supervisor may assume your duties. Fuel handling operations may continue.

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SENIOR REACTOR OPERATOR EXAMINATION Question 93 Which one of the following meets ALARA for performing ajob? ,

a. 1 man accomplishing the job in I hour in a 60 mR/hr field.

b. I man installing shielding for 30 minutes in a 60 mR/hr field and then accomplishing the job in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in a 6 mR/hr field.

c. 2 men accomplishing the job in 25 minutes in a 60 mR/hr field.

d. 2 men installing shielding for 15 minutes in a 60 mR/hr field and then accomplishing the job in 25 minutes in a 6 mR/hr field.

Question 94 Which one of the following describes the JAF administrative limit for the maximum TEDE which a radiation worker may accumulate in one year with the maximum dose extensions approved?

a. 2 Rem.

b. 3 Rem.

c. 4 Rem.

d. 5 Rem. j i

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SENIOR REACTOR OPERATOR EXAMINATION Question 95 Routine makeup nitrogen cupplied to the Drywell to mainiain an inerted state should be supplied by which one of the following train configurations?

a. Train 'A'is preferred.

b. Train 'B' is preferred.

c. Trains 'A' & 'B'should be alternated for each makeup operation.

d. Trains 'A' & 'B'should be operated while cross-connected.

Question 96 You are the Shift Manager / Emergency Director and the following conditions exist:

A non-isolable steam leak is discharging into the Turbine Building. A ground-level release is in progress. Radiological hazards exist outside the plant. A Site Area Emergency has been declared. You have decided to evacuate the site.

Which one of the following describes where you will send non-essential personnel?

a. Nine Mile Training Center.

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b. State Fairgrounds.

c. Emergency Operating Facility.

d. Niagara Mohawk Service Center.

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SENIOR REACTOR OPERATOR EXAMINATION Question 97 Foam must not be used for fighting fires in the vicinity of new fuel for which one of the following reasons? ,

a. Voiding of fuel warranty.

b. Corrosive effect on cladding.

c. Danger of criticality.

d. Fouling of heat transfer surfaces.

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Question 98 An Unusual Event has been declared. Which one of the following describes the time limits for notifying off site agencies?

a. USNRC within 15 minutes, state and county within I hour.

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b. USNRC within 15 minutes, state and county within 15 minutes.

c. USNRC within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, state and county within 15 minutes. .

~ d. USNRC within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, state and county within I hour.

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SENIOR REACTOR OPERATOR EXAMINATION Question 99 The following conditions exist:

. An ATWS is in progress.

. The operators have reduced RPV level to -10 inches in accordance with EP-5 (Termination and Prevention of RPV Injection).

. SLC is injecting.

. Reactor power is 1%.

. Torus temperature is 157 'F.

Which one of the following Emergency Plan EALs must be declared and which evacuation must be performed?

a. Site Area Emergency; Radiologically Controlled Area Evacuation, b. General Emergency; Radiologically Controlled Area Evacuation.

c. Site Area Emergency; Protected Area Evacuation.

d. General Emergency; Protected Area Evacuation.

Question 100 EOP-4, ' Primary Containment Control,' Torus Level Control leg, directs the operator to

' Terminate and prevent HPCI operation irrespective of whether adequate core cooling is assured' if Torus level cannot be maintained above 10.75 feet.

Which of the following describes the effect of continued operation of the HPCI system?

Continued operation will:

a. damage the HPCI turbine by supplying high temperature cooling water to the oil system.

b. reduce Torus water level below the safety relief valve T-quenchers.

c. result in a direct discharge of steam into the Torus air space.

d. result in a loss of the last high pressure injection system on high exhaust backpressure.

""* END OF EXAMINATION "*"

LOSS OF SHUTDOWN COOLING * AOP-30 ATTACHMENT 2 Page 1 of 1 CORE DECAY HEAT VS. TIME AFTER SHUTDOWN I

Days after BTU /hr Days after BTU /hr shutdown shutdown 0 6.28E8 21 1.48E7 1 4.79E7 l 22 1.44E7 l 2 3.92E7 l 23 1.42E7 3 3.36E7 l 24 1.39E7 4 2.97E7 l 25 1.36E7 5 2.69E7 l 26 1.33E7 6 2.48E7 l 27 1.31E7 7 2.32E7 l 28 1.28E7 8 2.19E7 l 29 1.26E7 9 2.08E7 l 30 1.24E7 10 2.00E7 l 31 1.22E7 11 1.92E7 l 32 1.20E7 12 1.86E7 l 33 1.18E7 13 1.80E7 l 34 1.16E7 14 1.75E7 l 35 1.14E7 15 1.70E7 l 36 1.12E7 16 1.66E7 l 37 1.10E7 17 1.62E7 l 38 1.09E7 ,

18 1.58E7 l 39 1.07E7 19 1.54E7 l 40 1.06E7 20 1.51E7 l 730 9.13E5 I l

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LOSS OF SHUTDOWN COOLING * AOP-30 ATTACHMENT 3 Page 1 of 1 ALTERNATE COOLING METHODS METHOD APPROXIMATE HEAT LIMITATIONS REMOVAL CAPACITY (BTU /hr)

Decay Heat Removal 3.00E7 * Gates removed between cavity and spent fuel pool Puel Pool Cooling 3.30E6 * Gates removed between cavity and spent fuel pool e RBC must be available

  • SW must be available Fuel Pool Cooling 2.40E7 * RHR must be available Assist
  • RHRSW must be available o Gates removed between cavity and spent fuel pool RWCU Blowdown Mode 2.06E6 * No isolation signal present
  • 1 pump running * Makeup source must be
  • 125 gpm blowde,wn flow available (see list below)
  • 125 gpm makeup flow
  • Main Condenser-or Radwaste must be available RWCU Recire Mode 1.70E6 No isolation signal present RWCU Blowdown Mode 1.00E6 * No isolation signal present
  • gravity drain * Makeup source must be
  • 50 gpm blowdown flow available (see list below)
  • 50 gpm makeup flow

must be available Makeup Sources

Condensate transfer keep-full using Core Spray or RHR

  • Condensate /Feedwater

Condensate transfer to skimmer surge tanks (gates removed)

Condensate transfer to fuel pool using DHR (gates removed)

Condensate transfer using service box connections on the refuel floor (gates removed)

  • Fire Protection System water from local fire hose stations or outside sources

RHR service water cross-tie Fire Water Crosstie Rev. No. 10 Page . 19 of 19

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SRO ANSWER KEY 1) B 26) D 51) D 76) B 2) B - 27) B 52) C 77) B 3) B' 28) A 53) B 78) A 4) C 29) C 54) C 79) D 5) D 30) A 55) A 80) A 6) D 31) DELETED 56) A 81) B 7) B 32) B 57) A 82) D-8) C~ 33) D 58) D 83) B 9) DB 34) D 59) D 84) C 10) A 35) C 60) D 85) B 11) C 36) B 61) A OR B 86) D 12) A 37) D 62) A 87) A

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NEW YORK POWER AUTHORITY EXAMINATION / QUIZ JAMES A. FITZPATRICK NUCLEAR POWER PLANT COVER SHEET Examination Title: USNRC REACTOR OPERATOR EXAMINATION Examination Submitte y:sAAr Date: 11/03/97 Supervisor Approval: a

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A .E. mocci.5 Date: roles /97 Authorized Reference . ATTACHED Minimum Acceptable Grade: 80 Total Exam Points: 100 Grade: Graded By: Time Limit: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> STUDENT DATA Name: S.S.#:

Last First M.I.

Employer: NEW YORK POWER AUTHORITY Date:

Department:

GUIDFLINES 1. Remain quiet during the exam. If you have any questions during the exam, raise your hand. Your instructor wii! provide clarification wherever possible.

2. You are expected to do your own work and not to help anyone else.

3. Use only the authorized reference material. .

4. At the completion of this examination, you are to sign the following certification.

I certify all answers contained in this examination are my own. In addition, I have not received nor given any unauthorized assistance, nor have used any unauthorized references.

Student Signature: Date:

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REACTOR OPERATOR EXAMINATION

' Question 1

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With the plant operating at 50% power, which one of the following Main Generator faults will cause an automatic reactor scram?

a. High Stator Winding Temperature.

b. High Differential Current, c. i.ou ofIsolated Phase Bus Duct Cooling.

d. Low Hydrogen Pressure.

Question 2 An instrument failure has resulte'. , w ator scram from 20% power. The following conditions exist:

. Minimum RPV level react > u of <ches.

. Maximum RPV pressu. ,

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v 1005 psig.

. _Drywell pressure is 0 psig.

. All APRMs are downscale.

. Two control rods have failed to insert.

Under these conditions, the control rods will be inserted in accordance with which one of the following procedures?

a. AOP-01 (Reactor Scram).

b. EOP-02 (RPV Control).

c. EOP-03 (Failure to Scram).

d. EP-3 (Backup Control Rod Inse tia).

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i REACTOR OPERATOR EXAMINATION Question 3 Which one of the following is the reason that the Reactor Mode Switch should be taken out of the RUN position immediately after a Reactor Sciam? ,

a. Enable SRM and IRM rodblocks.

b. Prevent MSIV isolation.

c. Enable the SDIV high-level bypass circuitry.

d. Lower the APRM scram setpoint to 15%.

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Question 4 A reactor scram has just occurred followed by a Residual Transfer. Which one of the following describes the operators' concems regarding the MSIVs under these conditions?

a. Ensure the MSIVs close to minimize the possibility of Main Turbine overspeed.

b. Ensure the MSIVs close to minimize the possibility of Turbine Building contamination, c. Ensure the MSIVs remain open to minimize Torus heat load.

d. Ensure the MSIVs remain open to maintain availability of Turbine Scaling steam.

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Question 5 A power ascension is in progress with the following conditions:

. Power levelis 70%.

. Load line is 100%.

. Two Feedwater pumps are operating.

Which one of the following describes when and how the Recire. Pumps will runback if one Feed Pump trips?

a. Immediately runback to minimum speed.

b. When RPV level lowers to 196.5 inches, runback to minimum speed.

c. Immediately runback to 44% speed.

d. When RPV level lowers to 196.5 inches, runback to 44% speed.

Question 6 The following conditions exist:

. A Group 11 isolation has occurred due to high Drywell pressure.

. Present Drywell pressure is 5 psig.

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The EMERG OVERR DRYWELL HI PRESS keylock switch on the PCP panel has been taken to its OVERRIDE position.

. No other operator actions have been taken.

Which one of the following describes the CAD isolation valves that can be opened at this time?

a. All CAD isolation valves.

b. All CAD isolation valves except 27AOV-111 through 118 (CAD vent valves).

c. All CAD isolation valves except 27MOV-113,117,122,123 (CAD purge valves).

d. All CAD isolation valves except 27AOV 131 A/B,132A/B (CAD make-up valves).

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REACTOR OPERATOR EXAMINATION Question 7 The plant is operating at full power when the following occur:

. Generated MWe starts to decrease.

. Reactor power starts to decrease.

Which one of the following could have caused these symptoms?

a. Decrease in grid frequency.

b. Jet Pump malfunction.

c. Loss of feedwater heating.

d. Inadvertent SRV opening.

Que: tion 8 With a high Drywell pressure, Emergency RPV Depressurization is required if Torus Water Level cannot be maintained below PSP (Pressure Suppression Pressure). Which one of the following is the basis for performing an Emergency RPV Depressurization if'the Pressure Suppression Pressure Limit is exceeded?

a. To ensure that the vacuum breakers will not become submerged and fail to function.

b. To ensure adequate free volume (airspace) of the Torus for steam suppression.

i c. To prevent damaging the Torus. l l

d. To prevent steam from the Drywell bypassing the Suppression Pool. !

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REACTOR OPERATOR EXAMINATION Question 9 Which one of the following would give positive indication that SRV 'C' is opot when its h control switch is taken to OPEN7 l

a.~ SRV red light is on.

, b. SRV white light is on.

c. SRV tailpiece temperature rises and stabilizes at 285 *F.

d. EPIC alarm ' SONIC DET RV-C' RESET is received.

Question 10 The following conditions exist:

. A plant transient raised RPV pressure to 1150 psig.

. The SRVs have opened.

. RPV level is 150 inches.

Assuming no operator action, which one of the following describes when the SRVs are expected to close?

a. Before RPV pressure decreases below approximately 1050 psig, b. 120 seconds after the initial transient.

c. After RPV pressure decreases below approximately 50 psig.

d. When both RHR and Core Spray pumps are secured.  !

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Question 11 l A reactor scram occurred but many control rods failed to insert due to a high water level in the Scram Discharge Volume. The APRMs read 9 %. Which one of the following actions -

will be most effective in inserting control rods?

a. Manuallyinitiate ARI.

b. De-energize scram solenoids.

c. Manually insert control rods.

d. Close the CRD Flow Control valve.

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Question 12 Following the trip of one Recirc. Pump with the reactor at power, the operators have closed the discharge valve of the tripped pump. Which one of the following is the reason that this is l done?

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a. Stops reverse rotation of the tripped pump.

b. Prevents backflow through the idlejet pumps.

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c. Prevents runout of the operating recirc. pump.

i d. Lowers the probability of entering the instability region of the power / flow map.

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Question 13 The following conditions exist:

. Condenser vacuum is 25.1 inches Hg.

. Turbine load is 170 MWe.

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AOP-31 (Loss of Condenser Vacuum) has been entered.

Which one of the following actions, by itself, will make it MORE LIKELY that a manual Turbine Trip will be required?

a. Starting the Mechanical Vacuum pumps.

b. Increase load to 255 MWe.

c. Decrease load to 85 MWe, d. Placing the spare Air Ejector sets in service.

Question.14 With the plant shutdown, an Emergency Diesel Generator is running and is tied to its bus for load testing. Which one of the following describes the response to a complete loss of offsite power?

a. The Tie Breakers will trip and the diesel will maintain the bus loads.

b. The Diesel Output breaker will trip and the diesel will switch to isochronous mode, then the Diesel Output breaker recloses, c. The Diesel Output breaker will trip and the diesel will switch to droop mode, then the Diesel Output breaker recloses. f l

d. The Tie breakers and the diesel will trip.

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REACTOR OPERATOR EXAMINATION Question 15 Bus 10400 is powered by the Main Generator via breaker 10402. Which one of the following ways of opening this breaker will not allow closing the Station Reserve breaker 10412?

a. Manually opened locally.

b. Manually opened from the control room, c. Automatically opened on overcurrent.

d. Automatically opened on undervoltage.

Question 16 Which one of the following describes the loads in the 24 VDC Power System?

a. Each load breaker is connected to 48 VDC potential (input) from its associated

!24 VDC charger.

b. Half the loads on a 24 VDC distribution bus are powered from +24 VDC. The other half are powered from -24 VDC.

c. Each load breaker is connected to 24 VDC potential (input) from its associated 112 VDC charger, d. Half the loads on a 48 VDC distribution bus are powered from +48 VDC. The other half are powered from -48 VDC.

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REACTOR OPERATOR EXAMINATION Question 17 The following Narrow Range RPV level conditions exist:

. 'A' indicates 215 inches and is rising slowly.

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. B indicates 185 inches and is lowering slowly.

. 'C' indicates 214 inches and is rising slowly.

. Feedwater control is selected to the 'A' Column.

Selecting the 'B' RPV Level Column will result in which one of the following effects on level trends?

l a. 'A' and 'C' will continue to rise. 'B' will lower.

b. 'A' and 'C' will continue to rise. 'B' will rise.

c. 'A' and 'C' will lower. 'B' will lower.

d. 'A' and 'C' will lower. 'B' will rise.

Question 18 in which one of the following ways does a loss of 125 VDC Bus 'A' affect the ADS /SRV system?

a. Loss of'A' logic, ADS remains functional.

b. None of the ADS /SRV valves can be opened, c. The ADS /SRV valves cannot be opened from the remote panel.

d. Only valves F, J, K & L remain fully functional.

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REACTOR OPERATOR EXAMINATION l Question 19 AOP-43 (Shutdown From Outside the Control Room) requires the operators to remove RHR pumps 'A' and 'C' from service. Which one of the following describes the reason that bis .

step is necessary?

a. Prevent water hammer in the event of a LOCA signal.

b. Prevent inadvertent Drywell spray.

c. Prevent inadvertent LPCI injection.

d. Prevent draining the RPV to the Torus.

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Question 20 The following events occur:

. The plant is at 20% power.

. High radiation in the Off Gas system starts the Off Gas Timer.

. No operator action is taken.

Which one of the following will be the most likely cause of an automatic reactor scram?

a. High Reactor Power, b. Low RPV Level.

c. MSIV closure.

d. High RPV Pressure.

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Question 21 Which one of the following describes the use of ESW for Drywell cooling during a LOCA?

a.- It is the preferred method.-

b. It may be used only on loss of RBCLC.

c. It may be used only if directed by EOP-4.

d. It is prohibited.

Question 22 On a Loss ofInstrument Air pressure during normal plant operation, which one of the following describes if and when the MSIVs will go closed?

a. Inboards remain open; outboards close immediately.

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i b. Inboards and outboards close immediately. I c. Inboards close eventually; outboards close immediately.

d. Inboards remain open; outboards close eventually.

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. Question 23 The following conditions exist:-

. A valid Reactor Scram has occurred on low RPV level.

. The EDGs have auto started in response to high Drywell pressure. ,

. The Recire. pumps are running at minimum speed as expected.

i Which one of the following describes the status of the containment isolations?

a. Group I isolated; Group 11 isolated.

b. Group I not isolated; Group 11 not isolated.

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c. Group I isolated; Group II not isolated.

d. Group I not isolated; Group II isolated.

Question 24 During a plant startup RPV pressure is 900 psig. Loss of CRD flow will have which one of the following effects on control rod motion and scram times? .

a. Normal rod motion is unaffect.; and scram times will be within acceptable limits.

b. Normal rod motion is lost and scram times will not meet acceptable limits.

c. Normal rod motion is unaffected but scram times will not meet acceptable limits.

d. Normal rod motion is lost but scram times will be within acceptable limits.

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i Question 25 During power operation with RHR pump 'A' in Torus Cooling, an operator mistakenly manually opens RHR pump 'A' Shutdown Cooling Suction valve (10MOV-15A) locally at the valve. Which one of the following describes the expected automatic actions, if any?

a. There will be no automatic actions.

b. When 10MOV-15A reaches 10% open, it will automatically close the 'A' RHR Pump Suction Torus Isolation Valve (10MOV-13A).

c. When 10MOV-15A reaches full open, the RHR Torus Cooling / Torus Spray outboard valve (10MOV-39A) will auto close.

d. The 'A' RHR pump will trip on low suction pressure.

Question 26 Which one orthe following describes the consequences of spraying the Drywell if Drywell conditions are not in the pemtissible region of the Drywell Spray Initiation Curve?

a. Water sprayed into the Drywell will turn to steam raising pressure even further.

b. The cold water will put excessive thermal stress on the Drywell which may lead to its failure.

c. The effect is unpredictable and would result in putting the plant in an unanalyzed condition.

d. Drywell pressure would drop more rapidly than could be handled by the vacuum breakers.

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Question 27 The following conditions exist:

l . The operators are conducting EOP-4. ,

l . HPCI and RCIC are injecting.

l . Torus level is 10.9 ft. and decreasing rapidly.

l Which one of the following actions,if any, must be.taken regarding HPCI and RCIC if Torus level cannot be maintained above 10.75 feet? -

a. Trip both HPCI and RCIC.

b. Trip HPCI, RCIC may remain running.

c. Trip RCIC, HPCI may remain running.

d. Both HPCI and RCIC may remain running.

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Qaestion 28 The Reactor Building Ventilation system is in operation when the exhaust plenum radiation levels exceed 10' cpm. Which one of the following d: scribes the expected response of the Reactor Building Ventilation and SBGT systems to this event?

a. Reactor Building Ventilation will isolate and neither train of SBGT will start.

b. Reactor Building Ventilation will isolate and both trains of SBGT will start.

c. Reactor Building Ventilation will not isolate and neither train of SBGT will start.

d. Reactor Building Ventilation will not isolate and both trains of SBGT will start.

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REACTOR OPERATOR EXAMINATION Question 29

. In the event that normal shutdown cooling capability has been lost, which one of the following states the minimum shutdown time before Fuel Pool Cooling Assist will provide adequate cooling?

a. Iday.

b. 4 days.

c. 7 days.

d. 9 days.

I Question 30 Which one of the following describes why it is important to establish forced Recire. flow during a Loss of Shutdown Cooling event?

a. Coolant stratification may mislead the operators into assuming bulk water temperature is below 212 'F.

b. Cooling of the recire. loop will produce a reactivity effect when the first recire.

pump is started.

c. Unstable transition boisia;; at low pressure may cause clad dam age. l I

d. Steam build up in the RHR s'uction piping will lead to waterhammer when RHR l flow is restored.

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REACTOR OPERATOR EXAMINATION Question 31 l

Which one of the following limits takes precedence during the operation of the SBGT system I with the Reactor Building isolated?

a. Maintain RB AP more negative than -0.25 inches of water.

b. Maintain charcoal filter temperatures less than 170 'F.

c. Limit SBGT flow to a maximum of 6000 scfm.

d. Maintain Reactor Building Ventilation exhaust radiation levels less than 10 cpm.

Question 32 Following a reactor scram the pressure in the Scram Discharge Volume (SDV) rises to RPV'

pressure. Which one of the following describes the most likely reason for this condition?

a. One or more CRDM seals have failed.

b. The scram nas not been reset.

c. The SDV vent valves have failed closed.

d. The CRDH flow control valve has failed open.

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REACTOR OPERATOR EXAMINATION Question 33 Which one of the following RWM conditions, if any, will prevent inseition of a selected rod using the Emergency In Svitch?

a. None.

b. Select Error.

c. Withdraw block.

d. Insert block.

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Question 34

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The following conditions exist:

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. The plant is shut down.

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. The 'A' RHR loop is in Shutdown Cooling. ,

. A LPCI initiation signal on low RPV level occurs. i Which one of the following describes the operator actions, if any, which must be taken in order for LPCI 'A' to start injecting?

a. None.

b. Reset the Group 2 isolation, manually start the pump and reset the injection valve isolation signal.

c. Manually align the suction path for the desired pump and reset the LPCI initiation signal.  ;

d. Manually align the suction path for the desired pump, manually start the pump, and reset the injection valve isolation signal.

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- Question 35 i l

The following sequence of events has occurred.

. A LOCA has occurred resulting in LPCI injection. -

. Offsite power is then lost. ,

. EDGs 'B', 'C', & 'D' start and load normally.

. EDG 'A' fails to start. .

Under these conditions, which of the following RHR pumps will be running two minutes after the loss of power? l a. All four b. 'B', 'C', & 'D'

c. 'A', 'C', & 'D'

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d. 'B' & 'D'

Question 36

- The follow events occur:

. A low RPV level causes HPCI to start and inject.

. HPCI is the only available injection system.

. RPV level starts to increase.

. The HPCI Aux. Oil Pump breaker trips.

Assuming no operator action, which one of the following describes the expected response of HPCI?

a. HPCI will trip when the Aux. Oil Pump breaker trips and can not restart.

b. HPCI will trip on High Level and can not restart.

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c. HPCI will trip on High Level and can restart on low level.

d. HPCI will continue mnning until manually tripped.

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REACTOR OPERATOR EXAMINATION Question 37 The following events have occurred:

. A LOCA has occurred.

. The Core Spray pumps auto staned on low level.

. RPV level subsequently recovered to 180 inches.

. The operators took both Core Spray Ptunp Switches to STOP.

. Drywell pressure is 2.3 psig.

Which one of the following describes the expected response of the Core Spray pumps to these events?

a. After auto-starting they remain on until the initiation logic is reset. l I

b. They stop when switched to STOP but restart if Drywell pressure increases above their auto-start setpoint.

c. They stop when switched to STOP but restart iflevel decreases below their auto-start setpoint.

d. They stop when switched to STOP and remain off.

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Question 38 l

Which one of the following describes the effect of a loss of 600 VAC power on the Core l 1. Spray system?

a. Core Spray pumps will not auto-start when required. They can be staned

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manually.

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b. Core Spray pumps cannot be started either automatically or manually.

l c. Core Spray pumps will start normally but their discharge valves will not open l automatically. l l

d. Core Spray pumps will stan normally but will trip on low flow. j l i

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REACTOR OPERATOR EXAMINATION Question 39 The operator takes the SLC keylock switch to START SYS-A. Pump 'A' receives a start signal but fails to start due to mechanical binding ofits bmake contactor. Which one of the following describes the expected response of the Squib Valves and RWCU system isolation valves to these events?

a. Neither Squib valve will fire; RWCU will not isolate.

b. Only the 'A' Squib valve will fire; RWCU will isolate.

c. Both Squib valves will fire; RWCU will isolate.

d. Both Squib valves will fire; RWCU will not isolate.

Question 40 Following a Residual Transfer and prior to the operator taking any actions, which one of the following describes the ability to start the SLC pumps and fire the squib valves?

a. The. pumps can be started and the squib valves will fire.

b. The pumps cannot be started and the squib valves will fire.

c. The pumps can be started and the squib valves will not fire. 1 d. The pumps cannot be started and the squib valves will not fire.

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REACTOR OPERATOR EXAMINATION Question 41 The plant is operating at 100% power when a Generator Load Reject occurs. Which one of the following describes the RPS input that generates the first expected scram signal?

a. High RPV Pressure, b. High Neutron Flux, c. Turbine Control Valve Fast Closure.

d. Turbine Stop Valve Closure.

Question 42 The reactor is operating at 25% power. Which one of the following describes the response,if any, of RPS if the 'A' inboard and 'D' outboard MSIVs are closed?

a. Full Scram.

b. Half Scram in Channel 'A'.

c. Half Scram in Channel 'B'.

d. No effect.

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REACTOR OPERATOR EXAMINATION l

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Question 43 l

l A normal plant startup is in progress and the following conditions exist:

. The Reactor Mode Switch is in STARTUP. -

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. All the IRM range switches are on RANGE 2.

. No IRMs are bypassed.

Which one f the following describes the efTect on half scrams or rod blocks, if any, that will

! occur if the lxM 'A' Mode Switch is placed in the STANDBY position?

a. None, as long as its companion APRM is not downscale.  !

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b. Rod Withdrawal Block only.

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c. RPS Half Scram only.

d. Rod Withdrawal Block and RPS Half Scram. .

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Question 44 The following conditions exist:

. AllIRM Range switches are on RANGE 2.

. The SRM detectors are partially withdrawn. i l . SRM 'A' reads 80 cps.

Which one of the following describes the ability to withdraw SRM 'A' and the status of rod blocks?

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l a. The detector can be further withdrawn and a rod block exists.

b. The detector can be further withdrawn and no rod block exists.

c. The detector cannot be further withdrawn and a rod block exists.

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d. The detector cannot be further withdrawn and no rod block exists.

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_ Question 45 A Recirculation Flow Sununer fails resulting in zero output. Which one of the following is the highest power level at which the APRM will generate a rod block but not a scram signal?

a. 100 %

b. 75 %

c. 60%

d. 50 %

Question 46 Assuming no change in vessel inventory, starting the Recire pumps will affect Fuel Zone and Wide Range RPV level indication in which one of the following ways?

a. Fuel Zone rises; Wide Range rises.

b. Fuel Zone rises; Wide Range lowers.

c. Fuel Zone lowers; Wide Range rises.

d. Fuel Zone lowers; Wide Range lowers.

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REACTOR OPERATOR EXAMINATION Question 47 RCIC is in operation due to a small LOCA. Which one of the following describes the expected position of the RCIC Turbine Governor Valve (13HOV-2) and the RCIC Turbine Steam inlet Isolation Valve (13MOV-131) if RPV level rises to 222.5 inches?

a. Turbine Govemor Valve open; Turbine Steam Inlet Isolation Valve open.

b. Turbine Govemor Valve closed; Turbine Steam Inlet Isolation Valve open.

c. Turb.6- Governor Valve open; Turbine Steam Inlet Isolation Valve closed.

d. Turbine Governor Valve closed; Turbine Steam Inlet Isolation Valve closed.

Question 48 The following events have occurred:

. An Automatic Depressurization System (ADS) initiation has occurred. '

. The initiation signals are still present.

. A blowdown is in progress.

Taking the AD'S Normal / Override switches to OVERRIDE and back to NORMAL will have which one of the following effects on the ADS Valves?

a. ADS Valves will close and remain closed.

b. ADS Valves will close then reopen immediately.

c. ADS Valves will close then reopen after 120 seconds.

d. ADS Valves will remain open.

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Question 49 The following conditions exist:

. Drywell pressure has risen from 1.810 2.5 psig.

. Torus pressure has risen from 0 to 2.5 psig.

These conditions are symptomatic of which one of the follow'mg? )

a. SRV cycled to control pressure and an SRV tailpiece failure inside the Torus.

b. Small break LOCA in the Drywell and a Downcomer failure inside the Torus.

c. Small break LOoA in the Drywell and a Torus to Drywell vacuum breaker failed -

to open.

d. SRV cycled to control pressure and an SRV tailpiece vacumn breaker stuck open.

Question 50 With the Mode Switch in STARTUP, which one of the following conditions will result in the automatic closure of the MSIVs?

a. RPV Level is 50 inches.

b. Steamline pressure is 750 psig.

c. Main Condenser Vacuum is 10 inches Hg.

d. Turbine Stop valves not fully closed.

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REACTOR OPERATOR EXAMINATION Question 51 The plant is in shutdown cooling when a relay failure results in a spurious ADS logic Channel 'A' low-low-low level signal. No other level trips have occurred. Which one of the .

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following describes the effect that this event will have on ADS?

a. ADS willinitiate.

b.- ADS will not initiate because the RHR or Core Spray pump running interlock is bypassed in shutdown cooling.

c. ADS will not initiate because both channels are needed for ADS initiation.

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d. ADS will not initiate because there is no low-level trip.

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Question 52 RFP 'A' has just tripped on high reactor vessel level. Which one of the following conditions must be satisfied before the RFP 'A' hydraulic coupling automatically disengages?

a. HP and LP stop valves closed.

b. RFP turbine tripped signal sensed.

c. Turbine speed less than 4 RPM.

d. MGU and MSC on low speed stops.

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-Question 53-

, The following events occur.

. The plant is operating at full power with the MGUs and Master Controller balanced. - ..

. The Master Controller output slowly fails downscale. l

. RPV level lowers to 185 inches at which point the operator takes both MGUs to manual.

. No further operator action is taken.

Which one'of the following describes the response of Feed Flow and RPV level after the MGUs have been shifted to manual?

a. Flow will increase to 100%; Level will increase to 200 inches.

b. Flow will increase to 100%; Level will remain at 185 inches.

c.- Flow will increase to greater than 100%; Level will increase to 200 inches.

d. Flow will remain less than 100%; Level will continue to trend down.

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Question 54 The SBGT system has failed to auto start in response to a HPCI start signal. Which one of I the following will occur as a result of the failure of SBGT to start?  ;

I a. HPCI start up sequence will not complete and the HPCI turbine will not start.

i b. The HPCI turbine will start but may trip on High Exhaust Pressure.

. c. The HPCI turbine will start but may trip on High HPCI Area Temperature.

d. HPCI flow rate will be limited due to decreased condenser efficiency.

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REACTOR OPERATOR EXAMINATION Question 55 Which one of the following is the reason that operation of an EDO at loads near 2000 KW is to be avoided?

a. Excessive wear on turbocharger drive gears.

b. Main bearing degradation due to inadequate lube oil cooling.

c. ' Potential Lube oil sump fire due to increased piston blow by.

d. Overheating of exhaust system.

Question 56 Following a LOCA with concurrent Loss of Offsite Power, which one of the Eollowing will be the first to be reenergized when the 'A' and 'C' EDG breakers close?

a. 'A' ESW Pump. -

I b. 'A' RHR Pump.

c. 'C' RHR Pump.

d. 'A' Core Spray Pump.

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REACTOR OPERATOR EXAMINATION Question 57 The operator withdraws a control rod one notch but the rod position indications show that the rod is withdrawing continuously until it reaches full out position. Which one of the following could be the cause of this?

a. Stuck collet piston.

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b. High CRDH pressure.

c. Uncoupled rod.

d. Leaking HCU Scram Inlet valve (03AOV-126).

Question 58 Reactor power is 5%. The RWM is fully operational and has generated a Withdraw Block.

Under these conditions, which one of the following is the maximum number of rods with insert errors that could possibly be moved in the withdraw direction?

a. None.

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b. One.

c. Two.

d. Three.

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REACTOR OPERATOR EXAMINATION Question 59 The plant is operating at full power when the following Recire. Pump Seal readings are noted: .

. #1 (inner) Seal Cavity pressure is 1000 psig.

. #2 (outer) Seal Cavity pressure is 150 psig.

Which one of the following will cause these conditions?

a. Normal operation ofboth seals.

b. Failure of both seals.

c. Partial failure of the #1 seal.

d. Partial failure of the #2 seal.

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Question 60 During the startup of the 'A' Recire. Pump the following conditions exist:

. The 'A' Recire. Pump Discharge valve is 85% open.

. The 'B' Recire. Pump Discharge valve is fully open.

. Total Feed Flow is 30%.

. Feedwater pump 'A' is running; Feedwater pump 'B' is secured.

. RPV levelis 195 inches.

Which one of the following describes the most restrictive Recire. Pump speed limitations currently in effect?

a. Both pumps are limited to 30%.

b. Both pumps are limited to 44%.

c. Pump 'A' is limited to 30%; 'B' is not limited.

d. Pump 'A' is limited to 30%; 'B' is limited to 44%.

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REACTOR OPERATOR EXAMINATION -

Question 61.

The drive mechanism of a fully withdrawn control rod is uncoupled. Which one of the

. following indications during the coupling check indicates that the rod is uncoupled?

a. Individual Rod Drift Alarm.

b. Individual Rod Overtravel Alarm.

c. '49' will be displayed in the rod position window.

d. Individual Rod Full Out light remains energized.

Question 62 Three of the eight LPRM detectors supplying an RBM channel have failed downscale.

Which one of the following describes the response, if any, of the RBM to these failures?

a. There will be no functional effect since the RBM still has sufficient LPRM irputs to function.

b. The rod block setpoint will be automatically adjusted downward to compensate for the lost inputs.

c. An Inop. Rod Block will be generated until one detector is bypassed.

d. ' A Rod Block will be generated until the PUSH TO SETUP pushbutton has been depressed.

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l l Question 63

! Which one of the following describes the effect of spraying the Drywell during a LOCA when Drywell pressure is below 2.7 psig?

a. Unnecessary damage to equipment in the Drywell.

b. Partial de-inerting of the Primary Containment.

l c. Inability to vent the Primary Containment.

L d. Mechanical failure of the Torus to Drywell vacuum breakers.

l

!

l

!

l Question 64 i The operators are unable to reset an inadvertent Group I isolation signal. Which one of the l following conditions, ifit existed, would cause this problem?

!

l a. A control switch for one of the MSIVs is in the OPEN position.

b. The Reactor Mode Switch is in RUN.

l l c. The control switches for the Main Steam Line Drain valves are in the OPEN l position.

l d. The AP across the MSIVs is 125 psid.

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REACTOR OPERATOR EXAMINATION Question 65 During plant operation it is noted that 345 KV bus voltage is 380 KV. Which one of the following is the appropriate response, if any, to this condition?

a. No response required.

b. Reduce generator output voltage to restore 345 KV bus voltage to normal.

c. Cor. tact the Load Dispatch Center and request that 345 KV bus voltage be reduced.

d. Increase Generator Isolated Phase Cooling to maximum.

Question 66 The following sequence of events occurs:

. 600 VAC power is lost for 3 minutes.

. After 600 VAC power is restored,125 VDC power is briefly lost.

. 125 VDC power is then restored.

After restoration of 125 VDC power, which one of the following will be the source, if any, of 120 VAC UPS Instrument Power 7 a. Nothing,120 VAC will be deenergized.

b. 600 VAC via the UPS MG Set.

c. 600 VAC via the 600/120 VAC transformer.

d. 125 VDC via the UPS MG Set.

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REACTOR OPERATOR EXAMINATION Question 67 Loss of all 125 VDC power would have which one of the following effects on the Emergency Diesel Generators? ,

a. Diesels would auto-start and load.

b. Diesels would auto-start, but would not auto load.

c. Diesels would not start and could not be started at the Engine Control Panel.

d. Diesels would not auto-start but could be started at the Engine Control Panel.

.

Question 68 Which one of the following describes the effect of the Control Room Inlet Radiation Monitor channel failing upscale?

a. Alarm only.

b. The intake and Exhaust dampers close and the Recire. damper opens.

c. The Control Room Supply fans trip and the Exhaust Damper closes. .

d. The Emergency Supply fan starts and the Inlet filter system is placed in service.

.

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REACTOR OPERATOR EXAMINATION Question 69 Which one of the following describes a potential path for radioactive contamination to the discharge canal during normal power operation?

a. Drywell Air Cooler tube leak.

b. RBCLC Heat Exchanger tube leak.

c. Recombiner condenser tube leak.

d. Main Condenser tube leak.

l Question 70 Which one of the following describes the response of any TIP detector not in its shield when a Group I and Orc * 11 Containment Isolation Signal occurs?

a. A Group I Isolation will cause the TIP to withdraw to the Lead Shield position. A Group II has no further effect.

b. A Group I Isolation will cause the TIP to withdraw to the Lead Shield position. A Group II will activate the shear valve if the TIP is still inserted.

c. A Group I Isolation will have no effect. A Group II Isolation will actuate the shear valve if the TIP is not withdrawn within 10 minutes.

d. A Group I Isolation will have no effect. A Group II Isolation will cause the TIP to be withdrawn to the Lead Shield position.

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REACTOR OPERATOR EXAMINATION I

Question 71

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The crew is conducting EOP-5 (Secondary Containment Control) when Reactor Building ventilation isolates on high radiation. The radiation level is subsequently seen to decrease below the isolation setpoint. Which one of the following describes under what condition, if any, it is permissible to override the high radiation isolation to restart the Reactor Building ventilation system?

a. It is not permissible.

b. Two Reactor Building area temperatures are above maximum normal.

c. After it is confirmed that no primary system is discharging into the Reactor Building.

d. If Reactor Building AP cannot be maintained at a negative pressure with SBGT.

Question 72 l

Inadvertent closure of which one of the following CRD HCU valves will result in the l

inability to scram the affected rod?

l n. Scram Inlet Valve - 126.

l

! b. '4nsert Header Isolation - 101.

l c. Exhaust Water Header Isolation - 105.

!

d. Withdraw Header Isolation - 102.

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REACTOR OPERATOR EXAMINATION Question 73 l

The plant is operating at 50% power with RCIC testing in progress. Under these conditions, Tech Specs require an immediate reactor scram if Torus temperature reaches which one of the following temperatures?

a. 95'F ,

b. 105'F c. I10'F d. 120 'F Question 74 i

Fuel handling operations are in progress when a Fuel Pool leak is discovered. Which one of l

the following states the initial point at which immediate evacuation of the Refuel Floor i

becomes mandatory? I a. When the presence of the leak is verified. j b. When level decreases below its Tech Spec limit (33 feet).

c. When uncovering of spent fuel is imminent.

d. When uncovering of spent fuel has occurred.

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REACTOR OPERATOR EXAMINATION l

Qucstion 75 A plant stettup is in progress and Recire. pump speed is 30%. APRM readings are as listed below: .

. Channel A 2.3%

. Channel B 4.0%

. Channel C 5.0%

. Channel D 4.7%

. Channel E 2.4%

. Channel F 5.1%

If the Reactor Mode Switch is placed in RUN, which one of the following describes the ability to raise power with control rods and/or recire. flow?

a. The power can be raised using rods or recire flow.

b. Power can be raised using rods only.

.

c. Power can be raised using recire, only.

d. Power cannot be raised.

Question 76 The plant is operating at full pov.er when the pressure compensation for the in service RPV level column is lost. Which one of the following describes the effect that this will have on actual RPV water level?

a. RPV level will lower until a reactor scram occurs, b. RPV level will lower (by about 12 inches) and stabilize.

I c. RPV level will rise until a reactor scram occurs.

d. RPV level will rise (by about 12 inches) and stabilize.

.

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REACTOR OPERATOR EXAMINATION Question 77 The plant is at full power and the 'A' Pressure Regulator is in control. Failure of which one of the following inputs to the EHC Pressure Regulators will have the smallest impact on RPV pressure?

a. 'A' Pressure Regulator throttle pressure fails high.

b. 'A' Pressure Regulator throttle pressure fails low.

c. 'B' Pressure Regulator throttle pressure fails high.

d. 'B' Pressure Regulator throttle pressure fails low.

i

)

Question 78 The plant is operating at full power when RBCLC flow to the RWCU system is lost. Which one of the following is the expected response of the system isolation and the Holding pumps to this event?

a. The system will not isolate; The Holding pumps will start.

b. The system will isolate; The Holding pumps will trip.

c. The system will not isolate; The Holding pumps will trip.

d. The system will isolate; The Holding pumps will start.

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REACTOR OPERATOR EXAMINATION Question 79 The plant is at 70% power with all Condensate, Condensate Booster, and Feed pumps running. Which one of the following describes the expected plant response to the trip of one Condensate pump?

a. The remaining pumps will remain in service and RPV level will not be affected.

b. One Feed pump will trip on low suction pressure but RPV level will not be affected.

c. One Feed pump will trip on low suction pressure and RPV level will decrease.

d. One Condensate Booster pump will trip but RPV level will not be affected.

Question 80 Which one of the following describes the purpose of the Reactor Steam supply to the Off Gas Hydrogen Recombiner?

a. Dilutes hydrogen to below the explosive limit.  !

b. Increase temperature which improves efficiency of recombination.

c. Improves removal of radioactive iodines from gas stream.

d. Improves cooling of the charcoal filters during accident conditions.

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REACTOR OPERATOR EXAMINATION -

- Question 81 Fire Main use during a fire on site caused its pressure to lower to 90 psig for 30 seconds.

.

Pressure subsequently recovered to 120 psig where it has remained for the past 10 minutes.

Assuming no operator action concerning the Fire Pumps, which one of the following identifies the Fire pumps that should be running at this time?

a. Makeup Pump only.

b. Makeup Pump and Motor Driven Fire Pump only.

c. Makeup Pump, Motor Driven Fire Pump and One Diesel Driven Fire Pump only.

d. Makeup Pump, Motor Driven Fire Pump and Both Diesel Driven Fire Pumps.

Question 82 The following air pressures exist in the Instrument and Service Air headers:

. Instrument Air is 100 psig.

. Service Air is 90 psig.

Unoer these conditions, which one of the following describes the expected position of the Instrument to Service Air Isolation valve (39FCV-110) and the Breathing Air Isolation valve (39FCV-111)?

a. Both will be open.

b. FCV-110 will be open. FCV-11I will be closed.

c. FCV-110 will be closed. FCV-111 will be open.

d. Both will be closed.

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REACTOR OPERATOR EXAMINATION Question 83 An RBCLC Makeup Tank Level annunciator is alarming due to a high level. Which one of

-

the following is the most likely cause of this condition?

a. Tube leak in the RBCLC heat exchanger.

b. Tube leak in the RWCU NRHX.

c. RBCLC low-low pressure.

d. RHR pump seal cooler leak.

J Question 84 During normal power operation, which one of the following sources can be used for emergency makeup to the Spent Fuel Pool?

a. CRD.

b. Condensate Transfer.

c. Core Spray. .

d. RHR Service Water, i

.

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REACTOR OPERATOR EXAMINATION

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Question 85 t

The Reactor Mode switch is in the REFUEL position, and the Refueling Platform (bridge) is over the Reactor Vessel. Which one of the following would cause a Rod Block under these conditions? I a. The Auxiliary Hoist is loaded.

b. The Fuel Grapple is in the FULL UP position.

c. The Service Platform Hoist is unloaded and not FULL UP.

d. All rods are Full-In, except for a selected rod at position 02.

Question 86 In accordance with AP-02.04, which one of the following activities requires an instruction or procedure to perform?

a. Checking a relay energized or deenergized.

b. Changing a fish basket.

c. Checking an oil sump level, j d. Opening drain valves within a PTR boundary.

.

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Question 87 During normal plant operations, you have been assigned to perform a routine task that is govemed by a Reference Use procedure without step signoffs. .Which one of the following describes the requirements for procedure review and reference?

a. No prior review of the procedure is required. Reference to the procedure during the task is not required.

b. Review the procedure prior to performing the task. Reference to the procedure during the task is not required.

c. Review the procedure prior to performing the task. Refer to the procedure prior to performing each step.

d. No prior review of the procedure is required. Refer to the procedure prior to performing each step.

Question 88 The plant is at full power when ST-SD (APRM Calibration) shows that the AGAF for an APRM is 1.02. Which one of the following describes the significance of this reading?

a. There is no significance if FRP is greater than MFLPD.

b. The reactor will scram at a higher power than allowed.

'

c. The reactor will scram at a lower power than required.

d. The APRM has too few inputs.

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RI ACTOROPERATOREXAMINATION .

Question 89 Operation with a high hotwell level (>l 12 inches) is likely to have which one of the following consequences?

a. Condenser tube damage due to high tube vibration.

b. Condenser Air Removal pump damage due to high moisture intake.

c. Unmonitored release to the lake via the Cire. Water system.

d. Condensate pump damage due to runout.

Question 90 You are hanging a PTR on a circuit breaker and the PTR form has a slash through the first check block (' Initials first') for that component. Which of the following describes the meaning of the slash on the PTR form?

a. This is a replacement for a lost tag.

b. No independent verification is required.

c. Dual concurrent verification is required.

d. The position of the circuit breaker is not being changed.

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REACTOR OPERATOR EXAMINATION Question 91 The scram times of 136 control rods have been measured and average 3.50 seconds to position 04. What is the slowest scram tirne that the remaining control rod can have and still -

satisfy the requirements of Tech Specs?

a. 3.554 sec.

b. 3.764 sec, c. 7.000 sec.

d. 10.900 sec.

.

Question 92 During fuel handling operations the operator in the control room notes that the SRMs are reading below 3 cps. Under which one of the following conditions, if any, may fuel handling continue?

a. The plant has been shutdown for more than 90 days.

b. A core spiral offload is in progress. -

c. A control rod blade replacement is in progress.

d. None. Fuel handling must always be terminated if SRMs fall below 3 cps.

.

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REACTOR OPERATOR EXAMINATION Question 93 l

A task in the RCA requires that you enter a Very High Radiation Area during normal plant operations. Which one of the following describes the minimum key (s) and RWP coverage requirements necessary to enter the area?

a. Single key from radiation Protection; Non-routine RWP b. Single key from Shift Manager; Operations standing RWP.

c. One key from Radiation Protection and one key from Shift Manager; Non-routine RWP.

d. One key from Radiation Protection and one key from Shift Manager; Operations standing RWP.

Question 94 You are wearing single PCs while working in the Reactor Building when immediate evacuation of the Reactor Building is directed over the Gaitronics. You should remove your PCs at which one of the following places?

a. Your current location when you hear the announcement.

b. Area Normal Step Off Pad.

c. Prior to entering the Reactor Building Airlock.

d. Admin Building RCA Access Point.

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REACTOR OPERATOR EXAMINATION Question 95 You are NCOI performing a shutdown from outside the Control Room. When you arrive at Panel 25RSP you report successful completion of all actions you were required to perform at other lo.:ations. Which one of the following actions remains to be accomplished?

a. Tripping the Main Turbine.

b. Closing the MSIVs.

I c. Closing the HPCI outboard steam supply.

d. Tripping the Recire. pumps.

Question 96 An Alert has been declared and the operators are conducting EOP-6 (Radioactivity Release Control). Which one of the following is a type of accident that this EOP is designed to mitigate?

a. Dropped fuel bundle in the Spent Fuel Pool.

b. Radwaste spill in the Radwaste Building.

c. Main Steam leak in the Turbine Building.

.

d. Fire in the SBGT filters.

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REACTOR OPERATOR EXAMINATION-Question 97 Following a failure to scram an operator has been directed to implement EP-3 (Backup Control Rod Insertion) at Panels 09-15 and 09-17 to remove and replace fuses. Which one of the following describes the desired outcome of this evolution?

a. Open the scram inlet and outlet valves.

b. Deenergize the RPS power supply buses.

c. Vent and Drain the Scram Discharge Volume.

d. Reset RPS.

Question 98 The reactor is operating at full power when the following events occur:

. The Turbine Control Valves close.

. The Turbine Bypass Valves fully open.

. The Reactor Scrams.

. The SRVs open briefly.

Which one of the following could have caused this chain of events?

a. Turbine Load Reference signal has failed downscale.

b. The MSIVs have closed.

c. The Backup (B) Pressure Regulator has failed low.

d. The Maximum Combined Flow Limiter has failed downscale.

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Question 99 A scram has occurred due to a transient resulting from a loss of UPS. Not all rods have fully

~

inserted. Which one of the following should be used to evaluate reactor power to determine .

l if entry into EOP-2 (RPV Control) is required?

l a. APRM chart recorders.

b. SPDS display.

c. Steam Flow.

d. Number of open SRVs.

.

Question 100 The following conditions exist:

. A LOCA has occurred at 100% power.

. EPIC is not available.

. 16TI-107 and 108 both indicate 256 *F.

. Drywell pressure on panel 09-3 indicates 40 psig.

. RPV 09-5 Wide Range indicates 40 inches.

. RPV 09-3 Fuel Zone Recorder indicates -130 inches.

Which one of the following describes the use of the Fuel Zone Recorder and the Wide Range :

Instruments?

NOTE: Figures 4.7 and 4.8 of EOP-4 are provided.

.

a. Neither the Fuel Zone Recorder nor the Wide Range is usable.

b. Fuel Zone Recorder is usable; Wide Range is not usable.

c. Fuel Zone Recorder is not usable; Wide Range is usable.

d. Both the Fuel Zone Recorder and the Wide Range are usable.

Page 50 of 50 l * *"* END OF EXAMINATION * * * * *

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LOSS OF SHUTDOWN COOLING * AOP-30 ATTACHMENT 2 Page 1 of 1 CORE DECAY HEAT VS. TIME AFTER SHUTDOWN Days after BTU /hr Days after BTU /hr shutdown shutdown 0 6.28E8 21 1.48E7 1 4.79E7 l 22 1.44E7 2 3.92E7 l 23 1.42E7 3 3.36E7 l 24 1.39E7 4 2.97E7 l 25 1.36E7 5 2.69E7 l 26 1.33E7 l

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6 2.48E7 27 1.31E7 7 2.32E7 l 28 1.28E7 8 2.19E7 l 29 1.26E7 9 2.08E7 l . 30 1.24E7 10 2.00E7 l 31 1.22E7 11 1.92E7 l 32 1.20E7 12 1.86E7 l 33 1.18E7 13 1.80E7 l 34 1.16E7 14 1.75E7 l 35 1.14E7 15 1.70E7 l 36 1.12E7 16 1.66E7 l 37 1.10E7 17 1.62E7 l 38 1.09E7 18 1.58E7 l 39 1.07E7 19 1.54E7 l 40 1.06E7 20 1.51E7 l 730 9.13E5 Rev. No. 10 Page 18 of 19

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LOSS OF SHUTDOWN COOLING * AOP-30 ATTACHMENT 3 Page 1 of 1 ALTERNATE COOLING METHODS METHOD -

APPROXIMATE HEAT LIMITATIONS i REMOVAL CAPACITY (BTU /hr)

Decay Heat Removal 3.00E7 * Gates removed between cavity and spent fuel pool Fuel Pool Cooling 3.30E6 * Gates removed between cavity and spent fuel pool i

  • RBC must be available
  • SW must be available

. Fuel Pool Cooling 2.40E7 * RHR must be available Assist

  • RNRSW must be available e Gates removed between cavity and spent fuel pool RWCU Blowdown Mode 2.06E6 * No isolation signal present-
  • 1 pump running * Makeup source must be
  • 225 gpm blowdown flow -

available (see list below)

  • 125 gpm snakeup flow
  • Main Condenser.or Radwaste must be available RWCU Recirc Mode 1.70E6 No isolation signal present RWCU Blowdown Mode 1.00E6 * No isolation signal present
  • gravity drain * Makeup source must be
  • 50 gpm blowdown flow available (see list below)
  • 50 gpm makeup flow .
  • Condensate /Feedwater
  • Condensate transfer to skiauner surge tanks (gates removed)
  • Condensate transfer to fuel pool using DHR (gates removed)
  • Condensate transfer using service box connections on the refuel floor (gates r2 moved)
  • Fire Protection System water from local fire hose stations or outside sources
  • Fire Water Crosstie

.

Rev. No. 10 Page 19 of 19

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b An R. v;er levelinstrument rnav not be used if either of th3 following conditions exists:

+ An instrurnent run terrporature is at or above the RPV Saturation Terrporature (Fig 4.7)

. The instrurnent roads at or below its Minimum Usable indcating Level (Fig 4.8)

FIGURE 4.7 RPV SATURATION TEMPERATURE e00

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RO ANSWER KEY 1) B 26) D 51) D 76) D 2) A 27) B 52) C 77) D.

i 3) B 28) B 53) B 78) D -

4) B 29) C 54) C 79) A 5) D 30) A 55) A 80) A 6) D 31) DELETED 56) A 81) C 7) B 32) B 57) A 82) C 8) C 33) D 58) D 83) B 9) DB 34) D 59) D 84) B 10) A 35) C 60) D 85) A 11) C 36) B 61) OR B 86) D 12) A 37) D 62) *

.. 87) B 13) B 38) C taj ti 88) B 14) A 39) C 64) A 89) C 15) C 40) A 65) C 90) C 16) A 41) C 66) C 91) C ,

17) B 42) D 67) C 92) B 18) A 43) D 68) A 93) C 19) B 44) DA 69) B 94) D 20) B 45) D 70) D 95) C 21)- D 46) B 71) A 96) C 22) D 47) C 72) D 97) A 23) D 48) C 73) C 98) A 24) D 49) B 74) C 99) B 25) A 50) A 75) D 100) B

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ATTACHMENT 2

RO EXAMINATION AND ANSWER KEY l

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ATTACHMENT 3 JAF COMMENTS ON WRITTEN EXAMINATION

. r RO 009 SRO 009 During the post-examination review, it was discovered that the key contained an incorrect answer, D vice the correct answer, B. This was a typographical error that occurred while balancing the examination di. tractors. The first submittal (attached) indicated the answer correctly.

Distractor. A is incorrect because the red light on indicates that the pilot solenoid is energized, not that the main valve is open.

l Distractor C is incorrect because the SRV tailpiece would rise to approximately 380

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degrees if the valve were open.

Distractor D is incorrect because the EPIC alarm RESET condition indicates that the high noise level condition associated with an open SRV has cleared.

I The key was changed from D to B to correct this error.

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010 TIER 1 GROUP 1/1 LICENSE LEVEL RS KNOWLEDGE LEVEL L ANSWER A

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Which one of the following would give positive indication that an SRV is currently open as a result of an automatic actuation caused by high RPV pressure?

a. White acoustic monitor light is on.

b. Tailpiece temperature is 235 *F.

c. Tailpiece temperature is 310 *F.

d. Red valve open light is on.

295025 HIGH REACTOR PbSSURE 2.4.03 l Ability to identify post-accident instrumentation.

IMPORTANCE 3.5/3.8 10CFR55.41(6)/() 10CFR55.43( )/() SOURCE 10CFR55 REASON REFERENCE SDLP-16B, Page 40 ,

ATTACHMENT

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LESSON PLAN SDLP-16B OBJECTIVE 1.01 NOTES

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CHANGES FROM ORIGINAL OUTLINE ORIGINAL SYSTEM / EVENT # ORIGINAL K/A#

REASON FOR CHANGE KNOWLEDGE LEVEL L-Lower (Recall) H= Higher LICENSE LEVEL R=RO S=SRO RS=Both SOURCE N=New Question B= Exam Bank (Not seen before) S-Bank (Seen in training program) M= Modified 10CI'R55 listings are the sub-paragraph numbers under 10CFR 55 4 I (for ROs) or 55.43 (for SROs) addressed by this question.

10CFR$$ reference is listed as (Assigned by K/A Manual) / (Assigned by question author)

Group and imponance are listed as RO/SRO values

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RO 031 SRO031 This question was deleted from the examination. During the post-examination review it was determined that the question had no correct answer. The limits stated form an envelope that bounds the operation of the system and no direction exists to violate one limit at the expense of another.

a. _ OP-20, STANDBY GAS TREATMENT SYSTEM, directs: IF reactor building differential pressure is less negative than --0.25 inches water, THEN ensure that SGT Train A (B) is in service per Subsection D.l(2).' No direction is given allowing this limit to be violated to meet other limits.

b. OP-20, STANDBY GAS TREATMENT SYSTEM, directs if the high temperature annunciator is received then the affected train is shutdown and cooling flow for the charcoal filters established using the other train.2 No direction is given allowing this limit to be violated to meet other limits.

c. OP-20, STANDBY GAS TREATMENT SYSTEM, directs: Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125F1-106A(B).3 No direction is given allowing this limit to be violated to meet other limits.

ONO, STANDBY GAS TREATMENT SYSTEM, revision 22, steps D.I.6 on pg.1 I, D.2.6 on pg.13, G.5.2 on pg. 28 and G.6.2 on pg. 29,

OP-20, STANDBY GAS TREATMENT SYSTEM, revision 22, steps G.I .4 on pg. 20 and G.2.4 on pg.

21.

OP-20, STANDBY GAS TREATMENT SYSTEM, revision 22, steps D.1.5.b on pg.11, D.2.5.b on pg.

13, G.5.3 on pg. 28 and G.6.3 on pg. 29.

1 ARP 09-75 2-16 ANNUNCIATOR SGT SYS B LEGEND ACT CHAR ..

mP HI CONTROLLED COPY SENSOR / 01-125TS-1*? SCT FILTEA TRAIN "B" CHARCOAL FILTER TEMP !

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TRIP POINT SWITCH (l' f)

CAUSE Heat from decay of fission products adsorbed by charcoal filters.

AUTOMATIC None ACTION OPERATOR 1. Refer to OP-20, Standby Cas Treatment System,

. ACTION section C for actions to be taken.

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l Rev. No. 3 PORC Meeting No.90-088 Date 08/29/90 Page 1 of 1 l

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ARP 09-75-1-16

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ANNUNCIATOR SCT SYS A l j

LEGEND ACT CHAR j

TEMP i HI SENSOR / 01-125TS-12A SGT FILTER TRAIN "A" CHARCOAL FILTER TEMP TRIP POINT SWITCH (170*F)

c.- r-n ni t.ED COPY CAUSE Heat from decay of fission products adsorbed by charcoal filters. ,

AUTOMATIC None ACTION OPEFATOR 1. Refer to OP-20, Standby Gas Treatment System, ACTION section C for actions to be taken.

Rev. No. 4 PORC Meeting No.90-088 Date 08/29/90 Page 1 of 1

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATING PROCEDURE STANDBY GAS TREATMENT SYSTEM * .

OP-20 REVISION 22 i REVIEWED BY: PLANT OPERATING REVIEW COMMITTEE MEETING NO. NA DATE NA APPROVED BY: - e DATE /2[T[74 RESPON5)BLE P'ROCED OWNER APPROVED BY: km0 -- - DATE 11 V f6

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P % MAlfAGER

EFFECTIVE DATE: December 4, 1996 FIRST ISSUE D FULL REVISION D LIMITED REVISION 8

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  • REFERENCE USE * * T I

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********.**.**.**..****** yync COPY # g* *.* ***.* ES
  • *

WITH TEMPORARY CHA

  • TECHNICAL
            • .******************
  • NOT UPDATEDBEFERENCE USE i

PERIODIC REVIEW DUE DATE 2/13/98 .

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STANDBY GAS TREATMENT SYSTEM * CP-20

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REVISION SUMMARY SHEET REV. NO. CHANGE AND REASON FOR CHANGE 22 Added Precaution C.2.1 to require Reactor Building Ventilation be isolated before performing any of the following activitics. This action is necessary to comply with the requirements of safety evaluation JAF-SE-96-071:

  • Fuel hanuling
  • Core alterations
  • Movement of heavy loads over the spent fuel pool or open reactor cavity

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2. Added Subsection G.10 to provide guidance for operation cf the Standby Gas Treatment System during filter sampling. (PCR dated 3/26/96)

20 1. Added Subsection G.7, to provide steps for operating SBGT when secondary containment penetrations are opened or degraded per PCR #10 dated 10/25/95.

2.. Changed description of activated charcoal in

Section-B, System Description per PCR #9 dated 7/10/95.

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. Revised Precaution C.2.2 to ine'.ude time limits per PCR #8 dated 7/10/95 and J. Dunham.

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Rev. No. 22 Page 2 of 45

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I STANDBY GAS TREATMENT SYSTEM * OP-20 l

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l TABLE OF CONTENTS l SECTION PAGE

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A. REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . .4

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B. SYSTEM DESCRIPTION . . . . . . . . . . . . . . . . . . . . 5 C. PLANT OPERATING REQUIREMENTS . . . .. . . . . . . . . . . 7 l D. STARTUP . . . . . . . . . . . . . . . . . . . . . . . . . 9 E. NORMAL OPERATION . . . . . . . . . . . . . . . . . . . . 14 F. SHUTDOWN . . . . . . . . . . . . . . . . . . . . . . . . 16 G. SPECIAL PROCEDURES . . . . . . . . . . . . . . . . . . . 19 H. ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . 36 1. REFERENCES . . . . . . . . . . . . . . . . . . . . . 37 2. TABLE 1 - VALVE LINEUP . . . . . . . . . . . . . . . 38 3. TABLE 2 - MAJOR COMPONENT POWER SUPPLIES . . . . . . 43

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STANDBY GAS TREATMENT SYSTEM * OP-20 A. REQUIREMENTS A.1 Technical Specifications Volume 1A Sections 3.7.B, 3.7.C and 4.7.C Volume 1B Section 3.8 A.2 Commitments None A.3 Validation Validated per ODSO-35.

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Rev. No. 22 Page 4 of 45

l STANDBY GAS TREATMENT SYSTEM * OP-20 i B. SYSTEM DESCRIPTION The Standby Gas Treatment System includes two identical filter tra',ns. Each filter train is a full capacity system -

that has the ability to maintain reactor building to i

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atmosphere differential pressure more negative than negative O.25 inches water gauge.

Each filter train includes the.following:

  • Demister: Removes entrained moisture, and in conjunction with the air heater, maintains humiolty less than 70% at the inlet to the charcoal filter.
  • 39 KW Electric Air Heater: Maintains humidity less than 70% at the inlet to the charcoal filter.
  • Prefilter: Removes particles.
  • High Ef ficiency Particulate Absolute Pre-Filter (HEPA) :

Designed to be capable of removing at least 99.97% of the 0.3 micron particles which impinge on the filter, however credit is only taken for 90% removal capability.

  • Activated Charcoal Filter: Removes in excess of 95% of the iodine in the air stream, with 10% of the iodine in the form of methyl iodide, with air entering the charcoal

- filter at less than *iO% humidity. Charcoal filter material is iodide or T2DA impregnated activated carbon.

  • High Efficiency Particulate Absciute Af^er-Filter (HEPA) :

Designed to be capable of removir.g at least 99.97% of the 0.3 micron particles which impinge on the filter, however credit is only taken for 90% removal capability.

  • Fan: Provides the differential pressure to draw gases through the train for treatment. The fan discharges to the stack.

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Rev. No. 22 Page 5 of 45

STANDBY GAS TREATMENT SYSTEM * OP-20 Each filter train can take suction from one or more of the following suction supplies:

  • Reactor Building above 369' elevation
  • Reactor Building below 369' elevation
  • Drywell vent connections
  • Torus vent connections
  • HPCI gland seal exhauster
  • Auxiliary Gas Treatment System Standby gas treatment trains are cross-tied at the fan suctions to allow drawing cool air over the charcoal filter of the inactive train to remove decay heat.

T'he Standby Gas Treatment System auto-initiates when any of the following conditions occur:

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  • Drywell pressure high (2.7 psig increasing) : Both trains start
  • RPV water level low (177 inches decreasing) : PCIS logic A sensors start A train; PCIS logic B sensors start B train

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Rev. No. 22 Page 6 of 45 l

l STANDBY GAS TREATMENT SYSTEM * OP-20 C. PLANT OPERATING REQUIREMENTS C.1 Prerequisites C.1.1 System valves are lined up per Attachment 2, with exceptions approved by the Shift Manager.

c.1.2 System power supplies are lined up per Attachment 3, with exceptions approved by the Shift Managen.

c.1.3 The following systems are in operation per their respective operating procedure, with exceptions approved by the shift Manager:

  • 4160 V and 600 V Normal And Emergency AC Power Distribution per OP-46A
  • Process Radiation Monitoring System per OP-31
  • Fire Protection System per OP-33.

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Fev. No. 22 Page 7 of 45

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STANDBY GAS TREATMENT SYSTEM * OP-20 C.2 Precautions I l

C.2.1  !

Reactor building ventilation shall be isolated before performing any of the following activities.

This action is necessary to comply with the requirements of safety evaluation JAF-SE-96-071:

  • Fuel handling I

e Core alterations

  • Movement of heavy loads over the spent fuel pool or open reactor cavity
  • Placing RX MODE switch in START & HOT STBY, without Primary Containment Integrity in effect C.2.2 During normal operation, 27MOV-120 (containment ;

exhaust to standby gas treatment isol valve) shall remain closed when primary containment is required per Tech Spec 4.7.B.4.

C.2.3 Operating a SGT train with the charcoal filters installed to vent paint fumes, welding fumes, or smoke could damage the charcoal filter. Guidelines to prevent possible charcoal filter damage from

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paint fumes are as follows:

  • Painting shall stop during periods of SGT operation.

required for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the completion of painting.

  • SGT should not be run for at least 30 minutes following the completion of painting.
  • If a SGT lun is desired within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following painting, Peactor Building Ventilation should not be isolated until the end of the SGT run.
  • SGT runs are kept as short as possible within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following painting.

C.2.4 To prevent plugging of the spray nozzles from debris caused by rust or corrosion, the fire protection water supply spray header between i 76FCV-107A/B and the spray nozzles shall be drained i following system actuation.

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Rev. !!c. 22 Page 8 of 45

. 1 STANDBY GAS TREATMENT SYSTEM * OP-20

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D.- STARTUP i TABLE OF CONTENTS SUBSECTION g D.1 Train A Startup . . . . . . . . . . . . , , . . . . . , lo D.2 Train B Startup . . . . . . . . . . . . . . , , . , , , 12 l

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Rev. No. 22 Page 9 of 45

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STANDBY GAS TREATMENT SYSTEM * OP-20 D.1 Train A Startup CAUTION Operating a standby gas treatment train with the charcoal filters installed to vent paint fumes, welding fumes, or smoke could damage the charcoal filter. See Precaution C.2.2.

D.1.1 Ensure open at least one of the follcaing valves:

D.1.3 Verify the 'ollowing:

Comoonent Status ,

  • Red light for AIR HTR 01-125E-5A On D.1.4 IF standby gas treatment is being placed in service to support any of the following:
  • Torus venting
  • Drywell venting

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  • Auxiliary Gas Treatment System operation THEN ensure required standby gas treatment suction valves are lined up.per the applicable procedure prior to proceeding to Step D.1.5.

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Rev. No. 22 Page 10 of 45 l

STANDBY GAS TREATMENT SYSTEM 0 OP-20 l

D.1.5 IF SGT Train B is shutdown, I THEN perform the following: l j

a. Verify open TRAIN B CLG VLV 01-125MOV-100B.

NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2A (SGT fan A suct isol valve).

b. Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A.

D.1.6 IF RB DIFF PRESS 01-125DPI-100A or B indicates less negative than - 0.25 inches water, TEEN ensure SGT Train B is in service per Subsection D.2.

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Rev. No. 22 Page 11 of 45

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STANDBY GAS TREA'.WENT SYSTEM * OP-20 D.2 Train B Startup -

CAUTION Operating a standby gas treatment train with the charcoal filters installed to vent paint fumes, welding fumes, or smoke could damage the charcoal filter. See Precaution C.2.2.

D.2.1 Ensure open at least one of the following valves:

D.2.3 Verify the following:

Comoonent Status

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  • Red light for AIR HTR 01-125E-5B On D.2.4 IF standby gas treatment is being placed in service to support any of the following:
  • Torus venting
  • Drywell venting

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Auxiliary Gas Treatment System operation I TREN ensure required standby gas treatment suction valves are lined up per the applicable procedure prior to proceeding to Step D.2.5.

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Rev. No. 22 Page 12 of 45

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I STANDBY GAS TREATMENT' SYSTEM * OP-20 D.2.5 IF SGT Train A is shutdown, THEN perform the following:  ;

a. Verify open TRAIN A CLG VLV 01-125MOV-100A.

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NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2B (SGT fan B suct isol valve). .

b. Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A.

D.2.6 IF RB DIFF PRESS 01-125DPI-100A or B indicates less negative than - 0.25 inches water, TEEN ensure SGT Train A is in service per Subsection D.1.

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Rev. No. 22 Page 13 of 45 I

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STANDBY GAS TREATMENT SYSTEM * OP-20 E. NORMAL OPERATION E.1 The Standby Gas Treatment System is normally maintained in the following standby lineup:

  • Valves lined up per Attachment 2 Component power supplies lined up per Attachment 3

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Valves Common To Both SGT Trains Comoonent Status ABOVE EL 369' SUCT 01-125MOV-11 . . . . . . . . . Closed BELOW EL 369' SUCT 01-125MOV-12 . . . . . . . . . Closed Train A Standbv Lineun Comoonent Status AIR HTR 01-125E-5A . . . . . White light on, red light off HPCI GLAND SEAL SUCT 01-125MOV-13A . . . . . . . . Closed

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TRAIN A CLG VLV 01-125MOV-100A . . . . . . . . . . . Open TRAIN A INLET 01-125MOV-14A . . . . . . . . . . . Closed 1 J

FN DISCH 01-125MOV-15A . . . . . . . . . . . . . . Closed TRAIN A FN 01-125FN-1A . . . . . . . . . . . . . Shutdown Train B Standbv Lineuo

Component Status AIR HTR 01-125E-5B . . . . . White light on, red light off HPCI GLAND SEAL SUCT 01-125MOV-13B . . . . . . . . Closed TRAIN B CLG VLV 01-125MOV-100B . . . . . . . . . . . Open TRAIN B INLET 01-125MOV-14B . . . . . . . . . . . Closed FN DISCH 01-125MOV-15B . . . . . . . . . . . . . . Closed TRAIN B FN 01-125FN-1B . . . . . . . . . . . . . Shutdown

,Section ( E continued on next page)

Rev. No. 22 Page 14 of 45 i

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STANDBY GAS TREATMENT SYSTEM * *

OP-20 E. (Cont)

E.2 Whenever standby gas treatment is in service, monitor the following parameters per ODSo-17:

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Rev. No. 22 Page 15 of 45 q

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STANDBY GAS TREATMENT SYSTEM * OP-20 F. SHUTDOWN TABLE OF CONTENTS SUBSECTION PAGE F.1 Train A Shutdown . . . . . . . . . . . . . . . . . . . . 17 F.2 Train B Shutdown . . . . . . . . . . . . . . . . . . . . 18 l

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Rev. No. 22 Page 16 of 45 l

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STANDBY GAS TREATMENT SYSTEM * OP-20 F.1 Train A Shutdown *

F.1.1 Ensure SGT Train A operation is not required.

F.1.2 IF SGT Train B is shutdown, . l THEN ensure closed the following valves: J l

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F.1.3 Close TRAIN A INLET 01-125MOV-14A.

F.1.4 Verify the following:  !

Comoonent $1gug

  • White light for AIR HTR 01-125E-5A On F.1.5 IF SGT Train B is in service,  !

TEEN ensure flow rate is 3000 to 6000 scfm i on SGT FLOW 01-125FI-106A.

NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2B (SGT fan B suct isol valve).

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Rev. No. __ 22 Page 17 of 45

STANDBY GAS TREATMENT SYSTEM * OP-20 F.2 Train B Shutdown -

F.2.1 Ensure SGT Train B operation is not required.

F.2.2 IF SGT Train A is shutdown, THEN ensure closed the following valves:

F.2.4 Verify the following:

Comoonent Status

- * TRAIN B FN 01-125FN-1B Shutdown

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  • White light for AIR HTR 01-125E-5B On F.2.5 IF SGT Train A is in service,

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TEEN ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A.

NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2A (SGT fan A suct isol valve) .

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STANDBY GAS TREATMENT SYSTEM 0 OP-20 G. SPECIAL PROCEDURES TABLE OF CONTENTS SUBSECTION PAGE G.1 Train A Charcoal Filter Cooling . . . . . . . . . . . . 20 G.2 Train B Charcoal Filter Cooling . . . . . . . . . . . . 21 G.3 Train A Charcoal Filter Fire Protection Water Spray . . 22 G.4 Train B Charcoal Filter Fire Protection Water Spray . . 25 G.5 Train A Auto-Initiation Verification . . . . . . . . . . 28 G.6 Train B Auto-Initiation Verification . . . . . . . . . . 29 G.7 Maintenance of Secondary Containment Integrity with a Degraded or Open Reactor Building Penetration . . . . 30 G.8 SGT Train A Operation During Filter Testing . . . . . . 31 G.9 SGT Train B Operation During Filter Testing . . . . . . 33 G.10 SG'.' Train Operation During Filter Sampling . . . . . . . 35

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Rev. No. 22 Page 19 of 45

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STANDBY GAS TREATMENT SYSTEM * OP-20 G.1 Train A Charcoal Filter Cooling G.1.1 IF amber SBGT A WTR SPRAY SYS HI TEMP light is on at panel FPP, THEN exit Subsection G.1 and proceed to Subsection G.3.

G.1.2 WHILE performing the following steps, periodically monitor annunciator 09-75-1-16 SGT SYS A ACT CHAR TEMP HI.

G.1.3 Ensure SGT Train B is in service per Subsection D.2.

G.1.4 IF SGT Train A is in service, THEN shutdown SGT Train A as follows:

a. Close TRAIN A INLET 01-125MOV-14A.

b. Verify the following:

Comoonent Status

TRAIN A FN 01-125FN-1A Shutdown

TRAIN A CLG VLV 01-125MOV-100A Open

NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2B (SGT fan B suct isol valve).

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Rev. No. 22 _ Page 20 of 45

. _ _ _ _ _ _ _ _ _ _ _ _ _ .

STANDBY GAS TREATMENT SYSTEM * OP-20 G.2 Train B Charcoal Filter Cooling G.2.1 IF amber SBGT B WTR SPRAY SYS HI TEMP light is on at panel FPP, THEN exit Subsection G.2 and proceed to .

Subsection G.4. 1 G.2.2 WHILE performing the following steps, periodically monitor annunciator 09-75-2-16 SGT SYS B ACT CHAR TEMP HI. 1 G.2.3 Ensure SGT Train A is in service per Subsection D.1.

G.2.4 IF SGT Train B is in service, THEN shutdown SGT Train B as follows:

a. Close TRAIN B INLET 01-125MOV-14B.

b. Verify'the following:

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Component Status

. * TRAIN B CLG VLV 01-125MOV-1008 Open

NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2A (SGT fan A suct isol valve). -

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Rev. No. 22 Page 21 of ., 45

STANDBY GAS TREATMENT SYSTEM * OP-20 NOTE: The amber SBGT A WTR SDRAY SYS HI TEMP light will come on and an alarm bell will ring at panel FPP when the temperature setpoint of the charcoal filter heat detector is reached. SGT Train A charcoal filter water spray is a manually actuated system.

G.3 Train A Charcoal Filter Fire Protection Water Spray G.3.1 Shutdown SGT Train A as follows:

a. Close TRAIN A INLET 01-125MOV-14A.

b. Verify the following:

Comoonent Status

  • Red light AIR HTR 01-125E-5A Off G.3.2 Initiate water spray per Step a, b, or c:

a. To initiate water spray from panel FPP in Control Room, perform the following:

1) Depress SBGT A Spray System INIT pushbutton, 2) Verify red SBGT A WTR SPRAY SYS VLV OPEN light is on.

b. To initiate water spray from local breakglass station, break glass or remove retainer ring from SGT Train A breakglass station and verify button pops out, c. To initiate water spray from flow control valve emergency release station, pull down SGT Train A emergency release lever.  ;

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Rev. No. 22 Page 22 of 45

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STANDBY GAS TREATMENT SYSTEM * OP-20 CAUTION To prevent plugging of the spray nozzles from debris caused by rust or corrosion, the water spray header between 76FCV-107A and the spray nozzles shall be drained following system actuation.

G.3.3 WHEN train A water spray is no longer required, perform the following:

a. Close 76 FPS-123 (west SGT sprinkler supply gate 3 vdivC).

b. Drain fire protection supply header in SGT Room as follows:

1) Connect hose to fire protection supply header low point drain located by charcoal filter side panel.

2) Route hose to nearest floor drain.

3) Open fire protection supply header drain valve.

c. Drain 76FCV-107A flow control station header as follows:

1) Connect hose to drain header located under flow control valve.

2) Route hose to nearest floor drain or suitable container.

3) Open MAIN DRAIN and AUXILIARY DRAIN valves.

NOTE 1: Scaffolding may be necessary to reach overhead supply header drain plug.

NOTE 2: Supply header drain plug is located approximately 20 feet above and north of 71MCC-142 and panel 66HV-3B.

d. Drain fire protection supply header as follows:

1) Connect funnel and hose under supply header drain plug.

2) Route hose to nearest floor drain or suitable container.

, 3) Remove. supply header drain plug.

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Rev. No. 22 Page 23 of 45 x ,

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STANDBY GAS TREATMENT SYSTEM * OP-20 e. WHEN supply header is drained, perform the following:

1) Close SGT Room supply header drain valve and disconnect hose.

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2) Close MAIN DRAIN and AUXILIARY DRAIN valves for 76FCV-107A (flow control valve) and disconnect hose.

3) Install overhead supply header drain plug and disconnect funnel and hose.

f. Ensure WEST SGT TRAIN A SPRINKLER 3REAK GLASS STATION 76BGS-19 retaining ring and glass cover are installed.

g. Ensure closed emergency release lever for 76FCV-107A.

h. Depress plunger on drip check valve for 76PS-107A located by funnel to depressurize pressure switch.

i. Depress RESET pushbutton at panel 76CP-107A.

a j. Open the priming valve for 76FCV-107A and verify pressure rises on 76PI-107AB.

k. WHEN pressure on 76PI-107AB is stable, close priming valve for 76FCV-107A.

1. Crack open 76 FPS-123 and verify pressure rises on 76PI-107AA.

m. WHEN pressure is stable on 76PI-107AA, fully open 76 FPS-123.

n. Verify the following at panel 76CP-107A:

  • Red FLOW CONTROL VALVE OPEN light is off
  • Red GATE VALVE OPEN light is on o. Verify the following at panel FPP:
  • Green HDR VLV TROUBLE light is off
  • Red VLV OPEN light is on
  • Amber SBGT A WTR SPRAY SYS HI TEMP light is off

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Rev. No. 22 Page 24 of 45

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STANDBY GAS TREATMENT SYSTEM * *

OP-20 NOTE: The amber SBGT B WTR SPRAY SYS HI TEMP light will come on and an alarm bell will ring at panel FPP when the temperature setpoint of the charcoal filter heat detector is reached. S3T Train B charcoal filter water spray is'a manually actuated system. .

G.4 Train B Charcoal Filter Fire Protection Water Spray G.4.1 Shutdown SGT Train B as follows:

a. Close TRAIN B INLET 01-125MOV-14B.

b. Verify the following:

Component Status

  • Red light AIR HTR 01-125E-5B Off G.4.2 Initiate water spray per Step a, b, or c:

a. To initiate water spray from panel FPP in

- Control Room, perform the following:

1) Depress SBGT B INIT pushbutton.

2) Verify red SBGT B WTR SPRAY SYS VLV OPEN light is on.

b. To inir.iate water spray from local breakglass station, break glass or remove retainer ring from SGT Train B breakglass stution and verify

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button pops out.

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c. To initiate water spray from flow control valve emergency release station, pull down SGT Train B emergency release lever.

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Rev. No. 22 Page 25 of 45 I

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STANDBY GAS TREATMENT SYSTEM * OP-20 CAUTION To prevent plugging of the spray nozzles from debris caused by rust or corrosion, the water spray '.eader

. between 76FCV-107B and the spray nozzles shall be drained following system actuation.

G.4.3 WHEN train B water spray is no longer required, perform the following:

a. Close 76 FPS-122 (east SGT sprinkler supply gate valve).

b. Drain fire protection supply header in SGT Room as follows:

1) Connect hose to fire protection supply header low point drain located by charcoal filter side panel.

2) Route hose to nearest floor drain.

3) Open fire protection supply header drain valve.

c. Drain 7GFCV-107B flow control station header as

-

follows:

1) Connect hose to drain header located under flow control valve.

2) Route hose to nearest floor drain or !

suitable container. I 3) Open MAIN DRAIN and AUXILIARY DRAIN valves.

NOTE 1: Scaffolding may be necessary to reach

overhead supply header drain plug. )

l NOTE 2: Supply header drain plug is located approximately 20 feet above and north of 71MCC-142 and panel 66HV-3B.

d. Drain fire protection supply header as follows:

1) Connect funnel and hose under supply header drain plug. l i

2) Route hose to nearest floor drain or suitable container.

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, 3) Remove supply header drain plug.

Rev. No. 22 Page 26 of 45

STANDBY GAS TREATMENT SYSTEM * OP-20 e. WHEN supply header is drained, perform the following:

1) Close SGT Room supply header drain valve and j disconnect hose. .

l 2) Close MAIN DRAIN and AUXILIARY DRAIN valves for 76FCV-107B (flow control valve) and disconnect hose.

3) Install overhead supply header drain plug and disconnect funnel and hose.

f. Ensure EAST SGT TRAIN B SPRINKLER BREAK GLASS STATION 76BGS-20 retaining ring and glass cover are installed.

g. Ensure closed emergency release lever for 76FCV-107B.

l h. Depress plunger on drip check valve for 76PS-107B located by funnel to depressurize pressure switch.

i. Depress RESET pushbutton at panel 76CP-107B.

j. Open the priming valve for 76FCV-107B and verify

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pressure rises on 76PI-107BB. <

k. WHEN pressure on 76PI-107BB is stable, close priming valve for 76FCV-107B.

1. Crack open 76 FPS-122 and verify pressure rises on 76PI-107BA.

m. WHEN pressure is stable on 76PI-107BA, fully i open 76 FPS-122.  !

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n. Verify the following at panel 76CP-107B:

  • Red FLOW CONTROL VALVE OPEN light is off
  • Red GATE VALVE OPEN light is on o. Verify the following at panel FPP:
  • Green HDR VLV TROUBLE light is off
  • Red VLV OPEN light is on
  • Amber SBGT B WTR SPRAY SYS HI TEMP light is off

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Rev. No. 22 Page 27 of 45

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STANDBY GAS TREATMENT SYSTEM * OP-20 G.5 Train A Auto-Initiation Verification

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G.5.1 Verify the following:

Comnonent Status

  • AIR HTR 01-125E-5A White light is on, red light is on

)

  • TRAIN A FN 01-125FN-1A Running G.5.2 IF reactor building differential pressure is less negative than - 0.25 inches water, THEN ensure SGT Train B is in service per i Subsection D.2.

G.5.3 IF SGT Train B is shutdown, ,

THEN ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A.

A NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2A (SGT fan A suct isol valve) .

G.5.4 IF both SGT trains are in service, THEN one SGT train may be shutdown per Subsection F.1 or F.2, at the Shift Manager's discretion.

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l Rev. No. 22 Page 28 of 45 l

STANDBY GAS TREATMENT SYSTEM * OP-20

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G.6 Train B Auto-Initiation Verification G.6.1 verify the following:

Comoonent Status -

. red light is on

  • TRAIN B FN 01-125FN-1B Running G.6.2 IF reactor building differential pressure ,

is less negative than - 0.25 inches water, TEEN ensure SGT Train A is in service per Subsection D.1.

G 6.3 IF SGT Train A is shutdown, TREN ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A.

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NOTE: SGT flow rate is adjusted by throttling 01-125SGT-2B (SGT fan B suct isol valve).

G.6.4 IF both SGT trains are in service, THEN one SGT train may be shutdown per Subsection F.1 or F.2, at the Shift Manager's discretion.

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Rev. No. 22 Page 29 of 45

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STANDBY GAS TREATMENT SYSTEM * OP-20 G.7 Maintenance of Secondary Containment Integrity with a Degraded or Open Reactor Building Penetration G.7.1 Place SBGT train in service per Section D.

G.7.2 Isolate reactor building ventilation as follows: j a. Depress the following pushbuttons at panel 09-75:

  • RB VENT ISOL A
  • RB VENT ISOL B b. Verify isolation per Section G of OP-51A.

G.7.3 Prior to opening a secondary containment penetration notify the SM and Fire Protection Supervisor of the following:

Penetration identification number

Penetration area and elevation G.7.4 Establish communications between work site and j control room.

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G.7.5 WHEN secondary containment penetration is open, verify the following:

Flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A (B)

RB DIFF PRESS 01-125DPI-100A(B) indicates GREATER THAN negative 0.25 inches water G.7.6 IF reactor building differential pressure cannot be

maintained GREATER TRAN negative 0.25 inches water, THEN reseal secondary containment penetration.

G.7.7 IF reactor building differential pressure can be maintained GREATER TRAN negative 0.25 inches water, THEN restore from reactor building isolation per Section G of OP-51A.

G.7.8 WHEN secondary containment penetration is closed and maintenance is complete, nstore from reactor

building isolation per Secti G of OP-51A.

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Rev. No. 22 Page 30 of 45

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STANDBY GAS TREATMENT SYSTEM 0 OP-20 G.8 SGT Train A Operation During Filter Testing b

G.8.1 Ensure open the following valves:

G.8.3 Verify the following:

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G.8.5 WHEN testing is complete, perform the following:

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a. Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A by throttling 01-125SGT-2A.

b. Close TRAIN A INLET 01-125MOV-14A.

G.B.6 Verify the following:

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Rev. No. 22 Page 31 of 45

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STANDBY GAS TREATMENT SYSTEM * OP-20 G.8.7 IF testing of SGT trains is complete, THEN close the following valves:

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Rev. No. 22 Page 32 of 45 l

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l STANDBY GAS TREATMENT SYSTEM * OP-20 l

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G.9 SGT Train B Operation During Filter Testing G.9.1 Ensure open the following valves:

G.9.3 Verify the following:

is on G.9.4 IF flow rate is not 6000 to 6100 scfm on SGT FLOW 01-125FI-106A, THEN throttle 01-125SGT-2B to establish 6000 to 6100 scfm on SGT FLOW 01-125FI-106A.

. G.9.5 WHEN testing is complete, perform the following:

a. Ensure flow rate is 3000 to 6000 scfm on SGT FLOW 01-125FI-106A by throttling 01-125SGT-2B.

b. Close TRAIN B INLET 01-125MOV-14B.

G.9.6 Verify the following:

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Rev. No. 22 Page 33 of 45

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STANDBY GAS TREATMENT SYSTEM * OP-20 G.9.7 IF testing of SGT trains is complete, THEN close the following valves:

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Rev. No. 22 Page 34 of 45 L. )

STANDBY GAS TREATMENT SYSTEM * OP-20 G.10 SGT Train Operation During Filter Sampling G.10.1 IF SGT Train A will be sampled, THEN perform the following:

a. Declare SGT Train A inoperable per ODSO-34.

b. Ensure SGT Train A is shutdown per Section F.

c. Close 01-125SGT-3A (SGT train A fan 1A suct cross-tie isol valve).

d. WHEN sampling of SGT Train A is complete, perform the following:

1) Open 01-125SGT-3A.

2) IF it is desired to operate SGT Train A, THEN startup SGT Train A per Section D.

3) Consider declaring SGT Train A operable per ODSO-34.

G.10.2 IF SGT Train B will be sampled, THEN perform the following:

a. Declare SGT Train B inoperable per ODSO-34.

b. Ensure SGT Train B is shutdown per Section F.

c. Close 01-125SGT-3B (SGT train B fan IB suct cross-tie isol valve).

d. WHEN sampling of SGT Train B is complete, perform the following:

1) Open 01-125SGT-3B.

2) IF it is desired to operate SGT Train B, THEN startup SGT Train B per Section D.

3) Consider declaring SGT Train B operable per ODSO-34.

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Rev. No. 22 Page 35 of 45

RO 044 SRO 944 During the post-examination review, it was discovered that the key contained an incorrect answer, D vice the correct answer, A.

Distractor B is incorrect because an SRM reading less than 100 cps whose detector is not full in will generate a rod withdrawal block.

Distractors C and D are incorrect because detector motion is never blocked.

The key was changed from D to A to correct this error.

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SDLP-07B KEY AIDS a) Purpose - to allow the operator to swap recorder indication from IRM J to APP.M/RBM on startups or back to IRM on shutdowns.

b) Positions - IRM-OFF-APRM (RBM) -

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(1) RBM A(B)/IRM G(D)

(2) All other APRM/IRM i 3) Bypass Switches ,

a) Allows operator to bypass an Inop LOR 1.05.a.4.1 IRM channel. LOR 1.11.b.10 b) Joystick type c) Allow bypassing only one IRM per RPS channel at a time.

'

d) One switch for Channels A, C, E and G e) One switch for Channels B, D, F and H 6. Interlocks a. SRM 1) Retract Permissive Interlock for detector withdrawal.

a) Interlock between:

(1) SRM Log Count Rate (2) SRM Detector Position

(3) IRM Range Switches b) Interlock does not stop detector movement.

c) Interlock will cause a rod block if the following conditions are met:

(1) SRM detector not full in And (2) SRM count rate <100 cps. l l

d) Interlock is bypassed when:

s.

-44-J

ANNUNCIATOR ROD ARP 09-5-2-2 LEGEND WITHDRAWAL BLOCK DEVICE NA SETPOINT NA Reference: ESK-10P. 1.84-101 CAUSES e Any Reactor Mode Switch position:

- APRM high flux

- APRM inoperative

- RBM high flux (if reactor power is above 30%)

- RBM inoperative (if reactor power is above 30%)

- Recirc Flow Comparator trip

- Recirc Flow Converter upscale or inoperative

- CRD Hydraulic System SDIV level high l

- RPIS malfunction 1

- RWM withdraw block (below 20% reactor power)

- SDIV high water level trip bypassed j

e Reactor Mode Switch in Run

- APRM downscale

- APRM upscale (flow biased) l

- RBM downscale (if reactor power is greater than 30%)  ;

.

e Reactor Mode Switch in Startup/ Hot Standby:

- APRM upscale (12%) l

- Refuel platform over core )

- Service platform hoist loaded p r< < v m < <

"r9n n ,

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(Continued on next page)

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Rev. No. 3 PORC Meeting No. NA Date 6/23/95 Page 1 of 3

U ANNUNCIATOR ROD ARP 09-5-2-2 LEGEND WITHDRAWAL BLOCK CAUSES (Cont)

  • Reactor Mode Switch in Startup/ Hot Standby or Refuel:

- SRM detectors not fully inserted in the core with count rate below 100 cps, and associated IRM range switch on ,

range 2 or below. ,

. - SRM high flux

- Refueling interlocks

- SRM inoperative

- IRM downscale (bypassed on range 1)

- IRM high flux

- IRM detector not full in

- IRM inoperative e Reactor Mode Switch in Refuel:

.

- Refueling platform near or over the core with a load on the 1, fuel platform hoist, or fuel grapple not full up

- Service platform hoist loaded

- Gelection of a second control rod with any other rod not

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full in

,

- SDIV high water level trip bypassed f i

- Rod select power turned off or no rod selected

- Refuel platform power turned off e Reactor Mode Switch in Shutdown:

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Reactor Mode switch in shutdown AUTOMATIC ACTIONS Rod withdrawal block i

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(Continued on next page) j Rev. No. 3 PORC Meeting No. NA Date 6/23/95 Page 2 of 3 J

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ANNUNCIATOR ROD ARP O9-5-2-2 LEGEND WITHDRAWAL BLOCK PROCEDURE 1. Determine cause of rod block at panel 09-5.

2. Correct cause of alarm prior to attempting to withdraw control rods. -

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4 Rev. No. 3 PORC Meeting No. NA Date 6/23/95 Page 3 of 3 e

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SRO 647 During the administration of the examination, a typographical error was noted in that distractors A and C were the identical. Distractor C was changed from:

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Turbine Govemor Valve open; Turbine Steam Inlet Isolation Valve closed.

to:

Turbine Governor Valve open; Turbine Steam Inlet Isolation Valve open.

This corrected the typographical error but necessitated a key change for the SRO exam from C to A. The determination to change distractor C vice distractor A was based on the fact that some candidates had already recognized A to be a conect answer and marked their answer sheets to reflect their choice.

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RO 061 SRO O61 During the post-examination review, it was discovered that there were two correct answers given for the question.

The rod drift indication however is not referenced as a symptom of an uncoupled control rod in the applicable procedure, AOP-25, UNCOUPLED CONTROL ROD. 'Ihat procedure states the symptom:

An overtravel alarm is received during a coupling check of control rod."

Both the ROD DRIFT and ROD OVERTRAVEL' annunciators will alarm if the respective condition exists for any of the 137 control rods. Each of the control rods also has an individual rod drift light on the full core display. There is actually no " Individual" Rod Overtravel alarm as the question asks nor is there an " individual" Rod Drift alarm (there are however, individual rod drift lights). This ambiguity apparently led the

!

candidates to associate individual in the sense of "an alarm caused by moving an individual rod." That perspective, coupled with the procedural symptom makes B also a correct answer.

The answer key was changed to reflect either A or B as a correct answer.

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ANNUNCIATOR ROD DRIFT ARP 09-5-2-3 LEGEND

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DEVICE Not applicable SETPOINT Not applicable CAUSES 1. A control rod that is not selected moves off a latched even numbered position.

2. A control rod that is selected moves off an even numbered position or past an odd numbered position after rod sequence timer has stopped.

AUTOMATIC ACTIONS None PROCEDURE

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Enter AOP-27, Control Rod Drift *.

033: 3 8 Rev. No. 7 PORC Meeting No. NA Date 1/17/96 Page 1 of 1

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'ARP 09-5-2-4 ANNUNCIATOR ROD OVERTRAVEL'

LEGEND-

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SENSOR / Reed switch S-50 located 3" past full out position TRIP POINT

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.CAUSE' CRD and rod NOT coupled AUTOMATIC None ACTION

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P OPERATOR Refer to F-AOP-25, Uncoupled Control Rod *

ACTION

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Rev. No. 2 PORC Meeting No. ff7- // Z.

Date /2/h2 37 Page 1 of 1 t

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UNCOUPLED CONTROL ROD * AOP-25 A. SYMPTOMS '

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  • Lack of a noticeable change in neutron monitoring

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indication during rod movement.

B. AUTOMATIC ACTIONS  :

None

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Rev No. 4 Page 4 of 9 d

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ATTACHMENT 4 ^

NRC RESOLUTION OF JAF COMMENTS ON WRITTEN EXAMINATION RO-9, SRO-9 Accepted error in answer key. The key was changed from D to B.

i RO-31, SRO-31 Accepted comment. Question was deleted from the examination. i RO-44, SRO-44 Accepted error in answer key. The key was changed from D to A SRO 47 Accepted change in answer key to reflect change announced during examination administration to correct that A and C were the same answer. The key was changed from C to A RO-61,SRO-61 Accepted comment that there were two correct answers. The J4 answer key was changed to reflect either A or B as correct answers.

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