IR 05000338/1998301
| ML20202D518 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/28/1999 |
| From: | Michael B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 50-338-98-301, 50-339-98-301, NUDOCS 9902020015 | |
| Download: ML20202D518 (450) | |
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January 28,1999 NOTE TO: NRC Document Control Desk Mail Stop 0-5-D-24 4 m r.J FROM: Beverly Michael, Licensing Assistant, Operator Licensing and Human Performance Branch, Division of Reactor Safety, Region 11 SUBJECT: OPERATOR LICENSING EXAMINATIONS ADMINISTERED AUGUST 17 - 21 AND AUGUST 31 - SEPTEMBER 3,1998, AT NORTH ANNA POWER STATION DOCKET NOS. 50-338/98-301 & C0-339/98-301 During the period August 17 - 21 and August 31 - September 3,1998, 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:
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.
Attachments:
As stated b ,. s , ,
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s October 2, 1998 Virginia Electric and Power Company A'ITN: Mr. J. Senior Vice President--Nuclear Innsbrook Technical Center
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5000 Dominion Boulevard Glen Allen. VA 23060 SUBJECT: NRC EXAMINATION REPORT NOS. 50-338/98-301 AND 50-339/98-301
Dear Mr. O'Hanlon:
On August 17-21 and August 31-September 3, 1998, the NRC administereo examinations to employees of your company who had applied for li. censes to operate the North Anna Power Station. At the conclusion of the examination, the examiners discussed the examination questions and preliminary findings with those members of your staff identified in the enclosed report. !
A Simulation Facility Report is included in this report as Enclosure 2 Enclosure 3 is the Facility Post-Examination Comments. Enclosure 4 is the NRC Resolution of post-examination comments. A copy of the written examination questions and answer key, as noted in Enclosure 5 was provided to the members of your training staff at the conclusion of the examination. '
Of the fifteen senior reactor (SRO) and reactor operator (RO) applicants who received written examinations and operating tests 14 candidates passed (and one failed) the examination, representing a 93 percent pass rate. The as-submitted written examination was considerably improved over the 1996 examination submittal. The quality of the job performance measures (JPM)
followup questions in the proposed operating tests was not consistent with NRC examination standards.
In a
REGION 11 Docket Nos.- 50-338. 50-339 License Nos.: NPF-4. NPF-7 Report'No.:
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50-338/98-301. 50-339/98-301 Licensee: Virginia Electric and Power Company i
Facility: North Anna Power Station. Units 1 & 2 l Location: Mineral. Virginia !
Dates: August 17-21. and August 31-September 3. 1998 Examiners:
Richard S. Baldwin ,
Chief License Examiner i Larry S. Mellen. License Examiner .
Edwin Lea. License xaminer !
A 1 Approved by: / ;
Thomas A'. Peebles. Chief l Operator Licensing and Human Performance Branch Division of Reactor Safety
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EXECUTIVE SUMMARY l
North Anna Power Station Units 1 & 2 -
NRC Examination Report No. 50-338/98-301 and 50-339/98-301
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- During the periods of August 17-21 and August 31-September 3.1998. NRC examiners conducted an announced operator licensing initial examination in accordance with the guidance of Examiner Standards. NUREG-1021. Interim Revision 8. This examination implemented the operator licensing requirements of 10 CFR 555.41. 555.43, and S55.45.
Seven Senior Reactor Operator (SRO) candidates and eight Reactor Operato,r (RO)
candidates received written examinations and operating tests. All examinations were administered by NRC operator licensing examiners. The written examination was administered by the licensee on August 27. 1998, and the operating tests were administered by the NRC the weeks of August 17-21 and August 31-September 3. 1998. l l
Doerations
- Control room activities were observed during the examination validation and examination weeks. The operators were found to be attentive and i professional in their duties. (Section 01.1) !
- In general. the examiners found the as-submitted written examination and operating tests met the requirements of NUREG-1021 with one exception in the area of JPM follow-up questions which was noted to need improvement. l The examination quality was improved as compared to the 1996 examination submittal. (Section 05.1)
. Fourteen of fifteen candidates passed the examination. Overall performance on the operating test was satisfactory with strengths noted !
in the creas of 3-way communication, crew briefs and annunciator I response procedure usage. Weaknesses were noted in the areas of l determining tail pipe temperature with a leaking PORV. identification of radiological posting requirements, reluctance of R0s to take manual action without SR0 prior approval, and the willingness of two of the four crews to enter Technical Specification 3.0.3 when it was preventable. (Section 05.1)
. Candidate Pass / Fail l
SRO R0 Total Percent Pass 7 7 14 93.3 Fail 0 1 1 6.6
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Reoort Details
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Summary of Plant Status During the period of the examino, ions Unit 1 and Unit 2 were at 100 percent power.
I. Doerations 01 Conduct of Operations l 01.1 Control Room Observation j l
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During validation and administration of the examination, the examinen i observed the conduct of operations by currently licensed operators in j the control room. The reactor operators (R0s) were attentive to the i
- evolutions in progress. The senior reactor operators (SR0s) limited l personnel for official business only which contributed to a quiet, professionally managed control room.
05 Operator Training and Qualifications l 05.1 Initial Licensina Examinations a. Scope l
l NRC examiners conducted regular. announced operator licensing initial !
examinations during the periods of August 17-21. and August 31-September 3. 1998. NRC examiners administered examinations developed by the licensee's training department, under the requirements of an NRC security agreement, in accordance with the guidelines of the Examiner Standards (ES). NUREG-1021. Interim Revision 8. Six Senior Reactor Operator (SRO) upgrade, one SRO instant and eight Reactor Operator (RO)
applicants received written examinations and operating tests.
b. Observations and Findinas l
- The licensee developed the SR0 and RO written examinations. three Job
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Performance Measure (JPM) sets, and four dynamic simulator scenarios, with one spare scenario, for use during this examination. All materials were submitted to the NRC on schedule. NRC examiners reviewed, modified as necessary, and approved the examination prior to administration. The NRC conducted an on-site preparation visit during the week of August 3.
1998, to validate examination materials and familiarize themselves with the details required for examination administration.
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(1) Written Examination The examination review was expedited due to the organization of the submitted examination materials. Relevant portions of the reference materials were attached to each test item.
This was the licensee's second time developing the examination in accordance with the Examiner Standards and the pilot program. The quality of the licensee's submittal was good and had shown i improvement as compared to the 1996 examination submittal. The number of technical errors noted were minimal. Most NRC coirnents i were to assure clarity in the question stem and to enhance the l quality of the incorrect distractors. The NRC recommended replacing only three questions due to quality of the questions.
The final examination was considered a good product. in that, it i discriminated a competent from a less than competent candidate. )
l (2) Operating Test Development I
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The NRC reviewed three walkthrough examination sets submitted by the facility. These were comprised of job performance measures (JPMs) and administrative JPMs and administrative questions. The !
examiners found the JPMs were developed to the appropriate' level .
as described in NUREG-1021. Some minor technical errors were !
noted such as the incorrect designation of critical steps. The quality of some of the JPM follow-up questions were weak in that several JPM questions were considered direct look-up and lacked operational validity and some were non-discriminatory. These questions were either changed or references were not allowed to answer these questions. Increased attention in this area is needed to supply JPM follow-up questions consistent w'th the guidelines of NUREG 1021. Interim Revision 8.
The NRC reviewed four simulator scenarios (plus one spare) l developed for the examination. Some changes ar d additions were I made to the scenarios to enhance the examiners' opportunity to observe candidates perform all required competencies. One scenario set did not have the required minimum number of l malfunctions as required by NUREG-1021. This was corrected during i the examination preparation week. Overall, the scenarios were l I
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found to be challenging and at the appropriate level of difficulty. The final scenarios were considered a good examination tool providing ,
discrimination between satisfactory from less then satisfactory performance.
During the examination weeks the examiners found three procedures that were confusing or hard to use. The facility acted promptly to resolve these procedural issues.
The facility administered the written examination on August 27. 1998 in
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accordance with NUREG-1021 and by direction of the examination assignment sheet (Enclosure 7). The licensee during the course of the
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examination requested, by telephone. two, thirty minute extensions to the four hour time period of the examination. The two extensions were granted by the NRC Branch Chief. providing a total of five hours for the written examination. The facility requested the extension as the !
candidates needed the extra time to adequately finish the examination. l l
c. Examination Results and Conclusions l The facility licensee submitted post-examination comments for one l written examination question. of which the NRC accepted (see Enclosures l 3 and 4). The acceptance of this comment did not change the outcome of l
the grading for any of the candidates.
The quality of the licensee's proposed examination met the Examiners l Standards. The licensee had improved the quality of the examination
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submittal when compared to their previous examination submittal (Report l
No.96-300). Some improvement in JPM question development is warranted in order to comply wit! the guidelines of NUREG 1021. Interim Revision 8.
The examiners reviewed the results of the written examination and found that fourteen of fifteen candidates passed this examination. Overall SR0 candidate performance on the written examination was satisfactory.
performance with one candidate failing the examination and two RO candidates achieving a grade less then 82 percent. The licensee conducted a post-examination item analysis of the SRO and RO written
examinations. This analysis identified seven questions where both SRO i and RO candidates exhibited knowledge deficiencies. The analysis also identified three other SRO specific knowledge weaknesses and three other l RO specific knowledge weaknesses. The examiners concluded that no generic knowledge weaknesses existed. A generic knowledge weakness
. exists when multiple questions on the same system or topic were missed by a large number of candidates.
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i 4 Examiners also identified several weaknesses in candidate performance
'during the operations portion of the examination. Details of the weaknesses are described in each individual's examination report Form ES-303-1. " Operator Licensing Examination Report." Copies of the '
evaluations have been forwarded under separate cover to the Training :
Manager in order to enable the licensee to evaluate the weaknesses and ,
provide appropriate remedial training for those operators, as necessary.
In general, these weaknesses included the following: knowledge of radiological poc. ting requirements, tail pipe temperature determination, and candidates appeared hesitant to take manual control of systems when automatic controlMrs were not functioning properly prior to obtafning ;
SR0 verbal approval, This contributed to one of the four crews having an unnecessary reactor trip when manual control of feedwater was required following a steam generator pressure transmitter failure.
Additionally, two crews exceeded a Technical Specification Limiting l Condition for Operation tire limit and voluntarily entered Technical Specification 3.0.3 when it could have been avoided by placing the J bistables in a tripped condition.
l During s.enario performance NRC examiners noted strengths in the areas l l of three-way communications. SRO crew briefing techniques, and use of I l annunciator response procedures. Candidates consistently followed the l ,
licensee's communications procedures, briefing procedures and reviewed annunciator response procedures in accordance with operations standards and expectations, j
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Manaaement Meetinas i
X1. Exit Meeting Summary At the conclusion of the site visit the examiners met with representatives of the plant staff listed on the following page to discuss the results of the examinations and other issues. No proprietary material provided was provided.
PARTIAL LIST OF PERSONS CONTACTED Licensee S. Crawford. Senior Instructor Nuclear G. Crisman. Supervisor Operations Support J. Dauberman. Supervisor. Shift Operations C. Funderburk Manager. Station Safety and Licensing A. Kozak Simulator Support Coordinator H. Le. Nuclear Oversight J. Scott. Supervisor. Operations Training W. Shura. Nuclear Training Supervisor. Simulator ,
M. Whalen. Licensing Technical Analysis !
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M. Morgan. Senior Resident Inspector L. Garner Project Engineer RII E. Lea. Project Engineer / Examiner. RII L. Mellen. Examiner RII ITEMS OPENED. CLOSED. AND DISCUSSED Closed None.
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ENCLOSURE 2
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SIMULATION FACILITY REPORT Facility Licensee: Virginia Electric and Power Company
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North Anna Power Station Units 1 & 2 i Facility Docket Nos: 50-338 and 50-339 l
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Operating Tests Administered on: August 17-21. August 31-September 4. 1998 l
This form is'to be used only to report observations. These observations *do not constitute audit or inspection findings and are not, without further verification and review, indicative of noncompliance with 10 CFR 55.45(b). l These observations do not affect NRC certification or approval of the -
simulation facility other than to provide information that may be used in future evaluations. No licensee action is required in response to these ;
observations.
While conducting the simulator portion of the operating tests, the following items were observed (if none, so state): ,
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l l lied DESCRIPTION 1. Diesel Generator (D/G) Synchronizing circuit could not reduce the speed of the l scopes rotation to less than l approximately 20 seconds. Additionally. -
l the D/G could be synchronized with the l synchroscope 180 degrees out of phase. l l: 2. During solid plant operations, the l subcooling monitor subcooling indication cycled from 0 degrees subcooling to a subcooled value.
3. The charging pumps would pump water with out a suction source.
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ENCLOSURE 3 ;
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FACILITY POST-EXAMINATION COMMENTS t,
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VIRGINIA ELECTRIC AND Powrn ConrANY RIcnn own,VIncINIA 2026I
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September 4,1998 Mr. T. A. Peebles, Chief Serial No.98-528 i Operator Licensing and Human Performance Branch NAPS /JHL I United States Nuclear Regulatory Commission Docket Nos. 50-338 !
Region 11 50-339 l Atlanta Federal Center License Nos. NPF-4 i 61 Forsyth St., SW, Suite 23T85 NPF-7 Atlanta, Georgia 30303 ;
Dear Mr. Peobles:
l VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 OPERATOR LICENSE EXAMINATION COMMENTS l The following comment is provided in relation to the operator license examination that was conducted at North Anna Power Station on August 27,1998. ,
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Question #99 (RO and SRO examinations): distractor "d" was inadvertently labeled as "a". This typographical errar was noted during examination l administration by one of the candidates. fhe proctor pointed out the error I f to the remaining candidates (three candidates had already completed the examination and left the area). The examination outcome was not affected j by this error. The error was corrected on the master examinations and !
answer keys, it is recommended that the NRC accept.this change and make l the correction to their answer key. There are no further utility official !
I comments on the examination.
lf you have any questions, please contact Mr. H. A. Royal at (540) 894-2446.
Very truly yours, l W. R. Matthews Site Vice President i l
Commitments made in this letter: None
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cc: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555
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I Mr. M. J. Morgan NRC Senior Resident inspector North Anna Power Station l I
Mr. R. S. Baldwin, License Examiner i U. S. Nuclear Regulatory Commission Region ll l Operator Licensing and Human Performance Branch i l
Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 ,
l Atlanta, GA 30303 1 I
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ENCLOSURE 4 NRC RESOLUTION OF FACILITY RECOMMENDATIONS
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Question #99: Recortmendation accepted. The typographical error will be corrected on the master examination.
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ENCLOSURE 5 t
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WRITTEN EXAMINATION (S) AND ANSWER KEY (S) (SR0/RO)
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ENCLOSURE 6
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NRC WRITTEN /WALKTHROUGH/ SIMULATOR EVALUATION FORMS i
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- NRC REVIEW OF l' NORTH ANNA AUGUST 1998 WRITTEN EXAMINATION 30 DAY SUBMITTAL V # CONCERN 1021 RESOLUTION 1 Distractor B is not plausible, Distractor C is a Appendix, B Resolved, ok another correct answer. 2.b/f/h/m 2 appears ok ok 3 Distractors A and D are not plausible. Font Appendix, B replace distractor a with loop delta l must inconsistencies in Stem. 2.b/f/hlm be downscaled. Distractor Replaced.
l'ont inconsistencies in Stem not fixed.
(WILL FIX FONT PROBLEM) Font Fixed ok 4 None of the distractors answer the question in the pt in the stem, remove the reference to stem. Reword Stem or reword distractors. procedures in the distractors. Distractor -
Replaced. Remove "whether or not a spccific scquence is required" from distractor D (WILL REWORD QUESTION TO MAKE DISTRACTOR D CORRECT AND WILL CHANGE SRO TO RO IN DISTRACTOR B TO MAKE IT INCORRECT) Reworded. ok 5 appears ok ok 6 appears ok ok 7 Distractors A and B do not appear plausible Appendix, B replace the answer with CARBOY drain.
2.b/f/hlm Question reworded. ok
Distractor A is a correct answer. Distractor D is not Appendix, B replace distractor A. Distractor replaced.
plausible.
2.b/f/h/m ok i
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NRC REVIEW OF l' NORTH ANNA AUGUST 1998 WRITTEN EXAMINATION 30 DAY SUBMITTAL V # CONCERN 1021 RESOLUTION
Distractor B is a second correct answer.
will replace distractor B. Distractor was replaced. ok 10 Replace distrac.ars A and B. Question has low Appendix B replace or modify distractors a and b with discriminatory value.
1.d. 2 9 more complex communications. reword stem to include procedure reference. level comprehension. Distractors A and B replaced. ok
Reword distractors as noted on written exam. Appendix B There is information in the distractors that towers reword distractors (delete teaching) .
their validity 1.d. 2.g Distractors A. B, and C replaced. ok
All 4 answers are correct. Reword stem.
modify stem to refer to procedure and include reference to the earliest time the step must be accomplished. Stem Modified, ok 13 Low discriminatory validity Appendix B ok '
1.d 2 9 14 Distractor C appears to be a valid answer. Appendix B resolved. ok Question is a direct lookup and as such requires low 1.d level of knowledge 15 Distractor B appears to be a second correct answer. i Will review Distractor B and modify, if needed. Distractors A and B modified.
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Reword distractors as noted on written exam. Appendix B There is information in the distractors that lowers reword distrqctors (delete teaching) '
their validity 1.d 2.g " comprehension. All distractors modified.
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NRC REVIEW OF i' NORTH ANNA AUGUST 1998 WRITTEN EXAMINATION 30 DAY SUBMITTAL V # CONCERN 1021 RESOLUTION 17 Distractor C is not plausible Appendix, B Willlook at distractor C. Distractor 2.b/flh/m modified. ok
There are NO correct answers. The stated correct answer is incorrect, because the switch must be will reword to include return switch to returned to the operate position per NRCODP-46- operate. Distractors A, B and D LP-1 page 28, Revision 13. reworded. Replace "and operate" with
"then operate"in distractor D ( WILL REWORD TO BE CONSISTENT)
Reworded. ok
All four answers are correct. With absence of Appendix B will reword the question to make distractors additionalinformation in the stem, the other causes 1.a/ble of loss of condenser vacuum are as plausible as the wrong. Stem reworded to make 2.k distractors incorrect. ok ,
failure of the operator to maintain condenser vacuum, by not follow the steps of 1-OP-3G.1. As it is currently written, the question has no operation '
validity 20 The stem of the question must state in accordance Appendix b, with 0-MOP-52.1 or the question is invalid. will reword stem._ Stem reworded. ok 1.c 21 appears ok ok 22 Change Distractor B to * decreasing Sigma Theta * Appendix B, and change Distractor D to " Stability class change 1.d will reword based on NRC comments.
from C to B"in order to maintain the level of the _Rewordinn of distractors and channed ,
question as comprehension answer. ok 23 Low discriminatory validity Appendix B will review question and increase 1.d, 2.g discriminatory validity._ Question replace
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by question written by NRC. ok
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" NORTH ANNA AUGUST 1998 WRITTEN EXAMINATION 30 DAY SUBMITTAL v # CONCERN 1021 RESOLUTION 24 Distractors A and D are essentially the same, and Appendix, B will replace distractor A with " skill of the as such are easily eliminated.
2.b/f/hlm craft" or ' simple' Distractor reworded.
o_k 25 Distractor D is not plausibic, in that the stem asks Appendix, B remove the first part of distractor D.
about prompt effects and the answer is based on 2.b/f/hlm the effects at two weeks Distractor reworded. ok 26 appears ok ok 27 Replace Distractor D. Reword other distractors and Appendix, B leave question unmodified. ok the correct answer as indicated on the written 2.b/f/hlm examination.
i 28 appears ok ok 29 appears ok ok 30 Reword Stem. Replace distractors C & D Appendix B leave distractor alone. modify stem to have 1.c N-36 at bottom of scale and N35 within 2.b/f/hlm tolerance. Correct answer is C. Modify N31 reading to match. Stem reworded and answer channed. ok
Thermodynamics for the stem does not work. The Appendix B, way the question is written, if it were modify to ensure that the answers are 1.c consistent with the thermodynamics.
thermodynamically possible, Distractor D would be
. Modified question per NRC direction. ok a correct answer since there is obvious heat transfer in the loops. Th is greater than TC and maintaining the temperature difference.
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NRC REVIEW OF
NORTH ANNA AUGUST 1998 WRITTEN EXAMINATION ,
30 DAY SUBMITTAL V # CONCERN 1021 RESOLUTION 32 There was not enough material submitted to will verify question is valid. Resolved. ok determine the validity of this question 33 appears ok ok 34 Distractor C appears to be required by procedure.
Since there are periods of operations allowed when replace distractor C. Distractor C replaced with an incorrect answer. ok the Robert Shaw panelis not operable, the only option would be Distractor C.
35 appears ok ok ;
36 There are two sets of answer "a' and two of answer Appendix B
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"b". The second set of answers is not plausible reword the letters for the second set of a 1.c and b. Leave distractors unmodified. ;
2.b/f/h/m Corrected typoDraphical errors. ok 1 37 Edit Stem as shown on written examination. will reword stem. _ Stem reworded. ok 38 Distractor C is not plausible. Replace as written on Appendix B will modify stem. Modified per NRC examination. 1.c direction. ok 2.b/f/h/m i 39 appears ok ok 40 Distractor D is not related to question stem Appendix B agreed to not modify question. ok 1.c Z.b/f/h/m 41 Low level of knowledge, Low operational validity, Distractor D is modify distractors._ Modified stem and Low discrimantory value, implausible distractors, not related to three distractors. ok question stem *
42 appears ok ok
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NRC REVIEW OF
" NORTH ANNA AUGUST 1998 WRITTEN EXAMINATION 30 DAY SUBMITTAL V # CONCERN 1021 RESOLUTION 43 Modify Question as written on examination. Distractor D is will Modify Question as written on not related to examination.. Question and distractors question stem modified nor NRC direction. ok 44 Modify Question as written on examination. Low Appendix b will Modify Question as written on operational validity 1.a/ble 2.k examination. Comprehension. Stem and distractors modified ner NRC direction. '
Level of question now comprehension.
9k 45 appears ok ok 46 The answers use the terms rapidly and slowly. Appendix b will review the distractors. Removed These terms are ambiguous. Distractor A could be 1.c correct depending on the definition of the terms. undefined term from distractors. ok 47 appears ok ok
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Distractor D is not thermodynamically piausible Appendix B Modify distractors C and D as written on 2.b/f/hlm examination. Distractors C and D
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modified. Verify that distractor D is still incorrect. (DISTRACTOR D VERIFY INCORRECT). ok 49 appears ok ok 50 Distractor D is not plausible Appendix B don't modify question. ok 2.b/f/hlm 51 Replace distractors A and B Appendix B modify distractor A. _ Distractor A modified.
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NRC REVIEW OF l' NORTH ANNA AUGUST 1998 WRITTEN EXAMINATION 30 DAY SUBMITTAL v # CONCERN 1021 RESOLUTION 53 appears ok ok 54 Low discriminatory validity Appendix B ok. question stays as written 1.d, 2.g 55 Distractor C is not plausible Appendix B ok. question stays as written 2.b/f/h/m 56 appears ok ok 57 appears ok ok 58 Low discriminatory validity Appendix B will attempt to modify distractors C and D.
1.d. 2.g Distractors C and D modified. ok 59 appears ok ok 60 Minor edits to stem and answer will make minor edits. Minor edits made to stem and distractor D. ok 61 Modify Question as described on the written Appendix B will make edits. Question distractors examination. 1.d,2.g modified. Question is now at analysis level. term rapidly used in the question is not defined, but is consistent with training. (VERIFIED THIS IS CONSISTENT WITH TRAINING) ok G2 appears ok 63 appears ok ok G4 appears ok '
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NRC REVIEW OF U NORTH ANNA AUGUST 1998 WRITTEN EXAMINATION 30 DAY SUBMITTAL v # CONCERN 1021 RESOLUTION !
65 Distractor D not plausible. Modify question as Appendix B will make edits as described on the written marked on written examination 2.b/f/h/m exam. Modified stem and all distractors per NRC direction ok 66 appears ok ok G7 Modify question as marked on written examination will make edits as described on the written exam. Modified all distractors per NRC direction. ok 68 appears ok ok 69 Distractor D not plausible. Appendix B will replace distractor. Distractors 2.b/fth/m reordered. Change 15in stem to 30 and l change answer to C (WILL CHANGE AS DESCRIBED). Changed. ok 70 appears ok ok 71 appears ok ok 72 Distractor A not plausible Appendix B will review and replace if possible.
2.b/f/h/m Distractor A replaced. ok 73 Distractor D not plausible. Replace with marked up Appendix B will replace distractor as written on distractor on written exam. 2.b/f/h/m examination. Distractor D replaced, ok 74 appears ok ok 75 Distractor D not plausible. Appendix B will review distractor D. Distractor D 2.b/f/hlm replaced. ok 76 appears ok '
ok
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NRC REVIEW OF
" NORTH ANNA AUGUST 1998 WRITTEN EXAMINATION 30 DAY SUBMITTAL V # CONCERN 1021 RESOLUTION 77 appears ok ok 78 Distractor A not plausible Appendix B replace distractor A. Distractor A 2.b/f/h/m replaced. ok 79 Distractor A not plausible Appendix B change distractor A to read 'close'
2.b/f/hlm Distractor A modified. ok 80 appears ok ok 81 Modify distractors as noted. Appendix B modify distractors as noted on written 2.b/f/h/m examination. Modified distractors A and C as requested by NRC. ok 82 appears ok ok 83 Distractor C not plausible Appendix B Replace distractors B and C. Distractors A 2.b/f/hlm and C were modified. Answer channed to the B position. ok 84 appears ok ok 85 appears ok ok 8G appears ok ok 87 Distractor B and D not plausible Appendix B modify distractor D to read transition to E-0.
2.b/f/h/m Distractor D modified. ok 88 appears ok ok i
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NRC REVIEW OF d NORTH ANNA AUGUST 1998 WRITTEN EXAMINATION 30 DAY SUBMITTAL v # CONCERN 1021 RESOLUTION 89 Modify stem to make distractor C the correct answer Appendix B Will lower power level to point where 2.b/flhlm distractor C is the answer. This was not possible. Stem modified and all clistractors and answer replaced. ok 90 Answer question on written exam ok 91 Answer question on written exam willlook at the distractors. Distractors were modified and reordered. ok 92 Distractor D not plausible Appendix B leave question as it is written. ok 2.b/flhlm 93 appears ok ok 94 appears ok ok 95 Review distractors Appendix B question will remain unaltered. ok 2.b/f/h/m i
96 appears ok ok l 97 appears ok ok 98 distractor D appears to be correct Appendix B add in accordance with AP-22-01. Stem 2.b/flh/m _ modified to make distractor D incorrect.
9k 99 appears ok ok 100 Modify distractors as shown on written exam Appendix B modify distra,ctors as marked on written 2.b/f/hlm examination. Distractors C and D were modified. ok
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NRC REVIEW OF
NORTH ANNA AUGUST 1998 WRITTEN EXAMINATION 30 DAY SUBMITTAL V # CONCERN 1021 RESOLUTION 101 appears ok ok 102 Modify Distractors as shown on written examination {
Appendix B will modify distractors. Distractors A and 2.b/flhlm C were modified. ok 103 distractor A appears to be correct Appendix B 11 was the correct answer. ok 2.b/f/h/m 104 Distractor C not plausible )
Appendix B replace distractor C. Distractor C 2.b/f/hlm replaced. ok 105 Distractor D not plausible, replace with NPSH Appendix B distractor Reword distractor with NPSH concerns.
2.b/flhlm Distractors reworded as requested.
ANSWER "A "IS INCORRECT SHOUI.D BE
"C."
(WlLL CORRECT ANSWER KEY).
Answer key corrected. ok 106 Distractor C is not plausible Appendix B Reph !istractor C. Replaced distractor 2.biffbim C . c s.
107 appears ok ok 108 appears ok ok 109 appears ok ok 110 Distractor A and B are not plausible Appendix B stem to be in mode 3. Modify distractors to 2.b/f/hlm make a correct. Modified stem and distractors and channed answer per NRC directions. ok 111 appears ok .
, ok
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NRC REVIEW OF
" NORTH ANNA AUGUST 1998 WRITTEN EXAMINATION 30 DAY SUBMITTAL v # CONCERN 1021 RESOLUTION 112 Distractor C is not plausible Appendix B question is ok, as written. Will verify that 2.b/f/h/m CC provision in TS is consistent with distractor C 113 appears ok _
ok 114 Low discriminatory validity Appendix b Questk n is ok as written. ok 1.d. 2.g 115 appears ok ok 116 Low discriminatory validity Appendix b leave question and assign Memory level.
1.d, 2.g ok 117 Distractor D is not plausible. Modify distractor A as Appendix B Will rewrite distractor D. Modified shown on written examination 2.b/f/hlm distractor D. Remove the words "i/ .
t conditions warrant" from distractor A.
(WiLL REMOVE THE TERM FROM THE DISTRACTOR). Removed terms. ok 118 All distractors do not appear plausible Appendix B rewrite distractors so there are 2.b/f/h/m mathematical ways to arrive at distractors.
_ Replaced with NRC nonerated question.
gk 119 Distractor D is not plausible Appendix B will add 543 to distractors. Modified as 2.b/f/hlm re_ quested. ok 120 appears ok ok 121 appears ok '
ok 122 appears ok ok
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NRC REVIEW OF
" NORTH ANNA AUGUST 1998 WRITTEN EXAMINATION 30 DAY SUBMITTAL v #
CONCERN 1021 RESOLUTION 123 appears ok ok 124 appears ok ok 125 Distractors D r td C not plausible Appendix B will provide TS sections with question.
2.biflhlm Oucstion Stem should state " technical Specifications provided" (WILL ENSURE THAT ALL QUESTIONS REQUIRING REFERENCES ARE IDENTIFIED) ok RESOLUTION KEY .
normal text - original resolution bold and underlined - second NRC review comments italic - required action by licensee for second comments !
(PARENTHESES AND BOLD)- required actions to resolve sccond comments when question complete last entry in Resolution block is - ok (
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EVALUATION OF SEI 1 WALK 1HROUGH EXAMINATION l' N. ANNA POWER STATION TOPIC CONCERN 1021 RESOLUTION Set 1 A.1 Perform a RCS leakrate hand calculation. Add representative time limit.15 JPM l-1/ADM minutes. DONE 7/30/98 There is not time limit required for the completion of this Type of JPM. A time frame for completion is required by Appendix C, APP C.
Question? 4. 5. "Every JPM shallidentify an estimated average time.. " 8.5 Add critical steps to the JPM.
Administrative JPMs also require critical steps being NOT necessary 7/30 identified. There are no Critical Steps identified. OK'as is.
Changed step 2 to have examiner hand data to candidate once they prove they can obtain the first point. 7/30 OK AS IS Set 1. A.1 21 day of a 28 day outage.
JPM l-1/ADM is the reference going to be allowed to answer this question. APP C. NO Type of lf so, the answer is considered a direct lookup. B.6 Question?
DONE Completion time?
NEW DONE 7/30/98 K/A is not referenced.
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TOPIC CONCERN 1021 RESOLUTION
Set 1 A.1 H emergency DG JPM l-1/ADM is a reference going to be allowed? I do not believe that the ES-602-1 if it is then this is a direct look Type of reference should be allowed because the person is in the 6. up in the procedure.
Question? field and would not have it available for use.
NO We need to provide a point value for each one of the sections of the answer in order to grade consistently. Part A 0.8 and part b 0.2 Completion time? done KA is not referenced. done 7/30/98 Review and approve a tagging record.
Set 1. A.2 JPM1-2/ADM Time for completion? APPC Determine time required. Will SRO do this O G minutes 7/30/98V Was this tagout done on the computer?? If it was not then we need a computer generated one to use as the key. YES Need to identify the critical steps. je. Step 2. OK Highlight the fail open valve, which is 1-BR-TCV-112A. Find When we use this we need a copy of the correct answer key the correct valve to make the to follow along with the candidate. In addition, we need a tag out correct O V 7/30/98 copy of the print marked up to reflect the correct answer.
Add in step 2 the valve that should have been closed and an ,
examiner cue. O V 7/30/98 '
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TOPIC CONCERN 1021 RESOLUTION in Set 1. A.2 Danger Tags to 120 volt breakers.
JPM1-2/ADM is the procedure going to be available to answer this NO RO question? If so then the answer is a direct look up.
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Type of is this question going to be asked with the JPM? Admin question? Question is going to be RO and JPMS do not require the use of follow up questions. The the jpm is SRO (NEW Bank) JPM is sufficient to cover the topic. ;
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KA is not referenced. will add O done.
Reworded the stem Set 1. A.2 Corrective maintenance. '
JPM1-2/ADM RO Does the particular piece of equipment require this special
Type of NO reference they should know type of removal? Or is it known that this is the-way it is this information question? done?
(NEW Bank) The problem I have is that you provided reference information that appears to be a guideline for doing this type This is an OPS standard on the of activity. What procedure does this come from?
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Added point values for grading consistency
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TOPIC CONCERN .
1021 RESOLUTION o
Review a Radiation Work permit and obtain a digital alarming Will develop a suvey map in a Set 1, A.3 dosimeter.
JPM 1-3/ADM question format that will break down the areas in two This JPM is trivial and will be part of entry into the RCA. The questions. What postings and JPM will need to be replaced. what gear do you need to get in NEW, BANK Completion time?
there. O MODIFlED Stillneed to develon based on St. Lucies examnie and ask this as one of the two questions.
Completed 8/6/98, good question.
Develop a JPM that takes a ,
survey map with various rad and contamination levels hot !
spots etc. and have the candidate determine the proper postings for those areas. ie the charging pump rooms.
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TOPIC CONCERN 1021 RESOLUTION ti Set 1, A.4 Determine the requirements for reporting rad condit. to the JPM 1-4/ADM state, Reword the question to get only the part of the answer in RO parenthesis.
The question appears to be partially a direct look up from the App C.
Type of procedure.
question? B.6.e, Changed as requested. 7/30/98 Bank /New Part of the answer will not be given by the candidates. The part about "this is done so that , , * will most likely not be provided as an answer.
done Completion time?
The KA is not on the question. done Set 1, A.4 NRC communicator JPM1-4/ADM RO The whole answer will not be provided as given. The answer Type of Reword the stem and the would have to be divided by points to ensure consistent question? grading. answer to shorten the answer.O V 7/30/98 The question is to nebulas in what it is asking? Shortened the question and KA not on the question made it more concise.
done t
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,, EVALUATION OF SET 2 WALKTHROUGH EXAMINATI'ON N. ANNA POWER STATION -
TOPIC CONCERN 1021" RESOLUTION Perform a shift turnover. (RO) Review and replace as Set 2 A.1 necessary. Rep / aced with a
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JPM li-1/ADM . Is this JPM going to be done on the simulator 7?? If it is not I don't know how to know that the candidate did a complete calculate a OPTR. OK Wi/I (RO) board walkdown with the examiner telling the candidate what review when net on site. O -
bulb is OUT. Replacement is a good JPM
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8/6/98 NEW BANK Completion time?
MODIFIED? ,
done This JPM is weak and can only be failed if the candidate does not find the bumt out bulb.
If a person does not get this correct he could potentially Fall the administrative section. I don't feel comfortable placing this much emphasis on one bulb. Especially if the examiner has to point it out to the candidate.
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TOPIC CONCERN -
1021 v RESOLUTION Set 2 A.1 JPM ll-1-ADM Perform a shift turnover. (SRO)
SRO Are we going to provide the candidate with a turnover sheet and logs to review or are we going to have to cue this Review and replace. Will NEW BANK replace O V 816/98 information as is described in the JPM??
MODIFIED?
Completion Time? Willrenlace with calculate QPTR. need to [\ VGood JPM replacement 8/6/98.
As above, the failure of this section would come about if the candidate did not find that the PT was NOT signed off. How would the candidate know this if the examiner did not cue him/her??????
Obtain an App R. Key Set 2 A.2 Replace this JPM.
JPM ll-2fADM Anticipated time to accomplish?
App C.
.EW BANK May have look for another
.AOD1 FLED Trivial JPM, this is usually part of a JPM to obtain the key topic.O v 7/30 R_cplaced with and use it in a task. .
guesiton concomina tubina load. which is OK..and added another cuestion that deals 1 with time for boilinn.
Set 2 A.2 Determine the risk category and risk-recommended allowed JPM ll-3/ADM outage time (SRO) The entire matrix was not l provided and is more difficult as i (SRO) Time to completion is not listed. first determined. Leave as is. i NEW BANK !
MODIFIED The JPM appears OK, however, it is not very difficult. IT seems kind of straight forward and there is no way to failit. i l
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TOPIC CONCERN 1021 RESOLUTION o
Set 2, A.3 Review a RWP and obtain DAD Replace with evaluation of Trivial radiation areas.
Replace D Willreview when it nets done. Completed 8/G/98 Set 2, A.2 Hang an electrical lagout RO ONLY Modified because the audit had LOOKS OK as is. a similar JPM.
Added valdidation time. Change to a different block of breakers.
Set 2, A.4 Call back to the station.
No reference allowed.
NEWIOLD/
Need to delineate the point breakdown for full and partial Will delineate the point BANK credit. In addition need to determine how much material is breakdown of the question.
needed for a complete answer.
DONE is the reference available or is this from memory? NO reference NO KA referenced done Set 2, A.4 Large break LOCA RO State on question that no l
NEW/OLD/ BAN If a reference is allowed this question is a direct Look up. reference allowed. Made NO K App C reference. DONE 7/30/98 Is this an open or closed reference question?
KA not referenced Add KA to ques' ion DONE 7/30/98 i
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TOPIC CONCERN 1021 RESOLUTION a
Set 2 A.4 Classify an emergency event (SRO)
SRO Bank?? JPM is not sufficient to evaluate this area. I would like the Classify the events during the SRO to classify the scenario thist he/she is in the SRO simulator scenario as the SRO.
position. In addition to that we will need another JPM such as this one that requires the candidate to exercise the use of Will add a PARS to this or get making a PAR determination. OR we will need the candidate another JPM.
to fill out a paper work to declare an event to the state or Develop another JPM that NRC. requires PARS determination.
Completion time?
O Revised this willlook at this at the site. Completed 8/6/98
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EVALUATION OF SET 3 WALKTHROUGH EXAMINATION
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N. ANNA POWER STATION i
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' TOPIC CONCERN 1021 RESOLUTION Set 3 A.1 Perform a Reactor Coolant System heat balance hand calc.
New/ Bank MODIFIED? Will need a completed copy of the procedure. Also where is Will put data in the cues for the data supposed to come from? We need data to provide examiner to deliver to l'
to the candidate to ensure consistency of administration.
candidate.O DONE 7/30/98 How do you get started in the procedure? It seems as if-
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there is no way to do this, see step 3.3.2. It does not state manual calculation. OK as is. P250 is operable only ;
the calculation function is not operable.
- There are no tolerances listed in the JPM. There needs to be tolerances.
Will add tolerance in the ,
Competion time? standards or attach a key. O DONE 7/30/98 i
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TOPIC CONCERN 1021 RESOLUTION
1 Set 3. A.1 Admin hours of work requirements.
O#1 It seems as if there is more of an answer required. The in the reference material page 12, it stipulates that the procedure limits the OATC to 12 NEW BANK operator should be limited to no more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on the MODIFIED hours. Question is ok as is board. How many hours does this operator continuously work? 15 is the shift turnover incorporated in this time frame?
NO 645 to 7 am does not count.
KA not referenced DONE 7/30/98 Completion time?
DONE 7/30/98 Set 3, A.1 Shift staffing requirements.
Q#2 App B Appears to be OK but is Trivial NEW BANK .
MODIFIED Completion time?
DONE KA not referenced.
DONE
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TOPIC CONCERN 1021 RESOLUTION ti Set 3, A.2 ' Review and approve a work order package (SRO)
SRO Replace this with something JPM lil-2/ADM more substantial.
This JPM has low discriminatory value. I am not sure that a App.B less than competent operator would not find this mistake.
NEW BANK Especially when the procedure states that the requirements MODIFIED in the procedure. NOT DONE YET WILL LOOK
.ON DEVEL OPED ONE A T THE '
SITE D.
The other signature does not have a date assigned to the '
signature.
Will review to replaceO.
Completion time? Completed at the site, Determine tagging boundry 8/6/98, this may be changed to complete a tagout because the boundry may have two or three methods and may be difficult to grade. DJ i
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TOPIC CONCERN -1021 RESOLUTION t'
Set 3, A.2 Perform independent verification of an electrical tagout (RO) Revise the JPM to identify a RO JPM lil-3/ADM The JPM in principle is OK. However, I am not sure that the different failure mechanism.
failure to FIND the wrong wording of the noun name could Misinterpertation of JPM. The NEW BANK possibly fail a candidate overall if he / she missed it. What is MODIFIED? the true safety significance of this? JPM really had the tag on the incorrect breaker and has to be found by the operator, if the tag was on an incorrect breaker, ie. the wrong train then I would agree that the failure was warranted.
Evaluate as OK based on discussions. Change the standard to reflect that it is the incorrect breaker O . did NOT DO THIS. O ****
Rewrote the JPM to have a tag on a breaker that should have been closed but was found to be f open.
SET 3, A.3 Review a RWP and obtain a DAD JPM lli-4/ADM i RO/SRO This will be part of the entry into the RCA. Willreplace O Wi// review this NEW DANK on site. Completed, replaced We will need to replace this with a survey map to allow the with evaluate a posting 8/6/98 MODIFIED? candidates to determine what posting is necessary.
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TOPIC CONCERN 1021 RESOLUTION II
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Set 3. A.4 Prepare a follow-up report of emergency to the state and JPM lil-5/ADM local governments. (RO)
RO The initial conditions state that "You are the Emergency Misread the question it states Is this JPM Coordinator" is this possible for the RO candidates to NEW, BANK, assume this position? Communicator.
or Modified?
Step 2 Standard states that the operator Transposes, I ment transfers will change believe it should be transfers. DONE Do we have the initial report??? If so what was the sectors normally would have the initial associated with it ?
report and it does not have any part initially done.
Is step 5 Critical? I supposed that since step 10 is critical then step 5 does not have to be.
OK as is How is step 11 critical, if the examiner cue's the candidate the required information.
NOT critical and will be changed. O DONE
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TOPIC CONCERN 1021 RESOLUTION
, o Set 3, A.4 Classify an emergency event. (SRO) It is 15 minutes from the time JPM lil-6/ADM they finish reading the ICs untill SRO Step 15 of the JPM, requires the operator to note the time the GE is determined. IT/S the General Emergency is met. There are no time frames in JPM NEW, FROM THE T/ME THEY RFAAD the initial conditions that would provide feed back to the THE LAST /N/T/AL BANK, candidate to determine this information. CONDIT/ONS.
MODIFIED?
Depending how this JPM works I would like to have the SRO Will get OPS opinion if this is a candidates fill out the form in step 22. We need to see how time critical JPM.
the actual procedure flows.
Will add this to the JPMO V The JPM provided has two page 8s. One states 8 of.10 and DONE the other states 8 of 9. have the SRO fill out and determine the PAR.
The candidates initial condition sheet is the wrong copy. It states it is for JPM l-1/ADM removed the 8 of 10 Completion time?
replaced with the correct handout sheet.
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EVALUATION OF SET 1,2, & 3 IN, AT WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION
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TOPIC CONCERN 1021 RESOLUTION JPM l-1/SIM SWAP RHR pumps with RCS partially drained.
1. Step 4, has a cue to provide to the candidate for This is not necessary to provide standpipe level and RVLIS level. The standpipe level to the operator because it will is provided in the initial conditions. Place the RVLIS be performed in the simulator.
level in the initial conditions. Therefore it is not critical.
2. Are the rest of the cues required or are they just there Yes they are there if we were incase of having to simulate this JPM? I am assuming not doing it in the simulator.
that the simulator will be set up to represent the initial conditions.
3. Critical tasks, if the operator does not open HCV-1758 The step is already critical.
will there be flow? If there is no flow the candidate Misread the JPM.
did not complete the Task of establishing flow from the other unit. This needs to be critical. OK AS IS.
4. The JPM appears OK othenvise.
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REVISION 5, 8/12/98 Page 1 of 32
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EVALUATION OF SET 1,2, & 3 INi
.4T WALKTHROUOH EXAMINATION FOR N. ANNA POWER STATION TOPIC C CONCERN 1021 RESOLUTION JPM l-1/SIM 1. The question asks about Unit 2. The reference Question 1 1. only valve number materialis Unit 1. I assume that the only difference is difference.
the valve numbers? 07 NEW BANK MODIFIED? 2.
Since the reference is NOT allowed it is not a direct look up but a memory level question.
3. The question asks how to establish the cooldown rate.
3. The stem of the question 11 could be assumed that ONLY one answer would needs to be revised to elicit the answer the question fully. You could do one or the j other or both. answer. Completed OK 7/28 1 4. How much answer is required for full credit?
4. Will modify the question and assign values for answer. CV 7/28 JPM I-1/SIM 1. Unit 2 question with Unit 1 reference.
Question #2 1.ok 2. The question asks for consequences the answer gives NEW BANK 2. Change the stem to state two but you could answer the question by providing what is the system response MODIFIED? either of them.
and what are the consequences.
RO/SRO Completed 7/28 ok APP C.
3.
If references are allowed then the second answer will 3. Will change as requested be a direct look up in the OP.
above. O V No reference allowed (
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l REVISION 5, 8!12/98 Page 2 of 32 i
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EVALUATION OF SET 1,2, & 3 IN .4T WALKTHROUGH EXAMINATION
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FOR N. ANNA POWER STATION TOPIC p CONCERN 1021 RESOLUTION JPMI-2/MCR Respond to Recir Spray heat exchanger service water outlet high radiation alarm.
MODIFIED Alternate Path? i Not sure that this meets the modified criteria. It is a different heat exchanger, 1. therefore it is an attemate path.
In the initial Conditions should have the annunciator alarm window numbers for the candidate to observe Do not need.
and for the examiner to point out as being lit.
2. Need to go over the basis for calling this a modified OK As IS, explained the JPM with the facility. The initial conditions appear to difference.
be very similar . The only difference being is the Rad monitor being in alarm. O/
3. Step 5 of the JPM, we need a better note to the 3. Will add the note to the examiner in order to let him know that this is the examiner. O Vadded the note alternate path item.
7/28 4. This JPM in my opinion is NOT an alternate path 4. The note is goveming the JPM. The actions that are in the JPM are NOT valve manipulation. This is OK govemed by the procedure the candidate will be in. If as is. Do not change the JPM.
the candidate does not do what the JPM states and does not CYCLE the valve will the candidate fail the i JPM? We need to address this to see if this meets the criteria for an alternate path JPM.
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REVISION 5,8/12/98 Page 3 of 32
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EVALUATION OF SET 1,2, & 3 IN, .NT WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC 9 CONCERN 1021 RESOLUTION JPMI-2/MCR 1. Is 1-SV-102-2 as described in the LP the same as 1-I Question 1 Yes they are.
SOV-SV-102-27 BANK Modified 2. The question does not elicit the last part of the NEW? Question was reworded OK.
answer. Allit asks for is the consequences of the l
valve alignment.
t 3. The question should be re-written to not provide the Re-write the question as stated. !
line up but to give the phase A isolation, the high high O , Wi// the candidates know ,
alarm and ask the flow path and the consequences. what this /-E-J is? Do we t This would then allow the candidate the opportunity to have to have the name of the ;
show his/her knowledge of the way the systeni works. procdure written out? O They t are supposed to know this ,
information. Do not have to put in the name. 7/30/98
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Will try to write a new question. ,
O JPMI-2/MCR 1. Are the candidates required to know this information l Question 2 OK AS IS from memory? Is this an immediate operator action that is required to memorized? If so it is ok.
Bank Modified New?
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REVISION 5, 8/12/98 Page 4 of 32
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EVALUATION OF SET 1,2, & 3 int .AT WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC o CONCERN 1021 RESOLUTION JPM l-3/SIM Establish redundant cold-let injection flow paths.
Modified ESF Simulator 1. The JPM does not have a step that represents Will fix both of these procedural step 26.(c) prob / cms.OV 7/28/98 RO/SRO 2. The JPM does not have a step that represents procedural step 26.(e) Check "B" charging pump running. IF this is a NO don't you have to go to the ,
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RNO and perform those actions? This is STEP 6 of '
the JPM should be step e. RNO and not step f. By procedure you skip step f.
3. !
What is the status of the "C" charging pump? it is running, this is something 4. The JPM appears to be modified that the candidate will have to determine.
JPM l-3/SIM No reference allowed Question 1 ,
t 1. In the stem of the question the word " occurs" is Modified, New fixed misspelled as addurs.
Bank?
2. Did the DG align itself to the bus?
yes it did but did not say it.
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3. Not sure that the whole answer will be provided. IT Develop a stem that would elicit seems that the first sentence " reduced safety the second part of the question.
injection flow to the core" would be sufficient to i
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answer this question. O Willlook at to reword. Not sure that the fix wi// do what was asked. Need to remove the wordO Completed 8/6/98 t
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REVISION 5, 8/12/98 Page 5 of 32
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EVALUATION OF SET 1,2, & 3 IN: .4T WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC ,, CONCERN 1021 RESOLUTION JPM l-3/SIM 1. Is this question from the bank? Is that what the Question 2 NO, comes from the content question 3432 is?
data base.
Modified, New, 2. What is the reference to this question? Is there one?
Bank? It is in the protection logic 3. Show us the logic how this occurs. O
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4. When these pumps shift, they get destroyed because Yes this is the reason why there is no levelin the sump, taking a suction from the sump that has no levelin it??? Is this the reason why?
5. What reference would the candidate's use to come up Will bring the reference and with this answer? discuss next time. O V Modified OK 7/28 JPM l-4/MCR Evacuate the control room due to fire BANK 1. In the initial conditions of the JPM ROOOM is will fix. F/XED misspelled.
2. The second sentence in the initiating cue is hard to will add ' procedure' in the understand. What do you mean? sentence F/XED 3. For the RO candidates how is steps 9 and 10 of the ok as is JPM supposed to be accomplished?
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REVISION 5, 8/12/98 Page 6 of 32
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EVALUATION OF SET 1,2, a 3 IN. AT WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC CONCERN 1021 33 RESOLUTION JPM l-4/MCR 1. Is it necessary to state that 1-FW-P-2 is the only AFW Question #1, Will delete AFW pump O V pump running. Can it just say it is the only pump running?
Bank, Modified, New? 2. Determining one S/G levelis trivial. Provide all three generators with pressure and level values and have the candidate determine the required actions of the f; eld operator. OV ,
JPM l-4/MCR 1. The first part of the question appears to be a direct When getting the answer we Question #2 look up from the caution of the procedure. may have to ask follow up. The Bank, Modified, facility will formulate this 2. This question should be NO reference. question. Comn/cted as New reauested.
will change this to NO reference Done. .
JPM l-5/SIM Transfer 1H emergency bus from 1H EDG to 1B station !
Modified service bus.
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RO 1. Step 5.4.4 is not in the JPM misread the procedure. it is in ,
the JPM 2. Are any of the Steps ie 5.4.5 will the candidate have Added to/crance to this OK to adjust this to get 60 Hz? If the simulator places no w. Will have to adjust. was the JPM where manipulation is not required then the tried on the simulator to ensure step is NOT critical.
it was critical.
3. Not sure that Step 7,8 and 10 are critical. Need to 7 and 8 are critical but 10 is not.
explain why they are. Will add a tolerance for step 7.
tAdded toicrances. and deleted
, criticalsten for step 10.
REVISION 5, 8/12/98 Page 7 of 32
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s EVALUATION OF SET 1,2,8 3 INi
.4T WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC ,, CONCERN 1021 RESOLUTION JPM l-5/SIM Question appears OK Question #1, New , Bank, Modified?
JPM l-5/SIM 1. Is the information in the answer in parenths. is that Question #2, Proposed replacement is OK but information also required? The NRC convention is that information that is NOT required and there for will also add an additional part b New , Bank, prescripted question that will amplification is placed in parenthesis.
Modified? elicit a different area. O The 2. new answer is backwards, in Need to provide point values for each part to ensure that . the first part of the grading consistency.
answeranswers the second 3. part of the nuestion and visa Why can the answer just be written as it is in the highlighted 5531 example? versa. O V Comn/cred B/6/98 added an additional cuestion as reauested. Rcolacement is OK. ;
OV Re-write the answer as it appears in the reference. O V Does not have to be changed based on the comment above.
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REVISION 5, 8/12/98 I Page B of 32 l
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EVALUATION OF SET 1,2, & 3 IN.
.NT WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC ,i CONCERN 1021 RESOLUTION JPM l-6/SIM Respond to Component Cooling Water S/ stem Malfunction Modified, 1.
The outline does not reflect that this JPM is an will fix the outline O Alternate Path, however, the JPM does.
RO COMPLETED 7/30/98 2. Appears to be modified.
Added additional stccs. OK as 3. In step B the candidate has to determine RCP 11 ,
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temperatures. Will the simulator model these will have to use time temperatures increasing until the candidate gets to compression, the simulator will step 13?
do it but the examiner will have 4. to provide the cue. See how Procedural Step 10 requires the candidate to stop the long it takes to get there and if affected RCPs. Are all three Pr.P affected as we see to long then maybe an override in JPM step 15 to trip all three RCPs?
will work.
All three will be affected and will trip all three RCPs.
JPM l-6/SIM 1. The second part of the answer is not clicited from the Question #1, stem of the question. on examiner copy will have the 2500. the piping is rated for Q3 l New, Bank, which is 2500 #. Ov 7/28/98 Modified?
JPM l-6/SIM 1. Does the 'A' CC pump immediately autostart??
Question #2, yes 2. Need to get an explanation of 11233 (5 second New, Bank, duration)
this will lock out the b cc pump Modified? from starting if it did not start it 3. would lock out. Add an The answer could be written better. examiner follow up question O iV, Rewritten as requested
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7/28/98 REVISION 5, 8/12/98 Page 9 of 32
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EVALUATION OF SET 1,2, & 3 INI
.4T WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC it CONCERN 1021 RESOLUTION JPM l-7/SIM Restore containment isolation valves following a SI.
Modified, 1. Need to get explanation of how this JPM was modified. Does not appear to be modified. Was not modified and will I RO/SRO change the outline. O FIXED 2. 7/30/98 JPM Step 7 states to open 109A and 1098 The procedure does not show an "A" and "B".
the switches are each train a 3. JPM otherwise appears to be OK. and b but for one valve.
Question #1, Containment depressurization ie 2. Stem of the question, should be ON not ONE. Containment Spray Modified, Bank, FIXED 7/28/98 New? 3. It seems pretty obvious that when you have dual indication for any valve that the valve is OPEN. I am Series solenoid valves. Need to understand how they work.
not sure about 104A-1 and 104A-2 what that means.
Explain.
Facility brought a replacement 4. May not get the part about the check valve. which was acceptable. No further action required.
JPM l-7/SIM 1. Why do we have to tell the candidate that he/she Question //2, Will change to remove the NOT should not make the mode change. Why not just ask and change the answer. O
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them to determine what should be done. l Modified, Bank, V The cuestion is OK as New? 2. chanced.
This seems to be a trivial SRO task.11 may be Will leave in for SRO, facility considered ok for the RO. ,
stated that the SROs have had problems with this in the past.
JPM l-8/ PLANT Collapse steam voids in a steam bound AFW pump Bank 1. JPM appears OK g
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REVISION 5, 8/12/98 Page 10 of 32
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EVALUATION OF SET 1,2, & 3 INF . ,4T WALKTHROUGH EXAMINATION FOR ,
N. ANNA POWER STATION TOPIC ii CONCERN 1021 RESOLUTION JPM l-8/ PLANT 1. Appears OK Question fli, !
New, Modified, Bank JPM l-8/ PLANT 1. Provide individual point values to each portion of the Question //2, will do. O done 7/28/98 answer to facilitate examiner consistency.
New, Modified, 2. From validation the answer was Why don't we ask to additionally explain what has to not complete, there needs to be Bank? be done if Si had occurred. added a part about the main feed pump breakers have to be racked to test and then closed.
This will be added. O Was THIS done or NOT? V 7130198 During validation the validator ,
was incorrect and the writer determined based on the stem ,
with the CN system in operation that the breakers were already '
racked in. no further information i's necessary.
Make it a two part question. on the same sheet. DONE 7/28/98 JPM l-9/ PLANT Place N, backup in sycs to spent fuel pool gate seals.
Revised sten 2 to remove Bank, RCA,11, 1. The JPM appears OK. reference to admin tonic.
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REVISION 5,8/12/98 Page 11 of 32
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EVALUATION OF SET 1,2, & 3 INi .JT WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC 8 CONCERN 1021 RESOLUTION JPM l-9/ PLANT 1. Appears to be ok Question #1, The question was not oK facility va:idation revealed that the RP Now, Bank, purnp could not be started which Modified? w >uld allow slucing. The question was modified and the replacement is OK. No further action required.
JPM l-9/ PLANT 1. List the point value of each portion of the answer.
Question #2, will add O DONE 7/28/98 2. Need to tell the candidate how many you need to get New, Bank, full credit.
Modified?
JPM l-10/ Prepare the SBO diesel for loading following an automatic PLANT start.
RO/SRO 1.
State in the initial conditions that 5.1.1 are verified will do this for all JPMs that complete.
have that requirement O
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Bank, Alternate '
Path. 2. DONE 7/28/98 It seems as if the JPM step 10 closes the DG output misread the JPM the actual breaker. Is that the case? I don't believe that this alternate path occurs in step 15. t JPM is a true alternate path. The candidate does not OK as is.
have to take an allemate action in accordance with Added steps to get sync. key, the procedure.
Completed 8/7/98 3. JPM otherwise appears ok.
JPM l-10/ 1. Appears OK PLANT Question #1, i
Bank New '
Modified?
t REVISION 5,8/12/98 Page 12 of 32 l
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EVALUATION OF SET 1,2, & 3 IN. AT WALKTHROUGH EXAMINATION -
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N. ANNA POWER STATION .
TOPIC p CONCERN 1021 RESOLUTION JPM l-10/ 1. Need point breakdown for each portion of the answer PLANT key. will do O DONE 7/28/98 Question #2, 2. Appears to be ok validation comment requires to consider the switch separately.
Bank New OK as changed.
Modified?
JPM SET 11 JPM ll-1/SIM Respond to a loss of RHR flow Bank, Alternate 1. JPM step 11 has two cues, I am not sure why it is one is to be provided by the RO/SRO that way. Please explain. examiner.
2. JPM otherwise appears OK JPM ll-1/SIM 1. Question appears OK Question #1, 2. Add a part *b' to the question to explain the reason Bank Modified Answer is on page 25 of the for not.having fuel movement in the area of the "A" lesson plan,5.c Will add O New? hot leg.
DONE added cart a and b to aucstion 1.
JPM ll-1/SIM 1. Question appears OK Question #2, 8
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Bank Modified New?
REVISION 5,8/12/98 Page 13 of 32
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EVALUATION OF SET 1,2, & 3 IN. .4T WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC o CONCERN 1021 RESOLUTION JPM ll-2/SIM Coordinate placing a Delta TITave channelin test May require to match Bank, Alternate Tave/ Tref.
1. JPM step 5.1.6.i requires the Steam dumps to be in
, Simulator steam pressure mode. The cue states that another THE candidate will place in operator will place it in this mode. Will another Tave mode.
ROISRO operator have to do this or not?
2. JPM step 12 is kind of confusing in respect to what is done. I realize that the field operator incorrectly Explain how this is an attemate places the wrong BS in trip. Does he/she leave it that pathi way when he is told to close the panel? Do we leave the plant in that configuration? OK as allemate path.
Need to place in the Tave mode, this information needs to be added to the JPM. This was done 8/7/98.
Will just stop work and leave it t in that configuration.
JPM ll-2/SIM 1. The first sentence is window dressing. It has nothing Question #1, to do with answering the question. It can be deleted will delete the first sentence. O 7/30/98 without affecting the answer or the ability to answer New, Modified, the question.
Bank?
2. The question is a memory level question. It has low AppB will make it a no reference discriminatory value. question O DONE, answer 3. was also chanacci.
The answer should be the reactor will trip because the UV coils on the B RTB open.
4. This should be a no reference question.
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REVISION 5, 8/12/98 Page 14 of 32
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EVAL'UATION OF SET 1,2, & 3 INi .NT WALKTHROUGH EXAMINATION FOR
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N. ANNA POWER STATION TOPIC it CONCERN 1021 RESOLUTION JPM ll-2/SIM 1. Question appears to be ok Question #2, New, Modified, Bank?
JPM ll-3/SIM Transfer the Si system from hot-leg to cold-leg recirc.
Modified S, 1. JPM steps 12 and 13 state that 1867A or 18670 ESF these are parallel flow paths so should be open, and 1867C or 1867D should be either one could be open to get open. The procedure does not state OR between the the required flow. Only one is two valves. Is this correct??? critical to be performed. Will 2. JPM appears to be OK otherwise. discuss this and point out to each examiner so they fully understand the implication of the step. The stens were rewritten to allcw cither or valve to be opened OK ASIS.
JPM ll-3/SIM 1. The question could be answered by stating that you Question #1, this is supposed to be done would have reduced Si flow. Nothing else is solicited. because some people Modified, New, 2. misunderstand the concept.
Do the candidates know what 50.46 IS?
Dank?
3. YES they do.
Trivial and should be replaced.
See the other aucstion concernina the wording of ncak cladinn temernerautre. [) V 7/30/06, fixed WILL change the question to add reference to E-0 attachment performance and finding the trecirc valve found open.
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REVISION 5, 8/12/98 Page 15 of 32
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EVALUATION OF SET 1,2, & 3 IN.
.NT WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC 3, CONCERN 1021 RESOLUTION JPM ll-3/SIM 1. What are the procedural requirements for the Question #2, will be open and tags to the shift Accumulator discharge valves in mode 5. Are they supervisor. On off type going to be racked out?
Modified, New, breakers not racked out.
Bank? 2. All we are really testing is the knowledge of the SSPS with fuses pulled there is pressu^.e requirement for the interlock. Knowing a deenergized to actuate With whether the plant is less than 2000 psig or not. the fuses are in nothing would happen. If they were in there would be an auto actuate above 2000.
OK AS IS.
JPM ll-4/MCR Place a waste gas decay tank on bleed. '
RO 1. JPM step 5 references procedural step 5.3.5 it should be 5.3.4 ok will be changed. OV Modified, 2. JPM step 15 references procedural step 5 it should be 5.3.10.3 ok will change O V 3. JPM step 16 allows a release of 2.7 + or - 0 '5, the procedure states that when adjusting the FCV that The release rate is always 3 you should NOT exceed mass flow on HP release scfm but the IC limits the flow to form. So :here should be a 2.7 and -0.25 tolerance. 2.7. so the tolerance as stated More than the flow on the form is NOT allowable . in the JPM is OK.
4. JPM appears ok otherwise.
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REVISION 5, 8/12/98 Page 16 of 32
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EVALUATION OF SET 1,2, & 3 IN. .dT WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC o CONCERN 1021 RESOLUTION JPM li-4/MCR 1. Questiori appears OK..
Question #1 no tolerances because the values are provided in the stem Modified, Bank and the formula comes directly New? from the procedure. There fore they should get the exact answer. No action necessary.
FOR the SRO (I) add a replacement question to replace this that is more in ;ine with SRO knowledge. O _/
Replacement aucstion is OK.
but I ano not sure that the candidates willanswer this gyestion this way. Was this va// dated ?O 7/30/98 they are required to know this information and it is verbatum from the training material.
JPM li-4/MCR 2. Question appears OK Question #1 Modified, Bank New? i JPM ll-5/SIM Respond to low pressure letdown relief line high temp alarm will review this at the site to Modified, 1.
determine suitability. O can JPM is short. Is there something that can be done to carry it out to the point that we Simulator make it longer?
want excess letdown in service.
RO 2. O v' JPM is OK as revised.
< Appears to work OK.
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REVISION 5, 8/12/98 Page 17 of 32 *
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EVALUATION OF SET 1,2, & 3 IN. elT WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC n CONCERN 1021 RESOLUTION JPM 11-5/SIM 1. Need to provide point values for each part of the Question #1, will do. O V Completed.
answer to allow examiner grading consistency. 7/28/98 Modified, New, 2. Need to tell the candida'es that we are looking for six Bank? items.
2. done 3. Otherwise question appears OK JPM ll-5/SIM 1. Need to provide point values for each part of the Question #2, will do O V 7/29/98 answer to allow examiner grading consistency.
Modified, New, 2. Validation brought up the fact Otherwise question appears OK that they should not consider Bank?
the valve packing leak itself fur the potential release pathway.
Change to the question is ok.
Put NOT in caps and bold O V JPM ll-6/MCR Vent the Unit 2 Pressurizer Relief Tank Bank 1. JPM appears to be OK RO Control Room JPM ll-6/MCR 1. The question appears OK Question #1,
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Bank, Modified, New?
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EVALUATION OF SET 1,2, & 3 IN, .AT WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC CONCERN it 1021 RESOLUTION JPM ll-6/MCR 1. The plant does not operate in absolute pressure.
Question #2, will change to psig. Completed Change the numbers in this question to psig numbers. 7/29/98 Bank, Modified, 2. I am not sure that 20/1 range + or -is appropriate for New? will figure out what it is exactly the values given. That gives an margin of 40 degrees. with tables and then use a + or -
10 deg F. Completed 7/29/98 3. Otherwise the question is OK JPM ll-7/SIM Transfer 1H emergency bus from 1H EDG to C reserve station service transformer 1. Added tolerances for steps 9 Bank and 10. Completed 7/29/98 RO 1. JPM appears OK JPM ll-7/SIM 1. Point values for each portion of the answer.
Question fil, will do O V 7/29/98 2. from the reference material, I don't believe that local Bank, Modified, operation of the breaker is necessary. O Also it is in reference material is incorrect in New? that it does not state loca!iy. It the stem so how is it an answer? can only be done locally.
3. The answer does not state waiting for the 15 seconds is this necessary ? not necessary for the answer.
JPM li-7/SIM 1. Question appears to be OK Question f/2, Validation comments.
Dank, Modified, answer is not correct as written, New? no manual operation.
JPM Il-BI Re-energize vital bus 2-1 from the inverter PLANT 1. Precedure step 5.4.4 is not listed in the JPM. Are the RO/SRO requirements of the step met and does not have to be ,will add. O v 7/29/98 Modified addressed? O ~ 2 2. JPM appears OK REVISION 5, 8/12/98 Page 19 of 32
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EVALUATION OF SR 1. .., & 3 IN,
.4T WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC it CONCERN 1021 RESOLUTION JPM 11-8/ 1. Question appears OK PLANT Question fli, 2.
i Why isn't the part of the reference material in ()s not Change the stem to elicit the Bank, Modified, required. NO protection is provided to prevent parenthesis answer. OV transferring the icad to a deenergized sola.
New? 7/29/98 l
JPM 11-8/ 1. Question appears OK PLANT Question 112, Bank, Modified, New?
JPM Il-9/
PLANT Align fire main to the auxiliary feedwater pumps suction.
1.
Bank JPM step 3 requires the AFW pumps to be stopped.
is the rest of the step in the procedure (4) completed, Neea to add information or cues Plant to JPM step 3 to have the RO ic Si reset AMSAC reset etc???
control room verify the SI, 2. JPM otherwise appears OK AMSAC etc. V Completed 7/29/98 JPM ll-9/ 1.
PLANT This question is a direct look up in 0-FCA-1 p 4 and 19 as provided in the reference material. This will will make no reference and Question fli, changed the stem slightly.
need to be replaced or no reference will be allowed.
Bank, Modified, O V 7/29/98 New?
JPM 11-9/ 1.
PLANT It appears that this also is partially a direct look up from the PT. Il should be replaced or no reference no reference allowable. O V Question 112, will be allowed. 7/29/98 Bank, Modified, " 'look at to see if they are New? required to know this from memory.
REVISION 5, 8/12/98 Page 20 of 32
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EVALUATION OF SET 1,2,8 3 IN. .dT WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC it CONCERN 1021 RESOLUTION JPM 11-10/ Open the RHR heat exchanger cooling water return valves PLANT Changed step 2 to reflect using a jumper.
getting the key and not RO/SRO referencing the admin JPM.
1. JPM appears OK 7/29/98 BANK Changed s' tep 6 to not give credit for the admin topic.
JPM 11-10/ 1. Provide grading criteria for full credit and examiner PLANT ok consistency.
Question #1, 2. Are the items in parens. required for full credit?
Bank, Modified, will get rid of parenthesis O V New? 7/29/98 3.
JPM 11-10/ 1. Is this a topic that RO candidates are responsible for? ,
PLANT OK ROs can do it. Wants to Do they normally make TS interpretations? O check with OPS to ensure that Question #2, 2.
RO knowledge. O V 7/30/98, The line up is kind of confusing. Will the candidates are required to know this Bank, Modified, know what the rest of the line up will be as described New? information.
in the stem of the question?
3. This appears to be a direct look up in TS but we need wiil understand.
to talk about it.
OK as is.
JPM SET 111 a<
i REVISION 5, 8/12/98 Page 21 of 32 l
_ _ _ _ _ _ _ _ _ _ _________...______m._______ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _____ _ _ _--
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EVALUATION OF SET i. 2, & 3 INi .,4T WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC p CONCERN 1021 RESOLUTION
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JPM lli-1/SIM Initiate forced feed and spill cooling due to loss of RHR.
Alternate path 1. Not sure that this is an alternate path JPM. Need to BarJ< Simulator discuss this.
2. Step 2 asks to stop sump pumps if desired. Should 2. JPM was revised to remove we have a cue that it is desired to stop the sump critical step.
pumps?? This step is listed as a critical step. How does it make it to this status? Need to explain.
3. In JPM step 5 the flow path is supposed to be 3. Steps 5,6, and 7 were checked. What are they going to be cht.cking? We revised.
should have that information there.
4. JPM step 6 requires the RWST isolation valves to be opened. The JPM states one or the other. The ;
procedure does not state either can be opened.
Resolvel 5. JPM step 10 same as 4 above.
7/29/98 JPM is OK as corrected JPM lil-1/SIM 1. Is it necessary to tell the candidates that these valves Question #1, Reward the question.
no longer get a signal? Can this be reworded to Completed 7/29/08 i avoid this?
Bank, Modified, New?
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2. What are those valves anyway?
JPM lli-1/SIM 1. Appears to be OK Question #2,
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Bank, Modified, New?
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REVISION 5, 8/12/98 Page 22 of 32
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EVALUATION OF SET 1,2, & 3 h4. AT WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC CONCERN
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1021 RESOLUTION JPM lil-2/MCR Configure U-2 emergency bus load to prevent EDG overload.
Bank, 1. JPM step 4, does this need an examiner cue 1. Not necessary because it is concerning the status of the 1-SW-P-1A, what header inthe initial conditions. 7/30/98 it is on? -
2. JPM Step 7 should have a cue that contains the 2. Item 4 in the initial pumps that are running. Or is this information conditions. 7/30/98 already available to the operator from the IC7 3. JPM otherwise appears OK JPM lil-2/MCR 1. How do you use this table to get that answer? Please Question #1, Proposed a modification to the explain.
stem based on the validation.
Bank, Modified, Stem as changed appears to be New? ok.
JPM lil-2/MCR 1.
Place in the stem condition (s).
Question #2, 1. will do O V Completed 81619 8 2. How do you get to the answer based on the Bank, Modified, reference material?
New? 2. correct answer. the re'ierence page from the lesson plan described those blocked and t ien you have to go to the prints to determine which ones are still in effect. ok as is 7/30/98 JPM lil-3/SIM Transfer the SI injection to the Hot-leg recirc mode Step 13 of the JPM was Modified , ESF 1. Appears to be modified. modified. 7/29/98 2. JPM appears to be OK REVISION 5, 8/12/98 Page 23 of 32
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EVALUATION OF SET 1,2, a 3 IN. .4T WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC n CONCERN 1021 RESOLUTION JPM lli-3/SIM 1. This question appears to be of a trivial nature. Is it Question #1 Point values were added for operationally valid? grading consistency. 7/29/98 NEW 2. I am not sure that this question should be an open reference question. Why? O ok to use the reference material V 7/30/98 JPM lli-3/SIM 1. Quesiion is OK as an open reference. Will the Question #2 Changed to closed reference.
candidate be able to use the control board to trace the system? If so we should state that in the question *
NEW on the examiners sheet to allow that information.
2. Provide a point breakdown for each part of the 2. Completed 7/29/98 answer to ensure consistency in grading.
JPM lil-4/SIM Shift from normal letdown to excess letdown.
Direct, 1. JPM step 5.1.5 states that the backboard operator Simulator 1. Done in the simulator and should close breaker # 22 to energize 3 drain valves. will not have to be cued. When The procedure does not state what position these the breaker closes the green should be in however, the JPM provides a cue that lights come on, the valves have green lights. WHY?
2. JPM appears to be OK otherwise.
JPM lil-4/SIM 1. Appears to be OK Modified the question. OK as Question #1, modified 7/29/98 I
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i REVISION 5, 8/12/98 Page 24 of 32
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I-EVALUATION OF SET 1,2, & 3 IN. AT WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC it CONCERN -1021 RESOLUTION JPM lil-4/SIM 1. Why are we not asking about what happens to the Add to the question what system. Not just pressure and flow. happens with the system and Question # 2, use the information that is presented in the reference materiaf. Wi// add this additional requirement to be asked D VCompleted 8/6/98 Added point values to the answer. 7/29/98 JPM lil-5/SIM Respond to a loss of Reactor Coolant System Pressure.
Direct. Sim 1. Is it necessary to state in the initiating cue that he/she 1. OK as is. Since the is to respond IAW 1-AP-44? Could you not state candidate is on the board he Alternate Path Respond to the alarm?
would be directed by the SRO 2. DO NOT CHANGE 7/30/98 What docs the Annunciator Response procedure state?
3.
Modified step 4 to inform the The JPM while important is not very difficult. Will examiner that it was the need to evaluate the whole set to determine if we alternate path step.
should keep this JPM.
7/30/98 The JPM was modified to identify immediate operator actions.
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REVISION 5, 8/12/98 Page 25 of 32
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EVALUATION OF SET 1,2, & 3 IN. .4T WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC it . CONCERN 1021 RESOLUTION i
JPM lli-5/SIM 1. The question asks what will happen! Is the spray 1. Yes it is. 7/30/98 valves sized large enough that pressure will not Question # 1 continue to increase?
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2. Will the Other heaters that are locked on will they
2. no they will not. 7130/08 eventually trip?
3. l Need to put point values for each item to ensure 3. added point values. 7/29/98 i consistency.
JPM lil-5/SIM 1. Question appears to OK as is. added point values to answer Question # 2 7/29/98
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REVISION 5. 8/12/98 page 26 of 32
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EVALUAT!ON OF SET 1,2, & 3 IN. .AT WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC 9 CONCERN 1021 RESOLUTION JPM 1116/MCR Respond 13 a Fuel Pit Bridge Radiation Monitor Alarm Modified, 1. Appears to be modified.
2. Is it necessary in the initiating cue to state the 2. Removed from the Stem.
procedure necessary? Can we let the candidates 7/30/98 figure ;t out on their own?
3. JPM should have procedure steps 1 and 2 of 3. Added 7/30/08 attachment 3 to provide procedural flow to the examiner.
4. JPM step 9 states that the procedural step 4 NOTE is 4. Not a note, but an IF THEN being used. What does this mean? There does not statement that applies to appear to be a NOTE before or after the step. subsequent steps. 7/30/98 5. JPM Step 11 states in () Step 4 NOTE again? What 7/30/98 does this mean?
6. How does the candidate know when the JPM should
,
6. Just add to the end go back be done? It appears if after finished the part of the to step in effect. O V Attachment that the candidate could go back to the Completed 813198 body of the procedure to finish this JPM.
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JPM 1116/MCR 1. Memory level, No reference is appropnate.
Question # 1 2. Why do we have to teach the candidates what action 2. FIXED 7/30/98 is supposed to happen. Why can't we just ask What -
actions are necessary and explain your answer.
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i REVISION 5,8/12/98 Page 27 of 32
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EVALUATION OF SET 1,2, & 3 IN. .AT WALKTHROUGH EXAMINATION '
FOR N. ANNA POWER STATION TOPIC it . CONCERN 1021 RESOLUTION JPM 1116/MCR 1. Agree with NO reference, just a memory level question.
Question # 2, 2. What are the status of the fans in Unit 17 2. They are on 3. Adding window dressing about thU bad connector. 3. removed WD 7/30/98 Just delete that and state the instrument failed high.
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REVISION 5, 8/12/98 Page 28 of 32
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EVALUATION OF SET 1,2, & 3 IN. .4T WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC 9 CONCERN 1021 RESOLUTION JPM lit 7/SIM Place the Containment Air Recirc Fans in operation.
Modified, 1. Appears to be modified.
Simulator Modified step 2. OK 7/29/98 2. What happened to step 5.1.3 2. Added step 5.1.3 7/30 3. NO, there is not much 3. JPM Step 4, is the SRO going to analyze this part??? interpretation. 7/30/98 4. What is containment pressure? Is the containment 4. This JPM the containment is subatmospheric containment going to have a pressure? What would the and is not at pressure.
candidates do if there was a pressure? How do they check the fan intakes clear as in the caution?
5. JPM step 7, how do the candidates know the 5. Added to the IC 7/30/98 containment is open for maintenance.
G. JPM step 8, don't you only start the 2 available fans? 6. Modified step 8. OK 7/29/98 7. JPM Step 9 cue states all red lights are lit. How can 7. It was a spurious trip, and that be if C fan was tripped in the Initial Conditions. was fixed. OK AS IS.
Was this fan fixed?
8/3/98 Added simulator 8. maltunction to make the Why would the operator STOP at JPM step 11? simulator actually work the Which represents step 5.1.8.d. It seems that the way the plant would. ie the candidate should perform procedural steps 5.1.9 and 2nd fan will trip if not started
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5.1.10.
at the same time.
8. added steps 7/30/98
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REVISION 5, 8/12/98 Page 29 of 32
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EVALUATION OF SET 1,2, & 3 IN.
.4T WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC '
n CONCERN 1021 RESOLUTION JPM 1117/SIM 1.
Question was replaced before the review. The ,
replacement question removed some information 1. Information was not originally Question # 1 correct. It is correct now.
required to answer the question. Why was the UV 7/30/98 cleared removed from the answer?? This seems to be an important piece of information 2. Assign point values to the answer to ensure examiner consistency. 2. Assigned point values to the answer. 7/30/98 JPM 1117/SIM 1.
This question appears to be a memory level question. 1. Changed to no reference.
Why is this using a Reference??
Question #2 7/30/98 2.
Are there unit differences? If so lets ask them.
2. NO unit differences. 7/30/98 JPM 111-8 Plant Align and control auxiliary feedwater flow locally.
Direct 1.
JPM appears to be OK, but the steam generator 1. There are no minuses there.
levels at (-) values are hard to read. At first I did not indicators go from 0 to 100%
read, the minus signs.
These are WIDE RANGE .
Need to capitalize Wide Range to understand that the Narrow ranges need to be obtained.
Need to use the graph to determine the 33% level for Narrow Range. 7/30/98 JPM 111-8 Plant 1. Memory Level question Question # 1 Added point breakdown for 2. It is not necessary to ask in the stem what action answer. 7/29/98 should you take to remedy this situation? Just ask 2. FIXED 7/30/98 what actions are necessary.
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j REVISION 5, 8/12/98 Page 30 of 32 i
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EVALUATION OF SET 1,2, & 3 IN, .4T WALKTHROUGH EXAMINATION FOR N. ANNA POVER STATION i TOPIC n CONCERN 1021 RESOLUTION JPM 111-8 Plant 1. Arc both units the same? If not ask differences. No Differences 7/30 Question # 2 added point values to the 2. This is a direct look up on the PalD. Recommend replacement. answer. 7/29/98 2. Question is OK AS IS.
JPM lil-9/ Plant Rack in a 4160 voit breaker. Replace this JPM with the Direct 1. original. Do not fault it that wt y JPM is lacking and not really an allemale path. it will make it better. O Alternate Path There are no other actions to perform once the grounding strap is identified. Decided not to do this, OK the 2.
way it was changed. 8/7/98 '
I would rather that we not fault this and perform the whole evolution.
3. One critical step in the JPM does not cut it.
JPM lil-9/ Plant 1. Question is teaching what the operator should or 1. Question was rewitten should not do. Just ask what should be done. 7/30/98 OK now.
Question # 1 Reword the stem of the question.
placed point values on the answer. 7/29/98 JPM lil-9/ Plant 1. Question appears to be memory level. Need to see how many memory level questions there are to see if Question # 2 this is acceptable.
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REVISION 5, 8/12/98 Page 31 of 32
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EVALUATION OF SET 1. 2, & 3 lb. AT WALKTHROUGH EXAMINATION FOR N. ANNA POWER STATION TOPIC o CONCERN 102.1 RESOLUTION JPM 111-Align the Fire Protection System to cool Unit -2 "B" Charging Removed the reference to the 10/ Plant Pump admin JPM 7/29/98 Direct 1. JPM step 4 should be Critical, because if they don't RCA 1. Made steps 4,5,6 critical.
have this stuff they can not do the task.
AP Action 2. JPM step 5 and 6 are critical. See # 1.
3. JPM Step 7 and 0 Connect are misspelled.
r 4. JPM Step 10 has the wrong valve number should be 694 vice 684 4. Corrected. 7/30/98 JPM lil- 1. It is confusing which BAT you are talking about in the 10/ Plant placed point values in the stem. Add to the stem the Unit designator before the answer. 7/29/98
"A" BAT.
Question # 1 2. The graph provides the volume necessary to answer !
2. It is a direct look and do not the question. Which would make this a direct look up. expect them to know from The rest of the answer I am not sure how you arrived memory this answer . Wi/// find at this because you only provided the mode 5/G TS. i Need to explain how we arrived at this answer. I another cuestion O V i Ren/acement is OK B/6/SB think that this also is a direct look up in TS.
JPM 111- 1. This question was revised prior to review. Will review 10/ Plant placed point values in the i rev. 1.
answer. 7/29/98 Question # 2 2. Question appears ok
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3. Need to provide point breakdown for grading consistency.
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REVISION 5,8/12/98 Page 32 of 32
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ENCLOSURE 7 '!
ASSIGNMENT SHEET
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$2 tsc UNITED STATES
- o NUCLEAR REGULATORY COMMISSIO'N f
7, REGION ll
., j ATLANTA FEDERAL CENTER
c 51 FORSYTH STREET. SW. SUITE 23T25 g
ATLANTA. GEORGIA 30303-3415
.....
August 19, 1993 Virginia Electric and Power Company !
ATTN: Mr. H. Ashley Royal . Superintendent Nuclear Training North Anna. Power Station P. O. Box 402 Mineral. VA 23117 SUBJECT: NORTHANNAEXAMASSIGNMENTS-REPORTN05.50-338/98-301AND50b3
Dear Mr. Royal:
You are authorized to administer initial written licensing examinations in accordance with NUREG 1021. Operator Licensing Examiner Standards. to the i applicants listed below on August 27. 1998. NRC Region II operator licensing '
staff will administer the operating tests. Either Larry Mellen at (404) 552-4531 I or myself will be available to answer questions on examination administration before or during the exam.
APPLICANT DOCKET NO. EXAMINATION TYPE
'
Charles A. Briley 55-22323 R0 Ronald D. Butler Jr. 55-22324 RO Edward J. Patrick. Jr. 55-22325 RO John W. Pfeiffer 55-22325 R0 Reginald T. Robinson 55-22327 R0 Robert E. Thompson 55-22329 R0 *
Manuel M. ValeCruz 55-22330 RO Eric F. Vestre 55-22331 RD Billy E. Standley. Jr. 55-22328 SRO I Vicky A. Harte 55-21415 SRO U John M. Kernisky 55-21724 SRO U Milton W. Hunden 55-20973 SRO U Mark A. Schry 55-21417 SRO U Douglas R. Spears 55-21418 SRO U Robert T. Williamson. Jr. 55-20550 SRO U l
. . .
_ - - _ _ ___-_ __
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Facility and Location: North Anna Nuclear Station Facility Contact: Joseph B. Scott. Jr.
Chief Examiner: Richard S. Baldwin Date and Times (Start /Stop) of Written Examination: August 27. 1998 10:00 a.m - 2:00 p.m Dates of 0perating Tests: Weeks of August 17 and 31. 1998
Sincerely
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Thomas A. Peebles. Chief Operator Licensing and Human Performance Branch Division of Reactor Safety
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l A a n n .r/m f/ O - 9 8- a o i U.S. Nuclear Regulatory Commission North Anna Power Station Written Examination Applicant Information Name: Region: II Date: North Anna Power Station - Units 1 & 2 License Levei[ RO Reactor Type: Westinghouse Start Time: Finish Time:
Instructions:
Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. The passing grade requires a final grade of at least 80.00 percent.
Examination papers will be collected four hours after the examination starts.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results Examination Value Points
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Applicant's Score Points Applicant's Grade Percent
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j' DISTRIBUTION CODE IE42 t . -
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NAME
[a][b][c][d] 1. [a] [b] [c] [d] 26.
[a][b][c][d] 2. [a] [b] [c] [d] 27.
[a][b].[c][d] 3. [a] [b] [c] [d] 28.
~[a][b][c][d] 4. [a] [b] [c] [d] 29.
[a]ib][c][d] 5. [a] [b] [c] [d] 30.
[a][b][c][dj 6. [a] [b] [c] [d] 31.
[a]b][c][d] 7. [a] [b] [c] [d] 32.
[a][b][c][d] 8. [a] [b] [c] [d] 33.
[a] [b] [c] [d] 9. [a] ['] [c] [d] 34.
[a] [b] [c] [d] 10. [a] [b] [c] [d] 35.
[a] [b] [c] [d] 11. [a] [b] [c] [d] 36.
[a] [b] [c] [d] 12. [a] [b] [c] [d] 37.
[a] [b] [c] [d] 13. [a] [b] [c] [d] 38.
[a] [b] [c] [d] 14. [a] [b] [c] [d] 39.
[a] [b] [c] [d] 15. [a] [b] [c] [d] 40.
[a] [b] [c] [d] 16. [a] [b] [c] [d] 41.
[a] [b] [c] {d] 17. [a] [b] [c] [d] 42.
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[a] [b] [c] [d] 18. [a] [b] [c] [d] 43.
[a] [b] [c] [d] 19. [a] [b] [c] [d] 44. l
[a] [b] [c] [d] 20. [a] [b] [c] [d] 45. !
[a] [b] [c] [d] 21. [a] [b] [c] [d] 41
[a] [b] [c] [d] 22. [a] [b] [c] [d] 47.
[a] [b] [c] [d] 23. [a] [b] [c] [d] 48.
{a] [b] [c] [d] 24. [a] [b] [c] [d] 49.
[a] [b] [c] [d] 25. [a] [b] [c] [d] 50.
.. . .
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-. _ _
NAME
[a] [b] [c] [d] 51. [a] [b] [c] [d] 76.
[a] [b] [c] [d] 52. [a] [b] [c] [d] 77.
[a] [b] [c] [d] 53. [a] [b] [c] [d] 78.
[a] [b] [c] [d] 54. [a] [b] [c] [d] 79.
[a] [b] [c] [d] 55. [a] [b] [c] [d] 80.
[a] [b] [c] [d] 56. [a] [b] [c] [d] 81.
[a] [b] [c] [d] 57. [a] [b] [c] [d] 82.
[a] [b] [c] [d] 58. [a] [b] [c] [d] 83.
[a] [b] [c] [d] 59. [a] [b] [c] [d] 84.
[a] [b] [c] [d] 60. [a] [b] [c] [d] 85. _
[a] [b] [c] [d] 61. [a] [b] [c] [d] 86.
[a] [b] [c] [d] 62. [a] [b] [c] [d] 87.
[a] [b] [c] [d] 63. [a] [b] [c] [d] 88.
[a] [b] [c] [d] 64. [a] [b] [c] [d] 89.
[a] [b] [c] [d] 65. [a] [b] [c] [d] 90.
[a] [b] [c] [d] 66. [a] [b] [c] [d] 91.
[a] [b] [c] [d] 67. [a] [b] [c] [d] 92.
[a] [b] [c] [d] 68. [a] [b] [c] [d] 93.
[a] [b] [c] [d] 69. [a] [b] [c] [d] 94.
[a] [b] [c] [d] 70. [a] [b] [c] [d] 95.
[a] [b] [c] [d] 71. [a] [b] [c] [d] 96.
[a] [b] [c] [d] 72. [a] [b] [c] [d] 97.
[a] [b] [c] [d] 73. [a] [b] [c] [d] 98.
'[a] [b] [c] [d] 74. [a] [b] [c] [d] 99.
[a] [b] [c] [d] 75. [a] [b] [c] [d] 100.
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QUESTION: 001 (10)
Unit 1 is operating at 28% power when all three "A" RCS loop flows and "A" RCP amps suddenly decrease to minimum. The breaker for the "A" RCP is still closed. Select the reactor protection system response to this event.
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a. Automatic reactor trip since poweris > P-10. I b. Automatic reactor trip only after the RCP breaker is opened
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c. No automatic reactor trip due to RCP breaker remaining closed.
d. No automatic reactor trip due to < P-8.
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QUESTION: 002 (1.0) :
t Select the one turnover aid that is NOT required to be prepared by the ofTgoing operator. t
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a. Verbal list of applicable shift orders.
b. Printout of the watchstation out-of-spec's. '
c~ Copy ofupcoming pts.
d. All applicable LOG-14s. :
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QUESTION: 003 (1.0)
Unit I hasjust been ramped to 100% following a refueling outage. You have relieved as the OATC and on your first set oflogs identify the following data points:
- Tavg "A" - 581 F, "B" - 580.5 F, "C" - 581 F e N41 - 100%, N42 - 99%, N43 - 100%, N44 - 100%
. Loop delta T "A" - 101%, "B" - 101.5%, "C" 101%
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Steam flow (1.0 X 10E+6 lbm/hr) "A" 4.3, "B" - 4.4, "C" - 4.35 Feed flow (1.0 X 10E+6 lbm/hr) "A" - 4.3, "B" - 4.45, "C" - 4.4
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+ First stage pressure - PT-1446 - 590 p' g, PT-1447 - 595 p ;
- Generator power- 962 MW Which of the following is correct concerning the reactor power status?
a. Reactor power is 100%, rescale loop delta-Ts to 100%.
b. Reactor power is 100% , but N42 needs to be adjusted to 100%.
I c. Reactor power is greater than 100%, power needs to be reduced immediately. I d. Reactor power is greater than 100%, NIs need to be adjusted up, then power reduction is required. l RO EXAM - REV. 2
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QUESTION: 004 (1.0)
Which one of the following is correct concerning placing N/A in the sign off block for a PT procedure step?
a. Steps that are being performed to prove operability may be marked N/A if a component (i.e. vent valve for a pomp) is tagged for short term.
b. Prior to marking a s'.ep N/A, concurrence must be obtained from a second individual (one ofwhom is an RO).
c. Steps may be marked N/A if the steps cannot be performed, provided they are annotated on the procedure remarks section and signed by another operator.
d. If the procedure is entered at some point other than the beginning, steps prior to the entry point must be marked N/A (assuming a specific sequence is required).
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RO EXAM - REV. 2
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QUESTION: 005 (1.0)
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Which one of the following describes the correct valve lineup for the given blender mode selector l switch position? -
1-CH-FCV-1113A - boric acid to blender 1-CH-FCV-1113B - blender to charging pump suction 1-CH-FCV-1114A - PG to blender 1-CH-FCV-1114B - blender to top of VCT a. BORATE: 1-CH-FCV-1113 A controlling,1-CH-FCV-1113B open,1-CH-FCV-1114A closed,1-CH-FCV-1114B closed.
b. MANUAL: 1-CH-FCV-1113A controlling,1-CH-FCV-1113B open,1-CH-FCV-1114A controlling,1-CH-FCV-1114B open.
c. DILUTE: 1-CH-FCV-1113 A closed,1-CH-FCV-1113B open,1-CH-FCV-1114A controlling,1-CH-FCV-1114B open, d. ALTERNATE DILUTE: 1-CH-FCV-1113 A closed,1-CH-FCV-1113B closed,1-CH-FCV-1114A controlling,1-CH-FCV-1114B closed.
RO EXAM - REV. 2
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QUESTION: 006 (1.0) :
i When tagging a patchcord to disable an annunciator, the is responsible for placing !
the annunciator in the computer disabled annunciator list. ,
a. unit CRO l
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c. unit SRO d. independent verifier of the tag
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QUESTION: 007 (1.0)
To prepare for maintenance, operators are tagging charging pump 2-CH-P-1B, which requires both the charging side and service water side to be drained. What actions must be taken to reduce the hazard of radioactive contamination of the Auxiliary Building atmosphere?
a. Drain all service water to a tan bladder. ;
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b. Drain charging water directly to the auxiliary building sump.
c. Drain charging water to a CARBOY. j d. Place auxiliary building general exhaust through the filters.
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Following a steam generator tube rupture, what actions are taken to prevent the release of radioactive efIluent to the atmosphere while maintaining the core in a safe condition in accordance ,
with 1-E-3 "SGTR"? l
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a. Identify the affected SG, isolate the afTected RCS loop, cooldown the RCS and then l
depressurize the RCS.
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b. Isolate the afTected SG, depressurize the RCS, then commence an RCS cooldown.
c. Identify the affected SG, isolate the affected SG, cooldown the RCS and then depressurize the RCS.
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l d. Identify the affected SG, isolate the affected SG, cooldown the RCS and then depressurize I the affected SG.
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QUESTION: 009 (1.0)
The crew is responding to a loss ofinstrument air using 1-AP-28 when the RO identifies that pressurizer levelis lowering rapidly, requiring a reactor trip. How should the procedures be used ;
at this time?
a. Exit 1-AP-28 and immediately initiate performance of1-E-0.
b. Immediately initiate performance of 1-E-0 and continue performance of 1-AP-28 as :
resources permit. '
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c. Continue pe6ormance of 1-AP-28 until an automatic reactor trip occurs, then exit 1-AP-28 and initiate performance of 1-E-0. i d. Continue performance of 1-AP-28 until completion, then if the cause for the pressurizer level decrease has not been corrected, trip the reactor and perform 1-E-0.
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i QUESTION: 010 (1.0)
In accordance with the Operations Standard titled " Communications," which of the following is correct concermng communications during performance ofEOPs?
l l a. US: " Don, stop RCS depressurization," RO (after closing PRZR PORV): "RCS depressurization is stopped," US: "RCS depressurization is stopped," RO: " Correct."
b. US: " Bob, verify pressurizer level > 28%," RO: "Yes, level is normal," US: " Understand, !
l level normal," RO: " Correct."
l l c. US: " Reduce AFW flow to 680 gpm total," BOP: " Lower flow to 680 gpm," US:
i " Correct." ;
d US:" Tom, verify RCS Tavg is 547 F," RO:"Yes, RCS Tavg is 547 and stable," US:
" Understand, Tavg stable at 547."
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QUESTION: 011 (1.0)
The unit has experienced a loss of heat sink. Why do the EOPs require the reactor coolant pumps '
to be stopped?
a. Limit the amount of heat input to the RCS.
b. Conserve RCS inventory.
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I c. Prevent damage to the RCP seals. ,
d. Lower the heat load on the component cooling water system.
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QUESTION: 012 (1.0)
Given the following plant conditions:
A LOCA inside of containment occurred at 1035
- An ALERT was declared at 1040
. The initial notification to the state and local governments was done at 1050 At 1055, a security ofIicer reports that steam has just started blowing from the equipment hatch (EPIP classification did not change)
In accordance with EPIP-2.01, what is the earliest time a follow-up report is required to the State EOC7 a. Immediately, b. 1125.
c, 1155.
d. Following the next emergency upgrade.
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QUESTION: 013 (1.0)
Due to a controller malfunction,1-CC-TCV-106 (NRHX outlet) is in manual control. The crew now desires to place another letdown orifice in service to increase purification flow. How will ;
RCS temperature respond to this letdown flow change and why?
a. Increase due to the mixed bed IX releasing boron.
b. Decrease due to the mixed bed IX releasing boron.
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c. Increase due to the mixed bed IX absorbing boron.
d. Decrease due to the mixed bed IX absorbing boron. .
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QUESTION: 014 (1.0)
Unit 1 is in Mode 4 and has been shutdown for 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> when "RHR SYSTEM LO FLOW"
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annunciator is received. RHR flow and amps are stable. What is the alarm setpoint for the Low Flow condition and what are your required actions? Attached is a copy of the applicable AR.
a. < 3200, increase RHR flow.
b. < 3200, Go to 1-AP-11 "Inss of RHR "
c. < 2500, increase RHR flow.
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d. < 2500, go to 1-AP-11 " Loss of RHR "
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QUESTION: 015 (1.0)
While performing a reactor startup, the 1/M plot is " Conservative" if the projected point of criticality starts out and, as rods are withdrawn, a. 10 steps above the ECP lower limit; stays at 10 steps above the ECP lower limit b. 10 steps below the ECP upper limit; stays at 10 steps below the ECP upper limit c. above the ECP window; works into the ECP window d. below the ECP window; works into the ECP window
RO EXAM - REV. 2
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QUESTION: 016 (1.0)
A failure to perform actions of 1-AP-28, " Loss ofInstmment Air," and shut the MSTVs when instrument air pressure is < 70 psig could result in:
a. a loss of heat sink.
b. a safety injection.
c. an inability to close the MSTVs.
d. excessive cooldown.
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QUESTION: 017 (1.0)
During a shutdown for refueling outage, letdown is diverted to the gas stripper in degas mode to !
reduce concentration of the RCS so that a. hydrogen; explosive atmosphere will not exist when the RCS is opened i b. hydrogen; gasses won't come out of solution causing a reactor vessel head bubble c. nitrogen; formation of nitric acid will be minimized when the RCS is opened ,
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d. nitrogen; gasses won't come out of solution causing a reactor vessel head bubble l
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QUESTION: 018 (1.0)
During radiography in the auxiliary building, area radiation monitor 1-RM-RMS-154 Hi and Hi Hi alarms come in. Once radiography is complete, what actions are required to reset the alarms?
a. Place the Operator Selector Switch in RESET then back in OPERATE to reset both the Hi and Hi Hi alarms.
b. Place the Operator Selector Switch in RESET then back in OPERATE to reset the Hi Hi alarm, the Hi alarm will clear when the radiation level is below the alarm setpoint.
c. Both the Hi and Hi Hi alarms will automatically clear once the radiation level is reduced to below their respective setpoints.
d. Dispatch an operator to locally reset the Hi and Hi Hi alarms; place the Operator Selector Switch in RESET then back in OPERATE.
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RO EXAM - REV. 2
QUESTION: 019 (1,0)
Unit I hasjust commenced hogging down containment following a refueling outage when the .
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Unit 2 RO notices megawatts decreasing and degrading condenser vacuum. Which of the following potential contributors to the loss of unit-2 condenser vacuum could be caused by j hogging unit-1 containment? -
r a. Blown air ejectorloop seal. I
b. Gland steam pressure lowering.
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c. Condenser vacuum breaker drifling open.
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d. Low auxiliary steam pressure at the air ejectors. ;
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QUESTION: 020 (1.0) j 1-FP-P-2 (Diesel-driven fire protection pump) will be tagged for maintenance. In accordance with 0-MOP-52.1, what compensatory actions are taken to provide an additional source offire protection water?
a. Open 1-FP-246 (Warehouse #5 Crosstie). '
b. Stage a fire truck inside the protected area.
c. Align a temporary diesel driven fire pump to the fire water header.
d. Route hoses from hose house A - D to hose house E - H.
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t QUESTION: 021 (1.0) !
l ~ Which one of the following is the power supply to RHR supply 1-RH-MOV-170l? !
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a. 1-EP-MCC-lJ1-2S.
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b. 1-EP-MCC-1B2-2.
c. 1-EP-MCC-lG2-1,
1 d. 1-EP-MCC-lCl-2.
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QUESTION: 022 (1.0) -
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Which of the following would result in a greater dispersion of gases while releasing a waste gas j decay tank? l a. Increasing delta T. <
- b. Decreasing Sigma Theta.' ,
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' c. Temperature inversion. ;
i d. Stability class change from C to B. I i
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RO EXAM - REV. 2
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l QUESTION: 023 (1.0)
l Given the following conditions:
l i . A large-break LOCA has occurred.
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The crew responded in accordance with 1-E-0, " Reactor Trip or Safety Injection."
- e No RNO actions were required.
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l The crew has just transitioned to 1-E-1, " Loss ofReactor or Secondary Coolant," from I-E-0 at step 26 due to containment pressure.
- Containment pressure reached 29 psia on 1-LM-PR-110B.
- RCS average temperature is 420*F.
- RCS pressure is stable at about 200 psig.
Which ONE of the following statements describes the primary method of decay heat removal?
a. Heat transfer between the RCS and the S/Gs due to natural circulation flow.
b. Heat transfer between the RCS and the S/Gs due to RHR forced circulation flow.
c. The injection of water from the containment sump and the removal of steam / water out the break.
d. The injection of water from LHSI and the removal of steam / water out the break.
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QfJESTION: 024 (1.0)
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l-l With both units at power, it is desired to start the standby main feedwater (MFW) pump and
- secure one of the running MF_W pumps. When performing this evolution, the procedure l be present because
! I a. need not; this is a skill of the craft evolution l
b. . must; it affects an "important to safety" system
c. must; the evolution requires verification to be documented by initials
d. need not; this is a frequently performed evolution that can be committed to memory l
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QUESTION: 025 (1.0)
Assuming the entire body has received an acute dose (50 rem) ofionizing radiation, what would be the prompt affects if no medical treatment was received?
a. No observable effects.
l b. Slight blood changes with no other observable effects.
c. Vomiting within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, with fatigue and loss of appetite.
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d. Severe blood change accompanied by hemorrhaging.
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QUESTION: 026 (1.0)
Unit 1 is at 100% power when annunciator A-H7, A.F.D. MONITOR, alarms. The RO determines that rod H-14 in control bank D has stepped into the core approximately 100 steps.
Which ONE of the following describes the effect this event will have on core flux patterns?
a. There should be a large variation on axial flux difference indicators and on power range detectors at the same elevation, b. There should be a large variation on axial flux difference indicators but a minimal effect on power range detectors at the same elevation.
c. There should be minimal effect on axial flux difference indicators but a large variation on power range detectors at the same elevation.
d. There should be minimal effect on axial flux difference indicators and on power range detectors at the same elevation.
RO EXAM - REV. 2
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QUESTION: 027 (1.0)
Following a large break LOCA the crew aligns the Safety Injection System for cold leg recirculation mode.
Which one of the following reasons is correct for closing 1-CH-MOV-1370 (RCP Seal Injection MOV)?
a. To maximize the amount of safety injection flow.
b. To prevent runout of the operating LHSI pump should the other LHSI pump fail.
c. To prevent damaging the RCP seals by flowing sump water to the seal faces.
d. To minimize the pressure transient felt by the #1 seal as the LHSI discharge is aligned to the HHSI suction.
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RO EXAM - REV. 2
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QUESTION: 028 (1.0)
Unit I has experienced a loss of feedwater ATWS and the operating crew is presently in 1-FR-S.I. The BOP is unable to trip or runback the turbine, What actions are required for the turbine trip failure and why?
a. Close the MSTVs and bypasses; assist in shutting down the reactor by adding negative reactivity due to moderator temperature defect.
b. Close the NRVs and bypasses; assist in shutting down the reactor by adding negative reactivity due to moderator temperature defect.
c. Close the MSTVs and bypasses; minimize use of the SG inventory, d. Close the NRVs and bypasses; minimize use of the SG inventory.
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QUESTION: 029 (1.0)
Unit 1 is in the process of a reactor startup with power at 1300 cps on Source Range N-31 and 1400 cps on N-32. Th RO is in the process of withdrawing control rods when a loss ofvital bus 1-II occurs. The operator releases the in-hold-out switch. What will N-32 stanup rate indication do and why?
a. Go to 0 dpm due to a loss of power to the instrument.
b. Immediately go to -1/3 dpm due to an automatic reactor trip.
c. Remain slightly positive for a short time then decrease to zero due to the reactor being suberitical.
d. Continue to increase in the positive direction due to the feedwater heater high level diverts failing open.
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i QUESTION: 030 (1.0)
A reactor startup is in progress with Source Range counts indicating 2.7 x 10E+4 cps on N-31 and N-32. Intermediate range detector N-35 indicates 3 X 10E-11 and N-36 indicates 1 X 10E- ;
11. What actions should be performed and why? '
a. Enter the AP for a failed intermediate range detector, maintain power < P-6, N-35 is undercompensated.
b. Enter the AP for a failed intermediate range detector, maintain power < P-6, N-36 is failed low.
c. Continue the startup, power is too low to determine if any intermediate range detector has failed. l i
d. Enter the AP for a failed intermediate range detector, continue the startup, adequate protection and monitoring is available with one intermediate range detector, i
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QUESTION: 031 (1.0)
Given the following conditions:
A small break LOCA has occurred
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The crew responded IAW EOPs and tripped the RCPs when required
The crew is currently in 1-ES-1.2, " Post LOCA Cooldown and Depressurization"
. RCS Pressure is 1490 psig.
Wide range Tcs are 505 F and slowly decreasing
Wide range Ths are 515 F and slowly decreasing
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CETCs are 581 F and stable e Containment pressure is 10 psia e
Containment radiation is 5.0 X 10E+1 R/hr e SG narrow-range levels are being maintained at a minimum of 40%
SG pressures are 715 psig snd decreasing slowly According to 1-ES-1.2, the requirements for natural circulation:
a. are not met, since CETCs are not decreasing.
b. are not met, since there is inadequate subcooling.
c. are not met, since SG parameters are not satisfied.
d. are met.
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l QUESTION: 032 (1.0)
Assume that "A" SG has faulted , the crew has proceeded through the EOPs to isolate the faulted i
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SG. Soon afterward, the other 2 SGs are determined to be faulted and the crew transitions to 2- ,
ECA-2.1, " Uncontrolled Depressurization of All Steam Generators." How should feedwater flow be controlled to all SGs?
a. 100 gpm to "B" and "C" SGs, "A" remain isolated. !
b. Isolate feed flow to all SGs.
c. 100 gpm to each SG.
d. Continue to feed "B" and "C" SGs until narrow range level >11%.
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QUESTION: 033 (1.0) ;
Unit 1 is in a refueling outage with the following conditions:
- The "A" RHR pump is running, returning to "C" loop.
. The "A" SW supply header is tagged out.
. 1-CC-E-1 A and 1-CC-E-1B are aligned to the "B" SW header. !
- 2-SW-P-1 A and 2-SW-P-1B are running.
- Solid State Protection system fuses are removed.
Which of the following conditions will result in a loss of RHR on Unit 17 a. Unit 1 SI.
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b. Unit 2 SI.
c. Unit 2 CDA.
d. Loss of1J 4160V emergency bus.
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QUESTION: 034 (1.0) :
Unit I control room operator received annunciator D-C8 " SMOKE DET SYS SMOKE INDICATION TROUBLE" How would the OATC determine which area was in alarm? ;
i a. Look at the P250 computer printout.
b. Call up the fire detection screen on SPDS.
c. Observe the P-250 CRT display for the latest alarm. :
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d. Look at the Robert Shaw panel to determine the affected zone.
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QUESTION: 035 (1.0) .
If a control room evacuation is required , where could you monitor reactor coolant system pressure from outside the control room?
a. Auxiliary Building penetration area.
d b. Safer.: ads 2 level.
c. Auxiliary Shutdown Panel.
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d. 1H EDG Control Room Emergency (CRE) panel. i
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QUESTION: 036 (1.0)
Hydrogen peroxide was just added to the Unit 2 Reactor Coolant System resulting in an increase in the primary coolant activity. The first indication that the activity level has risen will be seen on :
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and to lower the activity level, the crew should
a. Containment paniculate radiation monitor,2-RMS-RM-259; increase flow through the i letdown demineralizers.
b. Letdown radiation monitor,2-CH-RI-228; increase flow through the letdown !
deminerahzers.
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c. Containment paniculate radiation monitor,2-RMS-RM-259; decrease flow through the letdown demineralizers.
d. Letdown radiation monitor 2-CH-RI-228; decrease flow through the letdown demineralizers.
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RO EXAM - REV. 2 j
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QUESTION: 037 (1.0) .
Which one of the following is the first required action if, during implementation of 1-E-0, the turbine fails to trip automatically and the pushbuttons fail to trip the turbine?
l a. Close the NRVs and bypasses. '
b. Dispatch an operator to locally trip the turbine.
c. Manually open G-12 and the exciter field breaker d. Place both EHC pumps in PTL ,
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RO EXAM - REV_ 2
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QUESTION: 038 (1.0)
During performance of 1-E 3, the operator, when directed to adjust the setpoint on the ruptured SG's PORV to 5.5, mistakenly adjusts it to a setting of 5.8. At what pressure will the PORV lift?
a. 1035 psig b. 1050 psig c. 1065 psig d. 1091 psig
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RO EXAM - IGV. 2
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QUESTION: 039 (1,0)
A loss of feedwater has required the crew to trip the reactor and implement 1-E-0. The BOP ;
notices 1-FW-FI-100B is indicating 0 gpm. Which one of the following is a possible cause for these conditions? I
a. 1-FW-PCV-159A closed.
b. 1-FW-PCV-159B closed.
c. 1-FW-HCV-100C closed.
i d. 1-FW-HCV-100B closed.
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RO EXAM - REV. 2
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QUESTION: 040 (1.0)
i Which one of the following sets of conditions provides adequate heat sink if all RCPs are I stopped? '
a. "A" AFW flow 50 gpm,"B" AFW flow 50 gpm, Turbine driven AFW pump flow 300 l gpm.
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b. "A" AFW flow 120 gpm,"B" AFW pump flow 120 gpm, turbine driven AFW pump flow ;
120 gpm. I l
c. "A" SG narrow range level 9%, "B" SG narrow range level 3%, "C" SG wide range level 27%.
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i d. Adverse containment conditions exist, "A" SG narrow range level 18%, "B" SG narrow l range level 11%, "C" SG narrow range level 15%. .
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RO EXAM - REV. 2
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QUESTION: 041 (1.0)
During a Unit I refueling outage, the core onload is 25% complete. Which one of the following is a positive indication that criticality has occurred or is imminent during the onload?
a. 1/M nlot predicts criticality when 187th assembly is loaded.
b. Manipulator crane R/M alarm.
c. Containment evacuation alarm.
d. High flux at shutdown alarm.
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RO EXAM - REV. 2
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QUESTION:~ 042 (1.0) ;
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Following a LOCA on Unit 1, the design of containment and containment spray systems will ensure that:
a. peak containment pressure will be limited to the upper containment design pressure of 60 psig.
b, safety-related equipment will be subject to greater-than-design temperatures for no longer than 15 minutes. >
c. containment internal pressure can be returned subatmospheric within 30 minutes. ;
d. containment internal pressure remains subatmospheric after 60 minutes.
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RO EXAM - REV. 2
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QUESTION: 043 (1.0) . !
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j; Unit'l has experienced a large break LOCA. The crew has just transitioned from 1-E-0, to 1-E-l t-
-l' The following conditions exist:
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- "A" S/G N/R level is 8%, AFW flow is 120 gpm ;
e- "B" S/G N/R levelis 2%, AFW flow is 110 gpm
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- "C" S/G N/R levelis 2%, AFW flow is 110 gpm I e- RCS subcooling is 12 F e 'No RCPs are operating e. Core exit TCs are 825 F-l L e RVLIS full rangeis 53% !
- - ' Containment pressure is 37 psig
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What is the correct procedure to use for these conditions? !
a. Transition to 1-FR-C.2. .
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b. Transition to 1-FR-C3 l- c. Transition to 1-FR-H.1. .
I dc Transition to 1-FR-Z.l. 2
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RO EXAM - REV. 2
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h I QUESTION: 044 (1.0)
Unit 1 is operating at 50% power when the crewis required to evacuate the control room due to noxious fumes. Under which one of the following conditions would emergency boration be required in accordance with 1-AP-20, " Operation from the Auxiliary Shutdown Panel"?
a. The control room is still uninhabitable 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> following the reactor trip, b. Cooldown of the RCS to 350 F is required. '
c. I control rod remains fully withdrawn from the core after the reactor trip.
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d. IRPIs in the main control room indicated 8 rods remained 6 steps out of the core, the remaining rods are fully inserted. !
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QUESTION: 045 (1.0)
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While the plant is holding at 20% power, "B" RCP trips and causes a transient in "B" SG. ;
Select the statement below that correctly describes how steam flow and water level in "F," SG :
respond initially to the trip of the "B" RCP. t
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a.- Steam flow decreases, level decreases i
b. Steam flow decreases, level increases c. Steam flow increases, level increases
d. Steam flow increases, level decreases l
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QUESTION: 046 (1,0)
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l Unit 2 hasjust been tripped from 100% power due to a stuck open pressurizer safety valve. The crew hasjust tripped the reactor coolant pumps due to loss of subcooling. Pressurizer levelis i 70%. How would RVLIS full range respond when saturation conditions are reached in the RCS? i i
a. Decrease, then increase.
I b. Decrease rapidly. ;
c. Increase, then decrease.
d. Increase rapidly.
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i l ' QUESTION: 047 (1.0) L With the pressurizer level control selector switch in the 461/460 position, a failure causes the l following plant events to occur in the given sequence (assume no operator actions are taken):
1) Charging flow reduced to minimum 2) Pressurizer level decreases 3) Letdown secured and PRZR heaters off 4) PRZR level increases until high level trip j i
Which one of the following failures occurred? !
a. Level channel 460 failed low. l l
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b. . Level channel 460 failed high. ;
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c. Level channel 461 failed low. !
d. Level channel 461 failed high. l I
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RO EXAM - REV, 2
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QUESTION: 048 (1.0)
, i Unit I has experienced a loss of coolant accident and the crew is presently in 1-ES-1.2 " Post LOCA Cooldown and Depressurization" cooling down and depressurizing the RCS to refill the i pressurizer. Required subcooling is lost during the depressurization. How will the required ;
subcooling be re-establi:hed after the depressurization is stopped? l
! a. Stop the RCS cooldown. :
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b. Continue the RCS cooldown.
c. Energize pressurizer heaters. f
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d. De-energize pressurizer heaters.
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RO EXAM - REV. 2
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QUESTION: 049 (1.0) ;
When using 1-ES-1.1 "SI Termination" to recover from a safety injection, does the crew open j the BIT recirculation valves when isolating the BIT? ;
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a. Yes, to prevent overpressurizing the BIT while it is isolated .
b. Yes, to ensure the BIT is full by verifying recire flow.
c. No, to prevent diluting the inservice boric acid storage tank. ,
d. No, to ensure the inservice boric acid storage tank levelis maintained above the T.S. .
minimum. .
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RO EXAM - REV. 2
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QUESTION: 050 (1.0)
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A dropped rod has caused quadrant power tilt ratio (QPTR) to exceed its T.S. limit and cannot be restored, therefore power must be reduced to < 50% power. Why is power required to be less than 50%7 r i
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a. Regardless of QPTR value, when < 50% power, minimum DNBR is assured for Condition
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I and Condition II events. .
i b. Accident analysis for a large break LOCA indicates that core damage cannot occur when initial reactor poweris < 50%.
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c. When power is less than 50%, QPTR is assured to be within normal T.S. limits by virtue I of core design with a single dropped rod.
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d. Power must be lowered to allow reactor engineering to perform an incore flux map, to confirm that an asymmetric power distribution is occurring. ;
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RO EXAM - REV. 2 l
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QUESTION: 051 (1.0)
Which one of the following statements concerning pressurized thermal shock (PTS)is tme?
a. The reactor vessel heads at North Anna are not susceptible to PTS.
b. Carbon steel components must first be irradiated by an intense neutron flux before PTS becomes a concern.
c. A large break LOCA produces the most severe PTS hazard due to the cold RWST water injected resulting in a rapid RCS cooldown.
d. A steam break creates a high potential for PTS due to the large cooldown followed by the rapid repressurization of the RCS.
, RO EXAM - REV. 2
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QUESTION: 052 (1.0)
A station blackout has occurred and the crew is attempting to restore power to the IH emergency bus in accordance with 1-ECA-0.0 " Loss of All AC Power". The 1H EDG is running but the output breaker (15H2) is not closed. While attempting to close the output breaker manually using i attachment #4 of 1-ECA-0.0, which of the following items will prevent the output breaker from closing?
a. Incoming and running voltages not within 2 volts of each other.
I' b. 4160V Emer Gen Supply Feed to Bus 1H synchronizing switch in OFF. l
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c. Synchronizing scope rotating in the counter clockwise direction.
l d. Emergency diesel generator speed at < 880 RPM.
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RO EXAM - REV. 2
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QUESTION: 053 (1.0)
Unit 1 is operating at 100% power when a loss of the 1-III vital bus occurs. The operating crew should:
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a. perform 1-AP-3, " Loss of Vital Instrumentation," which will direct initiation of the appropriate MOP for restoration of the vital bus.
b. perform 1-AP-3, " Loss of Vital Instrumentation," to completion, then enter 0-AP-10, i
" Loss of Electrical Power," to restore power.
c. enter 0-AP-10, " Loss ofElectrical Power," and stabilize the unit in accordance with the
" Unit 1 CRO Loss ofPower Actions" attachment. ,
I d. perform the immediate actions of 1-AP-3, " Loss of Vital Instrumentation," to stabilize the l unit, then enter 0-AP-10, " Loss ofElectrical Power."
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l QUESTION: 054 (1.0)
l If a PRZR safety valve or a PRZR PORV were to fail 10% open, which one of the following could NOT be used to differentiate between whether it was the safety or PORV that was open?
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a. Tailpipe temperature.
b. Acoustical Monitor. j
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c. Valve position indicating light.
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l d. Press Safety Valve or PORV Open annunciator. '
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l RO EXAM - REV. 2 l
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QUESTION: 055 (1.0)
As directed by 1-ECA-0.0," Loss of All AC Power," the crew places the charging pumps in PTL.
The defeat of the charging pump automatic start is to prevent:
a. an uncontrolled over-pressurization of the RCS , and the resulting increased loss ofRCS inventory through the RCP seals when power is restored.
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b. an excessive cooldown of the RCS due to injection of cold RWST water when power is restored.
c. the unnecessary use of water that may be needed for long term recovery.
d. a LOCA caused by thermal shock of the RCP seals when power is restored.
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RO EXAM - REV. 2 l
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QUESTION: 056 (1.0)
At 4 % power during a startup on Unit I with the steam dumps in manual due to a failure of1-MS-PT-1464 (MS Hdr Pressure) the RO withdraws rods 2 steps. The outward rod motion continues after the IN-HOLD-OUT switch is released. As the rods step out, reactor power will and steam flow will a. increase; increase b. increase; remain the same c. remain the same; increase d. remain the same; remain the same
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RO EXAM - REV. 2
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QUESTION: 057 (1.0)
D A leak on the letdown line caused pressurizer level to drop. Given that the leak is isolated and pressurizer levelis subsequently restored, which one of the following describes the effect of the magnitude oflevel lost on the time required for PRZR pressure to return to normal? (Assume no operator actions after level restoration)
a. The smaller the initial decrease, the less time it will take due to the integral reset of the master controller.
b. The smaller the initial decrease, the longer it will take due to the integral windup of the master controller. ]
c. The larger the initial decrease, the less time it will take due to the insurge of water from the "C" hot-leg.
d. The larger the initial decrease, the longer it will take due to the insurge of relatively colder water.
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l QUESTION: 058 (1.0)
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During a reactor startup, what are the indications of the reactor achieving criticality?
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1 a. Increase in RCS temperature, rise in pressurizer level, SG swell.
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b. Stable positive startup rate v/ith no positive reactivity addition.
l c. Stable positive startup rate during boron dilution. j d. Stable positive startup rate during rod withdrawal.
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RO EXAM - REV. 2
QUESTION: 059 (1.0)
Given the following conditions:
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A steam break occurred inside ' Unit I containment.
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The immediate operator actions of 1-E-0 " Reactor Trip or Safety Injection" have been performed.
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Containment pressure has exceeded 28 psia and the crew has performed the continuous action steps for CDA actuation.
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SG pressure is 350 psig and lowering, "B" and "C" SG pressures are 825 psig.
Which one of the following caused the main steam line isolation?
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a. Manualinitiation of CDA. !
I b. High steam line differential pressure.
c. Intermediate high containment pressure.
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d. Phase A containment isolation signal.
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O RO EXAh! - REV. 2
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QUESTION: 060 (1.0)
O During the initial startup of an RCP with the pressurizer solid following a refueling outage, in
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accordance with OP-5.2, RCS pressure is controlled by; a. adjusting the charging flow control valve (1-CH-FCV-1122) in manual. '
b. manually adjusting charging flow through 1-CH-289 (1-CH-FCV-1122 manual bypass).
c. manual operation of 1-CH-PCV-ll45 (Letdown Pressure Control Valve) using the raise and lower pushbuttons. ,
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d. automatic operation of 1-CH-PCV-1145 (Letdown Pressure Control Valve) with adjustments to the potentiometer.
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RO EXAM - REV. 2 I l
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Ei QUESTION: 061 (1.0) :
(3 k e' Select the set of conditions that will cause an automatic safety injection.
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a. Manualinitiation ofphase A isolation.
b. PRZR pressure channel one 1860 psig, channel two 1870 psig, channel three 1865 psig.
c. Turbine load 20%; SG steam flows (in Ib/hr): A - 0.8 E+6, B - 0.9 E+6, C - 1.7 E+6; SG pressures decrease rapidly to 700 psig.
. d. Turbine load 100%; SG steam flows (in Ib/hr): A - 4.2 E+6, B - 4.9 E+6, C - 5 E+6; Loop Th: A - 600 F, B - 568 F, C - 567 F; Loop delta-Ts: A - 50 F, B - 52 F, C - 53 F.
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QUESTION: 062 (1.0)
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If all core exit thermocouples are inoperable during an event in which the RCPs were tripped, what other indication may be used to verify natural circulation cooling is occurring?
a. RCS hot leg temperatures.
b. Reactor coolant loop flow indication. t c. RCS subcooling as indicated on ICCM.
d.' SGlevel rise with feed flow to the SG.
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RO EXAM - REV. 2
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QUESTION: 063 (1.0)
U, The crew is in 1-ECA-0.0 " Loss of All AC Power" when it is necessary to throttle flow from the turbine driven auxiliary feedwater pump (1-FW-P-2) to the SGs due to excessive cooldown.
Safety injection has automatically initiated since entry into 1-ECA-0.0. Why is the BOP unable to .
reduce AFW flow?
a. 1-FW-MOV-100D is powered from the H emergency bus.
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b. 1-FW-MOV-100D is powered from the J emergency bus.
c. Safety injection must be reset prior to throttling the discharge MOV. l
' d. Steam generator levels must be > 18% prior to throttling AFW flow. I i
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O RO EXAM - REV. 2 l
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QUESTION: 064 (1.0)
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Annunciators K-D2, " Rad Monitor System Hi Rad Level ," cnd K-D4, " Rad Monitor Syst Hi-Hi Rad Level," were received due to high radiation on 1-RM-LW-111 (Clarifier Outlet).
Which of the following actions will NOT occur due to this condition?
a. 1-LW-PCV-115 (Liquid Waste TunnelIsol Control) closes. ;
b. Steam Generator Blowdown pumps trip.
c. 1-LW-FCV-100 (Holdup Tank Influent Valve) closes. ;
d. Contaminated Drains Tank pumps trip.
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RO EXAM - REV. 2 i
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QUESTION: 065 (1.0)
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'd The relief office is working in the fuel building performing new fuel receipt inspections and -
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" splashing" the assemblies when the Hi and Hi-Hi alarms are received on 1-RM-RMS-152 "New Fuel Storage Area." :
This condition willisolate MCR ventilation and:
a. dump bottled air and start all 41 and 42 fans.
b. dump bottled air and start all 41 pl 42 fans.
l c. start all 41 and 42 fans, but not dump bottled air.
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d. start all 41 gr 42 fans, but not dump bottled air.
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QUESTION: 066 (1.0) ;
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s Following a turbine runback, the steam dump banks 1 and 2 will TRIP OPEN at error signal, and banks 3 and 4 will TRIP OPEN at error signal.
l I a. 10 F; 16*F :
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!. b. 10 F; 24 F c. 16 F; 24 F
' d.' 16 F; 32'F ,
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RO EXAM - REV. 2
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f QUESTION: 067 (1.0)
Unit 1 was operating at 100% power when a loss of the "H" emergency bus occurred. As the crew was diagnosing the event, "B" steam generator feedwater line severed inside contaimant resulting in containment pressure rising to 34 psig. All safety systems functioned as designed and service water was throttled prior to the event. How is service water flow to the recirc spray heat exchangers affected by this event?
a. Sewice water flow through the "A" and "B" RSHXs will be isolated.
b. Service water flow through the "A" and "C" RSHXs will be isolated.
c. Service water flow through the "A" and "D" RSHXs will be isolated.
d. Service water through all RSHXs will be unaffected. ,
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t RO EXAM - REV. 2
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l QUESTION: 068 (1.0)
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O When a station service bus undervoltage occurs, the associated pressurizer backup heaters after voltage is restored. When an emergency bus undervoltage occurs, the r associated pressurizer backup heaters after voltage is restored.
a. are automatically restored; are automatically restored !
b. are automatically restored; must be manually reset c. . must be manually reset; must be manually reset
d. must be manually reset; are automatically restored !
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O RO EXAM - REV. 2
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QUESTION: 069 (1.0)
If the differential temperature across unit I reactor at 50% power is 30 F, what would be the differential temperature across the reactor at 100% power?
a. 15 F b. 30 F c. 60 F d. 90 F O .
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RO EXAM - REV. 2
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QUESTION: 070 (1.0) 1 l
Given the following table 4.8-1 from Technical Specifications, determine the correct load !
sequencing for the listed components with a loss of power on lH emergency bus. l (Assume that the following components were previously running) l 1. "A" component cooling water pump
2. "A" auxiliary feedwater pump
3. "A" outside recirc spray pump 4. "A" service water pump q a. 4, 1, 2, 3 b. 1, 4, 3, 2
c. 2,1, 4, 3 d. 3,4,2,1 ,
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RO EXAM - REV. 2
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QUESTION: 071 (1.0)
g k ) Unit 1 is operating at 100% p 3wer , when a steam break occurs inside containment. 200 seconds l after the CDA signal was rece ved, the following "A" train containment spray equipment l alignment existed :
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. "A" quench spray pump,1-QS-P-1 A, - RUNNING e "A" quench spray pump discharge valve,1-QS-MOV-101 A - OPEN j
+ "A" chemical addition tank outlet valve,1-QS-MOV-102A, - OPEN
. "A" inside recirc spray pump,1-RS-P-1 A, - NOT RUNNING l
- "A" outside recirc spray pump,1-RS-P-2A, - NOT RUNNING l
. "A" casing cooling pump,1-RS-P-3 A, - NOT RUNNING !
. "A" casing cooling pump discharge VALVE,1-RS-MOV-100A, - OPEN ;
e "A" casing cooling pump discharge,1-RS-MOV-101B, - CLOSED Select the set of components that are out of their required positions given the events that have l occurred.
a. 1-QS-MOV-102A,1-RS-P-1 A,1-RS-P-3 A..
l b. 1-QS-MOV-102A,1-RS-P-1 A,1-RS-P-3 A,1-RS-MOV-101B.
l ('N c. 1 -Q S-MOV- 102 A, 1 -RS-P-2 A, 1 -RS-P-3 A,, 1-RS-MOV-101 B .
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d. 1-RS-P-1 A,1-RS-P-2A,1-RS-MOV-101B.
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RO EXAM - REV. 2
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QUESTION: 072 (1.0)
O With the crew responding to a loss of secondarfheat sink, why is it vital to initiate bleed and feed of the RCS as soon as the criteria are satisfied?
a. RCS pressure boundary could be challenged ifPRZR PORVs are not manually opened.
b. Core damage could result due to inebility to inject high head safety injection flow into the RCS at high RCS pressure, c. Steam generator tubes are no longer covered and the iodine " scrubbing" is no longer occurring on the secondary side resulting in a greater offsite dose rate.
d. IfRCS temperatures are allowed to rise above 1000 F, bleed and feed will not be allowed and transition to 1-FR-C.1 " Response to Loss of Core Cooling" will be required.
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RO EXAM - REV. 2
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,e. . QUESTION: 073 (1.0) '
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- When starting an additional condensate pump, the discharge valve is normally throttled, then l opened after the pump is started. This is done to
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a. limit the effects of a stuck open discharge check valve.
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b. limit the motor's starting current to prevent an overcurrent trip. i
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c. prevent feedwater train oscillations.
l d. prevent pump runout. [
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RO EXAM - REV. 2
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,_ QUESTION: 074 (1.0)
<T V A rupture of the "A" service water supply header has occurred in the auxiliary building. Using the attached copy of 0-AP-12 " Loss of Service Water", determine which control room chiller must be re-aligned to isolate the ruptured service water header.
a. 1-HV-E-4 A.
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b. 1-HV-E-4 C.
c. 2-HV-E-4B.
d. 2-HV-E-4C.
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RO EXAM - REV. 2
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QUESTION: 075 (1.0)
(V~h Unit 1 is ramping up at 0.3%/ minute and is presently at 50% power with turbine controlin impulse pressure in (BfP IN). The safeguards operator hasjust called in and reported that the
"A" SG PORY is blowing steam. (Assume the PORV had slowly opened approximately 5% over a 15' minute period). The ramp is stopped. As the PORV is closed, indicated steam flow from the S/Gs will and turbine load will i n. decrease; increase b. decrease; remain the same c. remain the same; increase ,
l d. decrease, decrease I I
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RO EXAM - REV. 2
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QUESTION: 076 (1.0)
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L Unit 2 is being ramped up after a maintenance outage. Tavg is 2 F higher than Tref. With rods in manual, the indicated rod speed will be steps per minute. Ifrods were taken to automatic, indicated rod speed would be steps per minute.
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a. _8; 8 b. 8; 48 c. 48; 8 -
d. 48; 48
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l RO EXAM - REV. 2 l i
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QUESTION: 077 (1.0)
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With the unit initially at 36% power in a chemistry hold, which one of the following can be used i
to confirm that a control rod has dropped into the core? j
a. Individual Rod Position Indicator (IRPI). I
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b. Power-range negative rate trip alarm. ;
c. Annunciator A C7 "NIS PR UP DET DEV - DEF <50%".
I d. Annunciator A D-2 " Rod Control Non-Urgent Failure". I
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RO EXAM - REV. 2 .
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t QUESTION: 078 (1.0)
O 1-RC-P-1B ("B" RCP) amps start fluctuating and the indicated vibrations begin increasing
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rapidly. The backboards operator reports that "B" RCP proximity vibration indicationjust pegged high, then the indication went to zero. The amps continue to fluctuate. With respect to the RCP only, which one of the following actions should be taken and why?
a. Do not trip "B" RCP, the vibration instrument has failed and amp indication is known to !
occasionally fluctuate.
b. Do not trip the "B" RCP, because the only failure was the vibration monitoring indication / sensor failed.
c. Trip the "B" RCP, the vibration monitoring indication was over-ranged and therefore failed low.
d. Trip the "B" RCP, vibrations have returned to normal but fluctuating amps are an RCP trip criterion. ,
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RO EXAM - REV. 2
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QUESTION: 079 (1.0)
O . A loss of the 1-I DC bus has resulted in the Terry Turbine (1-FW-P-2) starting. What actions must be taken to shutdown the Terry Turbine?
a. Place the control switches in CLOSE.
b. Place the control switches to OPEN, then return to AUTO.
c. Manually close the inlet isolation to the trip valve.
d. Locally vent air from the valve operator.
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QUESTION: 080 (1.0)
O Which one of the following statements is correct if a High-High alarm is initiated by radiation monitor (1-RM-VG-101, " Process Vent Particulate Rad Monitor) during a waste gas decay tank release?
a. 1-GW-FCV-101 (Decay Tanks Emuent Flow Control) will close automatically and must be reset locally before it can be reopened.
b. 1-GW-FCV-101 (Decay Tanks Emuent Flow Control) will close automatically and will reopen automatically when the alarm condition clears and the CLOSE push-button is depressed.
c. 1-GW-TV-102A (Containment Vacuum Pump Discharge) will close automatically and must be reset locally before it can be reopened.
d. 1-GW-TV-102A (Containment Vacuum Pump Discharge) will close automatically, and will reopen when the alarm condition clears and the OPEN push-button is depressed.
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QUESTION: 001 (1.0)
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Unit 1 is operating at 28% power when all three "A" RCS loop flows and "A" RCP amps suddenly decrease to minimum. The breaker for the "A" RCP is still closed. Select the reactor protection system response to this event.
a. Automatic reactor trip since power is > P-10.
b. Automatic reactor trip only after the RCP breaker is opened i
c. No automatic reactur trip due to RCP breaker remaining closed.
d. No automatic reactor trip due to < P-8.
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ANSWER: d REFERENCE: ID-E2 AR OBJECTIVE: 8964 SOURCE: New
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kJ K/A: 003-K3.04 LEVEL: Comprehension Distracters plausible: Either RCP breaker position or low flow will cause reactor trip, required to have loss offlow on only 1 of 3 loops above P-8.
Distracters wrong: Either RCP breaker position or low flow will cause reactor trip, required to have loss offlow on only 1 of 3 loops above P-8.
Answer correct: Loss of flow on all three flow transmitters on one loop < P-8 will not result in a reactor trip.
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RO KEY - REV. 2
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I VIRGINIA POWER 1-EI-CB-21E ANNUNCIATOR A8 1-AR-E-A8 l I . NORTH ANNA POWER STATION REV. 1 !
SDPROVAL: ON FILE
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Effective Date:05/14/97
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RHR < 3200 gpm 1 SYSTEM OR c LO FLOW < 2500 gpm (see Reactor Data Book)
NOTE: This annunciator.is disabled when both RHR pumps are in PULL-TO-LOCK.
1!. 0 Probable Cause 1.1 RER pump tripped 1.2 RHR pump cavitating 1.3 RHR flow reduced by 1-AP-11 2.0 Operator Action ACTION EXPECTED RESPONSE NOT OBTAINED
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2.1 RHR PUMP - RUNNING GO TO 1-AP-11, LOSS OF RHR.
2.2 .RHR PUMP - CAVITATING
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IF RHR flow was reduced by 1-AP-11, LOSS OF RHR, THEN continue according with 1-AP-13..
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IF NOT, THEN increase RHR flow. l 2.3 GO TO 1-AP-11, I LOSS OF RHR.
3.0 References {
3.1 Generic Letter 88-17 3.2 1-AP-11, Loss of RHR 3.3 Instrument Loop 11715-RH-004 3.4 1-ICP-RH-F-1605 3.5 1-OP-5.4 i
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3.6 DCP 97-004, Residual. Heat Removal Low Flow Alarm Setpoint '
l } 3.7 Tech Spec 3.9.8.2, 3.9.8.1, 3.7.9.2, 3.4.1.3 l (<10 Actuation 4.1 1-RH-FC-1605A l-END-
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QUESTION: 081 (1.0)
o A LOCA on Unit I has resulted in containment pressure exceeding 28 psia on 1-LM-PR-110B (Containment Pressure Recorder). What actions are required in accordance with the continuous action page of 1-E-0 " Reactor Trip or Safety Injection"?
a. Verify RCPs tripped and ensure QS pump discharge valves closed.
b. Manually initiate both trains of SI and ensure CC pumps stopped.
c. Close MSTVs ana bypasses and manually actuate both trains of CDA.
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d. Manually actuate both trains of CDA and ensure QS pumps running.
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RO EXAM - REV. 2
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QUESTION: 082 (1.0)
The mechanical chiller is removed from service for maintenance. Both unit's containments are being cooled by service water to the containment air recirc coolers. If a occurs on Unit 1, then SW will isolate to _ containment (s).
a. safety injection; only Unit I b. safetyinjection; both c. containment depressurization actuation; only Unit I d. containment depressurization actuation; both O
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U RO EXAM - REV. 2 l
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QUESTION:' 083 (1.0)
k A LOCA has occurred on Unit 2 resulting in a safety injection. The high head safety injection system has failed. The crew is depressurizing the RCS to enhance core cooling in accordance with 1-FR-C.I. As RCS pressure decreases to psig, core cooling will be enhanced due to injecting water into the RCS.
a. 120; SIaccumulators b. 150; LHSIpumps c. 250; LHSIpumps d. 675; SIaccumulators
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RO EXAM - REV. 2
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QUESTION: 084 (1.0) ;
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Containment partial pressure is at 9.3 psia with containment temperature of 101 F. Chilled water is being supplied to the containment air recire fans. Service water temperature is 88 F. In an effort to lower containment temperature, the unit supervisor requests that the Unit 2 turbine l building operator lower the setpoint of the thermostat knob on the mechanical chiller. How will !
this adjust affect the containment parameters and what is the major concern? !
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a. Partial pressure will rise and temperature will rise, containment temperature exceeding 105 F requiring an engineering evaluation.
i b. Partial pressure will rise and temperature will lower, containment partial pressure going ;
above the T.S allowable. L
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l c. Partial pressure will lower and temperature will lower, containment panial pressure going f below the T.S. allowable. )
l d. Partial pressure willlower and temperature will rise, containment temperature exceeding ;
the T.S. limit of120 F. i I
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QUESTION: 085 (1.0) .
Due to a loss of a feedwater pump on Unit 1, the crew has been ramping down at 4% per minute for 5 minutes. Tavg is presently 3 degrees higher than Tref. How would the steam dumps respond to 1-MS-PT-1447 (Channel IV First Stage Pressure) failing low?
a. Steam dumps arm only.
b. Steam dumps arm, banks 1 and 2 modulated open to 25%.
c. Steam dumps arm, banks 1,2,3,4 receive trip open signal. '
d. Steam dumps do not arm, banks 1,2,3,4 receive trip open signal.
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RO EXAM - REV. 2
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QUESTION: 036 (1.0)
,3 d Following a refueling outage, an individual accide atally opened the breaker for the operating spent fuel pit cooling pump (1-FC-P-1 A). How would .his condition be identified by the control room operator?
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a. "4160/480V BKR AUTO TRIP " annunciator.
l b. "SFP HUHI-HI TEMP" annunciator.
c. " LOSS SFP COOL FLOW" annunciator.
d. Spent fuel pit temperature increasing on Unit 2 vertical board.
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QUESTION: 087 (1.0)
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Unit 2 was operating at 100% power with pressurizer level channel I in trip due to drifling out of tolerance. Pressurizer level channelII hasjust failed low. No reactor trip occurred and channel III of pressurizer level is indicating 64%. Based on these conditions, a .
t a. safe operating conditions exists, no reactor trip is required, and a unit shutdown is required due to insufficient number of operable pressurizer level channels.
b. reactor trip was required but failed to occur, and a unit shutdown is required due to an inoperable reactor protection system.
l c. safe operating condition exists, no reactor trip is required, and continued operation is allowed if the channel is placed in trip within one hour.
d. reactor trip was required but failed to occur, an unsafe operating condition exists, and the crew must transition to E-0. l
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RO EXAM - REV. 2
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, QUESTION: 088 (1.0)
\# Given the following conditions:
- Unit 1 is operating at 50% power
- 15F3 is tagged out ior breaker maintenance
- The IH emergency bus is powered from the Unit station service bus While checking neutral bus volts, the OATC inadvertently takes the 15B2 breaker to TRIP.
As a result of this action, final status of the sta'.:on service bus will be and the emergency bus will be _ . (Assume all equipment operates as designed.)
a. eneigized; energized b. energized; de-energized c. de-energized; de-energized d. de-energized; energized n
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QUESTION: 089 (1.0) '
(3 kl Unit 2 is operating at 75% power when the "A" waterbox inlet closes. Condenser pressure will }
increase .
a. due to steamjet air ejector becoming steam bound. l
I b. because turbine load is too high for 3 waterboxes. ;
c. due to increasing water level in "B" hotwell, f i
d. and turbine load will automatically lower to return condenser pressure to normal.
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RO EXAM - REV. 2
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,._ QUESTION: 090 (1.0) !
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Unit 1 is operating at 100% power with the following conditions:
+ 1-FW-P-lC tagged out for seal cooler modifications '
- l-FW-P-1B has just tripped due to an oil leak from the outboard bearing Which one of the following will initially cause 1-FW-P-3 A to automatically start?
a. 1 of 2 breakers open on 2 of 3 main feedwater pumps.
b. steam flow > feed flow by 34% on 1 of 3 steam generators.
l c. 1 of 3 steam generator levels < 18% on 2 of 3 channels.
d. AMSAC.
l c,
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RO EXAM - REV. 2
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QUESTION: 091 (1.0)
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Unit 1 is operating at 70% power with pressurizer level controlin MANUAL due to erratic operation of 1-CH-FCV-1122 (Normal charging flow control). At what level in the pressurizer !
will all pressurizer backup heaters automatically energize?
a. 15 %
b. 59 % l
c. 62 %
d. 69.5 % i
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L! ,) 1 QUESTION: 092 (1.0) ,
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During a normal unit cooldown at 480 F, a steam break on the 40" main steam header will result
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in:
a. a safetyinjection only.
i b. a main steam line isolation only.
c. a main steam line isolation and safety injection.-
i d. neither a main steam line isolation or safety injection.
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RO EXAM - REV. 2
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QUESTION: 093 (1.0)
As the backboards operator is taking his logs, he places all Unit I radiation monitors in Check Source. Which one of the following will be a result of performing this action?
a. Letdown isolation.
b. Containment pressure increase.
c. "B" vent stack flow decrease. l d. RSHX radiation monitor pumps start.
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QUESTION: 094 (1.0)
. On a loss ofinstrument air, the service air dryer bypass (2-IA-TV-211) will automatically open when IA pressure lowers to psig, and when pressure is restored.
a. 70; .will automatically re-open b. 70; must be manually reset -
c. 90; will automatically re-open d. 90; must be manually reset
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RO EXAM - REV. 2
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QUESTION: 095 (1.0)
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U While in Mode 6 with control rod unlatching in progress, the following plant conditions exist:
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The equipment hatch, with temporary hatch cover, is in place
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The outer door of the personnel hatch is open for maintenance on the rotating ring
. The inner door of the personnel hatch is closed e The containment closure team is established NSS desires to open the inner door to the personnel hatch for 30 minutes to take scaffolding in containment. Using the attached copy of TS 3.9.4, determine if thi= should be allowed.
a. Yes, neither core alterations nor movement ofirradiated fuel is in progress.
b. Yes, provided someone is assigned to close one airlock door if the need arises.
c. No, one door on the personnel hatch must be closed at all times during core alterations.
d. No, the surveillance requirement cannot be met for verifying the personnel hatch penetration is isolated.
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RO. EXAM - REV. 2
QUESTION: 096 (1.0)
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The following conditions exist:
. Unit 1 is operating at 100% power
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Unit 2 is in day 3 of a refueling outage in the process of performing 2-PT-57.4 (SI Functional)
. Outside temperature is 38 F
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Service water spray valves are closed and bypasses are open for the SI functional For the functional test, safety injection is initiated on Unit 2. How will component cooling head tank level respond and why?
a. Increase, the additional heat added to the SW system by Unit 2 HHSI pumps.
b. Increase, the heat being removed from the Unit 2 RCS as the RCS cooldown from 547 F to 535 F continues.
c. Decrease, due to lowering CC temperatures caused by SW going on cpcays.
l d. Decrease, the standby CC pump will start forcing more flow through the CC heat exchangers, reducing CC temperatures. l
7"~%.
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RO EXAM - REV. 2
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QUESTIONi 097 (1.0) !
A i U During core onload, the crew secures the last containment air recirc fan due to decreasing
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l containment temperatures. How does this action affect refueling activities?
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a. The RCS leak detection system is inoperable, therefore refueling activities must stop.
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b. Containment purge and exhaust system is inoperable, refueling must stop if containment purge and exhaust are in service.
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c. Containment temperature monitoring is inaccurate, refueling may continue as long as local .l
. temperature monitoring is performed. l
.d. ~ Partial pressure in containment will rise, but refueling may continue as long as panial j pressure is maintained < 12 psia. l l
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RO EXAM - REV. 2
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, QUESTION: 098 (1.0)
f A complete loss of the station service buses has resulted in a natural circulation cooldown. How is level maintained in the steam generators in accordance with AP-22.1, " Loss of 1-FW-P-2, Turbine-driven AFW Pump?"
a. Main feedwater regulating bypass valves in manual.
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I b. Local control of feedwater regulating bypass inlet isolation. !
l c. Manual operation of auxiliary feedwater discharge MOVs and/or HCVs.
d. Local operation of auxiliary feedwater manual isolation to the individual SGs.
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RO EXAM - REV. 2
QUESTION: 099 (1.0)
- V) On the turbine control panel, when the Overspeed Protection Controller is placed in the Overspeed Test Position, then the is/are disabled to allow testing of the a. mechanical overspeed; OPCs b. mechanical overspeed; electrical overspeed c. OPCs; mechanical and electrical overspeed trips
- $ OPCs; Joad drop anticipator circuit and electrical overspeed trips
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s QUESTION: 100 (1.0) !
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Assume that all systems functioned as designed. Following a loss of offsite power, the I subcooling indication on Train A ofICCM would:
a. be fully functional.
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b. indicate DATALINK FAILURE.
c. indicate -550 F.
d. be inaccurate.
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RO EXAM - REV. 2
RO Answer Key
[a] [b] [c] C] 1.
[] [b] [c] [d] 26. '
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[a] [6] W [d] 2. [a] [b] [g [d] 27.
[a] [b] 3 [d] 3. [a] [b] M [d] 28.
[a] [b] [c] E 4. M [b] [c] [d] 29.
R [b] [c] [d] 5. [a] [b] [( [d] 30.
l [a] W [c] [d] 6.
[a] [4 [c] [d] 31. _ _ l
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[a] [b] m [d] 7.
[a [b] [c] [d] 32.
[a] [b] N [d] 8. [a] [b] N [d] 33.
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[a] M [c] [d] 9. [a] [b] [c] M 34.
[a] [b] [c] M 10. [a] [b] M [d] 35.
M [b] [c] [d] 11. [a] M [c] [d] 36.
4 [b] [c] [d] 12. [a] [b] [c] M 37.
[a] M [c] [d] 13. [a] [b] u [d] 38. !
[4 [b] [c] [d] 14. M [b] [c] [d] 39. I
[a] [b] [c] M 15. [a] 4 [c] [d] 40.
[a] M [c] [d] 16. [a] [b] [c] M 41. !
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[4 [b] [c] [d] 17. [a] [b] [c] [G 42.
[a] 4 [c] [d] 18. 4 [b] [c] [d] 43.
[a] [b] [c] [g 19. N [b] [c] [d] 44.
M [b] [c] [d] 20. 4 [b] [c] [d] 45.
M [b] [c] [d] 21. [a] M [c] [d] 46.
[a] [b] [c] [q 22. [a] [b] [c] [4 47.
[a] [b] [c] [4 23. [a] M [c] [d] 48.
{a] [b] M [d] 24. [a] [b] M [d] 49.
[a] M [c] [d] 25. M [b] [c] [d] 50. l
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[a] [b] [c] [W 51. [a] [b] [] [d] 76.
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[a] M [c] '[d] 52. [a] [4 [c] [d] 77.
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[a] [b] [c] 'M 53. [a] ib) M [d] 78.
l [a] [b] [c] M '54. [a] [b] [5 [d] 79.
l [a] [b] [c] M 55. [a] [b] [c] M 80.
M [b] '[c] [d] 56. [a] [b] [c] M 81.
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[a] [b] [c] p] 57, [a] [b] M [d] 82.
[a] M [c] [d] 58. [a] M [c] [d] 83.
[a] [b] [4 [d] 59. [a] [G [c] [d] 84.
[a] [b] [c] M 60. [A] [b] [c] [d] 85.
[a] [b] [c] [4 61. [a] M [c] [d] 86.
[a [b] [c] [d] 62. M [b] [c] [d] 87.
{} [a] M [c] [d] 63.
[a] [b] [c] W] 64.
[a] [b] [c] M 88.
[4 [b] [c] [d] 89.
M [b] [c] [d] 65. [a] [b] [a [d] 90.
'
[4] [b] [c] [d] 66. [a] [4 [c] [d] 91.
[a] [b] W [d] 67. [a] M [c] [d] 92.
[a] [( [c] [d] 68. [a] [4 [c] [d] 93.
[a] [b] [g [d] 69. [a] [b] [c] M 94.
[4 [b] [c] [d] 70. [a] M [c] [d] 95.
[4 [b] [c] [d] 71. [a] [b] W [d] 96.
[a] M [c] [d] 72. [a] [5 [c] [d] 97.
[a] [b] M [d] 73. [a] [b] [4 [d] 98.
(] .[a] [b] [c] M 74. [a] [b] M [d] 99.
[a] [g [c] [d] 75. M [b] [c] [d] 100.
a e #
' 3-27-87 l i
l gs l O TABLE 4.8-1
LIST OF LOAD SE00ENCING TIMERS AND DESIGN SETPOINTS
"H" BUS TIMER SET POINT INITIATINGII) TOLERANCE IDENTIFICATION (SECONDS) SIGNAL (SECONDS)
1FWEA01-62 20 SI +1.00 I FWEA01 -62A 25 LOP 1.25
!
iSWEA03-62 10
LOP +0.50 1 RSOA01 -62B 35 LOP +
_1.75 1RSOA01-62A 210 CDA +21.0
-
,
ICCPA01-62Y 15 LOP +
_0.75 1CCPA01-62X 20 LOP +1.00 1RSI A01-62A 20 LOP +1.00 ()
,/ m _
1RSIA01-62 195 CDA +9.75 IQSSA01-62A 15 LOP +
_0.75 lHVRA03-62 30 LOP +
_1.50 lHVRA04-62 10 LOP +
_0.50 lHVRB04-62 10 LOP +
_0.50 1PGSA02-62A 10 (2) A
_0.50 i
lENSH06-62A 15 LOP +0.75
_
lHVRC04-62 10 LOP +0.50 i
ISWSA35-62A1A 15 SI + l
_1.50 1SWSA35-62B1A 15 SI +1.50 l
,
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/
NORTH ANNA UNIT 1 3/4 8-4a Amendment No. 91
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s e
a 3-27-87
<~~
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C/
TABLE 4.8-1 (Continued)
LIST OF LOAD SEQUENCING TIMERS AND DESIGN SETPOINTS
"J" BUS TIMER SET POINT INITIATING (I) TOLERANCE IDENTIFICATION (SECONDS) SIGNAL (SECONDS)
1FWEB01-62 20 SI +1.00 1FWEB01-62A 25 LOP
~
+1.25 1SWEB03-62 10 LOP +0.50
~
1RSOB01-62B 35 LOP
~
+1.75 1R50BC1-62A 210 CDA +
_21.0 1CCPB01-62Y 15 , LOP +0.75 1CCPB01-62X 20 LOP +1.00
~
1RSIB01-62A 20 LOP +1.00 1RSIB01-62 195 CDA i9.75'
10SSB01-62A 15 LOP
~
+0.75 1HVRB03-62 30 LOP +1.50 1HVRD04-62 10 LOP +0.50 1HVRE04-62 10 LOP +0.50
~
lHVRF04-62 10 LOP +0.50 1PGSB02-62A 10 (2) +
_0.50 1ENSJ06-62A 15 LOP +0.75 1SWSB35-62A1B 15 SI +1. 5 0 1SWSB35-62B1B 15 SI +1.50 (1) SI - Safety Injection LOP - Loss of Offsite Power CDA - Containment Depressurization Actuation !
(2) Low primary grade water header pressure (~'s (_), 240RTH ANNA UNIT l 3/4 8-4b Amendment No. 91
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VIRGINIA POWER NORTH ANNA POWER STATIO4WORMAT10N ONLY ABNORMAL PROCEDURE NUMBER PROCEDURE TITLE REVISION (O,f 0-AP-12 LOSS OF SERVICE WATER 11 PAGE (WITH EIGHT ATTACHMENTS)
1 of 12 PURPOSE To provide the instructions to use in the event of a loss of Service Water.
=.
ENTRY CONDITIONS This procedure is entered when there is a loss of Service Water as indicated by any or all of the following:
. *
Annunciator Panel "J" B-3, SERV WTR RETURN HDR LO FLOW, is LIT, or
{
Annunciator Panel "J" D-3, SW PP l-PlA, 2-PlA AUTO TRIP, is LIT, or !
Annunciator Panel "J" E-3, AUX SW PP l-P4 LO FLOW, is LIT, or
Annunciator Panel "J" H-3, SW PP l-PlB, 2-PlB AUTO TRIP, is LIT, or
Annunciator Panel "J" D-4 AUX SW PP 2-P4 LO FLOW, is LIT, or
Annunciator Panel "J" E-4, AUX SW PP l-P4, 2-P4 AUTO TRIP, is LIT.
RECOMMENDED APPROVAL: DATE- EFFECTIVE p'
'
RECOMMENDED APPROVAL - ON FILE ^
APPROVAL: DATE
[g[/(o[77 APPROVAL - ON FILE
_ _ _ ___- ____________________ -__ _ .
NUMBER PROCEDURE TITLE REVISION
0-AP-12 LOSS OF SERVICE WATER PAGE 2 of 12
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STEP --
ACTION / EXPECTED RESPONSE j RESPONSE NOT OBTAINED
_
NOTE: *
If a Reactor trip is initiated, then, to restore cooling to necessary plant equipment, this procedure should be performed in conjunction with Emergency Operating Procedures.
- Loss of Service Water will result in loss of Component Cooling and Residual Heat Removal Systems for the affected unit (s). This procedure should be performed in conjunction with the appropriate
= Abnormal Procedures.
t
- To ensure proper operation of important equipment, CC temperatures should be continuously monitored during loss of Service Water conditions.
- In emergency situations, Attachment 8 may be used to place Auxiliary Service Water Pumps in service. If the Auxiliary Service Water pumps are placed in service, then NRC reportability requirements should be evaluated.
l I 1. __ CHECK SERVICE WATER SYSTEM INTEGRITY:
a) Check Service Water Reservoir a) Do the following:
level - GREATER THAN 310 FEET 1) If the Service Water Reservoir is intact, THEN begin a makeup using either Attachment 8 or 0-OP-49.3, SERVICE MATER RESERVOIR MAKEUP.
2) If level cannot be restored, THEN place the Auxiliary Service Water Pumps in operation using either Attachment 8 or 0-OP-49.2, SERVICE WATER SYSTEM LAKE-To-LAKE OPERATION.
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(STEP 1 CONTINUED ON NEXT PACE) -
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NUMBER. PROCEDURE TITLE , REVISION 11 i 0-AP-12 LOSS OF SERVICE WATER
, l PAGE {
3 of 12 :
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STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -;
1. CHECK SERVICE WATER SYSTEM ;
INTEGRITY (Continued).
%
' b) Check the following for b) Initiate appropriate procedure flooding - NOT INDICATED: based on location of flooding:
l
,
- Auxiliary Building Sump level * FAP-39.1, TURBINE BUILDING
- NORMAL l FLOODING !
- -4 hiller Room Sump level -
NORMAL * 0-AP-39,2, AUXILIARY BUILDING
- Turbine Building Valve Pit FLOODING !
Sump level - NORMAL
- No' report of flooding H flooding is in other plant areas, IliEE do the following-
1 1) Evaluate the need to isolate affected header or equipment. l
g 2) H required, Ill.EH stop the Service Water Pumps on the affected header, 3) H required, THEN isolate the affected header using either of.the following:
- Attachment 6 for "A" Service Water Header rupture
- Attachment 7 for "B" Service Water Header rupture
e
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-_-__ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ -
NUMBER PROCEDURE TITLE REVISION
0-AP-12 LOSS OF SERVICE WATER PAGE 4 of 12
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--
STEP --
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
_
2. CHECK SERVICE WATER SUPPLY HEADER STATUS:
"
a) Verify at least one Supply a) Trip both Reactors.
Header - INTACT C0 T0 Step 14
_
b) Verify both Supply Headers - b) Ver'ify running or start at IETACT least one Service Water Pump on
~~
the intact Supply Header and GO TO Step 3.
If at least one Service Water Pump on the intact Supply Header cannot be started, THEN trip both Reactors and CO TO Step 14 c) Verify at least one Service c) Start at least one Service Water Pump on each Supply Water Pump on each Supply Header - RUNNING Header.
If one Supply Header has NO l running SW Pump, THEN align Service Water to both headers using Attachment 4.
If Service Water Pumps are NOT available, THEN place the Auxiliary Service Water Pumps in operation using either of the following:
- 0-0P-49.2, SERVICE WATER SYSTEM 1AKE-TO-IAKE OPERATION 0B
- Attachment 8 If at least one Supply Header is in service, THEN GO TO Step 3.
If no Supply Headers are in service, THEN trip both Reactors and CO TO Step 14
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s NUMPER PROCEDURE TITLE REVISION
0-AP-12 1 DSS OF SERVICE WATER PACE O 5 of 12
-
STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 3. _ VERIFY RETURN HEADER FLOWPATHS:
a) Verify No. 4 (A) Return Header a) Perform the following:
- FLOW INDICATED
' 1) Check for valve lineup
- l-SU-FI-103A problems.
v-Q3 2) Align the desired Return Header flowpath:
- 2-SU-FI-103B If return is aligned to gg spray, THEN open Spray Array Valves as required for
- 1-SU-FI-110A cooling:
pg * l-SU-MOV-121A
- l-SW-MOV-122A
- 2-SU FI-110B = 2-SW-MOV 221B l' * 2-SW-MOV-222B (
if return is aligned to -
Bypass Spray, THEN open Bypass Spray Valves:
- l-SU-MOV-123A
- 2.sg.MOV.223B If return is aligned to the lake, TliEN open Service Water Discharge to Cire Tunnel Valves:
- l-SU-MOV-120A
- 2-SU-MOV-220A (STEP 3 CONTINUED ON NEXT PACE)
.
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NUMBER PROCEDURE TIT.2 REVISION
0-AP-12 LOSS OF SERVICE WATER PACE 6of12l ,
!
! --
STEP --
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 3. VERIFY RETURN HEADER F14WPATHS (Continued):
b) Verify No. 3 (B) Return Header b) Perform the following:
- - FLOW INDICATED 1) Check for valve lineup
- l-SU-FI-104B problems.
l
'
QE 2) Align the desired Return
Header flowpath:
- 2-SU-FI-104A If return is aligned te QB spray, THEN open Spray Array Valves as required for
- l-SU-FI-111B cooling:
l l QB * 2-SU-MOV-221A
! * 2 -SU-MOV-222A
!
- 2-SW-FI-111A * l-SU-MOV-121B
- l-SU-MOV-122B l
.
t >
If return is aligned to l
'
Bypass Spray, THEN open Bypass Spray Valves:
- l-SW-MOV-123B l * 2-SW-MOV-223A II return is aligned to the lake, THEN open Service Water Discharge to Cire Tunnel Valves:
- 1-SW-MOV-120B
- 2-SU-MOV-220B
.
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NUMBER PROCEDURE TITLE REVISION
0-AP-12 LOSS OF SERVICE WATER PAGE 7 of 12 V
-
STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 4. _ VERITY SERVICE WATER SYSTEM - CO TO Step 8.
STABLE:
- Running Service Water Pump amps
- STABLE
- Service Water Pump Discharge ~
pressure - NORMAL
- Bots. Service Water Supply Headers - IN SERVICE
- Both Return Header flows - NORMAL 5. _ VERIFY THE FOLLOWING EQUIPMENT - Have the Unit SRO enter the Action UPERABLE: Statement requirements of Tech Spec 3.7.4 for Unit 1 and Unit 2
- All four Emergency Diesel and perform the actions required Generators by the Action Statement.
- All four Service Water Pumps at the Service Water Reservoir
- Service Water Reservoir
- Both Service Water Supply 1ieaders
- Both Service Water Return Headers 6. CHECK SIRVICE WATER RESERVOIR Restore level as necessary.
LEVEL - BETWEEN 313 FEET AND 315
. FEET 7. _ RETURN TO PROCEDURE AND STEP IN EFFECT !
!
liqTI: Throughout the remainder of this procedure, AFFECTED UNIT refers to the unit without Service Water available. l I
I S. _ EVALUATE THE NEED TO SHUT DOWN THE UNITS BASED ON THE STATUS OF THE SERVICE WATER SYSTEM
.
O I
_ _ _ _ _ _ _ _ _
NUMBER PROCEDURE TITLE REVISZON
0-AP-12 LOSS OF SERVICE WATER PAGE 8 of 12
-
STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. _ CHECK AFFECTED UNIT RCP Perform the followin5: *
TEMPERATURES - NORMAL:
a) Trip affected unit.
- RCP Pump Bearing - LESS THAN 225c'F
- RCP Stator Winding - LESS THAN 300*F 10. _, SECURE COMMON CC LOADS USING ATTACHMENT 5 11. _ MONITOR THE FOLLOUING SERVICE 9ATER SYSTEM LOADS:
- Control Room Chillers
- CC Heat Exchangers/ System
- Aux Building IA Compressors
- Charging Pumps l 12. _ INITIATE l-OP-21.ll, BEARING
! COOLING SUPPLY TO THE UNIT 1 CONTROL ROOM CHILLERS
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NUMBER PROCEDURE _ TITLE REVISION
-
11 :
0-AP-12 LOSS OF SERVICE WATER PAGE 9 of 12 i
-
STEP -
. ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
,
13. _ RESTORE SERVICE WATER TO AFFECTED ;
HEADER: t a) Check status of following:
1) Affected unit Supply Header 1) Continue efforts to restore
- AVAILABLE Service Water System and
= RETURN TO Step 8.
2) Service Water Pump - 2) Cross-connect Service Water AVAILABLE to both units using l Attachment 4..
Continue efforts to restore Service Water System and RETURN TO Step 8. '
'
b) Start Service Water Pump IO . c). RETURN TO Step 4
,
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- 14, _ CHECK AFFECTED UNIT RCP Perform the following: [
TEMPERATURES - NORMAL: ;
a) Trip affected unit. [
- RCP Motor Bearing LESS THAN '
195*F b) Stop affected unit RCPs with high temperatures.
- RCP Pump Bearing - LESS THAN '
225*F
300*F 15. _ SECURE COMMON CC LOADS USING ATTACHMENT 5
.
.
- . - -
NUMBER PROCEDURE TITLE REVIS10N
0-AP-12 LOSS OF SERVICE WATER PAGE 10 of 1 l
--
STEP --
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 16. _ MONITOR THE FOLIEVING SERVICE WATER SYSTEM LOADS:
- Control Room Chillers
- CC Heat Exchangers/ System
- Aux Building IA Compressors :
- Charging Pumps
_
CAUTION: To keep Charging in service, the Charging Pumps should be cycled to prevent overheating until a cooling source is restored.
17. _ ALIGN ALTERNATE COOLING TO CHARGING PUMPS USING EITHER OF THE FOLLOWING:
- Attachment 3 (Fire Protection System as cooling source)
- Attachment 2 (PC as cooling source)
18. __ INITIATE l-OP-21.11, BEARING COOLING SUPPLY TO THE UNIT 1 CONTROL ROOM CHILLERS 19. __ ALIGN CHARGING PUMP SUCTION TO THE RWST
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NUMBER -PROCEDURE TITLE
-
REVISION
0 AP-12 LOSS OF SERVICE WATER PACE 11 of 12
-
STEP -
ACTIDN/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
..
20. _ RESTORE SERVICE WATER TO BOTH Perform the following:
UNITS:
a) Check status of following: 1) II at least one Service Water.
Supply Header is intact &ED at
.
!
least one Service Water Pump is
- Both Service Water Supply avaflable, IEEE start a pump on !
Headers - INTACT the intact header. i
== !
&ED 2) Continue efforts to restore I Service Water System. !'
- Two Service Water Pumps -
AVAILABLE 3) Determine if Service Water !
System or Service Water loads b) Start Service Water Pumps can be crosstied.
4) RETURN TO Step 14
.
21. _ VERIFY SERVICE WATER SYSTEM - RETURN TO Step 14 STABLE:
- Running Service Water Pump amps
- STABLE l
- Service Water Pump discharge pressure - NORMAL l
l
- Both Service Water Supply Headers - IN SERVICE
- Both Return Header flow NORMAL l
22. _ SECURE ALTERNATE COOLING TO CHARGINC PUMPS USING EITHER OF THE i FOLLOWING:
i
- Attachment 3 (Fire Protection System as cooling source)
. Og !
- Attachment 2 (PG as cooling i source)
.
n - , , - --
NUtiBER PROCEDURE TITLE REVISION
0-AP-12 IASS OF SERVICE WATER ij'
PAGE 12 of 12
-
STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 23. _ VERIFY THE FOLLOWING EQUIPMENT - Have the Unit SRO enter the Action OPERABLE: Statement requirements of Tech Spec 3.7.4 for Unit 1 and Unit 2
- All four Emergency Diesel and perform the actions required Generators by the Action Statement.
- All four Service Water Pumps at -
the Service Water Reservoir
-
- Service Water Reservoir
- Both Service Water Supply Headers
- Both Service Water Return Headers 24. _ CHECK SERVICE WATER RESERVOIR Restore level as necessary.
LEVEL - BETWEEN 313 FEET AND 315 FEET 25. _ REMOVE BEARING COOLINO WATER TO CONTROL ROOM CHILLERS FROM SERVICE USING l-OP-21.11, BEARING COOLING SUPPLY TO THE UNIT 1 CONTROL ROOM CHILLERS 26. _ RETURN SERVICE WATER SYSTEM TO NORMAL BY PERFORMING APPLICABLE t
SECTIONS OF THE FOLLOUING l PROCEDURES:
- 0-OP-49.lA, VALVE CHECKOFF -
- 0-OP-49.1, SERVICE WATER SYSTEM NORMAL OPERATION 27. _ RETURN TO PROCEDURE Al'D STEP IN EFFECT
- END -
.
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' NUMBER ATTACHMENT TITLE REVISION 0-AP-12 '
REFERENCES ATTACHMENT PAGE r- 1 4 1 of 1 (
- Tech Spec 3.7.4, 3.7.5.1
11715-FM-78A, B, C, F, C, H
- System Description 17-1
NRC SSOMI Service Water Issue -'
CTS 02-89 2164-025
CTS 02-91-1808-003 Tech Spec Amendment 152/136
=
OP 95-1006, Revise procedures for SW/RSHX problems, St. Order 213
- DR 90-1670
0-OP-9A, VALVE CHECKOFF - PRIMARY GRADE WATER i
0-OP-49.1, SERVICE WATER SYSTEM NORMAL OPERATION
0-OP-49.2, SERVICE WATER SYSTEM 1AKE-TO-1AKE OPERATION
0-OP-49.3, SERVICE WATER RESERVOIR MAKEUP
0-OP-49.lA, VALVE CHECKOFF - SERVICE WATER i
- 0-AP-39.1 TURBINE BUILDING FLOODING
0-AP-39.2, AUXILIARY BUILDING FLOODING
0-MOP-49.08, REMOVING NO. 1 SUPPLY (A) AND NO. 4 RETURN (A) HEADERS FROM SERVICE AND RETURNING TO SERVICE
0 MOP-49.09 REMOVING NO. 2 SUPPLY (B) AND NO. 3 RETURN (B) HEADERS FROM SERVICE AND RETURNING TO SERVICE
1-OP-21.11 BEARING COOLING SUPPLY TO THE UNIT 1 CONTROL ROOM CHILLERS
DCP 95 127. Charging Pump Casing Replacement
DCP 95 216, Charging Pump Casing Replacement
-
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NUMBER ATTACHMENT TITLE REVISION l
,
l 0-AP-12 11 COOLING CHARGING PUMPS WITH PC ATTACHMENT WHEN SERVICE WATER IS NOT AVAIIABLE PAGE 2 1 of 10 E0IE: The capacity of the alternate PG supply will provide cooling for one Charging Pump on each unit. Operating one Charging Pump at a time on each unit will be necessary.
1. _ Place all Charging Pump Bearing temperatures on trend on the P 250.
2. _ Monitor the running Charging Pump temperatures.
3. _ VHEN-che running Charging Pump bearing temperature alarms on high temperature (170*F), THEN stop the running Charging Pump and align another available Charging Pump for operation:
Y4060A CHARGING PMP 1A THR BRC T
Y4061A CHARGING PMP 1B INBD BRG T l I
Y4062A CHARGING PMP 1B OTBD BRC T
Y4063A CHARGING PMP 1B THR BRG T
Y4064A CHARGING PMP 1C INBD BRG T
Y4065A CHARGING PMP 1C OTBD BRG T
Y4066A CHARGING PMP 1C THR BRG T N0_TE : A key is required to unlock the Auxiliary Building Appendix R locker.
4, _ Get a 2 1/2-inch fire hose, a 2 1/2-inch double female fitting, and a spanner wrench from the Appendix R locker located on the second floor of the Auxiliary Building.
.
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NUMBER ATTACHMENT TITLE REVISION 0-AP-12 I
COOLING CHARGING PUMPS WITH PG ATTACHMENT WHEN SERVICE WATER IS NOT AVAIIABLE PAGE ,
2 ;!
2 of 10
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i EQIE: All PG valves are located in the Fuel Building Basement except as indicated.
5. Locally align a Standby Primary Grade Water Pump as the cooling source: I a) H 1-PG-P-2A is desired to be used, IllDi perform the following: ,
'
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_ 1) Stop 1-PG-P-2A.
-
4i
_ 2 Open 1-PG-17, 2A PG Utr Stby Pp Disch to Boron Ion Exch Isol Vv. I
_
3) Close 1-PG-18, 2A PG Wer Stby Pump Disch to PC Supply Hdr Isol Vv.
I
'
l b) H 1-PG-P-2B is desired to be used, THEN perform the following:
_ 1) Stop 1-PG-P-2B.
_ 2) Open 1-PG-25, 2B PG Utr Stby Pp Disch to Baron Ion Exch Isol Vv.
__
3) Close 1-PG-26, 2B PG Utr Stby Pump Disch to PC Supply Hdr Isol Vv.
c) Verify open or open the following valves:
_ 1) 1-PG-44, lA Primary Grade Utr Tank Recire Hdr Inlet Isol Vv
,,__. 2) 1-PG-82, Boron Cleanup Ion Exch to lA PG Utr Tank Isol Vv d) Verify closed or close the following valves:
j __, 1) 1-PG-33, lA PC Utr Svce Pp Disch to Baron Ion Exch Isol Vv
_ 2) 1 PG-42, 1B PG Utr Svce Pp Disch to Boron Ion Exch Isol Vv
_ 3) 1-PG-45, 1B Primary Grade Utr Tank Recire Hdr Inlet Isol Vv
_ 4) 1-PG-85 Boron Cleanup Ion Exch to 1B PG Utr Tank Isol Vv
_ 5) 1-PG-83, lA Primary Grade Water Tank Fill Line Isol Valve (located in yard near PG Tanks)
_ 6) 1 BR-344, Boron Cleanup Filter To PG Water Tanks Isol Valve (located in Auxiliary Building basement near Boron Cleanup lon Exchangers)
_
7) 1-BR TV-119, PC Water Tank Fill Isolation (operated from Liquid Waste Panel in Control Room) '-
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I NUMBER ATTACHMENT TITLE REVISION j 0-AP-12 11 I COOLING CHARGING PUMPS WITH PC i ATTACHMENT WHEN SERVICE WATER IS NOT AVAILABLE PAGE 2 3 of 10
6. Connect a 2 1/2-inch fire hose (with double female fitting) between the following:
l
__ * l-PC-1033, 1-BR-TV-119 PG Outlet Drain Valve (located in the Auxiliary l Building Basement behind 1 CC-E-1A) '
AND
__
- l-SU-1214, Service Water Supply Edr No 1 Test Conn Check Vv (check valve located north of 1-CC-E-1B and 2-CC-E-1A)
2B
__
l-Fu-1213. Service Water Supply Hdr No 2 Test Conn Check Vv (cheek valve located north of 1-CC-E-1B and 2-CC-E-1A)
7. Close the Supply Header Isolation Valve that is being used to supply cooling to the Charging Pumps:
__
l-SW-681, CH Pumps Gear Box Clrs SW Supply Hdr No 1 Isol Vv, for No. 1 (A) Supply Header (located upstream of 1-SU-1214)
9.B
__
l-SW-694, CH Pumps Gear Box Clrs SW Supply Hdr No 2 Isol Vv, for No. 2 (B) Supply Header (located upstream of 1-SU-1213)
8. Place the Charging Pump Lube Oil Cooler Alternate Supply Header in service by opening the isolation valve from the Supply Header that is being used to supply cooling to the Charging Pumps:
__
l-SW-711. CH Pps Lube Oil Clrs SW Altn Sply Hdr Isol Valve, for No. 1 (A) Supply Header (located behind 2-CH-P-1C cubicle)
EB
__ l-SW-707, CH Pps Lube Oil Clrs SW Altn Sply Hdr Isol Valve, for No. 2 (B) Supply Header (located behind 1-CH-P-1A cubicle)
9. Verify the isolation valve from the Supply Header that is j foT being used to supply cooling to the Charging Pumps is closed:
__ * 1-SU-711 for No. 1 (A) Supply Header
__
l-SU-707 for No. 2 (B) Suppl 9 Header
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NUMBER ATTACHMENT TITLE REVISION
.
. 0-AP-12
COOLING CHARGING PUMPS WITH PG
!
ATTACHMENT WHEN SERVICE WATER IS NOT AVAIIABLE PAGE
4 of 10
E.,0JI: All Service Water valves that are operated in Steps 10, 11, 12, l and 13 are located in the Auxiliary Building Basement behind the respective Charging Pump cubicles.
10. IE the No. 1 (A) Supply Header is being used to supply cooling to the Charging Pumps, 7_H,1N perform the following valve alignment for the Unit 1 Charging Pump that will be placed in service:
1-CH-P-1A ~
]
,_ a) Ver.ify open 1-SU-688, lA CH Pp Gear Box Clr SU Sply Hdr No 1 Inl Isol.
!
_ b) Verify open 1-SU-710, lA CH Pump Lube Oil Clr SU Altn Supply Isol Valve.
, c) Open 1-SU-666, lA CH Pump Lube Oil Clr SU Altn Supply Isol Valve.
)
i
_ d) Close 1-SU-660, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol. '
!
_ e) Close 1-SU-643, 1C CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol Vv.
]
_ f) Verify closed 1-SU-649, 1B CH Pump Lube Oil Clr SU Altn Supply Isol ;
Valve.
i
_ g) Verify closed 1-SU-632, 1C CH Pump Lube Oil Clr SU Altn Supply Isol i Valve. ,
!
1-CH-P-1B ,
.,,,_ a) Verify open 1-SU-660, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 In1 )
Isol. ,
_ b) Verify open 1-SU-709, 1B CH Pump Lube Oil Clr SU Altn Supply Isol valve.
_ c) Open 1-SU-649, 1B CH Pump Lube Oil Clr SU Altn Supply Isol Valve.
_,_ d) Close 1-SU-688, lA CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
_ e) Close 1-SU-643, 1C CH Pp Gear Box Clr SV Sply Hdr No 1 Inl Isol Vv.
_ f) Verify closed 1 SU-666, lA CH Pump Lube Oil Clr SU Altn Supply Isol Valve.
,,,,,, g) Verify closed 1-SU-632, 1C CH Pump Lube Oil Clr SU Altn Supply.Isol i
Valve.
\
l (STEP 10 CONTINUED ON NEXT PAGE)
_ _ -_. .
NUMBER ATTACHHENT TITLE REVISION l 0-AP-12 11 l COOLING CHARGING PUMPS WITH PC l ATTACHHENT WHEN SERVICE WATER IS NOT AVAILABLE PAGE j 2 5 of 10 10. ]I the No. 1 (A) Supply Header is being used to supply cooling to the Charging Pumps, THEN perform the following valve alignment for the Unit 1 Charging Pump that will be placed in service (Continued):
1-CH-P-lC
_ a) Verify open 1-SU-643, 1C CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol Vv.
_ b) Verify open 1-SW-708, 1C CH Pump Lube oil 1r SW Altn Supply Isol Valve.
_ c) Open 1-SW-632, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
_ d) Close 1-SW-688, lA CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
_ e) Close 1-SU-660, 1B CH Pp' Gear Box Clr SW Sply Hdr No 1 In1 Isol.
_ f) Verify closed 1-SW-666, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
_ g) Verify closed 1-SW-649, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
11. JI the No. 1 (A) Supply Header is being used to supply cooling to the Charging Pumps, THEN perform the following valve alignment for the Unit 2 Charging Pump that will be placed in service:
2-CH-P-1A
_ a) Verify open 2 SW-629, lA CH Pp Gear Box Clrs SW Sply Hdr No 2 In1 Isol Vv.
_ b) Verify open 2-SW-632. lA CH Pump Lube 011 Clr SW Altn Supply Isol Valve.
l __,c) Open 2-SW-617, lA CH Pump Lube 011 Clr SW Altn Supply Isol Valve.
_ d) Close.2-SW-611, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
! _ e) Close 2-SU-594, 1C CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
_ f) Verify closed 2-SW-599, 1B CH Pump Lube 011 Clr SW Altn Supply Isol l Valve.
._ g) Verify closed 2-SW-582, 1C CH Pump Lube oil Clr SW Altn Supply Isol l Valve.
l (STEP 11 CONTINUED ON NEXT PACE)
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NUMBER ATTACHMENT TITLE REVISION ;
- 0-AP-12 11 i COOLING CHARGING PUMPS VITH PC I ATTACHMENT VHEN SERVICE WATER IS NOT AVAIlABLE PAGE 2 (
6 of 10
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11. If the No. 1 (A) Supply Header is being used to supply cooling to the Charging Pumps, Ilg;ti perform the following valve alignment for the [
Unit 2 Charging Pump that will be placed in service (Continued): !
2-CH-P-1B
+
_ a) Verify open 2-SW-611, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 In1 !
- 1 sol. '
. b) Verify open 2-SU-631, 1B CH Pump Lube Oil 1r SW Altn Supply Isol l Vahve.
l _ c) Open 2-SW-599, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve. ;
r
, d) Close 2-SW-629, lA CH Pp Gear Box Clrs SW Sply Hdr No 2 In1 Isol Vv. !
L
_ e) Close 2-SW 594, 1C CH Pp Gear Box SW Clr Sply Hdr No 1 Inl Isol.
l !
_ f) Verify closed 2-SU-617, lA CH Pump Lube Oil Clr SW Altn Supply Iso)
- Valve.
i I
_ g) Verify closed 2-SU-582, 1C CH Pump Lube Oil Clr SW Altn Supply Isol i
'
Valve, l
!
2-CH-P 1C
_ a) Verify open 2-SW 594, 1C CH Pp Gear Box Clr SW Sply Hdr No 1 In1 Isol. l
_ b) Verify open 2-SW-630. 1C CH Pump Lube Oil Clr SW Altn Supply Isol valve.
___ c) Open 2-SU-582. 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
_ d) Close 2-SW-629, lA CH Pp Gear Box Clrs SW Sply Hdr No 2 Inl Isol Vv.
.,, e) Close 2-SW-611, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 In1 Isol.
_ f) Verify closed 2 SW 617, lA CH Pump Lube Oil Clr SW Altn Supply Isol 1
'
valve.
_ g) Verify closed 2 SW-599. 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
,
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i NUMBER ATTACHMENT TZT1.E REVISION '
0-AP-12 11 l l '
COOLING CHARGING PUMPS WITH PG ATTACHMENT VHEN SERVICE WATER IS NOT AVAIIABLE PAGE l 2 7 of 10 l
l 12. II the No. 2 (B) Supply Header is being used to supply cooling to the Charging Pumps. TjiEN perform the following valve ali nment 5 for the Unit 1 Charging Pump that will be placed in service:
i 1-CH-P-1A
_ a) Verify open 1-SU-687, lA CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol.
_ b) Verify open 1-SW-710, lA CH Pump' Lube Oil 1r SU Altn Supply Isol Valve.
_ c) Open 1-SW-666, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
l
!
_ d) Close 1-SU-659, 1B CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol.
l
_ e) Close 1-SU-642, 1C CH Pp' Gear Box Clr SW Sply Hdr No 2 Inl Isol Vv.
_ f) Verify closed 1-SW-649, 1B CH Pump Lube Oil Clr SU Altn Supply Isol Valve.
l ,_. g) Verify closed 1-SW-632, 1C CH Pump Lube Oil Clr SU Altn Supply Isol
! Valve.
I-CH P-1B
_ a) Verify open 1-SW-659, 1B CH Pp Gear Box Clr SW Sply Hdr No 2 In1 Isol.
_ b) Verify open 1-SW-709, 1B CH Pump Lube Oil Clr SU Altn Supply Isol Valve.
_ c) Open 1-SW-649, 1B CH Pump Lube Oil Clr SW Altn Su i Isol Valve.
_ d) Close 1-SW-687, lA CH Pp Gear Box Cooler SW Sply he: No 2 Inl Isol.
__ e) Close 1-SW-642, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol Vv.
_ f) Verify closed 1-SW-666, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
_ g) Verify closed 1-SW 532, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
(STEP 12 CONTINUED ON NEXT PAGE)
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I NUMBER ATTACHMENT TITLE REVISION
, 0-AP-12 11 i COOLING CHARGING PUMPS WITH PG '
ATTACHMENT WHEN SERVICE WATER IS NOT AVAI W LE PACE
lO 8 of 10 ,
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12. IE the No. 2 (B) Supply Header is being used to supply cooling to the i
,
Charging Pumps, IHEN perform the following valve alignment for the !
{ Unit 1 Charging Pump that will be placed in service (Continued):
l l l
j 1-CH-P-lC .
!
!
__ a) Verify open 1-SW-642, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol Vv.
~
!
' __ b) Verify open 1-SU-708, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Vaiare .
__ c) Open 1-SU-632, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ d) Close 1-SU-687, lA CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol. '
__ e) Close 1-SU-659, 1B CH Pp Cear Box Clr SW Sply Hdr No 2 Inl Isol.
__ f) Verify closed 1-SW-666, lA CH Pump Lube Oil Clr SW Altn Supply Isol I
- Valve.
I
__ g) Verify closed 1-SU 649, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
13. II the No. 2 (B) Supply Header is being used to supply cooling to the Charging Pumps, THEN perform the following valve alignment for the Unit 2 Charging Pump that will be placed in service:
2-CH-P-1A
__ a) Verify open 2-SW-628 lA CH Pp Gear Box Clrs SW Sply Hdr No 2 In1 Isol Vv.
__ b) Verify open 2 SW-632, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
l __ c) Open 2-SU-617, lA CH Pump Lube Oil Clr SU Altn Supply Isol Valve.
__ d) Close 2-SW-610, 1B CH Pp Gear. Box Clr SW Sply Hdr No 2 Inl Isol.
__ e)_Close 2-SU 593, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 In1 Isol.
,
__ f) Verify closed 2-SW-599, 1B CH Pump Lube Oil Clr SU Altn Supply Isol i
{ Valve. 1
~.
,
__ g) Verify closed 2 SU 582. 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
(STEP 13 CONTINUED ON NEXT PACE)
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NUMBER ATTACHMENT T2TLE REVISION !
0-AP-12 11 COOLING CHARCING PUMPS WITH PC ATTACHMENT WHEN SERVICE WATER IS NOT AVAILABLE PAGE 2 9 of 10
)
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13. II the No. 2 (B) Supply Header is being used to supply cooling to the Charging Pumps, IHf;E perform the following valve alignment for the Unit 2 Charging Pump that vill be placed in service (Continued):
2-CH-P-1B
_ a) Verify open 2-SW-610, 1B CH Pp Gearbox Clr SW Sply Hdr No 2 Inl Isol.
.-
_ b) Verify open 2-SU-631, 1B CH Pump Lube Oil Clr SW Altn Supply Isol 1 Vaive.
_ c) Open 2-SU 599, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
_ d) Close 2-SW-628, lA CH Pp Gear Box Clrs SW Sply Hdr No 1 Inl Isol Vv.
_ e) Close 2-SW-593, IC CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol Vv.
_ f) Verify closed 2-SW-617. lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
_ g) Verify closed 2-SW-582, 1C CH Pump Lube Oil Clr SW Altn Supply Isol k Valve.
2-CH-P-lc
_ a) Verify open 2-SW-593, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol.
_ b) Verify open 2-SW-630, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
_ c) Open 2-SU-582, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
_ d) Close 2-SW-628, lA CH Pp Gear Box Clrs SW Sply Hdr No 1 In1 Isol Vv.
_ e) Close 2-SW-610, 1B CH Pp Cear Box Clr SW Sply Hdr No 2 Inl Isol.
_ f) Verify closed 2-SW-617 lA CH Pump Li ni1 M=
SW Altn Supply Isol Valve.
_ g) Verify closed 2-SW-599, 1B CH Pu=p Lube Oil Clr SW Altn Supply Isol Valve.
.
_ ~ . . . . _ . _ . _ _ _ _ _ . _ . _ _ . _ _ _ _ . _ ___ .. _ __--_ _. . _ _ _ _ _ _ _ _ .
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NUMBER ATTAC19fENT TITLE REVISION
.. 0-AP-12 ;
COOLING CHARGING PUMPS WITH PC ATTACHMENT WHEN SERVICE WATER IS NOT AVAIlABLE PAGE
3 10 of 10 li
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14. __ Locally verify open or open 1-PG-81,1-BR-TV-119 PC Outlet Isolation Valve (located downstream of 1-BR-TV-119). '
15. __ Locally open 1-PG-1033, 1-BR-TV-119 PG Outlet Drain Valve,
.(Fire Hose connection).
,
16. __ Start the Standby Primary Grade Water Pump alfgned in Step 5.
-.
_
17. Start the desired Unit 1 Charging Pump:
__
- 1-CH-P-1A
__ * 1-CH-P-1B i
__
- 1-CH-P lc i
l 18. Start the desired Unit 2 Charging Pump: '
__
- 2-CH-P-1A
__ * 2-CH P-1B
__
- 2-CH-P-1C 19 UHEN the Service Water System has been restored, THEN perform the following:
__ a) Stop the Standby Primary Grade Water Pump started in Step 16.
__ b) Close 1-PC-1033.
__ c) Return the PC System to a normal lineup using 0-OP-9A, VALVE CHECKOFF - PRIMARY GRADE WATER.
__ d) Open 1-BR-344, Boron Cleanup Filter To PG. Water Tanks Isol Valve (located in Auxiliary Building Basement near Boron Cleanup Ion Exchangers).
__ e) Remove the 2 1/2-inch fire hose and the double female fitting from 1-PC-1033 and store in the Appendix R locker on the second floor of the Auxiliary Building. -
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NUMBER ATTACHMENT TITLE REVISION 0-AP-12 11 COOLING CHARGING PUMPS WITH FIRE PROTECTION ATTACHMENT SYSTEM VHEN SERVICE WATER IS NOT AVAIIABl.E PAGE 3 1 of 8 1. __ Place all Char-ing Pump Bearing temperatures on trend on the P-250.
2. __ Monitor the running Charging Pump temperatures.
3. __ WHEN the running Charging Pump bearing temperature alarms on high temperature (170*F), IHEN stop the running Charging Pump and align another available Charging Pump for operationi
Y4063A CHARGING PMP 1B THR BRG T l l
Y4064A CHARGING PMP 1C INED BRG T
Y4065A CHARGING PMP 1C OTBD BRG T
Y4066A CHARGING PMP 1C THR BRG T NOTE: A key is required to unlock the Auxiliary Building Appendix R locker.
4. __ Get two 2 1/2 inch to 1 1/2-inch reducers, two 1 1/2-inch double female fittings, and a spanner wrench from the Appendix R locker located on the second floor of the Auxiliary Building.
5. Install a 2 1/2 inch to 1 1/2-inch reducer (with a 1 1/2-inch double female fitting) to each of the following:
__ = l-SW-1214, Service Water Supply Hdr No 1 Test Conn Check Vv (check valve located north of 1-CC-E-1B and 2-CC-E-1A)
.
! __
1-SW 1213, Service Water Supply Hdr No 2 Test Conn Check Vv
! (check valve located north of 1-CC-E-1B and 2-CC-E-1A)
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NUMBER ATTACHMENT TITLE l REVISION
,, 0-AP-12 11 '
COOLING CHARGING PUMPS WITH FIRE PROTECTION ATTACHMENT SYSTEM VHEN SERVICE WATER IS NOT AVAILABLE PAGE
Ot 2 of 8 EgIE: The fire hose stations listed in the next two steps are the preferred hose stations. If the listed hose station is inoperable, then the next closest hose station should be used.
6. __ Connect a 1 1/2-inch fire hose from hose station near the elevator in the Auxiliary Building Basement to the double female fitting on No. 1 (A)
Supply Header connection, 1-SW-1214 (located north of 1-CC-E-1B and 2-CC-E-1A).
7. __ Connect a 1 1/2-inch fire hose from hose station in the northwest section of the Auxiliary Building Basement to the double female fitting on No. 2 (B) Supply Header connection, 1-SU-1213 I. located north of 1-CC-E-1B and 2-CC-E-1A).
8. Close the following Supply Header Isolation Valves:
__ a) 1 SU-681, CH Pumps Cear Box Clrs SW Supply Hdr No 1 Isol Vv, for No. 1 (A) Supply Header (located upstream of 1-SW-1214)
__ b) 1-SW-694, CH Pumps Gear Box Clrs SW Supply Hdr No 2 Isol Vv, C.)/ for No. 2 (B) Supply Header (located upstream of 1-SU-1213)
9. Start a Fire Pump:
__
1-FP-P-1, Motor-Driven Fire Pump
__ * l-FP-P 2, Diesel Driven Fire Pump If 1-FP-P-2 cannot be started using the normal control system, THEN start 1-FP-P-2 using the seismic start switch (located on the blue Peerless MAN-TROL panel on the north side of the engine) as follows:
1) Raise the cover on the left toggle switch.
2) Place the toggle switch to the START position and release when the engine starts. Switch spring returns to the RUN position.
3) If the engine does not start, THEN raise the cover on the right toggle switch, select the other battery, and try again to start the engine.
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_
NUMBER ATTACHMENT TITLE REVISION 0-AP-12 11 COOLING CHARGING PUMPS WITH FIRE PROTECTION ATTACHMENT SYSTEM WHEN SERVICE WATER IS NOT AVAIIABLE PAGE 3 3 of 8 10. Open both Charging Pump Lube Oil Cooler Alternate Supply Header Isolation Valves:
_ a) 1-SW-711, CH Pps Lube Oil Clrs SW Altn Sply Hdr Isol Valve, for No. 1 (A) Supply Header (located behind 2-CH-P-lc cubicle)
_ b) 1-SU-707, CH Pps Lube Oil Clrs SW Altu Sply Hdr Isol Valve, for No. 2 (B) Supply Header (located behind 1-CH-P-1A cubicle)
p' OLE : AM Service Water valves that are operated in Steps 11, 12, 13, and 14 are located in the Auxiliary Building Basement behind the respective Charging Pump cubicle.
11. Close the following No. 2 (B) Supply Header to Seal and Gear Box Coolers to the Unit 1 Charging Pumps:
_ a) 1-SU-687, lA CH Pp Gear Box Cooler SW Sply Hdr No 2 Inl Isol.
_ b) 1 SW-659, 1B CH Pp Gear Box Clr SW Sply Hdr No 2 In1 Isol.
_ c) 1-SW-642, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol Vv.
12. Close the following No. 1 (A) Supply Header to Seal and Gear Box Coolers to the Unit 2 Charging Pumps:
_ a) 2-SW-629, lA CH Pp Gear Box Clrs SW Sply Hdr No 2 Inl Isol Vv.
_ b) 2-SU-611, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
_ c) 2-SW-594, 1C CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
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NUMBER ATTACHMENT TITL?. REVISION '
0-AP-12 '
11 ,
. ATTACHMENT COOLING CHARGING PUMPS WITH FIRE PROTECTION i; SYSTEM WHEN SERVICE WATER IS NOT AVAIlABLE PAGE ;
g -) 3 4 of 8 I V
13, Perform the following valve alignment for the Unit 1 Charging Pump that will be placed in service:
,
1-CH-P-1A
__ a) Verify open 1-SU-688, lA CH Pp Gear Box Cooler SW Sply Hdr No 1 Inl Isol.
I
__ b) Verify open 1-SW-710, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
!
__ c) Op n 1-SU-666, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve. i
__ d) Close 1-SU-660, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
{
___ e) Close 1-SU-643,1C CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol Vv,
!
__ f) Verify closed 1 SU-649, 1B CH Pump Lube Oil Clr SW Altn Supply Isol j Valve. '
__ g) Verify Valve, closed 1-SW-632, 1C CH Pump Lube Oil Clr SW Altn Supply Isol !
1-CH P-1B
__ a) Verify open 1-SU-660, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
__ b) Verify open 1 SW 709, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ c) Open 1-SW 649, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve. 1 i
__ d) Close 1 SU-688, lA CH Pp Gear Box Cooler SW Sply Hdr No 1 Inl Isol.
__ e) Close 1-SU-643, 1C CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol Vv.
I
__ f) Verify closed 1-SU-666, lA CH Pump Lube Oil Clr SW Altn Supply Isol l Valve.
i
__ g) Verify closed 1-SW-632, 1C CH Pump Lube 011 Clr SW Altn Supply Isol Valve.
(STEP 13 CONTIKUED ON NEXT PACE) 1 o .
NUMBER ATTACHMENT TITLE REVISION l
'
0-AP-12 11 COOLING CHARCING PUMPS WITH FIRE PROTECTION '
ATTACHMENT SYSTEM VHEN SERVICE WATER IS NOT AVAIlABLE PACE l
5 of 8 l l
13. Perform the following valve alignment for the Unit 1 Charging Pump that will be placed in service (Continued):
1-CH-P-1C
__ a) Verify open 1-SU-643, 1C CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol Vv,
__ b) Verify open 1-SU-708, 1C CH Pump Lube Oil Clr SU Altn Supply Isol valve.
=-
__ c) Open 1-SU-632, 1C CH Pump Lube Oil Clr SU Altn Supply Isol Valve.
__ d) Close 1-SU-688, lA CH Pp Gear Box Cooler SW Sply Hdr No 1 Inl Isol.
__ e) Close 1-SU-660, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol Vv.
__ f) Verify closed 1-SW-666, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ g) Verify closed 1-SW 649, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
.
14. Perform the following ;alve alignment for the Unit 2 Charging Pump that will be placed in service:
2-CH-P-1A
! __ a) Verify open 2-SU-628, lA CH Pp Gear Box Clrs SW Sply Hdr No 1 Inl l
Isol Vv.
I
'
__ b) Verify open 2-SU-632, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ c) Open 2-SW-617, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
l l
__ d) Close 2-SU-610, 1B CH Pp Gear Box Clr SW Sply Hdr No 2 In1 Isol.
l
__ e) Close 2-SU 593, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 In1 Isol.
__ f) Verify closed 2-SW-599 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ g) Verify closed 2-SU-582, 1C CH Pump Lube Oil Clr ,SW Altn Supply Isol Valve. -
l h (STEP 14 CONTINUED ON NEXT PACE)
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NUMBER ATTACHMENT TITLE REVISION '
'
. 0-AP-12 11
>
l COOLING CHARGING PUMPS WITH FIRE PROTECTION I ATTACHMENT
.
SYSTEM VHEN SERVICE WATER IS NOT AVAIlABLE PAGE 3'
,
6 of S k
i 14. Perform the following valve alignment for the Unit 2 Charging Pump 6 that will be placed in service (Continued):
2-CH-P-1B !
.
_., a) Verify open 2-SU-610, 1B CH Pp Gear Box Clr SW Sply Hdr No 2 In1 Isol.
i
_,b) Verify open 2 SW 631, 1B CH Pump Lube Oil Clr SW Altn Supply Isol
.
l Valve. -l'
s
.
_ c) Open 2-SW-599, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve. i
,_'d) Close 2-SU-628, lA CH Pp Gear Box Clrs SW Sply Hdr No 1 Inl Isol Vv. ;
. . l
_ e) Close 2 SW-593, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol. I
,
c
_ f) Verify closed 2-SW-617, lA CH Pump Lube Oil Clr SW Altn Supply Isol l Valve.
.
_ g) Verify closed 2-SW-582, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
'
2-CH-P-lC
!
_ a) Verify open 2-SU-593, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 Inl ;
Isol. t
_ b) Verify open 2-SW 630, 1C CH Pump Lube 011 Clr SW Altn Supply Isol Valve. ;
,_ c) Open 2-SW-582, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
_ d) Close 2-SW-628 lA CH Pp Gear Box Clrs SW Sply Hdr No 1 Inl Isol Vv.
_ e) Close 2-SW-610, 1B CH Pp Gear Box Clr SW Sply Hdr No 2 In1 Isol.
'
_ f) Verify closed 2 SW-617 lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
,_ g) Verify closed 2-SW-599,-1B CH Pump Lube Oil Clr SW Altn Supply Isol valve.
.
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NUMBER ATTACHMENT TZTLE REVISION 0-AP-12 11 COOLING CHARGING PUMPS WITH FIRE PROTECTION ATTACHMENT SYSTEM UHEN SERVICE VATER IS NOT AVAI1ABLE PAGE 3 7 of 8 NOTE: FP valves listed are for the preferred hose stations. The valve number may be different if another hose station is used.
15. Open the Fire Hose Isolation Valves that are connected to the Service Water Supply Headers:
_
- l-FP-167, AUX BLDG FIRE PROTECTION HOSE RACK IS01ATION VALVE (near elevator in Auxiliary Building basement)
,
_
- l-FP-163, AUX BLDG FIRE PROTECTION HOSE RACK IS01ATION VALVE (near stairs to Auxiliary Building second floor)
16. Start the desired Unit 1 Charging Pump:
_
- l-CH-P-1A
_
- l-CH-P-1B
- l-CH-P-lc
_
17. Start the desired Unit 2 Charging Pump:
_
- 2-CH-P-1A
_
- 2-CH-P-1B
_
- 2-CH-P-IC NOTE: FP valves listed are for the preferred hose stations. The valve number may be different if another hose station is used.
18. UHEN the Service Water System has been restored, THEN perform the following:
a) Close the Fire Hose Isolation Valves that are connected to the Service Water Supply Headers:
_
- l-FP-167, AUX BLDC FIRE PROTECTION HOSE RACK ISOLATION VALVE (near elevator in Auxiliary Building basement)
_
l-FP 163, AUX BLDG FIRE PROTECTION HOSE RACK ISOLATION VALVE (near stairs to Auxiliary Building second floor),
j (STEP 18 CONTINUED ON NEXT PACE)
,
-.-. . .._-._ - , . . -.- --_. - - - - . - - - - ~ . - - -
i NUMBER ATTACHMENT TITLZ
,
, , 0-AP-12 REVISION l 11 l ATTACHMENT COOLING CHARGING PUMPS WITH FIRE DROTECTION
! 3 SYSTEM WHEN SERVICE WATER IS NOT AVAILABLE PAGE i l
8 of 8 l
l l
18. WHEN the Service Water System has been restored, THEN perform the following.(Continued):
,
b) Remove the fire hoses from the Service Water Supply Headers and l store them on the hose racks: l
__ a Northeast section (near elevator in Auxiliary Building basement) !
__
Northwest section (near stairs to Auxiliary Building second floor) l
!
c) Remove the following two 2 1/2-inch to 1 1/2-inch reducers, along with the double female fittings, and store them in the Auxiliary Building Appendix R locker:
a
__
1-SW-1214, Service Water Supply I!dr No 1 Test Conn Check Vv (check valve located north of 1-CC-E-1B and 2-CC-E-1A)
a
__
1 SU-1213, Service Water Supply Hdr No 2 Test Conn Check Vv (check valve located north of 1-CC-E-1B and 2-CC-E-1A)
v l
l
~~
_
- - - _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _
NUMBER ATTACHMENT TITLE REVISION 00AP-12 11
_ AL1GNING ONE SW PUMP PER SUPPLY HEADER A1TACHMENT WHEN NO PUMPS ARE RUNNING ON ONE HEADER PAGE 4 1 of 3
CAUTION: Discharge pressures for ).0Tli running Service Water Pumps must be maintained greater than 30 psig (monitored in the Control Room) in order to avoid pump runout.
In order to maintain SW pump discharge pressures above 30 psig, throttling of the SW outlet valve (s) for thd CCHX(s) supplied from the No. 2 (B) Supply Header may be necessary.
1. H .N.Q Service Water Pumps are running on No. 2 (B) Supply Header, I
THEN align one pump to No. 2 (B) Supply Header:
_ a) Ensure 1-SU-P-1A and 2-SU-P-1B are both running.
b) Select either 1-SW-P-1A or 2-SU-P-1B to be aligned:
_
- l-SW-P-1A
_
- 2-SU-P-1B c) H 1-SU-P-1A was selected, THEN perform the following:
_
1) Throttle open 1 SU-4, lA SW Pp Disch to Supply Hdr No 2 Isol Valve, while maintaining SW Pump discharge pressure > 30 psig in the Control Room on 1-SU-PI-101A.
2) V_ HEN discharge pressure stabilizes, THEN do the following:
_
a. Throttle closed 1-SU-6, lA SW Pp Disch to Supply Hdr No 1 Isol Valve.
_
b. Throttle open 1-SW-4
_
c. Repeat substeps a. and b. until 1-SW-4 is full open Mi.D. l-SW-6 is full closed.
_
3) RETURN T0 step in effect.
(STEP 1 CONTINUED ON NEXT PAGE) -
-
_- . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
_ _ _ _ _ _ _ _ _ _ _ _ . _ . _ . _ . . _ .
NUMBER ATTACHMENT TITLE REVISION 0 AP-12 11 ALIGNING ONE SW PUMP PER SUPPLY HEADER -
ATTACHMENT WHEN NO PUMPS ARE RUNNING ON ONE HEADER PACE !
2 of 3 1. IE EQ Service Water Pumps are running on No. 2 (B) Supply Header.
Ilig align one pump to No. 2 (B) Supply Header: (continued)
d) lE 2-SU-P-1B was selected, IllE perform the following:
_
1) Throttle open 2 SW-11, 1B SW Pp Disch to Supply Hdr No 2 Isol Valve, while maintaining SW Pump discharge pressure > 30 psig in the Control Room on 2-SW PI 201B. --
__
2) }DjG discharge pressure stabilizes, Eg do the following:
_
a. Throttle closed 2-SW-13, 1B SW Pp Disch to Supply Hdr No 1 Isol Valve.
_ b. Throttle open 2 SW-11.
,_,
c. Repeat substeps a. and b until 2-SW 11 is full open AND 2-SW-13 3 is full closed.
_ 3) RETURN T0 step in eff *
- < ,*,********************
CAUTION: Discharge pressures for BOTH running Service Water Pumps must be maintained greater than 30 psig (monitored in the Control Room) in order to avoid pump runout.
In order to maintain SW pump discharge pressures above 30 psig, throttling of the SW outlet valve (s) for the CCHX(s) supplied from the No. 1 (A) Supply Header may be necessary.
- .***************************
2. 1[ ILO Service Water Pumps are running on No, 1(A) Supply Header.
THEN align one pump to No. 1 (A) Supply Header;
_ a) Ensure 1-SW-P 1B and 2 SU-P-1A are both running.
b) Select either 1-SW P-1B or 2-SW-P-1A to be aligned
_
=
1 SW P 1B
.
._
2-SW P-1A (STEP 2 CONTINUED ON NEXT PACE)
s , _ _ _ _ _ . .
NUMBER ATTACHMENT TITLE REVISION 0 AP-12 11 ALIGNING ONE SW PUMP PER SUPPLY HEADER ATTACHMENT WHEN NO PUMPS ARE RUNNING ON ONE HEADER PAGE 4 3 of 3 2. If EQ Service Water Pumps are running.on No. 1(A) Supply Header.
THEN align one pump to No. 1 (A) Supply Header: (continued)
c) II l-SW-P-1B was selected, IHEN perform the following:
__ 1) Throttle open 1-SU-13, 1B SW Pp Disch to Supply Hdr No 1 Isol Valve, while maintaining SW Pump discharge pressure > 30 psig in the Control Room on 1-SU-PI-101B.
=
2) WHEN discharge pressure stabilizes, THEN do the following:
__ e. Throttle closed 1-SU-ll, 1B SW Pp Disch to supply Hdr No 2 Isol Valve.
__ b. Throttle open 1-SU-13.
__ c. Repeat substeps a. and b. until 1-SU-13 is full open AND 1 SW-11 is full closed.
__ 3) RETURN To step in effect, d) If 2-SW-P-1A was selected, THEN perform the following:
__ 1) Throttle open 2-SW 6, lA SW Pp Disch to Supply Hdr No 1 Isol Valve, l while maintaining SW Pump discharge pressure > 30 psig in the l Control Room on 2 SU-PI-201A.
2) UHEN discharge pressure stabilizes, THEN do the following:
l
__ a. Throttle closed 2-SW-4, lA SW Pp Disch to Supply Hdr No 2 Isol Valve.
l __ b. Throttle open 2-SW-6.
l
,
l __ c. Repeat substeps a. and b. until 2-SW-6 is full open AND 2-SW-4 is full closed.
l __ 3) RETURN TO step in effect.
.
O
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. . . .
. .
.
.
NUMBER ATTACHMENT TIT 1.E REVISION
.
0 AP-12 gg SECURING COMMON CC LOADS 5 g of 3 1. _ Secure the Baron Evaporators by pushing the INTERLOCK OFF pushbuttons.
2. Verify stopped or stop both Spent Fuel Pool Cooling Pumps:
_
- 1-FC-P-1A
_ * 1-FC-P-1B
=_
3. Secure SG Blowdown by closing the following Unit 1 $G Blowdown Trip Valves:
_ * 1-BD-TV-100A
_
- 1-BD-TV-100B
_ * 1-BD TV-100C
.
_$ 1-BD-TV 100D
_
- 1-BD-TV-100E *
_
- 1-BD TV-100F I
l
\
4 Secure SC Blowdown by closing the following Unit 2 SC Blowdown Trip Valves: l
_ * 2-BD-TV-200A
_
- 2-BD-TV-200B
_ * 2 BD-TV-200C
_ * 2-BD-TV-200D
_
- 2-BD-TV-200E
_
2-BD-TV-200F
-
NUMBER ATTACHMENT TITLE REVISION 0 AP-12 11 SECURING COMMON CC LOADS ATTACHMENT PACE ,
2 of 3 j fl 5. Secure steam to the gas strippers by closing the following valves:
__
l-BR-TCV-103A
__
- l-BR-TCV-103B
__
l-BR-PCV-159A
>
__
- l-BR-PCV-159B
=
6. Secure Gas Stripper Discharge Pumps:
__
- l-BR-P-10A
__
- l-BR-P-10B 7. Secure Gas Stripper Compressors:
__ * l-BR-C-1A l k
__
- l-BR-C-1B 8. Secure Waste Cas Compressors:
__
- l-GW-C-1A
__
- 1-GV-C 1B 9. __ Secure 1-BR-P-8, Boron Evaporator Bottoms Cooler Pump.
!
l l
h
ATTACHMENT TITLE REVISION
,
0-AP-12_
SECURING COMMON CC IDADS ATTACHMENT PAGE C 5 3 of 3 D 10. Close the following Unit 1 and Unit 2 RCS Sample Trip Valves:
- 1-SS TV-100A
_ * 1-SS-TV-103A
- 1-SS-TV-112A
- 1-SS-TV-101A
.-
- 1-SS-TV-104A
- 14S-TV- 106A
- 1-SS-TV-102A l l-SS TV-100B
- 1 SS-TV-103B
- 1-SS-TV-1128
- 1-SS-TV-101B
_
- l-SS-TV-104B
_ * l SS-TV 106B
- 1 SS-TV 102B
< * 2-SS TV-200A
_ * 2 SS-TV 203A'
- 2-SS-TV-212A
_
- 2-SS-TV-201A -
l
_
2-SS-TV 204A l
2-SS-TV 206A j
'
_ * 2 SS-TV-202A
_
2-SS-TV-200B l
2 SS-TV 203B i
!
2 SS TV-212B
__. .
- 2-SS-TV-201B j
_
- 2-SS-TV-204B
- 2-SS-TV-206B
_ * 2-SS-TV-2028
.
O
,
.
I
NUMBER ATTACHMENT T1TLE REVISION 0-AP-12 11
"A" SERVICE WATER HEADER RUPWRE ATTACHMENT PAGE 6 1 of 5
'l '
EDIE: *
This Attachment provides instructions to align the Unit 1 CC Heat Exchangers to the "B" Service Water Header and secure the Service Water System crossties.
Steps may be performed in any order or together to expedite ;
isolation of the ruptured Service Water Header. ;
This Attachment may be modified as necessary by the Unit SRO to l ensure break isolation from the "B" Service Water Header. l
-.
1. Stop the following Service Water Pumps:
__
- l-SW-P-1A
__
- 2-SW-P-1B 2. Close the following valves to prevent header siphoning:
__
1-SU-6, lA SW Pp Disch to Supply Header No 1 Isol Valve
__
l-SU-13, 1B SW Pp Disch to Supply Header No 1 Isol Valve
__
2-SU-6, lA SW Pp Disch to Supply Header No 1 Isol Valve
__
2-SW-13, 1B SW Pp Disch to Supply Header No 1 Isol Valve 3. __ Start a second Service Water Pump on the "B" Service Water Header as l directed by the Unit SRO.
l l
4 Do the following to align the 1 CC-E-1A to the "B" Service Water Header:
l
__ a) Close 1-SW-223, lA Component Cooling Hx SW Sply Hdr No 1 Isol Vv.
i
__ b) Open 1-SW-222, lA Component Cooling Hx SW Sply Hdr No 2 Isol Vv.
__ c) Close 1-SU-230, lA Component Cooling Hx SW Ret Hdr No 4 Isol Vv.
__ d) Throttle open 1-SW-231, lA Component Cooling Hx SW Ret Hdr No 3 Isol Vv, as directed by the Unit SRO.
~.
-. . - - - --- - _ _ . - . . . . - . - - . . - - _ - - . - - . - ~.
_ _ _ _ _ . . _ _ _ _ _ _ _.. _____
NUMBER . ATTACHMENT TITLE REVISION 0-AP-12
"A" SERVICE WATER HEADER RUPTURE ATTACHMENT *
PACE
2 of 5 ,
?
5. Do the following to align the 1-CC-E-1B to the "B" Service Water Header:
,.
__ a) Close 1-SU 233, 1B Component Cooling Hx SW Sply Hdr No 1 Isol Vv,
__ b) Open 1-SU 232, 1B Component Coeling Hx SW Sply Hdr No 2 Isol Vv.
__ c) Close 1-SW-241, 1B Component Cooling Hx SW Ret Hdr No 4 Isol Vv. i
__ d) Throttle open 1-SW-240, 1B Component Cooling Hx SV Ret Hdr No 3 l Inci Vv, as directed by the Unit SRO.
6. !
Close the following Service Water Supply Valves to the CC System:
__
1 SU MOV 108A
__
1 SU-MOV-108B l
7. __ Close 1-SU-247, Service Water Return Hdr No 4 Isolation Valve.
{
O 8. Close the following valves to isolate Charging Pumps and Instrument Air Compressors from the "A" Service Water Header:
l l
l
__ 1-SU-681, CH Pumps Gear Box Clrs SW Supply Hdr No 1 Isol Vv (located in Auxiliary Building 244 foot level behind 2-CC-E-1A) ;
__
1-SU-678, CH Pumps Gear Box Clrs SW Return Hdr No 4 Isol Vv (located in Auxiliary Building 244 foot level west of 1-CC-E-1B)
__
1-SU 251. Inst Air Ht Exchs SW Sply Header No 1 Isol Valve (located in Auxiliary Building 259 foot level north of Cardox Tank)
__
1-SW-286, Inst Air He Exchs SW Ret Header No 4 Isol Valve (located in Auxiliary Building 259 foot level north of Cardox Tank)
9. Secsce the Service Water crosstie through 1-SW-RM-107 as follows:
__ a) In the Control Room, stop 1-SW-P-9B.
b.' In the Auxiliary Building Basement, close the following valves:
__
1-SW-249, SW Radiation Monitor 107 to Ret Hdr No 4 1 sol Vv
-
(* __
1-SU-504, 9B SW Rad Monitor Pump Suction Isolation Valve
.
NUMBER ATTACH.YENT TITLE RCVISION 0-AP-12 11
- A" SERVICE WATER HEADER RUPTURE ATTACHMENT PAGE 6 3 of 5 NOTE: Unit 1 "A" and "C" Control Room Chillers are normally supplied from the "B" Service Water Header. Unit 1 "B" Control Room Chiller is normally supplied from the "A" Service Water Header.
10. In the Unit 1 Chiller Room, do the following:
__ a) Close 1-SU-287, Heat And Vent Chillers SW Sply Hdr No 1 Isol Vv.
__ b) Close 1-SW-290, Heat And Vent Chillers SW Ret Hdr No 4 Isol Vv.
=
__ c) Open 1-SW-385, Heat And Vent Chiller 4C SW Outlet Hdr Isol Valve.
__ d) Open 1-SW-405, Heat And Vent Chiller 4C SW Outlet Hdr Isol Valve.
__ e) Open 1-SW-362, Heat And Vent Chiller 4C SW Inlet Hdr Isol Valve.
__ f) Open 1-SW-418, Heat And Vent Chiller 4C SW Inlet Hdr Isol Valve.
__ g) If 1-HV-E-4B was running prior to the event, THEN start 1-HV-E-4B l as directed by the Unit SRO.
l
'
NOTE: Unit 2 "B" Control Room Chiller is normally supplied from the "B" Service Water Header. Unit 2 "A" and "C" Control Room Chillers are normally supplied from the "A" Service Water Header.
11. In the Unit 2 Chiller Room, do the following:
i
! __ a) Close 2-SW-224, SW Sply Hdr No 1 to Cont Room HV Chlrs Isol Valve.
__ b) Close 2-SW-227, SV Ret Hdr No 4 to Cont Room HV Chlrs Isol Valve.
__ c) Open 2-SW 302. Heat And Vent Chiller 4C SW Outlet Hdr Isol Valve.
__ d) Open 2-SW-357 Heat And Vent Chiller 4C SW Outlet Hdr Isol Valve.
__ e) Open 2-SW-305, Heat And Vent Chiller 4C SW Inlet Hdr Isol Valve.
__ f) Open 2-SW-335, Heat And Vent Chiller 4C SW Inlet Hdr Isol Valve.
__ g) 11 2-HV-E-4A or 2-HV-E-4C were running prior to the event, THEN start 2-HV-E-4A or 2-HV-E-4C as directed by the Unit SRO.
-
O
,. - _
- . -.- - - ..~ -- -- - . - . . - . . - . . _ . - - . . - . . ..~. ..
,
NUMBER ATTACHMENT TIT 1.E REVISION 0 AP-12 ]
11 (
'
"A" SERVICE WATER HEADER RUPTURE ATTACHMENT I FACE
4 of 5 :
l
i I
12. In the control Room, verify the following valves are closed:
__
__
__
__ * 1-SU-MOV-101B, "A" SW Supply Header To RSHX Isol Valve
=.
__ 1-SP MOV-115A, Aux SW Pp Disch Hdr Iso Vv
__
1-SU-MOV-113B, Fuel Pit Coolers Supply Hdr (normally de-energized closed)
__ 1-SW-MOV 110B, Recire Air Cooler Supply From "A" Header (normally de-energized closed)
__
1-SU-MOV-114B, Recirc Air Cooler Return To "A" Header (normally de-energized closed)
__'a 2-SW-MOV-205C, "A" SW Return Hdr From RSHX Isol Valve
- 2-SW-MOV 205D, "A"
__
SW Return Hdr From RSHX Isol Valve
__
__
__
2-SW MOV 215B, Aux SW Pp Disch Hdr Iso Vv
___ * 2-SW MOV-213A. Fuel Pit Coolers Return Hdr (normally de-energized closed)
__ * 2-SU-MOV-210A, Recire Air Cooler Supply From "A" Header (normally de energized closed)
__
2-SW-MOV-214B, Recire Air Cooler Return To "A" Header (normally de-energized closed)
. ..
NUMBER ATTACHMENT TIT 1.E REVIS80N 0 AP-13 11
"A" SERVICE WATER HEADER RUPTURE ATTACHMENT PAGE 6 5 of 5 13. Secure the Service Water crosstie through 1-SW-P-10 as follows:
_ a) In the Control Room, stop 1-SU-P-10.
b) In the Service Water Pit in the Unit 1 Turbine Building Basement, close the following valves:
_
e 1-SW-31, SW Ret Hdr No 4 to SW Rad Mon Pump 10 Suet Isol Vv
_ = =1-SU-35, SW Rad Mon Pump 10 Disch to Ret Hdr No 4 Isol Vv E0Ig: 0-MOP-49.08, REMOVING NO. 1 SUPPLY (A) AND NO. 4 RETURN (A) HEADERS FROM SERVICE AND RETURNING TO SERVICE, provides instructions to drain the "A" Service Water Header to the lake. If the Service Water rupture is above 252 foot elevation, then this method could stop the Service Water leakage into the plant.
14. _ GO TO 0-MOP-49.08, REMOVING NO. 1 SUPPLY (A) AND NO. 4 RETURN (A) HEADERS FROM SERVICE AND RETURNING TO SERVICE, to complete isolation and tagout of the "A" Service Water Header as directed by the Shift Supervisor. l l t
. I NUMBER ATTACHMENT TITLE REVISION"
, 0 AP-12
"B" SERVICE WATER HEADER RUPTURE +
ATTACHMENT PAGE
J 1 of 5 li
i
,
i jio71: 1 This Attachment provides instructions to align the Unit 2 CC Heat Exchangers to the "A" Service Water Header and secure the Service Water System crosaties.
Steps may be performed in any order or together to expedite isolation of the ruptured Service Water Header.
This Attachment may be modified as nedessary by the Unit SRO to ensure break isolation from the "A" Service Water Header.
_
1, i Stop the following Service Water Pumps: '
_ * l-SW-P-1B
_
- 2-SW-P-1A 2. Close the following valves to prevent header siphoning:
_ l SU-4, lA SW Pp Disch to Supply Header No 2 Isol Valve
=
_ l SU-ll, 1B SW Pp Disch to Supply Header No 2 Isol Valve }
_ 2-SU-4, IA SW Pp Disch to Supply Header No 2 Isol Valve
_
2-SU-ll, 1B SW Pp Disch to Supply Header No 2 Isol Valve 3, _ Start a second Service Water Pump on the "A Service Water Header as directed by the Unit SRO.
4 Do the following to align the 2-CC-E-1A to the "A" Service Water Header:
_ a) Close 2-SU 176, lA Component Cooling Hx SW Sply Hdr No 2 Isol Vv
_ b) Open 2-SW-177, IA Component Cooling Hx SW Sply Hdr No 1 Isol Vv
_ c) Close 2-SU-184, lA Component Cooling Hx SW Ret Hdr No 3 Isol Vv
_ d) Throttle open 2-SU 185, lA Component Cooling Hx SV Ret Hdr No 4 j I
Isol Vv, as directed by the Unit SRO. 3
-
O o :
NUMBER ATTACHMENT TITLE REVISION 0-AP-12 11
"B" SERVICE WATER HEADER RUPTURE ATTACHMENT PACE 7 2 of 5 5. Do the following to align the 2-CC-E-1B to the "A" Service Water Header:
_ a) Close 2-SU-187, 1B Component Cooling Hx SW Sply Hdr No 2 Isol Vv
_ b) Open 2-SW-186, 1B Component Cooling Hx SW Sply Hdr No 1 Isol Vv
_ c) Close 2-SW-194, 1B Component Cooling Hx SW Ret Hdr No 3 Isol Vv
_ d) Throttle open 2-SW 195, 1B Component Cooling Hx SW Ret Hdr No 4 Isol Vv, as directed by the Unit SRO.
6. Close the following Service Water Supply Valves to the CC System:
_
- 2-SW MOV-208A
_
- 2-SW-MOV-208B j 7. _ Close 1-SW-250, Service Water Return Hdr No 3 Isolation Valve.
8. Close the following valves to isolate Charging Pumps and Instrument Air O Compressors from the "B" Service Water Header:
_
l-SW-694, CH Pumps Cear Box Clrs SW Supply Hdr No 2 Isol Vv (located in Auxiliary Building 244 foot level behind 2-CC-E-1A)
_
- l-SW 679, CH Pumps Gear Box Clrs SW Return Hdr No 3 Isol Vv (located in Auxiliary Building 244 foot level west of 1-CC-E-1B)
_= l-SW-254, Inst Air Ht Exchs SW Sply Header No 2 Isol Valve (located in Auxiliary Building 259 foot level north of Cardox Tank)
_
(located in Auxiliary Building 259 foot level north of Cardox Tank)
9. Secure the Service Water crosstie through 1-SW-RM-107 as follows:
_ a) In the Control Room, stop 1-SU-P-9A.
b) In the Auxiliary Building Basement, close the following valves:
_ 1-SW-246, SV Radiation Monitor 107 to Ret Hdr,No 3 Isol Vv
_
1-SW-503, 9A SU Rad Monitor Pump Suction Isolation Valve
.
- . . - - .. -.__ _ _ __.- - . . - . _ . ~ _ - - . -
NUMBER ATTACHMENT TITLE REVISION 0 AP-12 11 I
"B" SERVICE WATER HEADER RUPTURE !
. ATTACHMENT PACE j
3 of 5
!
l jio.TI: Unit 1 "A" and "C" Control Room Chillers are normally supplied from the "B" Service Water Header. Unit 1 "B" Control Room Chiller is '
'
normally supplied from the "A" Service Water Header. ;
,
10. In the Unit 1 Chiller Room, do the following: !
i
_,, a) Close 1-SW-288, Heat and Vent Chillers SW Sply Hdr No 2 Isol Vv.
I
_ b) C se 1 SW-289, Heat and Vent Chillers SW Ret Hdr No 3 Isol Vv. ;
'
_ c) Open 1-SW-385, Heat and Vent Chiller 4C SW Outlet Hdr Isol Valve. !
!
_ d) Open 1-SU-405, Heat and Vent Chiller 4C SW Outlet Hdr Isol Valve. i
_ e) Open 1-SU-362 Heat and Vent Chiller 4C SW Inlet Hdr Isol Valve. :
Y
_ f) Open 1-SU-418, Heat and Vent Chiller 4C SW Inlet Hdr Isol Valve.
i g) E l-HV-E-AA or 1-HV-E-4C were running prior to the event, THEN start i 1-HV-E 4A or 1-HV-E-4C as directed by the Unit SRO.
NOTE: Unit 2 "B" Control Room Chiller is normally supplied from the "B" !
Service Water Header. Unit 2 "A" and "C" Control Room Chillers are i normally supplied from the "A" Service Water' Header,
-
l 11. In the Unit 2 Chiller Room, do the following:
~
_ a) Close 2-SW-225, SW Sply Hdr No 2 to Cont Room HV Chlrs Isol Valve. i
_ b) Close 2-SW-226, SV Ret Hdr No 3 to Cont Room HV Chlrs Isol Valve.
_,,c) Open 2-SU-302 Heat and Vent Chiller 4C SW Outlet Hdr Isol Valve.
._ d) Open 2-SW 357, Heat and Vent Chil} er 4C SW Outlet Hdr Isol Valve.
L l
{
_ e) Open 2-SW 305, Heat and Vent Chiller 4C SW Inlet Hdr Isol Valve.
__ f) Open 2 SW 335, Heat and Vent Chiller 4C SW Inlet Hdr Isol Valve.
l
_ g) H 2-HV-E-4B was running prior to the event, THEN start 2-HV E-4B as directed by the Unit SRO.
-
k l
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l l
l
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)
NUMBER ATTACHMENT TITLE REVISION 0-AP-12 11
"B" SERVICE WATER HEADER RUPTURE ATTACHMENT PAGE 7 4 of 5
'l 12. In the Control Room, verify the following valves are closed:
__ * 1-SU-MOV-105A, "B" SW Return Hdr From RSHX Isol Valve
__
__
__
- .
__
1-SU-MOV-115B, Aux SW Pp Disch Hdr Iso Vv
__ * l-SW-MOV-ll3A, Fuel Pit Coolers Return Hdr (normally de-energized closed)
__ * l-SU-MOV-110A, Recire Air Cooler Supply From "B" Header (normally de-energized closed)
__
l-SW-MOV-ll4A, Recire Air Cooler Return To "B" Header (normally de-energized closed)
__
__
__
__
__ = 2-SW-MOV-215A, Aux SW Pp Disch Hdr Iso Vv
__ * 2-SW-MOV-213B, Fuel Pit Coolers Supply Hdr (normally de-energized closed)
__ 2-SU-MOV-210B, Recire Air Cooler Supply From "B" Header (normally de-energized closed)
__
2-SW-MOV-214A, Recire Air Cooler Return To "B" Header (normally de-energized closed)
~.
h l
l l _ _ _ - _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ . _ _ _ . - - - - - - - - _ - - - - - - - - - - - . - - - - - - - - . - . - - -
._ _ . - . _ _ _ . . _ _ . . _ _ _ _ _. _ . _ _ _ _. ..
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~ NUMBER ATTACHMENT TIT 1.E REVISION ;
0-AP-12 I
"B" SERVICE WATER HEADER RUPTURE ATTACHMENT
' PAGE 7 {
5 of 5 I
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13. Secure the Service Water crosstie through 1-SW-P-10 as follows: j
__ a) In the Control Room, stop 1-SU-P-10.
b) In the Service Water Pit in the Unit 1 Turbine Building Basement, !
close the following valves: )
__
1-SW-28, SW Ret Hdr No 3 to SW Rad Mon Pump 10 Suct Isol Vv i
__ * =.1-SW 34, SW Rad Mon Pump 10 Disch to Ret Hdr No 3 Isol vv ,
ERTI: 0-M0P-49.09, REMOVING NO.2 SUPPLY (B) AND NO. 3 RETURN (B) HEADERS
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FROM SERVICE- AND RETURNING TO SERVICE, provides instructions to drain the "B" Service Water Header to the lake. If the Service Water rupture is above 252 foot elevation, then this method could stop the Service Water leakage into the plant. i 14. __ GO TO 0 MOP-49.09, REMOVING NO.2 SUPPLY (B) AND No. 3 RETURN (B) HEADERS ()
FROM SERVICE AND RETURNING TO SERVICE, to complete isolation and tagout of the "B" Service Water Header as directed by the Shif t Supervisor.
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NUMBER ATTACHMENT TITLE REVISION l 0-AP-12 11 OPERATION OF AUXILIARY SERVICE WATrR PUMPS I ATTACHMENT PACE 8 1 of 3
'I Eglg: This Attachment provides instructions for aligning the Auxiliary Service Water Pumps for Service Water Makeup and for Lake-To-Lake operation.
1. Send an operator to put the following Service Water Overboard Discharge Valves in DEFEAT (located in the Service Water Logic Cabinet):
"A' HEADER :
_
- l-sW MOV-120A
_
- 2-SU-MOV-220A
"B" HEADER
_
- l SW-MOV-120B
._.
- 2 SW-MOV-220B 2. Verify the following Screen Wash Pumps are stopped: l k
_= l-CW-P-2B
_
- 2-CW-P-2A 3. Close the following valves:
_
- l SW-MOV-118
_
- l-SW-MOV-119
_
- 2-SW-MOV-219 4 J_[ 1-SW-P.4 will be started, THEN open the following valves:
_
- 1-SW MOV-115A
_
- 2-SW-MOV-215B
_ * l-SW-MOV-ll?
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NUMBER ATTACHMENT TITLE REVISION 0-AP 12
OPERATION OF AUXILIARY SERVICE WATER PUMPS ATTACHMENT PACE f'S B 2 of 3 (_,/ l 5. II 2-SW-P-4 will be started, THEN open the following valves:
__
- 2-SU-MOV-215A
__
- l-SW-MOV-ll5B
__
- 2-SW MOV-217
6. Start =the desired Auxiliary Service Water Pumps:
__
- l-SW-P-4
__
- 2-SW-P-4 7. If Service Water Reservoir makeup is desired, THEN do the following:
a. Open all Service Water Spray Valves:
,a'
l-SW-MOV-121A (L,l' __
__
1-SW-MOV-122A
__
- l-SW-MOV-121B
__
l-SU-Mov-122B
__ 2-SW-MOV-221A
__
- 2-SU MOV-222A
__
- 2-SU-MOV 221B i
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__ = 2-SU-MOV-222B b. Close the following Service Water Overboard Discharge Valves:
i
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- l-SW-MOV-120A
__ * l-SU-MOV-120B
__
- 2-SW-MOV-220A
.
['T __
- 2-SU-MOV-220B ()
NUMBER ATTACiMENT TITLE REVISZON 0-AP-13 11 OPERATION OF AUXILIARY SERVICE WATER PUMPS ATTACHMENT PACE 8 3 of 3 8. .If Lake-To Lake operation is desired, TlifN do the following:
a. Open the following Service Water Overboard Discharge Valves:
"A" HEADER
_e 1-SW-MOV-120A
_
- 2-SW-MOV-220A
,
__
"B" HEADER
_
- l-SW-MOV-120B
_ * 2-SU-MOV-220B b. Close all Service Water Spray Valves:
_
1-SW-MOV-121A
.__
- l-SW-MOV-122A
._, 1-SW-MOV-121B
_
- l SU MOV-122B
_
- 2-SU MOV-221A
_
2-SU-MOV 222A
_= 2-SW-MOV-221B
__
- 2-SU-MOV-222B 9. RETUPN To step in effect.
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02-27-96 RERJELING OPERATIONS CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 a.
The containment building penetrations shall be in the following sta The equipment door closed and held in place by a minimum of fou b. .
A minimum of one door in each airlock is closed, * and c. l Each penetration providing direct access from the containmen outside atmosphere shall be either:
1. Closed by an isolation valve, blind flange, or manual valve, or 2. and BeExhaust capable of being closed by an OPERABLE automat isolation valve.
APPLICABILITE During CORE ALTERATIONS or movement ofirradiated containment. n the fuel with ACTION:
With the requirements of the above specification not satisfied,immedi operations involving CORE ALTERATIONS or movement of irradiated fuel in the contai The provisions of Specification 3.0.3 are not applicable. nment building. '
g -SURVEILLANCE REQUIREMENTS b 4.9.4 ;
either in its closed / isolated condition or capable c Containment Purge and Exhaust isolation valve within 100 east hours prio!
building by:once per 7 days during CORE ALTERATIONS or ment movement of a.
Verifying the penetrations are in their closed / isolated condition, ** or b. Testing t...
]
applicable portions of Specifications 4.6.3.1.2 and 4.9.9.
Both a. doors of the containment personnel airlock may be open provided:
One personnel airlock door is OPERABLE (i.e., the door is capa bl. closed and that an individual is designated to close the door), and There is at least 23 feet of water above the top of the reactor pressure b2. flange during movement of fuel assemblies within the containment, or There is at least 23 feet.of water above the top of irradiated fuel assemb within the reactor pressure vessel during CORE ALTERATIONS e movement of fuel assemblies.
"
Q If both doors of the containment personnel airlock are open pursuant to 3.9.4.b above, one door shall be verified to be capable of being closed at surveillance frequency.
NORTH ANNA - UNIT 1 3/4 9 4 Amendment No.198 i
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A)nra A m . M c.r ,4 ,. s t D 98-30)
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U.S. Nuclear Regulatory Commission North Anna Power Station Written Examination Applicant Information Name: Region: II Date: North Anna Power Station - Units 1 & 2 License Levee SRO Reactor Type: Westinghouse Start Time: Finish Time:
Instructions:
Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. The passing grade requires a final grade of at least 80.00 percent.
Examination papers will be collected four hours after the examination starts.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results _ _ _
Examination Value Points Applicant's Score Points
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Applicant's Grade Percent
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DISTRIBUTION CODE IE42 e
- _ _ - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
wam
[a] [b] [c] [d] 1. [a] [b] [c] [d] 26.
[a][b][c][d] 2. [a] [b] [c] [d] 27.
[a] [b] [c) [d): 3. [a] [b] [c] [d] 28.
-[a][b][c][d] 4. [a] [b] [c] [d] 29.
[a][b][c][d] 5. [a] [b] [c] [d] 30.
[a] [b] [c] [d] 6. [a] [b] [c] [d] 31.
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[a][b][c][d] 7. [a] [b] [c] [d] 32.
[a][b][c][d] 8. [a] [b] [c] [d] 33.
[a][b][c][d] 9. [a] [b] [c] [d] 34.
[a] [b] [c] [d] 10. [a] [b] [c] [d] 35.
[a] [b] [c] [d] 11. [a] [b] [c] [d] 36.
[a] [b] [c] [d] 12. [a] [b] [c] [d] 37. 1
[a] [b] [c] [d] 13. [a] [b] [c] [d] 38.
[a][b][c][d] 14. [a] [b] [c] [d] 39.
[a][b][c][d] 15. [a] [b] [c] [d] 40.
[a][b][c][d] 16. [a] [b] [c] [d] 41.
[a] [b] [c] [d] 17. [a] [b] [c] [d] 42.
[a][b][c][d] 18. [a] [b] [c] [d] 43.
.
[a] [b] [c] [d] 19. [a] [b] [c] [d] 44.
[a] [b] [c] [d] 20. [a] [b] [c] [d] 45.
[a] [b] [c] [d] 21. [a] [b] [c] [d] 46.
[a] [b] [c] [d] 22. [a] Ib] [c] [d] 47.
[a] [b] [c] [d] 23. [a] [b] [c] [d] 48.
'[a] [b] [c] [d] 24. [a] [b] [c] [d] 49.
[a] {b] [c] [d] 25. [a] [b] [c] [d] 50.
c - _ _ - _ - _ _ _
- . _ - - - _ - .
NAME
[a] [b] [c] [d] 51. [a] [b] [c] [d] 76.
[a] [b] [c] [d] 52. [a] [b] [c] [d] 77.
[a] [b] [c] [d] 53. [a] [b] [c] [d] 78.
[a] [b] [c] [d] 54. [a] [b] [c] [d] 79.
[a] [b] [c] [d] 55. [a] [b] [c] [d] 80.
[a] [b] [c] [d] 56. [a] [b] [c] [d] 81. ;
[a] [b] [c] [d] 57. [a] [b] [c] [d] 82.
[a] [b] [c] [d] 58. [a] [b] [c] [d] 83.
[a] [b] [c] [d] 59. [a] [b] [c] [d] 84. 1
[a] [b] [c] [d] 60. [a] [b] [c] [d] 85.
[a] [b] [c] [d] 61. [a] [b] [c] [d] 86.
[a] [b] [c] [d] 62. [a] [b] [c] [d] 87. i
[a] [b] [c] [d] 63. [a] [b] [c] [d] 88. ,
[a] [b] [c] [d] 64. [a] [b] [c] [d] 89.
[a] [b] [c] [d] 65. [a] [b] [c] [d] 90. 7
[a] [b] [c] [d] 66. [a] [b] [c] [d] 91.
[a] [b] [c] [d] 67. [a] [b] [c] [d] 92.
[a] [b] [c] [d] 68. [a] [b] [c] [d] 93.
[a] [b] [c] [d] 69. [a] [b] [c] [d] 94.
[a] [b] [c] [d] 70. [a] [b] [c] [d] 95.
'
[a] [b] [c] [d] 71. [a] [b] [c] [d] 96.
[a] [b] [c] [d] 72. [a] [b] [c] [d] 97.
[a] [b] [c] [d] 73. [a] [b] [c] [d] 98.
[a] [b] [c] [d] 74. [a] [b] [c] [d] 99.
[a] [b] [c] [d] 75. [a] [b] [c] [d] 100.
_ - _ _ _ - . _ - . _ - -._ _ . _ _ -- _ _ __. . . .__
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QUESTION: 001 (1.0)
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The operating crew is in the process of recovering a dropped rod on Unit I when the Tavg/ Tref Deviation annunciator is received. The operating crew should:
'
a. insert control rods if Tavg is greater than Tref.
b. raise turbine load if Tavg is less than Tref.
c. insert control rods if Tavg is less than Tref. !
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. d. raise turbine load if Tavg is greater than Tref. i
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SRO EXAM LEV. 2 i l
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QUESTION: 002 (1.0) l l
Given the following conditions: l l
l Unit I was operating at 100% when an event occurred resulting in the annunciator sounding. i 30 seconds after the annunciators sounded you observe the following annunciators lit on the event l
"first out " panels: (Note: These are the only annunciators lit on their respective panels.)
l e D-B3, "PZR LO PRESS SI-RX TRIP" is amber !
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- D-E4, "NIS PWR RGE HI FLUX RATE RX TRIP" is white.
e D-G1, "STM GEN 1 A LO-LO LEVEL RX TRIP" is white. ;
- D-G2, "STM GEN 1B LO-LO LEVEL RX TRIP" is white !
. D-G3, "STM GEN IC LO-LO LEVEL RX TRIP" is white.
. E-D4, "AMS AC INITIATED" is white. j e E-C3," TURB STOP VV LO TURB TRIP"is white.
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- E-D3, " INTER-RH STOP VV LO TURB TRIP" is white. :
- E-F2, " FEED WTR PP BKRS OPEN TURB TRIP" is white.
Based on the above information, a has occurred.
a. steam break in containment I b. steam break outside containment l
c. LOCA inside containment i i
d. LOCA outside containment l
SRO EXAM - REV. 2 l
_ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _
QUESTION: 003 (1.0)
Unit I was ramping down due to increased coolant activity caused by a failed fuel pin, when a LOCA occurred. At what radiation levelis the adverse containment criteria satisfied and under
. what conditions may the adverse containment parameters be relaxed?
a. 1 X 10E+5 R/hr, after an engineering evaluation has been performed.
b. 1 X 10E+5 R/hr, when radiation level decreases to < 1 X 10E+5 R/hr.
.
c. 50% on High Range Recorder, after an Engineering Evaluation has been performed d. 50% on High Range Recorder, when radiation level decreases to < 1 X 10E+5 R/hr.
.
SRO EXAM - REV. 2 i
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i i QUESTION: 004 (1.0)
The crew is implementing 1-FR-C.2 " Response to Degraded Core Cooling" and while isolating the SI accumulators,1-SI-MOV-1865B will not close. Why must the crew depressurize the "B" accumulator before the RCS pressure is reduced below the accumulator pressure?
a. To prevent injecting nitrogen into the reactor coolant system, which could impede natural :
circulation cooling flow. l l
b. To prevent injecting nitrogen into the reactor coolant system, which would collect in the head region forming a head bubble.
c. To prevent injection nitrogen into the reactor coolant system, which would collect in the i PRZR and make pressure control difficult.
l d. To maintain some accumulator water inventory for disc pressurization ifit is required to isolate a loop later on in 1-FR-C.2.
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QUESTION: 005 (1.0)
Why must a minimum of 6" of water be maintained in the recirc spray sump during normal operation if 1-SI-176 (1-SI-MOV-1860B Valve Body Equalizing Line Isol Viv) is closed 7 Attached is a copy of 11715-FM-96.
a. To ensure adequate NPSH for the LHSI pumps following a steam break in containment.
b. To maintain a water seal, so that radioactive gases will not be released via this pathway following a LOCA.
c. To prevent thermal binding of 1-SI-MOV-1860B (LHSI Pump suction from Containment Sump) following a LOCA in containment.
d. To ensure that adequate inventory is available in the sump for the inside recirc spray pumps following a steam break in containment.
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SRO EXAM - REV. 2
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QUESTION: 006 (1.0)
Unit 2 is at 4% power in a chemistry hold. A steam generator tube leak develops in the "B" SG.
Why would 1-SS-RM-123 ("B" SG blowdown) be a better indication of the tube leak than 1-MS-RI-191 ("B" SG N-16) for these conditions?
a. The N-16 monitors are de-energized until 20% power. ,
b. N-16 gammas are not produced in sufficient quantities at this power.
c. The N-16 monitors input from power-range NI is blocked below P-10.
d. There is inadequate steam flow to cany the radioactivity to the steam line monitors.
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QUESTION: 007 (1.0)
The crew is responding to a SGTR on unit 2 in accordance with 2-E-3 "SGTR". As the RO depressurizes the RCS , charging pump amps will and safetyinjection flow will a. increase; increase b. increase; decrease c. decrease; decrease d. decrease; increase SRO EXAM REV. 2 l . . .
. .. . . .
_ _ _ _ _ _ _ _ _
- . - - _ - - . _ - .- - . . - . . . . . .
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L i-QUESTION: 008 (1.0)
.
Select the succession of responsibility for. station operation in the event of absences, incapacitation of personnel, or other emergencies:
1. Operations Maintenance Advisor .
2. Manager - Nuclear Safety and Licensing 3. Shift Supervisor
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4. Supervisor of Shift Operations a. 2,1, 4, 3 b. 1, 4, 3, 2 ;
c. 4,2,3,1 ,
d. 2, 4,1, 3 l
SRO EXAM - REV. 2
. . ._ _ .. . .. . - - . -
QUESTION: 009 (1.0)
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If, during a Unit 2' refueling, it is desired to release the "A" WGDT, who should request the backboards operator perform this task?
c. Annex Supervisor.
b. shift Supervisor.
- c. Unit 1 SRO.
d. Unit 2 SRO.
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SRO EXAM - REV. 2 l
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_ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
QUESTION: 010 (1.0)
While performing a Unit I reactor startup with "B" control bank at 90 steps, the "B" reactor coolant pump (RCP) trips due to an electrical fault. The crew should the reactor because a. trip; operation with less than 3 RCPs is not allowed while in Mode 1 or 2 b. trip; 3 RCPs are required when any control bank or shutdown bank rods are withdrawm c. not trip; the reactor is subcritical, therefore 3 RCPs are not required d. not trip; operation with < 3 RCPs is allowed for current conditions
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j SRO EXAM - REV. 2
. . . . . . . . .
.- _ _ _ _ _ .
_ - _ _ _ - _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _
QUESTION: 011 (1.0)
Using the attached ESK, determine which one of the following will NOT trip 1-SD-P-2B ("B" LP Heater Drain Pump)?
a. Ground overcurrent.
b. High drain tanklevel.
c. Low suction pressure.
d. Supply bus undervoltage.
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-l SRO EXAM - REV. 2
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. _ - - - - _ _
. . _ ._ - _ - - . __ . _ - _ _ - _ _ _ _ - . _ _ _ __ . ~ . .
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QUESTION: 012 (1.0)
With the unit operating at 2% power, which one of the following conditions requires entry into a technical specification action statement?
I a. RCS pressure drops to 2195 psig due to a failed open spray valve.
,
b. AFD is determined to be outside the limits specified in the core operating limits reports. ]
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c. 1-CC-E-1B is isolated for inleakage inspection. l d. Chemistry reports "A" BAST boron concentration is 12780 ppm for 0-PT-16 (BAST boron concentration). ,
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i QUESTION: 013 (1.0)
Providing assurance of fuel integrity (e.g., no melting) is the bases for what limiting safety system ,
,
setting? ;
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a. Overpower delta temperature.
b. Power range high positive flux rate.
i c. Overtemperature delta temperature. l i
d. Power range high flux - high setpoint. ;
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SRO EXAM - REV. 2 l
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QUESTION: 014 (1.0)
Select the EOP(s) that can be directly entered.
a. E-0 only.
b. E-0 and FR-S.I.
c. E-0 and ECA-0.0.
d. E-0, ECA-Oc0 and FR-S.I.
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QUESTION: 015 (1.0)
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At 0230 the "High Capacity SG Blowdown Trouble" annunciator came in due to a failed -
comparator card in the local panel. In an effort to restore the alarm capability until the card can t be replaced, the instrument technician recommends lining a lead to the card which will clear the
- annunciator. Whose permission must be obtained to lin the lead?
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a. Shin Supervisor. ;
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b. Operations Manager on Call. )
c. Superintendent of Operations.
i d. SNSOC. l i
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SRO EXAM - REV. 2
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QUESTION: 016.(1.0)
- The station emergency manager declared a site area emergency at 1215. The initial report to state and local government was completed at 1227. If an upgrade to a general emergency was declared at 1230, the PAR to tne state must be given by a. 1242 J
b. 1245 I i
c. 1300
d. 1327 l
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QUESTION: 017 (1.0)
The spillway operator has reported that a bass boat ran directly into the radial gates at approximately 30 mph. The FERC was notified in accordance with VPAP-2802 (Notifications and Reports). Is the Shin Supervisor required to notify the NRC7 Why or why not?
a. No, the FERC regional engineer will notify the NRC.
b. No, NRC notification is not required for events occurring outside of the protected area.
c. Yes, any notification required by VPAP-2802 to another federal agency requires NRC notification.
d. Yes, all boating accidents involving the North Anna dam require notification to the NRC.
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I SRO EXAM - REV. 2
. - _ - _ - - _ _ _ _ _ _ . . _ _
l QUESTION: 018 (1.0)
Given the following:
- Committed Dose Equivalent (CDE) is 2525 mr
- Deep Dose Equivalent (DDE)is 2335 mr
. Lens Dose Equivalent (LDE)is 744 mr
. Committed Effected Dose Equivalent (CEDE)is 405 mr
.
Total Organ Dose Equivalent (TODE) is 4865 mr
. Shallow Dose Equivalent (SDE)is 435 mr
- Maximum Extremity (ME)is 6565 mr What is the Total Effective Dose Equivalent?
a. 2740 mr b. 5270 mr
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c. 6444 mr d. 15249 mr SRO EXAM - REV. 2
_ - _ _ _ _
._ . __ _-
QUESTION: 019 (1.0)
A fire in the main control room required the crew to evacuate. The steam generator PORV l isolation switches have been taken to the EMER CLOSE position. With no funher operator !
action, Reactor Coolant System temperature will stabilize at F.
a. 543 b. 547 c. 550 d. 556
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SRO EXAM - REV. 2
_ _ _ ___ . _. . . _ . . . . . . _ . _ _ . _ _ . - . - - . . - _ . . _ _ _ _ _ _ . _ . _ - . _ _ _ _ _ . _ . . _ . _ _ . . . _ _ _ _ . _ . _ _ .
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QUESTION: 020 (1.0). :
i A LOCA has occurred and the crew is presently in 1-E-1 " Loss of Reactor or Secondary j
- Coolant". The following conditions exist I
- RCPs are secured
- Containment pressure is 47 psia and slowly increasing ;
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- Total AFW flowis 385 GPM
- SG W/R levels: "A" - 48%, "B" - 40%, "C" - 39%
- . RCS pressure 920 psig
. I .termediate ranges indicating 2 X 10E-11 with a SUR of 0 e tors exit TCs - 530 F
,
e RVLIS Oli range 4' 5%
Based on the above conditions, the crew should transition to a. 1-FR-C.2.
b. 1-FR-H.2.
c. 1-FR-S. I .
d. 1-FR-Z.1.
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SRO EXAM - REV,2
_ _ _ - _ _
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QUESTION: 021 (1.0)
Using the P250 printout the CRO has recognized the following indications on the "A" HP heater drain nump over a 3 day period:
DAY 1- Lower motor bearing temp - 190 F, Upper motor bearing temp - 188'F, ambient temp -
84 F, bearing cooling supply temp 78 F DAY 2 - Lower motor bearing temp - 194 F, Upper motor bearing temp - 189 F, ambient temp - !
88 F, bearing cooling supply temp 78 F DAY 3 - Lower motor bearing temp - 196 F, Upper motor bearing temp - 191*F, ambient temp -
88 F, bearing cooling supply temp 79 F Also on the aflernoon of day 1, the "C" main feedwater pump (MFP) was started and the "A" MFP was stopped. All oil levels are normal and bearing cooling flows are unchanged. i Which of the following explains the bearing temperature trend for the "A" HP heater drain pump?
a. Starting the "C" MFP has put an additional heat load on the bearing cooling system causing the heater drain pump bearing temps to increase, temperature trend is normal.
b. The lower motor bearing is in imminent danger of failing, the heater drain pump should be i secured immediately. i
c. Temperature surrounding the heater drain pump have increased due to rising ambient ,
temps and swapping MFPs, temperature trend is normal. l
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d. The temperature trend is abnormal, engineering should be contacted to provide assistance j in determining the cause of the temperature rise.
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SRO EXAM - REV. 2
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QUESTION: 022 (1.0)
A condensate pump discharge line break has resulted in a reactor trip. All AFW pumps have failed to automatically start. Prior to declaring a General Emergency on a Loss of All MFW and AFW, the operators are allowed to a. attempt to start the AFW pumps from the control room.
b. dispatch an operator to locally close motor driven AFW pump breakers c. perform required actions to restore feedwater as long as SG levels are maintained > 12%
d. attempt to isolate the condensate leak and restart a condensate pump i
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QUESTION: 023 (1.0)
Given the following conditions:
- Unit 1 is at 70% power
. "D" bank control rods are at 190 steps in automatic
. The selected first stage pressure hasjust failed high How will controls rods respond and how does the rod movement alone affect moderator temperature coefficient (MTC)? (Disregard any temperature changes from the rod movement.)
a. Rods will step out, MTC will be more negative due to neutrons being more likely to
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encounter a control rod.
b. Rods will step out, MTC will be less negative due to neutrons being less likely to encounter a control rod.
c. Rods will step in, MTC will be more negative due to neutrons being more likely to encounter a control rod.
d. Rods will step in, MTC will be less negative due to neutrons being less likely to encounter a control rod.
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i QUESTION: 024 (1.0)
During the core onload, new fuel assemblies were inadvenently placed on the outer periphery of the core. How would the control room crew identify that a problem existed during the power escalation? -
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a. Core differential temperature would be higher than NI power and main generator output.
b. Core differential temperature would be less than NI power and main generator output.
c. NI power would indicate lower than core differential temperature and main generator output.
d. NI power would indicate higher than core differential temperature and main generator i output.
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SRO EXAM - REV. 2
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l Given the following conditions:
l . Unit 1 is at 100% power
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The shift is loading the IJ EDG in accordance with 1-PT-82J," Emergency Diesel Generator Slow Start"
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, The safeguards watchstander has reported that breaker 1H1-2N K1 ("A" OUTSIDE RS PUMP DISCH,1-RS-MOV-156A) has tripped open and appears severely charred.
Based on the above conditions, the US should take the actions of technical specification (refer to the attached Tech Specs).
a. 3.0.3.
b. 3.0.5.
c. 3.6.2.2 (one containment recirculation spray subsystem inoperable)
d. 3.6.2.2 (two containment recirc spray subsystems inoperable)
SRO EXAM - REV. 2
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QUESTION: 026 (1.0)
Unit 1 is at 100% power when annunciator A-H7, A.F.D. MONITOR, alarms. The RO determines that rod H-14 in control bank D has stepped into the core approximately 100 steps.
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Which ONE of the following describes the effect this event will have on core flux patterns?
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a. There should be a large variation on axial flux difference indicators and on power range ;
detectors at the same elevation.
b. There should be a large variation on axial flux difference indicators but a minimal effect on power range detectors at the same elevation.
c. There should be minimal effect on axial flux difference indicators but a large variation on power range detectors at the same elevation.
d. There should be minimal effect on axial flux difference indicators and on power range detectors at the same elevation.
SRO EXAM - REV. 2
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-I QUESTION: 027 (1.0)
Following a large break LOCA the crew aligns the Safety Injection System for cold leg recirculation mode.
Which one of the following reasons is correct for closing 1-CH-MOV-1370 (RCP SealInjection MOV)? ,
a. To maximize the amount of safety injection flow.
b. To prevent runout of the operating LHSI pump should the other LHSI pump fail. ,
c. To prevent damaging the RCP seah by flowing sump water to the seal faces.
l d. To minimize the pressure transient felt by the #1 seal as the LHSI discharge is aligned to the HHSI suction. j
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QUESTION: 028 (1.0)
Unit I has experienced a loss of feedwater ATWS and the operating crew is presently in 1-FR-S.I. The BOP is unable to trip or runback the turbine. What actions are required for the turbine trip failure and why?
a. Close the MSTVs and bypasses; assist in shutting down the reactor by adding negative reactivity due to moderator temperature defect.
b. Close the NRVs and bypasses; assist in shutting down the reactor by adding negative reactivity due to moderator temperature defect.
c. Close the MSTVs and bypasses; minimize use of the SG inventory.
d. Close the NRVs and bypasses; minimize use of the SG inventory.
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SRO EXAM - REV. 2
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QUESTION: 029 (1.0)
Unit 1 is in the process of a reactor startup with power at 1300 cps on Source Range N-31 and 1400 cps on N-32. The RO is in the process of withdrawing control rods when a loss of vital bus 1-II occurs. The operator releases the in-hold-out switch. What will N-32 startup rate indication do and why?
a. Go to 0 dpm due to a loss of power to the instrument.
b. Immediately go to -1/3 dpm due to an automatic reactor trip.
c. Remain slightly positive for a short time then decrease to zero due to the reactor being suberitical.
d. Continue to increase in the positive direction due to the feedwater heater high level diverts failing open.
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SRO EXAM - REV. 2
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QUESTION: 030 (1.0)
A reactor startup is in progress with Source Range counts indicating 2.7 x 10E+4 cps on N-31 ;
and N-32. Intermediate range detector N-L indicates 3 X 10E-11 and N-36 indicates 1 X 10E-11. What actions should be performed and why?
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a. Enter the AP for a failed intermediate range detector, maintain power < P-6, N-35 is undercompensated.
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b. Enter the AP for a failed intermediate range detector, maintain power < P-6, N-36 is failed low. i
c. Continue the startup, power is too low to determine if any intermediate range detector has ,
failed. l
' d. Enter the AP for a failed intermediate range detector, continue the startup, adequate protection and monitor'mg is available with one intermediate range detector.
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QUESTION: 031 (1.0)
Given the following conditions:
. A small break LOCA has occurred
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The crew responded IAW EOPs and tripped the RCPs when required
. The crew is currently in 1-ES-;.2, " Post LOCA Cooldown and Depressurization"
. RCS Pressure is 1490 psig.
. Wide range Tcs are 505 F and slowly decreasing
. Wide range Ths are 515 F and slowly decreasing
. CETCs are 581 F and stable
- Containment pressure is 10 psia e Containment radiation is 5.0 X 10E+1 R/hr i e SG narrow-range levels are being maintained at a minimum of 40%
- SG pressures are 715 psig and decreasing slowly According to 1-ES-1.2, the requirements for natural circulation:
a. are not met, since CETCs are not decreasing.
b. are not met, since there is inadequate subcooling.
c. are not met, since SG parameters are not satisfied.
d. are met.
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SRO EXAM - REV. 2 l
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QUESTION: 032 (1.0)
Assume that "A" SG has faulted , the crew has proceeded through the EOPs to isolate the faulted SG. Soon afterward, the other 2 SGs are determined to be faulted and the crew transitions to 2-ECA-2.1, " Uncontrolled Depressurization of All Steam Generators." How should feedwater flow be controlled to all SGs?
a. 100 gpm to "B" and "C" SGs, "A" remain isolated.
b. Isolate feed flow to all SGs.
c. 100 gpm to each SG.
d. Continue to feed "B" and "C" SGs until narrow range level >l1%.
SRO EXAM - REV. 2
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QUESTION: 033 (1.0)
Udt 1 is in a refueling outage with the following conditions:
.
The "A" RHR pump is running, returning to "C" loop.
. The "A" SW supply header is tagged out.
. 1-CC-E-1 A and 1-CC-E-1B are aligned to the "B" SW header.
. 2-SW-P-1 A and 2-SW-P-1B are running.
- Solid State Protection system fuses are removed.
Which of the following conditions will result in a loss ofRHR on Unit 17 a. Unit 1 SI.
b. Unit 2 SI.
c. Unit 2 CDA.
d. Loss ofIJ 4160V emergency bus.
SRO EXAM - REV. 2
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e QUESTION: 034 (1.0)
Unit 1 control room operator received annunciator D-C8 " SMOKE DET SYS SMOKE c INDICATION TROUBLE" How would the OATC determine which area was in alarm? )'
a. Look at the P250 computer printout.
b. Call up the fire detection screen on SPDS.
c. Observe the P-250 CRT display for the latest alarm.
d. Look at the Robert Shaw panel to determine the affected zone.
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SRO EXAM - REV. 2
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l QUESTION: 035 (1.0)
If a control room evacuation is required , where could you monitor reactor coolant system pressure from outside the control room?
a. Auxiliary Building penetration area.
b. Safeguards 2"' level.
c. Auxiliary Shutdown Panel.
d. 1H EDG Control Room Emergency (CRE) panel.
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SRO EXAM - REV. 2
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QUESTION: 036 (1.0)
Hydrogen peroxide was just added to the Unit 2 Reactor Coo' ant System resulting in an increase in the primary coolant activity. The first indication that the activity level has risen will be seen on and to lower the activity level, the crew should .
a. Containment particulate radiation monitor,2-RMS-RM-259; increase flow through the letdown demineralizers.
b. Letoown radiation monitor,2-CH-RI-228; increase flow through the letdown demineralizers.
c. Containment particulate radiation monitor,2-RMS-RM-259; decrease flow through the letdown demineralizers.
d. Letdown radiation monitor 2-CH-RI-228; decrease flow through the letdown demineralizers.
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SRO EXAM - REV. 2
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i QUESTION: 037 (1.0)~
Which one of the following is the first required action if, during implementation of 1-E-0, the turbine fails to trip automatically and the pushbuttons fail to trip the turbine?
a. Close the NRVs and bypasses.
b. Dispatch an operator to locally trip the turbine.
- c. Manually open G-12 and the exciter field breaker d. Place both EHC pumps in PTL l
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SRO EXAM - REV. 2 l
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QUESTION: 038 (1.0)
During performance of 1-E-3, the operator, when directed to adjust the setpoint on the ruptured SG's PORV to 5.5, mistakenly adjusts it to a setting of 5.8. At what pressure will the PORV lift?
a. 1035 psig
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b. 1050 psig c. 1065 psig d. 1091 psig
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SRO EXAM - REV. 2
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l QUESTION: 039 (1.0) i A loss 'of feedwater has required the crew to trip the reactor and implement 1-E-0. The BOP
- notices 1-FW-FI-100B is indicating 0 gpm. Which one of the following is a possible cause for ;
- these conditions? ;
i a. 1-FW-PCV-159A closed. i b. 1-FW-PCV-159B closed.
c. 1-FW-HCV-100C closed.
i d. 1-FW-HCV-100B closed. l l
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QUESTION: 040 (1.0)
Which one of the following sets of conditions provides adequate heat sink if all RCPs are stopped?
a. "A" AFW flow 50 gpm, "B" AFW flow 50 gpm, Turbine driven AFW pump flow 300 gpm.
b. "A" AFW flow 120 gpm, "B" AFW pump flow 120 gpm, turbine driven AFW pump flow 120 gpm.
k c. "A" SG narrow range level 9%, "B" SG narrow range level 3%, "C" SG wide range level 27%.
d. Adverse containment conditions exist, "A" SG narrow range level 18%,"B" SG narrow range level 11%, "C" SG narrow range level 15%.
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QUESTION: 041 (1.0)
During a Unit I refueling outage, the core onload is 25% complete. Which one of the following is !
a positive indication that criticality has occurred or is imminent during the onload?
l a. 1/M plot predicts criticality when 187th assembly is loaded.
b. Manipulator crane R/M alarm. j c. Containment evacuation alarm.
l d. High flux at shutdown alarnt f t ;
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QUESTION: 042 (1.0)
Following a LOCA on Unit 1, the design of containment and containment spray systems will ensure that:
i a. peak containment pressure will be limited to the upper containment design pressure of 60
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psig.
b. safety-related equipment will be subject to greater-than-design temperatures for no longer than 15 minutes.
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c. containment internal pressure can be returned subatmospheric within 30 minutes. !
d. containment internal pressure remains subatmospheric afler 60 minutes.
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_ __ QUESTION; 043 (1.0) ;
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_ Unit I has experienced 2 large break LOCA. The crew has just transitioned from 1-E-0,' to 1-E ' ]r l. The following conditions exist: l l
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- - A" S/G N/Rlevelis 8%, AFW flowis 120 gpm :
e "B" S/G N/R level is 2%, AFW flow is 110 gpm
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. l "C" S/G N/R level is 2%, AFW flow is 110 gpm
- RCS subcoolingis 12 F
- ' No RCPs are operating -
- . Core exit TCs are 825*F -
e RVLIS full rangeis 53% i
- t Containment pressure is 37 psig ;
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What is the correct procedure to use for these conditions?
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a. Transition to 1-FR-C.2.
i b. Transition to 1-FR-C.3 !
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c. Transition to 1-FR-H.l. I t
. d. Transition to 1-FR-Z.1. I
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SRO EXAM-REV 2
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QUESTION: 044 (1.0)
Unit 1 is operating at 50% power when the crew is required to evacuate the control room due to noxious fumes. Under which one of the following conditions would emergency boration be required in accordance with 1-AP-20, " Operation from the Auxiliary Shutdown Panel"?
a. The control room is still uninhabitable 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> following the reactor trip.
b. Cooldown of the RCS to 350 F is required.
c. I control rod remains fully withdrawn from the core after the reactor trip.
d. IRPIs in the main control room indicated 8 rods remained 6 steps out of the core, the remaining rods are fully insened.
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SRO EXAM - REV. 2
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QUESTION: 045 (1.0)
While the plant is holding at 20% power, "B" RCP trips and causes a transient in "B" SG. :
Select the statement below that correctly describes how steam flow and water level in "B" SG respond initially to the trip of the "B" RCP.
a. Steam flow decreases, level decreases b. . Steam flow decreases, level increases
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c. - Steam flow increases, level increases d. Steam flow increases, level decreases l
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SRO EXAM - REV. 2
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QUESTION: 046 (1.0)
Unit 2 hasjust been tripped from 100% power due to a stuck open pressurizer safety valve. The crew hasjust tripped the reactor coolant pumps due to loss of subcooling. Pressurizer levelis 70%. How would RVLIS full range respond when saturation conditions are reached in the RCS?
a. Decrease, then increase.
b. Decrease rapidly.
c. Increase, then decrease.
d.. Increase rapidly.
SRO EXAM - REV. 2
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QUESTION: 047 (1.0)
With the pressurizer level control selector switch in the 461/460 position, a failure causes the following plant events to occur in the given sequence (assume no operator actions are taken): ,
1) Charging flow reduced to minimum
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2) Pressurizer level decreases 3) Letdown secured and PRZR heaters off i 4) PRZR level increases until high level trip l Which one of the following failures occurred?
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a. Level channel 460 failed low. '
b. Level channel 460 failed high.
c. Level channel 461 failed low.
d. Level channel 461 failed high.
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QUESTION: 048 (1.0)
Unit I has experienced a loss of coolant accident and the crew is presently in 1-ES-1.2 " Post LOCA Cooldown and Depressurization" cooling down and depressurizing the RCS to refill the pressurizer. Required subcooling is lost during the depressurization. How will the required subcooling be re-established after the depressurization is stopped?
a. Stop the RCS cooldown.
b. Continue the RCS cooldown. l c. Energize pressurizer heaters.
d. De-energize pressurizer heaters.
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SRO EXAM - REV. 2
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QUESTION: 049 (1.0)
When using 1-ES-1.1 "SI Termination" to recover from a safety injection, does the crew open the BIT recirculation valves when isolating the BIT 7 a. Yes, to prevent overpressurizing the BIT while it is isolated . l b. Yes, to ensure the BIT is full by verifying recire flow.
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c. No, to prevent diluting the inservice boric acid storage tank. l d. No, to ensure the inservice boric acid storage tank level is maintained above the T.S.
minimum.
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SRO EXAM - REV. 2
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QUESTION: 050 (1,0) :
A dropped rod has caused quadrant power tilt ratio (QPTR) to exceed its T.S. limit and cannot be restored, therefore power must be reduced to < 50% power. Why is power required to be less than 50%7 i a. Regardless of QPTR value, when < 50% power, minimum DNBR is assured for Condition I and Condition II events.
. b. Accident analysis for a large break LOCA indicates that core damage cannot occur when initial reactor power is < 50%.
c. When power is less than 50%, QPTR is assured to be within normal T.S. limits by virtue i of core design with a single dropped rod.
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d. Power must be lowered to allow reactor engineering to perform an incore flux map, to l confirm that an asymmetric power distribution is occurring.
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SRO EXAM - REV. 2
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QUESTION: 051 (1.0)
' Which one of the following statements concerning pressurized thermal shock (PTS) is true?
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a. The reactor vessel heads at North Anna are not susceptible to PTS.
b. Carbon steel components must first be irradiated by an intense neutron flux before PTS
- becomes a concern.
c. A large break LOCA produces the most severe PTS hazard due to the cold RWST water injected resulting in a rapid RCS cooldown.
d. A steam break creates a high potential for PTS due to the large cooldown followed by the rapid repressurization of the RCS.
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SRO EXAM - REV. 2
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QUESTION: 052 (1.0)
l A station blackout has occurred and the crew is attempting to restore power to the IH emergency bus in accordance with 1-ECA-0.0 " Loss of All AC Power" The IH EDG is running but the i output breaker (15H2)is not closed. While attempting to close the output breaker manually using attachment #4 of 1-ECA-0.0, which of the following items will prevent the output breaker from closing? !
a. Incoming and running voltages not within 2 volts of each other, b. 4160V Emer Gen Supply Feed to Bus 1H synchronizing switch in OFF.
c. Synchronizing scope rotating in the counter clockwise direction-l d. Emergency diesel generator speed at < 880 RPM. ;
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SRO EXAM - REV. 2
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QUESTION: 053 (1.0)
Unit 1 is operating at 100% powet when a loss of the 1-III vital bus occurs. The operating crew should:
a. perform 1-AP-3, " Loss of Vital Instrumentation," which will direct initiation of the appropriate MOP for restoration of the vital bus.
b. perform 1-AP-3, " Loss of Vital Instrumentation," to completion, then enter 0-AP-10,
" Loss of Electrical Power," to restore power.
c. enter 0-AP-10, " Loss of Electrical Power," and stabilize the unit in accordance with the
" Unit 1 CRO Loss ofPower Actions" attachment.
d. perform the immediate actions of 1-AP-3, " Loss of Vital Instrumentation," to stabilize the unit, then enter 0-AP-10, " Loss of Electrical Power."
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SRO EXAM - REV. 2
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QUESTION: 054 (1.0)
t If a PRZR safety valve or a PRZR PORV were to fail 10% open, which one of the following could NOT be used to differentiate between whether it was the safety or PORV that was open?
a. . Tailpipe temperature. ,
b. Acoustical Monitor.
c. Valve position indicating light.
d. Press Safety Valve or PORV Open annunciator,
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I SRO EXAM - REV. 2
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QUESTION: 055 (1.0)
As directed by 1-ECA-0.0, " Loss of All AC Power," the crew places the charging pumps in PTL.
The defeat of the charging pump automatic start is to prevent: -
a. an uncontrolled over-pressurization of the RCS , and the resulting increased loss of RCS l inventory through the RCP seals when power is restored.
b. an excessive cooldown of the RCS due to injection of cold RWST water when power is :
restored.
c. the unnecessary use of water that may be needed for long term recovery. *
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d. a LOCA caused by thermal shock of the RCP seals when power is restored.
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i SRO EXAM - REV. 2
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QUESTION: 056 (1.0) I l
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At 4 % power during a startup on Unit I with the steam dumps in manual due to a failure of 1-MS-PT-1464 (MS Hdr Pressure) the RO withdraws rods 2 steps. The outward rod motion i continues after the IN-HOLD-OUT switch is released. As the rods step out, reactor power will and steam flow will a. increase; increase
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b. increase; remain the same i
c. remain the same; increase ,
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d. remain the same; remain the same ;
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SRO EXAM - REV. 2
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l QUESTION: 057 (1.0) i A leak on the letdown line caused' pressurizer level to drop. Given that the leak is isolated and pressurizer level is subsequently restored, which one of the following describes the effect of the l magnitude oflevel lost on the time required for PRZR pressure to return to normal? (Assume no !
operator actions after level restoration)
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a. The smaller the initial decrease, the less time it will take due to the integral reset of the j
master controller.
b. The smaller the initial decrease, the longer it will take due to the integral windup of the 1 master controller, c. The larger the initial decrease, the less time it will take due to the insurge of water from the "C" hot-leg. '
d. The larger the initial decrease, the longer it will take due to the insurge of relatively colder water.
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SRO EMt - REV. 2
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QUESTION: 058 (1.0) '
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During a reactor startup, what are the indications of the reactor achieving criticality?
a. Increase in RCS temperature, rise in pressurizer level, SG swell. *
b. Stable positive startup rate with no positive reactivity addition.
c. Stable positive startup rate during boron dilution.
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d. Stable positive startup rate during rod withdrawal.
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SRO EXAM - REV,2
QL. 'STION: 059 (1.0)
Given the following conditions:
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A steam break occurred inside Unit I containment.
- The immediate operator actions of 1-E-0 " Reactor Trip or Safety Injection" have been performed.
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Containment pressure has exceeded 28 psia and the crew has performed the continuous action steps for CDA actuation. ;
SG pressure is 350 psig and lowering, "B" and "C" SG pressures are 825 psig. l l
Which one of the following caused the main steam line isolation?
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a. Manualinitiation of CDA. I b. High steam line differential pressure.
c. Intermediate high containment pressure. I d. Phase A containment isolation signal.
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SRO EXAM - REV. 2
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QUESTION: 060 (1.0)
During the initial startup of an RCP with the pressurizer solid following a refueling outage, in accordance with OP-5.2, RCS pressure is controlled by:
a. adjusting the charging flow control valve (1-CH-FCV-1122) in manual.
b. manually adjusting charging flow through 1-CH-289 (1-CH-FCV-1122 manual bypass).
c. manual operation of 1-CH-PCV-1145 (Letdown Pressure Control Valve) using the raise and lower pushbuttons.
d. automatic operation of 1-CH-PCV-1145 (Letdown Pressure Control Valve) with adjustments to the potentiometer.
l-SRO EXAM - REV. 2
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QUESTION: 061 (1.0)
Select the set of conditions that will cause an automatic safety injection. !
a. Manualinitiation of phase A isolation.
l b. PRZR pressure channel one 1860 psig, channel two 1870 psig, channel three 1865 psig.
c. Turbine load 20%; SG steam flows (in Ib/hr): A - 0.8 E+6, B - 0.9 E+6, C - 1.7 E+6; SG pressures decrease rapidly to 700 psig.
d. Turbine load 100%; SG steam flows (in Ib/hr): A - 4.2 E+6, B - 4.9 E+6, C - 5 E+6; Loop Th: A - 600 F, B - 568 F, C - 567 F; Loop delta-Ts: A - 50 F, B - 52 F, C - 53 F. ,
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SRO EXAM - REV. 2
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QUESTION: 062 (1.0)
If all core exit thermocouples are inoperable during an event in which the RCPs were tripped, what other indication may be used to verify natural circulation cooling is occurring?
a. RCS hot leg temperatures.
b. Reactor coolant loop flow indication.
c. RCS subcooling as indicated on ICCM.
d. SG level rise with feed flow to the SG.
SRO EXAM - REV. 2
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L QUESTION: 063 (1.0)
The crew is in 1-ECA-0.0 * Loss of All AC Power" when it is necessary to throttle flow from the turbine driven auxiliary feedwater pump (1-FW-P-2) to the SGs due to excessive cooldown.
Safety injection has automatically initiated since entry into 1-ECA-0.0. Why is the BOP unable to reduce AFW flow? ,
a. 1-FW-MOV-100D is powered from the H emergency bus.
b. 1-FW-MOV-100D is powered from the J emergency bus.
O c. Safety injection must be reset prior to throttling the discharge MOV.
d. Steam generator levels must be > 18% prior to throttling AFW flow.
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SRO EXAM - REV. 2
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QUESTION: 064 (1.0)
Annunciators K-D2, " Rad Monitor System Hi Rad Level," and K-D4, " Rad Monitor Syst Hi-Hi Rad Level," were received due to high radiation on 1-RM-LW-111 (Clarifier Outlet).
Which of the following actions will NOT occur due to this condition?
a. 1-LW-PCV-115 (Liquid Waste Tunnel Isol Control) closes.
b. Steam Generator Blowdown pumps trip.
c. 1-LW-FCV-100 (Holdup Tank Influent Valve) closes.
d.' Contamir.ated Drains Tank pumps trip.
SRO EXAM - REV. 2
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QUESTION: 065 (1.0)
The relief office is working in the fuel building performing new fuel receipt inspections and
" splashing" the assemblies when the Hi and Hi-Hi alarms are received on 1-RM-RMS-152 "New Fuel Storage Area."
This condition will isolate MCR ventilation and:
a. dump bottled air and start all 41 d 42 fans.
b. dump bottled air and start all 41 m 42 fans.
c. start all 41 M 42 fans, but not dump bottled air.
d. start all 41 g 42 fans, but not dump bottled air.
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SRO EXAM - REV. 2
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QUESTION: 066 (1.0)
Following a turbine runback, the steam dump banks 1 and 2 will TRIP OPEN at error signal, and banks 3 and 4 will TRIP OPEN at error signal.
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a. 10 F; 16*F b. 10 F; 24'F c. 16*F; 24 F d. 16 F; 32 F ;
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QUESTION. 067 (1.0)
Unit I was operating at 100% power when a loss of the "H" emergency bus occurred. As the crew was diagnosing the event, "B" steam generator feedwater line severed inside containment resulting in containment pressure rising to 34 psig. All safety systems functioned as designed and service water was throttled prior to the event. How is service water flow to the recirc spray heat exchangers affected by this event?
a. Service water flow through the "A" and "B" RSHXs will be isolated.
b. Service water flow through the "A" and "C" RSHXs will be isolated.
c. Service water flow through the "A" and "D" RSHXs will be isolated.
d. Service water through all RSHXs will be unaffected.
SRO EXAM REV. 2
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QUESTION: 068 (1.0)
When a station service bus undervoltage occurs, the associated pressurizer backup heaters after voltage is restored. When an emergency bus undervoltage occurs, the associated pressurizer backup heaters after voltage is restored.
a. are automatically restored; are automatically restored b. are automatically restored; must be manually reset
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c. must be manually reset; must be manually reset d. must be manually reset; are automatically restored SRO EXAM - REV. 2
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l QUESTION: 069 (1.0)
If the differential temperature across unit 1 reactor at 50% power is 30 F, what would be the differential temperature across the reactor at 100% power?
l a. 15 F ;
l b. 30 F j l
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l SRO EXAM - REV. 2
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QUESTION: 070 (1.0)
Given the following inble 4.8-1 from Technical Specifications, determine the correct load sequencing for the listed components with a loss of power on lH emergency bus.
(Assume that the following component; were previously running)
1. "A" component cooling water pump 2. "A" auxiliary feedwater pump 3. "A" outside recirc spray pump 4. "A" service water pump a. 4,1, 2, 3 b.- 1, 4, 3, 2 c. 2,1, 4, 3 d. 3,4,2,1
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SRO EXAM - REV. 2
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l QUESTION: 071 (1.0). j
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Unit 1 is operating at 100% power , when a steam break occurs inside containment. 200 seconds i after the CDA signal was received, the following "A" train containment spray equipment !
- alignment existed - I
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e "A" quench spray pump,1-QS-P-1 A, - RUNNING -
- - "A" quench spray pump discharge valve,1-QS-MOV-101 A - OPEN
- "A" chemical addition tank outlet valve,1-QS-MOV-102A, - OPEN e "A" inside recirc spray pump,1-RS-P-1 A, - NOT RUNNING ,
-* "A" outside recirc spray pump,1-RS-P-2 A, - NOT RUNNING i e "A" casing cooling pump,1-RS-P-3 A, - NOT RUNNING i e "A" casing cooling pump discharge VALVE,1-RS-MOV-100A, - OPEN l
- "A" casing cooling pump discharge,1-RS-MOV-101B, - CLOSED
)
.l Select the set ofcomponents that are out of their required positions given the events that have :
occurred.
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a. 1-QS-MOV-102A,1-RS-P-1 A,1-RS-P-3A..
l b. 1-QS-MOV-102A,1-RS-P-1 A,1-RS-P-3 A,1-RS-MOV-101B.
j c. 1-QS-MOV-102A,1-RS-P-2A,1-RS-P-3 A,,1-RS-MOV-101B. !
I d. 1-RS-P-1 A,1-RS-P-2A,1-RS-MOV-101B. l
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QUESTION: 072 (1.0)
With the crew responding to a loss of secondary heat sink, why is it vital to initiate bleed and feed of the RCS as soon as the criteria are satisfied?
a. RCS pressure boundary could be challenged if PRZR PORVs are not manually opened.
b. Core damage could result due to inability to inject high head safety injection flow into the RCS at high RCS pressure.
l c. Steam generator tubes are no longer covered and the iodine " scrubbing" is no longer l occurring on the secondary side resulting in a greater offsite dose rate. !
d. If RCS temperatures are allowed to rise above 1000 F, bleed and feed will not be allowed and transition to 1-FR-C.1 " Response to Loss of Core Cooling" will be required. l l
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SRO EXAM - REV. 2
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QUESTION: 073 (1.0)
When starting an additional condensate pump, the discharge valve is normally throttled, then ;
opened after the pump is started. This is done to:
a. limit the effects of a stuck open discharge check valve. r b. limit the motor's starting current to prevent an overcurrent trip.
c. prevent feedwater train oscillations.
d. prevent pump runout.
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SRO EXAM - REV. 2 e.,4
f QUESTION: 074 (1.0)
A supture of the "A" service water supply header has occurred in the auxiliary building. Using the attached copy of 0-AP-12 " Loss of Service Water", determine which control room chiller must be re-aligned to isolate the ruptured service water header.
a. 1-HV-E-4 A.
b. 1-HV-E-4 C.
c. 2-HV-E-4B.
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d. 2-HV-E-4 C.
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SRO EXAM - REV. 2
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QUESTION: 075 (1.0)
- Unit 1 is ramping up at 0.3%/ minute and is presently at 50% power with turbine control in impulse pressure in (IMP IN). The safeguards operator hasjust called in and reported that the
"A" SG PORV is blowing steam. (Assume the PORV had slowly opened approximately 5% over
= a 15 minute period). The ramp is stopped. As the PORV is closed, indicated steam flow from the S/Gs will and turbine load will a. decrease; increase b. decrease; remain the same c. remain the same; increase d. decrease, decrease.
a SRO EXAM - REV. 2
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I QUESTION: 076 (1.0)
Unit 2 is being ramped up after a maintenance outage. Tavg is 2 F higher than Tref. With rods in manual, the indicated rod speed will be steps per minute. If rods were taken to automatic, indicated rod speed would be steps per minute.
a. 8; 8.-
i b. 8; 48
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I SRO EXAM - REV. 2
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QUESTION: 077 (1.0)
With the unit initially at 36% power in a chemistry hold, which one of the following can be used to confirm that a control rod has dropped into the core?
a. ' Individual Rod Position Indicator (IRPI).
' b. Power-range negative rate trip alarm.
c. Annunciator A C7 "NIS PR UP DET DEV - DEF <50%". ,
j d. Annunciator A D-2 " Rod Control Non-Urgent Failure".
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SRO EXAM - REV. 2
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QUESTION: 078 (1.0)
' l-RC-P-1B ("B" RCP) amps start fluctuating and the indicated vibrations begin increasing rapidly. The backboards operator reports that "B" RCP proximity ibration indication just
)
pegged high, then the indication went to zero. The amps continue to fluctuate. With respect to i the RCP only, which one of the following actions should be taken and why? !
a. Do not trip "B" RCP, the vibration instniment has failed and amp indication is known to occasionally fluctuate. l
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b. Do not trip the "B" RCP, because the only failure was the vibration monitoring indication / sensor failed.
c. Trip the "B" RCP, the vibration monitoring indication was over-ranged and therefore failed low.
d. Trip the "B" RCP, vibrations have returned to normal but fluctuating amps are an RCP tnp criterion.
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SRO EXAM - REV. 2 l
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QUESTION: 079 (1.0)
l A loss of the 1-I DC bus has resulted in the Terry Turbine (1-FW-P-2) starting. What actions must be taken to shutdown the Terry Turbine?
l a. Place the control switches in CLOSE.
b. Place the control switches to OPEN, then return to AUTO.
c. Manually close the inlet isolation to the trip valve.
d. Locally vent air from the valve operator.
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SRO EXAM - REV. 2
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QUESTION: 080 (1.0)
Which one of the following st.itements is correct if a High-High alarm is initiated by radiation monitor (1-RM-VG-101, " Process Vent Particulate Rad Monitor) during a waste gas decay tank release?
a. 1-GW-FCV-101 (Decay Tanks Effluent Flow Control) will close automatically and must be reset locally before it can be reopened.
b. 1-GW-FCV-101 (Decay Tanks Efiluent Flow Control) will close automatically and will l reopen automatically when the alarm condition clears and the CLOSE push-button is depressed. i c. 1-GW-TV-102A (Containment Vacuum Pump Discharge) will close automatically and j must be reset locally before it can be reopened. j d. 1-GW-TV-102A (Containment Vacuum Pump Discharge) will close automatically, and will reopen when the alarm condition clears and the OPEN push-button is depressed. i
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QUESTION: 081 (1.0)
A LOCA on Unit I has resulted in containment pressure exceeding 28 psia on 1-LM-PR-110B (Containment Pressure Recorder). What actions are required in accordance with the continuous action page of 1-E-0 " Reactor Trip or Safety Injection"?
a. Verify RCPs tripped and ensure QS pump discharge valves closed.
b. Manually initiate both trains of SI and ensure CC pumps stopped. l
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c. Close MSTVs and bypasses and manually actuate both trains of CDA.
l d. Manually actuate both trains of CDA and ensure QS pumps mnning.
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SRO EXAM - REV 2 l
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QUESTION: 082 (1.0)
The mechanical chiller is removed from senice for maintenance. Both unit's containments are being cooled by service water to the containment air recirc coolers. If a occurs on Unit 1, then SW will isolate to containment (s).
a. safety injection; only Unit 1 b. safetyinjection; both
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c. . containment depressurization actuation; only Unit I d. containment depressurization actuation; both '
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SRO EXAM - REV,2 l
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t QUESTION: 083 (1.0)
A LOCA has occurred on Unit 2 resulting in a safety injection. The high head safety injection system has failed. The crew is depressurizing the RCS to enhance core cooling in accordance with 1-FR-C.I. As RCS pressure decieases to psig, core cooling will be enhanced due to' injecting waterinto the RCS.
In a. 120; SI accumulators
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y b. 150; LHSIpumps ,
c. 250; LHSIpumps F
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d. 675; SIaccumulators-
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i QUESTION: 084 (1.0)
Containment panial pressure is at 9.3 psia with containment temperature of 101 F. Chilled water ;
is being supplied to the containment air recirc fans. Service water temperature is 88 F. In an !
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effort to lower containment temperature, the unit supervisor requests that the Unit 2 turbine building operator lower the setpoint of the thermostat knob on the mechanical chiller. How will this adjust affect the containment parameters and what is the major concern? :
a. Partial pressure will rise and temperature will rise, containment temperature exceeding 105 F requiring an engineedng evaluation.
b. Panial pressure will rise and temperature will lower, containment panial pressure going above the T.S allowable.
l c. Partial pressure will lower and temperature will lower, containment partial pressure gomg below the T.S. allowable. j i
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d. Partial pressure will lower and temperature will rise, containment temperature exceeding the T.S. limit of 120 F. )
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I QUESTION: 085 (1.0)
Due to a loss of a feedwater pump on Unit 1, the crew has been ramping down at 4% per minute for 5 minutes. Tavg is presently 3 degrees higher than Tref. How would the steam dumps respond to 1-MS-PT-1447 (Channel IV First Stage Pressure) failing low?
a. Steam dumps arm only.
b. Steam dumps arm, banks 1 and 2 modulated open to 25%.
c. Steam dumps arm, banks 1,2,3,4 receive trip open signal.
d. Steam dumps do not arm, banks 1,2,3,4 receive trip open signal.
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SRO EXAM - REV. 2
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QUESTION: 086 (1.0)
Follow'mg a refueling outage, an individual accidentally opened the breaker for the operating spent fuel pit cooling pump (1-FC-P-1 A). How would this condition be identified by the control room operator?
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a. "4160/480V BKR AUTO TRIP " annunciator.
b. "SFP HI/HI-HI TEMP" annunciator.
c. " LOSS SFP COOL FLOW" annunciator.
d. Spent fuel pit temperature increasing on Unit 2 vertical board.
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SRO EXAM - REV. 2
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l QUESTION: 087 (1.0)
Unit 2 was operating at 100% power with pressurizer level channel I in trip due to drifting out of tolerance. Pressurizer level channelII hasjust failed low. No reactor trip occurred and channel III of pressurizer level is indicating 64%. Based on these conditions, a
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l a. safe operatirig conditions exists, no reactor trip is required, and a unit shutdown is ,
required due to insuflicient number of operable pressurizer level channels. I l
b. reactor trip was required but failed to occur, and a unit shutdown is required due to an l inoperable reactor protection system.
c. safe operating condition exists, no reactor trip is required, and continued operation is '
allowed if the channel is placed in trip within one hour. l l
d. reactor trip was required but failed to occur, an unsafe operating condition exists, and the crew must transition to E-0. ;
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QUESTION: 088 (1.0)
Given the following conditions:
- Unit 1 is operating at 50% power
. 15F3 is tagged out for breaker maintenance e The 1H emergency bus is powered from the Unit station service bus While checking neutral bus volts, the OATC inadvertently takes the 15B2 breaker to TRIP As a result of this action, final status of the station service bus will be and the emergency bus will be . (Assume all equipment operates as designed.)
a. energized; energized b. energized; de-energized c. de-energized; de-energized d. de-energized; energized
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SRO EXAM - REV 2
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QUESTION: 089 (1.0)
Unit 2 is operating at 75% power when the "A" waterbox inlet closes. Condenser pressure will increase
a. due to steam jet air ejector becoming steam bound.
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b. because turbine load is too high for 3 waterboxes.
c. due to increasing water level in "B" hotwell.
d. and turbine load will automatically lower to return condenser pressure to normal.
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SRO EXAM - REV. 2
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QUESTION: 090 (1.0)
Unit 1 is operating at 100% power with the following conditions:
- l-FW-P-lC tagged cut for seal cooler modifications
. 1-FW-P-1B hasjust tripped due to an oilleak from the outboard bearing Which one of the following will initially cause 1-FW-P-3 A to automatically start?
a. 1 of 2 breakers open on 2 of 3 main feedwater pumps.
b. steam flow > feed flow by 34% on 1 of 3 steam generators.
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c. 1 of 3 steam generator levels < 18% on 2 of 3 channels.
d. AMSAC.
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SRO EXAM - REV. 2
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QL ESTION: 091 (1.0)
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- Unit 1 is operating at 70% power with pressurizer level control in MANUAL due to erratic operation of 1-CH-FCV-1122 (Normal charging flow control). At what level in the pressurizer will all pressurizer backup heaters automatically energize?
a. 15 %
b. 59%
c. 62 %
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d. 69.5 %
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SRO EXAM - REV. 2 i
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QUESTION: 092 (1.0)
During a normal unit cooldown at 480 F, a steam break on the 40" main steam header will result in:
a. a safety injection only.
b. a main stearti!ce isolation only.
c. a main steam line isolation and safety injection.
d. neither a main ste.am line isolation or safety injection.
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SRO EXAM - REV,2
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i QUESTION: 093 (1.0)
As 'the backboards operator is taking his logs, he places all Unit I radiation monitors in Check '
Source. Which one of the following will be a result of performing this action?
J a. Letdown isolation. l b. Containment pressure increase.
c. "B" vent stack flow decrease.
d. RSHX radiation monitor pumps start. ,
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SRO EXAM - REV. 2
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I QUESTION: 094 (1.0)
On a loss ofinstmment air, the service air dryer bypass (2-IA-TV-211) will automatically open :
when IA pressure lowers to psig, and when pressure is restored. '
a. 70; will automatically re-open i
b. 70; must be manually reset c. 90; will automatically re-open
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d. 90; must be manually reset i
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QUESTION: 095 (1.0)
While in Mode 6 with control rod unlatching in progress, the following plant conditions exist:
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The equipment hatch, with temporary hatch cover, is in place
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The outer door of the personnel hatch is open for maintenance on the rotating ring
. The inner door of the personnel hatch is closed
. The containment closure team is established NSS de:. ires to open the inner door to the personnel hat ch for 30 minutes to take scaffolding in containment. Using the attached copy of TS 3.9.4, determine if this should be allowed.
a. Yee, neither core alterations nor movement ofirradiated fuel is in progres ,
b. Yes, provided someone is assigned to close one airlock door if the need arises.
c. No, one door on the personnel hatch must be closed at all times during core alterations.
d. No, the surveillance requirement cannot be met for verifying the personnel hatch penetration is isolated.
SRO EXAM - PEV. 2
QUESTION: 096 (1.0)
The following conditions exist:
- Unit 1 is operating at 100% power
- Unit 2 is in day 3 of a refueling outage in the process of performing 2-PT-57.4 (SI Functional)
- Outside temperature is 38 F
- Service water spray valves are closed and bypasses are open for the SI functional For the functional test, safety injection is initiated on Unit 2. How will component cooling head tank level respond and why?
a. Increase, the additional heat added to the SW system by Unit 2 HHSI pumps.
b. Increase, the heat being removed from the Unit 2 RCS as the RCS cooldown from 547 F to 535*F continues.
c. Decrease, due to lowering CC temperatures caused by SW going on sprays.
d. Decrease, the standby CC pump will start forcing more flow through the CC heat exchangers, reducing CC temperatures.
SRO EXAM - REV. 2
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QUESTION: 097 (1.0)
During core onload, the crew secures the last containment air recirc fan due to decreasing containment temperatures. How does this action affect refueling activities?
I a. The RCS leak detection system is inoperable, therefore refueling activities must stop.
l b. Containment purge and exhaust system is inoperable, refueling must stop if containment purge and exhaust are in service. !
c. Containment temperature monitoring is inaccurate, refueling may continue as long as local ,
temperature monitoring is performed.
l d. . Partial pressure in contLinment will rise, but refueling may continue as long as partial l pressure is maintained < 12 psia. ;
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QUESTION: 098 (1.0)
A complete loss of the station service buses has resulted in a natural circulation cooldown. How is level maintained in the steam generators in accordance with AP-22.1, " Loss of 1-FN-P-2, Turbine-driven AFW Pump?"
a. Main feedwater regulating bypass valves in manual.
b. Local control of feedwater regulating bypass inlet isolation.
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c. Manual operation of auxiliary feedwater discharge MOVs and/or HCVs.
d. Local operation of auxiliary feedwater manual isolation to the individual SGs.
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!
QUESTION: 099 (1.0)
On the turbine control panel, when the Overspeed Protection Controller is placed in the Overspeed Test Position, then the is/are disabled to allow testing of the a. mechanical overspeed; OPCs b. mechanical overspeed; electrical overspeed c. OPCs; mechanical and electrical overspeed trips
/ OPCs; load drop anticipator circuit and electrical overspeed trips s
g.g-41 SRO EXAM - REV. 2
_ _ - _ _ _ . _ _ _ ._. __ . . . . _
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QUESTION: 100 (1.0) I Assume that all systems functioned as designed. Following a loss of offsite power, the subcooling indication on Train A oflCCM would: J
!. a. be fully functional.
b. indicate DATALINK FAILURE.
c. indicate -550 F.
d. be inaccurate.
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8-10-92 I
3/4 LIMITING CONDmONS FOR OPCAATION AND SURVEllI 3/4.0 APPUCAB!LITY LIMmNG CONDmON FOR OPERATION !
3.0.1 OPERATIONAL MODES or other conditions speerfied .
e for 3.0.2
Adherence to the requirements of the Umiting Condition for Operation ACTION within the specified time interval shall consttuteo.n ated compliance wi t
the of theLimiting Coretion ACTION statement for Operation is restored prior to expiration is not required. of the speci e event n erval, completion 3.0.3 requirements, within one hour ACTION shall be irutia Specification does not apply by placing it, as applicable, in :
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1. }
AtJeast HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.
3. At least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and At least COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that permit operation under th ACTION may be taken in accordance with the specified time alimits s,the ure to as me meet the Umiting Condition for Operation.
Spectications. This specification is not applicable in MODES 5 or 6. Exceptions M these requiremen 3.0.4 unless the conditions of the Urniting Condition for Ope ,
contained in the ACTION statements unless otherwise excepted. This provisioi passage through OPERATIONAL MODES as required to comply with ACTION staterren .
!
3.0.5 When a system, subsystem because its emergency power sourc. train, component, or device is determined to be inopera e is inoperable, or solety because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the applicable Umiting Condition for Operation, provided:
1.
2. Its corresponding normal or emergercy power source is OPERABLE, and OPERABLE, or likewise satisfy the requirements of ins S .
the urut in a MODE in which the Speafication does not app ,
1. At least HOT STa.NDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.
At least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3.
At least COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Exceptions apcable in MODES to these S or 6. requirements are stated in the individual Specifications. This S
. .
NORW ANNA - UNIT 1 3/4 0-1 Amendment No. 79,f8,62,164
. . _ . . _ . _ . . ._._ _ _ _..___ _ __
--
9-2-93 g CONTAINMENT SYSTE 4 CONTAINMENT RECIRCULATION SPRAY SYSTEM _
_ LIMITING CONDITION FOR OPERATION
-
3.6.2.2
'
Two trains of containment recirculation spray shall consist of: .
ach train shall b '
a. 1. 1 One inside containment recirculation spray s inside and flow containment path, and recirculation spray pump,ubsystem com I associated heat exchanger 2.
outside containment recircA-One outside containm o an '
ion spray pump, associated heat exchanger capable andfiuid of transferring flow from path, the rind a casing cooling pu
__the outside recirculation spray pump. casing cooling tank to the suct b. ;
One casing cooling tank (shared with both trains) with:
shall 1. l Contained borated water volume of at least 116,500 ga 2.
Between 2300 and 2400 ppm boron concentration.
3.
A solution temperature a 35'F and s 50* F.
APPL ICABILITY* Modes 1,2. 3 and 4 I ACTION-a.
With one containment recirculation spray subsystem inope containment recirculation spray train, restore the inoperable OPERABLE status within 7 days or be in at leastnext HOT S 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the inoperable subsystem to OPERABLE e next s
b.
46 hours5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br /> or be in COLD SHUTDOWN within the next 30 ours.
Wrth two containment recirculation spray subsystems inope containment recirculation spray train, restore one inoperable OPERABLE next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and instatus COLD SHUTDOWNwithin 72 within hours theor be e
following in30ath c. .
within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STA COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. n
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NORTH ANNA - UNIT 1 3/4 6-12 Amendment No. 5,33, 172
, ~. . .- -..__.,--_..--....-.......-,_~.-.-..n_,._..~ -
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TA3LE 4.8-1 h
LIST OF LOA 0 SE0VENCING_T:MERS AND DESIGN Pi.TPOINTS -
"H" BUS i
TIMER SET DOINT- INITIATINGII) TOLERANCE ;
IDENTIFICATION (SELCADS) __ SIGNAL (SECONDS) !
1 FWEA01-62 20' SI +1.00
-
1FWEA01-62A 25 LOP
)
+).25 ISWEA03-62 10- LOP
.. t
+0.60
, )
1RSOA01-62B 35 LOP +
i
_1.75 1RS0A01-62A i 210 CDA +
_21.0 ,
.lCCPA01-62Y 15. LOP +
-.0. 7 5 ICCPA01-62X 20 ' LOP +1.00
, i 1RSIA01-62A 20 LOP
<- +1.00 ;
,
l
.lRSIAO -62 195 CDA +p.75 i lQSSA01-62A 15 i LOP -0.75 t lHVRA03-62 30 LOP 1.50 1HVRA04-62 10
LOP +0.50 !
!
1HVRB04-62 10 LOP +0.50 l
.lPGSA02-62A -10 (2) +
e
_0.50 I ( 1ENSH06-62A 15 LOP +0.75
.-
lHVRC04-62 10 LOP +
L _.0.50 1SWSA35-62A1A 15' SI
- 4).50 l l: 1SWSA35-62BlA 15 SI +
_1.50
.
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l NORTH ANNA UNIT 1 3/4 8-4a Amendment No. 91
,
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. . - -
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3-27-87 t
l TABLE 4.8-1 (Continued)
LIST OF LOAD SE00ENCING "J" TIMERS AND DESIGN SETPOINTS -
BUS TIMER SET POINT INITIATING (I) TOLERANCE IDENTIFICATION (SECONOS) SIGNAL (SECONDS) ,
1FWEB01-62 20 SI 1
+1.00 1FWEB01-62A 25 LOP
]
+1.25 ISWEB03-62 10 LOP +
_0.50
>
1RSOB01-62B 35 LOP +
_1.75 1RSOBC1-62A 210 i CDA +21. 0
'
1CCPB01-62Y 15 LOP +
_0.75 1CCPB01-62X 20 LOP +1.00
_
1RSIB01-62A 20 LOP +1.00
,
'
_
1RSI501-62 195 CDA +9.75'
~
IQSSB01-62A 15 LOP +0.75 1HVRB03-62 30 LOP +1. 50 1HVRD04-62 10 LOP
-
+0.50 1HVRE04-62 10 LOP +0.50 1HVRF04-62 10 LOP +0.50
_
l 1PGSB02-62A 10 i (2) +0.50
~
1ENSJ06-62A 15 LOP +0.75 1SWSB35-62A1B 15 SI +1.50
_
1SWSB35-62B1B 15 SI +1.50 i
(1) SI - Safety Injection LOP - Loss of Offsite Power CDA - Containment Deoressurization Actuation (2) Low primary grade water header pressure NORTH ANNA UNIT 1 3/4 8-4b Amendment No. 91
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. VIRGINIA POWER
%. NORTH ANNA POWER STATIO4Nf0HIATl0N ONLY ABNORMAL PROCEDURE NUMBER PROCEDURE TITLE REVISION 0-AP-12 LOSS OF SERVICE WATER 11 PAGE (VITH EIGHT ATTACHMENTS)
1 of 12 PURPOSE *
To provide the. instructions to use in the event of a loss of Service Water.
%
ENTRY CONDITIONS This procedure is entered when there is a loss of Service Water as indicated by any or all.of the following:
Annunciator Panel "J" S-3, SERV WTR RETURN HDR LO FLOW, is LIT, or
Annunciator Panel "J" D-3, SW PP l-PlA, 2-PlA AUTO TRIP, is LIT, or
Annunciator Panel "J" E-3, AUX SW PP l-P4 LO FLOU, is LIT, or
Annunciator Panel "J" H-3, SW PP 1-PlB, 2-PIB AUTO TRIP, is LIT, or
Annunciator Panel "J" D-4, AUX SW PP 2-P4 LO FLOU, is LIT, or
Annunciator Panel "J" E-4, AUX SW PP 1 P4, 2-P4 AUTO TRIP, is LIT.
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RECOMMENDED APPROVAL: DATIL
'
EFFECTIVE RECOMMENDED APPROVAL - ON FILE DATE APPROVAL:
DATE
/ / 7~)
- APPROVAL - ON FILE
_ __.m _ _ . _ .m._ _ _ _ . _ _._.
_ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ . _ _
-
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j NUMBER
' PROCEDURE TITLE REVZSIdNg
'
11 r ,
0-AP-12 LOSS OF SERVICE WATER 1 PAGE
- 2 of 12
- 11 i
--
STEP --
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
, EQIE: * If a Reactor trip is initiated, then, to restore cooling to necessary plant equipment, this procedure should be performed in conjunction with Emergency Operating Procedures. 3
i
- .
- Loss of Service Water will result in loss of Component Cooling ~
and Residual Heat Removal Systems for tNe affected unit (s). This l g
procedure should be performed in conjunction with the appropriate
= Abnormal Procedures.
- To ensure proper operation of important equipment, CC temperatures should be continuously monitored during loss of j Service Water conditions.
)
- In emergency situations. Attachment 8 may be used to place Auxiliary Service Water Pumps in service. If the Auxiliary l Service Water pumps are placed in service, then NRC reportability requirements should be evaluated.
1. __ CHECK SERVICE WATER SYSTEM INTEGRITY:
!
a) Check Service Water Reservoir a) Do the following:
-level - GREATER THAN 310 FEET 1) If the Service Water Reservoir is intact, THEN begin a makeup using either Attachment 8 or 0-OP-49.3, t
SERVICE VATER RESERVOIR MAKEUP.
2) If level cannot be restored, THEN place the Auxiliary Service Water Pumps in operation using either Attachment 8 or 0 OP-49.2, SERVICE WATER SYSTEM LAKE-TO-LAKE OPERATION.
<
(STEP 1 CONTINUED ON NEXT PAGE)
-
. _ _ _ .-- .
. , - .. . - . - . . . . . _ - - . - . . - . _
,
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V
, NUMBER PROCEDURE TITLE REVISION I
+'3 0-AP 12 11 LOSS OF SERVICE WATER I PAGE 3 of 12 l l
i
-
STEP -
ACTION / EXPECTED RESPONSE l
RESPONSE NOT OBTAINED 1. CHECK SERVICE WATER SYSTEM INTEGRITY (Continued):
b) Check the following for b) Initicte appropriate procedure flooding - NOT INDICATED: ;
based on location of flooding: '
- NORMAL FLOODING '
,
- =Ghiller Room Sump level -
NORMAL * 0 AP 39.2, AUXILIARY BUILDING '
- Turbine Building Valve Pit FLOODING Sump level - NORMAL
- No report of flooding IE flooding is in other plant areas, THEN do the following:
1) Evaluate the need to isolate
.
affected header or equipment. l
!
!
2) If required, THEN stop the j Service Water Pumps on the ,
affected header.
!
3) If required, THEN isolate
!
the affected header using either of the following:
- Attachment 6 for "A" Service Water Header rupture OR
__
P
- Attachment 7 for "B" Service Water Header rupture i
e
.
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- . . . - -
- -. . . . . - .. ,--.-
NUMBER PROCEDURE TITLE ' REVISION 11 9 .
0-AP-12 LOSS OF SERVICE WATER PAGE 4 of 12
,
ll
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STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 2. CHECK SERVICE WATER SUPPLY HEADER STATUS:
a) Verify at least one Supply a) Trip both Reactors.
Header - INTACT GO TO Step 14.
b) Verify both Supply Headers - b)Verffyrunningorstartat INTACT least one Service Water Pump on the intact Supply Header and GO
-
TO Step 3.
E at least one Service Water Pump on the intact Supply Header cannot be started, THEN trip both Reactors and CO To Step 14 c) Verify at least one Service c) Start at least one Service Water Pump on each Supply Water Pump on each Supply Header - RUNNING Header.
H one Supply Header has NO
,
running SW Pump, THEN align l Service Water to both headers j using Attachment 4.
g.
E Service Water Pumps are NOT available. THEN place the Auxiliary Service Water Pumps in operation using either of the following:
- 0-OP-49.2, SERVICE WATER SYSTEM LAKE-TO 1AKE OPERATION EE
- Attachment 3 E at least one Supply Header is in service. THEN GO TO Step 3.
H no Supply Headers are in service, THEN trip both Reactorr and GO TO Step 14
.
k-.
. _ . . - - _ . - , _ . _ ~ . - . ~ - . . = - _ . . - . - - - - . - . - - - . . - . . . . - . -
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NUMBER PROCEDURE TITLE
! REVISION
,
- 11 0-AP-12 LOSS OF SERVICE WATER
,
PAGE 5 of 12 l
-
STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 3. ,_ VERIFY RETURN HEADER FLOUPATHS:
_s a) Verify No. 4 (A) Return Header a) Perform the following:
- FLOW INDICATED 1) Check for valve lineup
- l-SW-FI-103A problems.
==
QR 2) Align the desired Return
,
!
Header flowpath:
- 2-SU-FI-103B If return is aligned to QR spray, THEN open Spray Array Valves as required for
- 1-SU-FI-110A cooling:
QB * 1 SW-MOV 121A
- 1-SU-MOV-122A
,
i
- 2-SU-FI-110B * 2-SU-MOV-221B
- 2-SW-MOV-222B i
!
l 11 return is aligned to j Bypass Spray, THEN open l Bypass Spray Valves:
- 1-SW-MOV-123A
- 2-SW-MOV-223B
!
l If return is aligned to the lake, THEN open Service Water Discharge to Cire Tunnel Valves:
- 1-SU-MOV-120A
- 2-SW-MOV-220A l'
,
j (STEP 3 CONTINUED ON NEXT PACE)
'.. -
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_ _ _ -
,
' NUMBER PROCEDURE TITLE REVISI0N 11 .
0-AP-12 LOSS OF SERVICE WATER PAGE 6 of 12
--
STEP --
ACTION / EXPECTED RESPONSE- RESPONSE NOT OBTAINED 3. VERIFY RETURN HEADER FIhWPATHS (Continued):
b) Verify No. 3 (B) Return Header b) Perform the following:
- FLOW INDICATED 1) Check for valve lineup
- 1-SW-FI-104B problems.
_
2E 2) Align the desired Return
,
= Header flowpath:
- 2-SU-FI-104A lE return is aligned to QR spray, THEN open Spray Array Valves as required for
- 1-SU-TI-111B cooling:
DE * 2-SV-MOV-221A
- 2-SW-MOV-222A
- 2-SW-FI-lllA * l SW-MOV-121B
- l-SW-MOV-122B II return is aligned to Bypass Spray, THEN open Bypass Spray Valves:
- 1-SW-MOV-123B
- 2-SW-MOV-223A 11 return is aligned to the lake. THEN open Service Water Discharge to Circ Tunnel Valves:
- 1-SW-MOV-120B
- 2-SW-MOV-220B
-
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, NUMBER PROCEDURE TITLE REVISION
0-AP-12 11 LOSS OF SERVICE WATER __
PAGE
_
7 of 12
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STEP ---
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 4. _ VERIFY SERVICE WATER SYSTEM - C0 TO Step 8.
STABLE:
- Running Service Water Pump amps
- STABLE
- Service Water Pump Dischstge -'
pressure - NORMAL
- Both Service Water Supply Headers - IN SERVICE
- Both Return Header flows - NORMAL 5. _ VERIFY THE FOLLOWING EQUIPMENT - Have the Unit SRO enter the Action OPERABLE: Statement requirements of Tech Spec 3.7.4 for Unit 1 and Unit 2
- All four Emergency Diesel and perform the actions required Generators by the Action Statement.
- All four Service Water Pumps at the Service Water Reservoir
- Service Water Reservoir
- Both Service Water Supply Headers
- Both Service Water Return Headers 6. __ CHECK SERVICE WATER RESERVOIR Restore level as necessary.
LEVEL - BETWEEN 313 FEET AND 315 FEET 7. _ RETURN TO PROCEDURE AND STEP IN EFFECT EDTE: Throughout the remainder of this procedure, AFFECTED UNIT refers to the unit without Service Water available.
8. _ EVALUATE THE NEED TO SHUT DOWN THE UNITS BASED ON THE STATUS OF THE SERVICE WATER SYSTEM
.
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NUMBER PROCEDURE TITLE REV2SION 11 ,
0-AP-12 LOSS OF SERVICE WATER PACE 8 of 12
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STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED w
- 9. _ CHECK AFFECTED UNIT RCP Perform the following:
TEMPERATURES - NORMAL:
a) Trip affected unit.
- RCP Pump Bearing LESS THAN 22i?F
'
10. _ SECURE COMMON CC LOADS USING ATTACHMENT 5
l 11. _ MONITOR THE FOLLOWING SERVICE VATER SYSTEM LOADS:
- Control Room Chillers '
- CC Heat Exchangers/ System *
- Aux Building IA Compressors
- Charging Pumps b
12. _ INITIATE l-OP-21.11, BEARING COOLING SUPPLY TO THE UNIT 1 l CONTROL ROOM CHILLERS L-
9
_ _ . . - _ . ~ . - - . . ~ . _ , _ _ _ . . . _ . ._-. . . . - _ - . . . _...._~._~.____m____ _ _ _ . _ -
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,; NUMBER. PROCEDURE TITLE
.
, REVISION
' 11-0-AP-12 LOSS OF SERVICE VATER PAGE 9 of 12 l' -
l STEP -
ACTION / EXPECTED RESPONSE i RESPONSE NOT OBTAINED 13. _ RESTORE SERVICE WATER TO AFFECTED HEADER:
!
a) Check status of following:
1) Affected unit Supply Header 1) Continue efforts to restore
- AVAllABLE Service Water System and-r .
RETURN TO Step 8.
2)-Service Water Pump - 2) Cross-connect. Service Water
!
AVAllABLE to both units using Attachment 4, Continue efforts to restore Service Water System and RETURN TO Step 8.
( b) Start Service Water Pump c) RETURN TO Step 4 I L
]
!
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- 14. _ CHECK AFFECTED UNIT RCP Perform the following:
TEMPERATURES - NORMAL:
l
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_
a) Trip affected unit.
'
high temperatures. !
- RCP Pump Bearing - LESS THAN '
225'T
300*F l
15. ,_ SECURE COMMON CC LOADS USINC ATTACHMENT 5 l-l'
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.-y , , , . - - . -- - - ...-,-.-r 44 - . . .-,, ,- c.-
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NUMBER- PROCEDURE T8TLE REVISIbN 11 .
0 AP-12 IDSS OF SERVICE WATER
- PAGE L 10 of 12
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STEP -'
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l
16. _ MONITOR THE FOLIDWING SERVICE WATER SYSTEM 1 DADS:
- Control Room Chillers
!
- CC Heat Exchangers/ System
- Aux Building IA Compressors :
- Charging _ Pumps-
=
j ***************************************
CAUTION: To keep Charging in service, the Charging Pumps should be cycled to prevent overheating until a cooling source is restored.
- -*********************************
17. _ ALIGN ALTERNATE COOLING TO-CHARGING PUMPS USING EITHER OF THE FOLLOWING:
- Attachment 3 (Fire Protection System as cooling sotrce)
9_B
- Attachment 2 (PG as cooling source)
18. _ INITIATE I-OP-21.11. BEARING COOLING SUPPLY TO THE UNIT 1 CONTROL ROOM CHILLERS 19, _ ALIGN CHARGING PUMP SUCTION TO THE RWST
.
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NUMBER PROCEDURE TITLI REVISION l l
'
0-AP-12 11 LOSS OF SERVICE WATER PAGE !
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11 of 12 l
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STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED ,
1 l 20, __ RESTORE SERVICE WATER TO BOTH !
UNITS:
Perform the following: l
'
1) II at least one Service Water
.
I a) Check status of following: Supply Header is intact AND at
least one Service Water Pump is
- Both Service Water Supply avaflable, IHEN start a pump on
,
ficaders - INTACT the intact header.
_
AND 2) Continue efforts to restore Service Water System.
- Two Service Water Pumps -
AVAILABLE 3) Determine if Service Water System or Service Water loads b) Start Service Water Pumps can be crosstied.
4) RETURN TO Step 14.
21 __ VERIFY SERVICE WATER SYSTEM - RETURN TO Step 14 STABLE:
- Running Service Water Pump amps
- STABLE
- Service Water Pump discharge pressure - NORMAL
- Both Service Water Supply Headers - IN SERVICE
- Both Return Header flow NORMAL 22. __ SECURE ALTERNATE COOLING TO CHARGING PUMPS USING EITHER OF THE FOLLOWING:
- Attachment 3 (Fire Protection System as cooling source)
,
E
- Attachment 2 (PC as cooling #
source)
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l l NUMBER. PROCEDURE TITLE 2) REVZSZ N !
11 .
!
.0-AP-12 LOSS OF. SERVICE WATER j PACE l l 12 of 12
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STEP --
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED' l
!
! 1
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t l 23. __ VERIFY THE FOLLOWING EQUIPMENT - Have the Unit SRO enter the Action [
OPERABLE: Statement requirements of Tech i Spec 3.7.4 for Unit 1 and Unit 2 l
- All four Emergency Diesel and perform the actions required {
j Generators by the Action Statement. t
'
"
l * All four Service Water Pumps at l the Service Water Reservoir' f i. == e l * Service Water Reservoir ;
! * Both Service Water Supply Headers [
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- Both Service Water Return Headers- !
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24 __ CHECK SERVICE WATER RESERVOIR Restore level as necessary. i l LEVEL - BETWEEN 313 FEET AND 315 !
l FEET l f
25 __ REMOVE BEARING COOLING VATER TO l CONTROL ROOM CHILLERS FROM SERVICE l USING l-OP-21.11. BEARING COOLING !
SUPPLY TO THE UNIT 1 CONTROL ROOM l CHILLERS [
v 26. __ RETURN SERVICE WATER SYSTEM TO ,
NORMAL BY PERFORMING APPLICABLE !
SECTIONS OF THE FOLLOWING
' PROCEDURES:
- 0-OP-49.lA, VALVE CHECKOFF -
SERVICE MATER
- 0-OP-49.1, SERVICE WATER SYSTEM i l NORMAL OPERATION I
27. __ RETURN.TO PROCEDURE AND STEP IN i
.
EFFECT i
,- END - l 1 i
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4 NUMBER ATTACHMENT TITLE REVISION
,
0 AP-12
REFERENCES '
ATTACHMENT
PAGE llI 1 of 1 I
- Tech Spec' 3.7.4, 3.7.5.1
- 11715-FM-78A, B, C, F, G, H
.
- System Description 17-1
NRC SSOMI Service Water Issue -
'
CTS-02-89-2164-025
CTS 02-91-1808-003, Tech Spec Amendment 152/136
OP 95 1006, Revise procedures for SU/RSHX problems, St. Order 213
- DR 90-1670
- 0-OP-9A, VALVE CHECK 0FF PRIMARY GRADE WATER
0-OP-49.1, SERVICE WATER SYSTEM NORMAL OPERATION
0 OP-49.2, SERVICE WATER SYSTEM 1AKE-TO-LAKE OPERATION
0-OP-49.3, SERVICE WATER RESERVOIR MAKEUP
- 0-OP-49.1A., VALVE CHECK 0FF SERVICE WATER
0-AP-39.1. TURBINE BUILDING FLOODINC 1
0-AP-39.2, AUXILIARY BUILDING FLOODING
- 1 0-MOP-49.08, REMOVING NO. 1 SUPPLY (A) AND NO. 4 RETURN (A) HEADERS FROM j SERVICE AND RETURNING TO SERVICE t
0-MOP-49.09, REMOVING NO. 2 SUPPLY (B) AND NO. 3 RETURN (B) HEADERS FROM SERVICE AND RETURNING TO SERVICE
1-OP-21.11, BEARING COOLING SUPPLY TO THE UNIT 1 CONTROL ROOM CHILLERS
DCP 95-127, Charging Pump Casing Replacement {
l
DCP 95-216, Charging Pump Casing Replacement
.
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I I ll NUMBER ATTACHMENT TITLE REVIF3ON 0-AP-12 11 COOLING CHARGING PUMPS WITH PG ATTACHMENT UHEN SERVICE VATER IS NOT AVAIIABLE- PAGE ,' ,
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2 1 of 10 l
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EDIE: The capacity of the alternate PG supply will provide cooling for f one Charging Pump on each unit. Operating one Charging Pump at a I time on each unit will be necessary. ;
1. __ Place all Charging Pump Bearing temperatures on trend on the P-250.
2. __ Monitor the running Charging Pump temperatures.
l
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3 __ UHEE-che running Charging Pump bearing temperature alarms on high I temperature (170*F), IHEN stop the running Charging Pump and align another i available Charging Pump for operation.
>
t
Y4061A CHARGING PMP 1B INBD BRG T I'
=
Y4062A CHARGING PMP IB OTBD BRG T
Y4063A CHARGING PMP 1B THR BRG T
= '
Y4064A CHARGING PMP 1C INBD BRG T
Y4065A CHARCING PMP IC OTBD BRG T
'
i
Y4066A CHARCING PMP 1C THR BRG T i
,
NOTE: A key is required to unlock the Auxiliary Building Appendix R ,
locker. *
!
4. __ Get a 2 1/2-inch fire hose, a 2 1/2-inch double female fitting, and a !
spanner. wrench from.the Appendix R locker located on the second floor of i
the Auxiliary Building.
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, NUMBER ATTACHMENT T1TLE '
REVISION
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0-AP-12 11 COOLING CHARGING PUMPS WITH PG ATTACHMENT L' HEN SERVICE WATER IS NOT AVAILABLE PAGE
2 of 10
EDIg: All PG valves are located in the Fuel Building Basement except as indicated.
5. Locally align a Standby Primary Grade Water Pump as the cooling source:
a) II 1-PG-P-2A is desired to be used, IHEN perform the following:
__ 1) Stop 1-PG-P-2A. i
__ 2) Open 1 PG-17, 2A PC Utr Stby Pp Disch to Boron Ion Exch Isol Vv.
_
__ 3) Close 1-PG-18, 2A PG Utr Stby Pum; Disch to PG Supply Hdr Isol Vv. i b) If 1-PG-P-2B is desired to be used, THEN perform the following: !
l
__ 1) Stop 1-PG-P 2B.
__ 2) Open 1-PG-25, 2B PG Utr Stby Pp Disch to Boron Ion Exch Isol Vv.
__ 3) Close 1-PG-26, 2B PG Utr Stby Pump Disch to PC Supply Hdr Isol Vv. I c) Verify open or open the following valves:
__ 1) 1-PC-44, lA Primary Grade Utr Tank Recire Hdr Inlet Isol Vv
__ 2) 1-PG-82, Boron Cleanup lon Exch to lA PG Utr Tank Isol Vv d) Verify closed or close the following valves:
__ 1) 1-PG 33, lA PG Utr Svce Pp Disch to Boron Ion Exch Isol Vv
__ 2) 1-PG-42, 1B PG Wtr Svce Pp Di,ch to Boron Ion Exch Isol Vv
__ 3) 1-PG-45, 1B Primary Grade Utr Tank Recire Hdr Inlet Isol Vv
__ 4) 1-PG-85, Boron Cleanup Ion Exch to 1B PG Utr Tank Isol Vv
__ 5) 1-PG-83, lA Primary Grade Water Tank Fill Line Isol Valve (located in yard near PG Tanks)
__ 6) 1-BR-344, Boron Cleanup Filter To PG Water Tanks Isol Valve (located in Auxiliary Building basement near Boron Cleanup lon Exchangers)
__
7) 1-BR-TV-119, PC Water Tank Fill Isolation (operated from Liquid Maste Panel in Control Room) :
__
NUMBER ATTACHMENT TITLE REVISION l
!
l 0-AP-12 11
! COOLING CHARGING PUMPS VITH PC l ATTACRMENT WHEN SERVICE WATER IS NOT AVAIIABLE PAGE l 2 3 of 10
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l 6. Connect a 2 1/2-inch fire hose (with double female fitting) between the following:
__ e 1-PG-1033, 1-BR-TV-119 PG Outlet Drain Valve (located in the Auxiliary Building Basement behind 1-CC-E-1A)
AND
__
- l-SU-1214, Service Water Supply Hdr No 1 Test Conn Check Vv (check valve located north of 1-CC-E-1B and 2-CC-E-1A)
=
QE
__
- l-SW-1213, Service Water Supply Hdr No 2 Test Conn Check Vv i (check valve located north of 1-CC-E-1B and 2-CC-E-1A)
7. Close the Supply Header Isolation Valve that is being used to supply cooling to the Charging Pumps:
l __
l-SU-681, CH Pumps Cear Box Clrs SW Supply Hdr No 1 Isol Vv, for No. 1 (A) Supply Header (located upstream of 1-SU-1214)
__
l-SU-694, CH Pumps Gear Box Clrs SW Supply Hdr No 2 Isol Vv, for No. 2 (B) Supply Header (located upstream of 1-SU-1213)
8. Place the Charging Pump Lube Oil Cooler Alternate Supply Header in service by opening the isolation valve from the Supply Header that is
,
being used to supply cooling to the Charging Pumps:
__
1-SL'-711, CH Pps Lube Oil Clrs SW Altn Sply Hdr Isol Valve, for No. 1 (A) Supply Header (located behind 2-CH-P-lC cubicle)
2B ,
__
=
l-SU-707, CH Pps Lube Oil Clrs SW Altn Sply Hdr Isol Valve, for.No. 2 (B) Supply Header (located behind 1.CH-P-1A cubicle)
9. Verify the isolation valve from the Supply Header that is NOT being used to supply cooling to the Charging Pumps is closed:
__ * 1-SW-711 for No. 1 (A) Supply Header ,
_
2B
.,
__ * l-SU 707 for No. 2 (B) Supply Header
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. NUMBER \
ATTACHMENT TITLE REVISION 0-AP-12
COOLING CHARCING PUMPS VITH PG ATTACHMENT VHEN SERVICE WATER IS NOT AVAIlABLE PAGE
4 of 10 l NOTE: All Service Water valves that are operated in Steps 10, 11, 12, and 13 are located in the Auxiliary Building Basement behind the respective Charging Pump cubicles.
10. If the No. 1 (A) Supply Header is being used to supply cooling to the Charging Pumps, IEEN perform the following valve ali5nment for the Unit 1 Charging Pump that will be placed in service:
1-CH-P-1A -'
__ a) Vezify open 1-SW-688, lA CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
__ b) Verify open 1-SU-710, lA CH Pump Lube Oil Clr SW Altn Supply Isol valve.
__ c) Open 1 SU-666, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ d) Close 1-SW-660, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
__ e) Close 1-SU-643, 1C CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol Vv,
__ f) Verify closed 1-SW-649, 1B CH Pump Lube Oil Clr SW Altn Supply Isol valve.
__ g) Verify closed 1-SW-632, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
1 CH-P-1B
__ a) Verify open 1-SU 660, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
__ b) Verify open 1-SW-709, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ c) Open 1-SW-649, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ d) Close 1-SU-688, lA CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol,
__ e) Close 1-SU-643. 1C CH Pp Cear Box Clr SW Sply Hdr No 1 In1 Isol Vv.
__ f) Verify closed 1-SW-666, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ g) Verify closed 1-SW-632, IC CH Pump Lube Oil Clr 5W Altn Supply Isol Valve.
(STEP 10 CONTINUED ON NEXT PACE)
__
NUMBER ATTACHMENT TITLE REVISION 0-AP-12 11 COOLING CHARGING PUMPS VITH PG ATTACHMENT WHEN SERVICE WATER IS NOT AVAILABLE PAGE 2 5 of 10
'l l i
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l 10. If the No. 1 (A) Supply Header is being used to supply cooling to the Charging Pumps, IHEN perform rhe following valve alignment for the Unit 1 Charging Pump that will be placed in service (Continued). i l
1.CH-P-lC
__ a) Verify open 1-SW-643, 1C CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol Vv.
__ b) Verify open 1-SU-708, 1C CH Pump Lube Oil 1r SW Altn Supply Isol !
Valve.
__ c) Open 1-SU-632, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
-
__ d) Close 1-SW-688, lA C'i Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
O
__ e) Close 1-SU-660, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 In1 Isol.
'
__ f) Verify closed 1-SU-666, lA CH Pump Lube Oil Clr SW Altn Supply Isol ,
Valve.
t
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__ g) Verify closed 1-SW-649, 1B CH Pump Lube Oil Clr SW Altn Supply Isol :
Valve.
t 11. If the No. 1 (A) Supply Header is being used to supply cooling to the Charging Pumps. THEN perform the following valve alignment for the '
Unit 2 Charging Pump that will be placed in service:
!
2-CH-P-1A ,
__ a) Verify open 2 SW-629, lA CH Pp Gear Box Clrs SW Sply Hdr No 2 Inl Isol Vv. l
__ b) Verify open 2-SW 632, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ c) Open 2-SW-617, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve. !
i
__ d) Close 2-SU-611, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
__ e) Close 2-SU-594, 1C CH Pp Gear Box Clr SW Sply Hdr No 1 In1 Isol. :
.
__ f) Verify closed 2-SW-599, 1B CH Pump Lube oil Clr SW Altn Supply Isol Valve.
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t
__ g) Verify closed 2 SU-582, 1C CH Pump Lube Oil Clr SW Altn Supply Isol f Valve.
(STEP 11 CONTINUED ON NEXT PACE)
l I I
. _ - _ - - - - - - - - - - -
. NUMBER A2TACHMENT-TITLE REVISION
0-AP-12
COOLING CHARGING PUMPS WITH TG ATTACHMENT WHEN SERVICE WATER IS NOT AVAlIABLE PAGE
6 of 10 11. IE the No. l (A) Supply Header is being used to supply cooling to the Charging Pumps, IHg8 perform the following valve alignment for the Unit 2 Charging Pump that will be placed in service (Continued):
1-CH-P-1B
__ a) Verify open 2-SU-611, 1B CH Pp Gear Box Clr SW Sply ddr No 1 Inl Isol.
__ b) Verify Valve, open 2-SU-631, 1B CH Pump Lube Oil 1r SW Altn Supply Isol
__ c) Open 2-SU-599, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ d) Close '2-SU-629, lA CH Pp Gear Box Clrs SW Sply Hdr No 2 In1 Isol Vv,
__ e) Close 2-SU-594, 1C CH Pp Gear Box SW Clr Sply Hdr No 1 Inl Irol.
__ f) Verify closed 2-SW-617, lA CH Pump Lube Oil Clr SU Altn Supply Isol Valve.
__ g) Verify closed 2 SW-582, 1C CH Pump Lube Oil Clr SU Altn Supply Isol Valve.
2-CH-P-lC
__ a) Verify open 2-SU-594, 1C CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
__ b) Verify open 2-SU 630, 1C CH Pump Lube Oil Clr SW Altn Supply Isol
Valve.
__ c) Open 2-SU-582, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ d) Close 2-SU-629, lA CH Pp Gear Box Clrs SW Sply Hdr No 2 Inl Isol Vv.
__ e) Close 2-SW-611, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
__ f) Verify closed 2-SW.617, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ g) Verify closed 2-SW-599, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
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1 NUMBER ATTACHMEhT TITLE REVISION 0-AP-13 11 COOLING CHARGING PUMPS WITH PC ATTACHMENT WHEN SERVICE WATER IS NOT AVAIleBLE PAGE
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7 of 10 fl 12. If the'No. 2 (B) Supply Header is being used r.o supply cooling to the Charging Pumps, IHEN perform the following velve alignment for the Unit 1 Charging Pump that will be placed in service:
1 CH-P-1A
__ a) Verify open 1-SW-687, lA CH Pp Gear Box Clr SW Sply Hdr No 2 In1 Isol.
__ b) Verify open 1-SW-710, lA CH Pump Lube Oil 1r SW Altn Supply Isol Vaive.
__ c) Open 1-SV-666, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ d) Close 1-SU-659, 1B CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol.
__ e) Close 1-SW-642, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol Vv.
__ f) Verify closed 1-SW-649, 1B CH Pump Lube Oil Clr SW Altn Supply Isol valve.
__ g). Verify closed 1-SW-632. 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
1-CH-P-1B
__ a) Verify open 1-SW-659., 1B CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol.
__ b) Verify open 1 SU-709, IB CH Pump Lube Oil Clr SW Altn Supply Iso)
Valve.
l __ c) Open 1-SU-649, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ d) Close 1-SU-687, lA CH Pp Gear Box Cooler SW Sply Hdr No 2 Inl Isol.
__ e) Close 1-SU-642, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol Vv.
__ f) Verify closed 1-SU-666, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
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__ g) Verify closed 1-SW-632. IC CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
(STEP 12 CONTINUED ON NEXT PACE)
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. NUMBER ATTACHMENT TITLE REVISION 0-AP-13
'
COOLING CHARGING PUMPS WITH PC
. ATTACHMENT WHEN SERVICE WATER IS NOT AVAILABLE PACE
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12, II the No. 2 (B) Supply Header is being used to supply cooling to the Charging Pumps, IHEH perform the following vaive alignment for the r Unit 1 Charging Pump that will be placed in service (Continued):
1-CH-P-lc i
__ a) Verify open 1-SW-642, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol Vv.
__ b) Verify open 1-SW-708, 1C CH Pump Lube Oil Clr SU Altn Supply Isol Velve.
__ c) Open 1-SU-632, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ d) Close 1-SU-687, lA CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol.
__ e) Close 1-SW-659, IB CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol.
__ f) Verify Valve, closed 1-SW-666, lA CH Pump Lube Oil Clr SW Altn Supply Isol
.
__ g) Verify closed 1-SU-649, 1B CH Pump Lube Oil Clr SW Altn Supply Isol
=
Valve.
13. II the No. 2 (B) Supply Faader is being used to supply cooling to the Charging Pumps, THEN perform the following valve alignment for the Unit 2 Charging Pump that will be placed in service:
2-CH-P-1A
__ a) Verify open 2-SU 628, lA CH Pp Gear Box Clrs SW Sply Hdr No 2 Inl Isol Vv.
__ b) Verify open 2 SU-632, IA CH Pump Lube Oil Clr SW Altn Supply Isol valve.
__ c) Open 2-SU-617. lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve,
__ d) Close 2-SW-610, 1B CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol.
__ e) Close 2-SU-593, 1C CH Pp Gear Box Clr SW sply Hdr No 2 Inl Isol.
__ f) Verify closed 2-SU 599, 1B CH Pump Lube Oil Clr SW Altn Supply Isol valve,
__ g) Verify closed 2-SW 582, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve, (STEP 13 CONTINUED ON NEXT PAGE)
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NUMBER ATTACHMENT TZTLE REVISION 0-AP 12 11 COOLING CHARGING PUMPS WITH PG
-
ATTACHMENT VHEN SERVICE WATER IS NOT AVAIIABLE PAGE
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2 9 of 10 -
fl 13. If the No. 2 (B) Supply Header is being used to supply cooling to the Charging Pumps. I}igi perform the following valve alignment for the Unit 2 Charging Pump that will be placed in service (Continued):
2-CH-P-1B
_ a) Verify open 2-SW 610, 1B CH Pp Gearbox Clr SW Sply Hdr No 2 Inl Isol.
-
-
_ b) Verify open 2-SW-631, 1B C" Pump Lube Oil Clr SW Altn Supply Isol Vakare .
_ c) Open 2-SU-599, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
_ d) Close 2 SU 628, lA CH Pp Gear Box Clrs SW Sply Hdr No 1 Inl Isol Vv.
_ e) Close 2-SW-593, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol Vv.
_ f) Verify closed 2-SW-617, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
_ g) Verify closed 2 SW 582, 1C CH Pump Lube 011 Clr SW Altn Supply Isol Valve.
2-CH-P-lC
_ a) Verify open 2 SW-593, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol.
_ b) Verify open 2-SW-630. 1C CH Pump Lube 011 Clr SW Altn Supply Isol Valve.
_ c) Open 2-SW-582, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
_ d) Close 2-SU-628, lA CH Pp Gear Box Clrs SW Sply Hdr No 1 Inl Isol Vv.
_ e) Close 2-SU 610, 1B CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol.
_ f) Verify closed 2-SU-617, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve..
_ g) Verify closed 2-SW-599, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
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. NUMBER ATTACHMENT TITLE REVISZON l i ,
0-AP 12 '
'
COOLING CHARGING PUMPS WITH PG
.
ATTACHMENT WHEN SERVICE WATER IS NOT AVAI W LE PAGE
10 of 10 !
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.14. ,__ Locally verify open or open 1-PG-81, 1-BR-TV-119 PG Dutlet Isolation Valve (located downstream of 1-BR TV-119) .
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15. __ Locally open 1-PG-1033, 1 BR-TV-119 PG Outlet Drain Valve, (Fire Hose connection).
!
l 16. __ Start the Standby Primary Grade Water Pump alfgned in Step 5.
l1 ' r-l 17. Start the desired Unit 1 Charging Pump:
__
- l-CH-P-1A 4 l
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__
- 1-CH-P-1B- 1
__
- l-CH-P-1C 18. Start the desired Unit 2 Charging Pump:
__
- 2-CH-P-1A
! __
- - 2-CH-P-1B
__
- 2-CH-P-1C
!
-19. l WHEN the Service Water- System has been restored, THEN perform the j following: '
__ a) Stop the Standby Primary Grade Water Pump started in Step 16.
__ b) Close 1-PG-1033.
i
__ c) Return the PC System to a normal lineup using 0 OP-9A, VALVE CHECKOFF PRIMARY GRADE WATER.
__ d) Open 1-BR 344, Boron Cleanup. Filter To PC Water Tanks Isol Valve'
(located in Auxiliary Building Basement near Boron Cleanup Ion Exchangers).
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__ e) Remove the 2 1/2--inch fire hose and the double female fitting from f 1-PG-1033 and store in the Appendix R locker on the second floor of the Auxiliary Building. -
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l NUMBER ATTACHMENT "EITLE REVI620N 0-AP-12 11 l COOLING CHARGING PUMPS WITH FIRE PROTECTION ATTACHMENT SYSTEM.WHEN SERVICE WATER IS NOT AVAILABLE PAGE 3 1 of 8 il 1. __ Place all Charging Pump Bearing temperatures on trend on the P-250.
2. __ Monitor the running Charging Pump temperatures.
3. __ EHEN the running Charging Pump bearing temperature alarms on high
. temperature (170*F), IHEH stop the running Charging Pump and align another available Charging Pump for operationi
- Y4066A CHARGING PMP 1C THR BRG T r N0'TE : A key is required to unlock the Auxiliary Building Appendix R l locker.
,
4. __ Get two 2 1/2-inch to 1 1/2-inch reducers, two 1 1/2-inch double female fittings, and a spanner wrench from the Appendix R locker located on the second floor of the Auxiliary Building.
5. . Install a.2 1/2 inch to 1.1/2-inch reducer (with a 1 1/2-inch double female fitting) to each of the following:
__
- 1-SU-1214, Service Water Supply Hdr No 1 Test Conn Chtck Vv (check valve located north of 1-CC-E-1B and 2-CC-E-1A)
__
- 1-SW-1213, Service Water Supply Hdr No 2 Test Co'nn Check Vv
,
(check valve located north of 1-CC-E-1B and 2-CC-E-1A)
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NUMBF.R ATTACHMENT TITLE REVISION
^ 0-AP-12 '
ATTACHMENT COOLING CHARCING PUMPS WITH FIRE PROTECTION SYSTEM UHEN SERVICE WATER IS NOT AVAILABLE PACE
2 of 6 HQIE: The fire hose stations listed in the next two steps are the preferred hose stations. If the listed hose station is inoperable, then the next closest hose station should be used.
6. __ Connect a 1 1/2-inch fire hose from hose station near the elevator in the Auxiliary Building Basement to the double female fitting on No. 1 (A)
Supply Header connection, 1-SW-1214 (located north of 1-CC-E 1B and 2-CC-E-1A).
7. __ Connect a 1 1/2-inch fire hose from hose station in the northwest section of the Auxiliary Building Basement to the double female fitting on No. 2 (B) Supply Header connection, 1-SU-1213 (located north of 1-CC E-1B and 2-CC-E-1A).
!
8. Close the following Supply Header Isolation Valves:
__ a) 1-SW-681, CH Pumps Cear Box Clrs SW Supply Hdr No 1 Isol Vv, for No. 1 (A) Supply Header (located upstream of 1-SW-1214)
__ b) 1-SW-694 .CH Pumps Gear Box Clrs SW Supply Hdr No 2 Isol Vv, for No. 2 (B) Supply' Header (located upstream of 1-SU 1213)
,
9. Start'a Fire Pump:
, __
l-FP-P 1, Motor Driven Fire Pump l
EE i
__ * l-FP-P-2, Diesel-Driven Fire Pump i
If 1-FP-P-2 cannot be started using the normal control system, THEN j start 1-FP-P-2 using the seismic start switch (located on the blue ~
Peerless MAN TROL panel on the north side of the engine) as follows: {
1) Raise the cover on the left toggle switch.
2) Place the toggle switch to the START position and release when the !
engine starts. Switch spring returns to the RUN position.
3) If the engine does not start, THEN raise the cover on the right l toggle switch, select the other battery, and try again to start the ;
engine. '
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NUMBER ATTACH.YENT TITLE REV1S' ION 0-AP-12 '
COOLING CHARGING PUMPS WITH FIRE PROTECTION ATTACHMENT SYSTEM WHEN SERVICE WATER IS NOT AVAILABLE PAGE
3 of 8
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'l 10. Open both Charging Pump Lube Oil Cooler Alternate Supply Header Isolation Valves:
__ a) 1-SW-711, CH Pps Lube Oil Clrs SW Altn Sply Hdr Isol Valve, for No. 1 (A) Supply Header (located behind 2-CH-P-lC cubicle)
__ b) 1-SW-707, CH Pps Lube Oil Clrs SW Altn Sply Hdr Isol Valve, for No. 2 (B) Supply Header (located behind 1-CH-P-1A cubicle)
EOTE. Atl Service Water valves that are operated in Steps 11,12, 13, and 14 are located in the Auxiliary Building Basement behind the respective Charging Pump cubicle.
11. Close the following No. 2 (B) Supply Header to Seal and Gear Box Coolers to the Unit 1 Charging Pumps:
__ a) 1-SW-687, lA CH Pp Gear Box Cooler SW Sply Hdr No 2 Inl Isol.
__ b) 1-SW-659, 1B CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol.
__ c) 1-SU-642, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol Vv.
12. Close the following No. 1 (A) Supply Header to Seal and Gear Box Coolers to the Unit 2 Charging Pumps:
__ a) 2-SU-629, lA CH Pp Gear Box Clrs SW Sply Hdr No 2 In1 Isol Vv.
__ bi 2-SU 611, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
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__ c) 2-SU-594, 1C CH Pp Gear Box Clr SW Sply Hdr No 1 In1 Isol.
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i NUMBER l ATTACHMENT TITLE REVISION
,
0-AP-12 L. *
COOLING CHARCIM, PUMPS WITH FIRE PROTECTION
-
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' ATTACHMENT SYSTEM WHF?' SERVICE WATER IS NOT AVAILABLE PAGE L 3 4 of 8
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13.
Perform the following valve alignment for the Unit 1 Charging Pump that will be placed in service:
1-CH-P-1A
E a) Verify open 1-SW-688, lA CH Pp Gear Box Cooler SW Sply Hdr No 1 Inl Isol.
b) Verify open 1-SW-710, lA CH Pump Lube Oil Clr SW Altn Supply Isol
..
Valve.
,
c) Open 1-SU-666, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
,,,, d) Close 1-SW-660, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
_ e) Close 1-SW-643, 1C CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol Vv.
_,,,,, f) Verify closed 1-SU-649, 1B CH Pump Lube Oil Clr SW Altn Supply Isol valve.
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g) Verify closed 1-SU-632, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve. I
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i 1-CH-P-1B
_
a) Verify open 1-SU-660, 1B CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol.
_ b) Verify open 1-SU-709, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
,
.,_,_ c) Open 1-SU-649, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
_ d) Close 1 SW 688, lA CH Pp Gear Box Cooler SW Sply Hdr No 1 Inl Isol.
_ e) Close 1-SU-643, 1C CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol Vv.
,_ f) Verify closed 1-SW 666, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
_ g) Verify closed 1 SU-632. 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
l (STEP 13 CONTINUED ON NEXT PACE) *
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NUMBER ATTACHMENT 'IITLE REVIS'lON l 0-AP-12 11 l COOLING CHARCING PUMPS WITH FIRE PROTECTION l ATTACHMENT SYSTEM VHEN SERVICE WATER IS NOT AVAILABLE PAGE 3 5 of 8
'l 13. Perform the following valve alignment for the Unit 1 Charging Pump that will be placed in service (Continued):
1-CH-P-lc
__ a) Verify open 1-SU-643, 1C CH Pp Gear Box Clr SW Sply Hdr No 1 Inl Isol Vv.
__ b) Verify open 1-SU-708, 1C CH Pump Lube Oil Clr SU Altn Supply Isol Valve.
=
__ c) Open 1-SU-632, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ d) Close 1-SW-688, lA CH Pp Gear Box Cooler SW Sply Hdr No 1 In1 Isol.
__ e) Close 1-SU-660, 1B CH Pp Gear box Clr SW Sply Hdr No 1 In1 Isol Vv.
__ f) Verify closed 1-SU-666, lA CH Pump Lube Oil Clr SU Altn Supply Isol Valve.
__ g) Verify closed 1-SW-649, 1B CH Pump Lube Oil Clr SU Altn Supply Isol Valve.
14 Perform the following valve alignment for the Unit 2 Charging Pump that will be placed in service:
2-CH-P-1A
__ a) Verify open 2-SU-628, lA CH Pp Gear Box Clrs SW Sply Hdr No 1 Inl Isol Vv.
__ b) Verify open 2-SW-632, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ c) Open 2-SW-617, lA CH Pump Lube 012 Clr SW Altn Supply Isol Valve.
__ d) Close 2-SU-610, 1B CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol.
__ e) Close 2 SU 593, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 In1 Isol.
__ f) Verify closed 2-SU-599,1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ g) Verify closed 2-SW-582, 1C CH Pump Lube Oil Clr SW Altn Supply Isol Valve. -
(STEP 14 CONTINUED ON NEXT PACE)
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NUMBER ATTACHMENT TITLE REVISION l 0-AP-12
' COOLING CHARGING PUMPS WITH FIRE PROTECTION ATTACHMENT SYSIEM WHEN SERVICE WATER IS NOT AVAI W LE PAGE l
6 of 8 i
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1 14 Perform the following valve alignment for the Unit 2 Charging Pump that will be placed in service (Continued):
l 2-CH-P-1B l l
__ a) Verify open 2-SW-610, 1B CH Pp Gear Box Clr SW Sply Hdr No 2 In1 Isol.
__ b) Verify open 2-SW-631, 1B CH Pump Lube 011 Clr SW Altn Supply Isol Valve.
_.
__ c) Open 2-SW-599, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ d) Close 2-SU-628, lA CH Pp Gear Box Clrs SW Sply Hdr No 1 Inl Isol Vv. l
__ e) Close 2-SW-593, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol.
__ f) Verify closed 2-SW-617., lA CH Pump Lube Oil Clr SU Altn Supply Isol Valve.
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__ g) Verify closed 2 SW-582, 1C CH Pump Lube Oil Clr SW Altn Supply Isol I Valve.
2-CH-P-1C
__ a) Verify open 2-SW-593, 1C CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol.
,
' __ b) Verify open 2-SW-630, 1C CH Pump Lube 011 Clr SU Altn Supply Isol valve.
__ c) Open 2 SW-582, IC CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ d) Close 2-SW-628, lA CH Pp Gear Box Clrs SW Sply Hdr No 1 Inl Isol Vv.
__ e) Close 2-SW-610 1B CH Pp Gear Box Clr SW Sply Hdr No 2 Inl Isol.
__ f) Verify closed 2-SW-617, lA CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
__ g) Verify closed 2-SW 599, 1B CH Pump Lube Oil Clr SW Altn Supply Isol Valve.
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NUMBER ATTACHMENT TITLE REVIS30N 0-AP-12 11 COOLING CHARGINJ PUMPS WITH FIRE PF9TECTION ATTACHMENT SYSTEM WHEN SERVICE WATER IS NOT AVAIIABLE PAGE 3 7 of 8 ;
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EQTE: FP valves listed are for the preferred hose stations. The valve l number may be different if another hose station is used. )
15. Open the Fire Hose Isolation Valves that are connected to the-Service Water Supply Headers: i
__
- 1-FP-167, AUX BLDG FIRE PROTECTION HOSE RACK ISOLATION VALVE (near elevator in Auxiliary Building basement)
__ * l-FP-163, AUX BLDG FIRE PROTECTION HOSE RACK ISOLATION VALVE (naar stairs to Auxiliary Building second floor) '
16. Start the desired Unit 1 Charging Pump: l
__ * 1-CH-P-lA
- l-CH-P-1B !
__
- 1-CH P-lC -
l 17. Start the desired Unit 2 Charging Pump: 1
__
- 2-CH-P-1A f
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__
- 2-CH P-1B
__ * 2-CH-P-lC i l
HQIf: FP valves listed are for the preferred hose stations. The valve I number may be different if another hose station is used.
18. WHEN the Service Vater System has been restored, THEN perform the f following:
a) Close the Fire Hose Isolation Valves that are connected to the Service Water Supply Headers:
__ 1-FP-167, AUX BLDC FIRE PROTECTION HOSE RACK ISOLATION VALVE (near elevator in Auxiliary Building basement)
__
l-FP-163, AUX BLDC FIRE PROTECTION HOSE RACK ISOLATION VALVE ,
(near stairs to Auxiliary Building second floor),
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(STEP 18 CONTINUED ON NEXT PACE)
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. NUMBER ATTACHMENT TZTLE 0-AP-12 REVISION l1
'
ATTACHMENT COOLING CHARGING PUMPS WITH FIRE PROTECTION SYSTEM WHEN SERVICE WATER IS NOT AVAILABLE PACE j
8 of 8 18. WHEN the Service Water System has been restored. THEN perform the following (Continued):
b) Remove the fire hoses from the Service Water Supply Headers and store them on the hose racks:
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__
Northeast section (near elevator in Auxiliary Building basement)
__
Northwest section (near stairs to Auxiliary Building second floor)
c) Remove the following two 2 1/2-inch to 1 1/2-inch reducers. along with the double female fittings, and store them in the Auxiliary Building Appendix R locker:
__ 1-SU-1214, Service Water Supply Hdr No 1 Test Conn Check Vv (check valve located north of 1-CC-E-1B and 2 CC-E-1A)
__ 1-SU-1213, Service Water Supply Hdr No 2 Test Conn Check Vv (check valve located north of 1-CC-E-1B and 2-CC-E-1A)
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I NUMBER ATTACHMENT *l8TLE REVISION 0-AP-12 11 ALIGNfNG ONE SW PUMP PER SUPPLY HEADER ATTACHMENT WHEN NO PUMPS ARE RUNNING ON ode HEADER PAGE 4 1 of 3
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CAUTION: Discharge pressures for ASIH running Service Water Pumps must be maintained greater than 30 psig (monitored in the Control Room) in order to avoid pump runout.
In order to maintain SW pump discharge pressures above 30 psig, throttling of the SW outlet valve (s) for thd CCHX(s) supplied from the No. 2 (B) Supply Header may be necessary.
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1. If HQ Service Water Pumps are running on No. 2 (B) Supply Header, THEN align one pump to No. 2 (B) Supply Header:
__ a) Ensure 1-SU-P-1A and 2 SU-P-1B are both running.
b) Select either 1 SU-P-1A or 2-SU-P-1B to be aligned:
__
- l-SW-P-1A
__
- 2-SU-P-1B t
l c) lE l-SW P-1A was selected. THEN perform the following:
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__ 1) Throttle open 1 SW 4, lA SW Pp Disch to Supply Hdr No 2 Isol Valve, while maintaining SW Pump discharge pressure > 30 psig in the Control Room on 1 SU-PI-101A.
2) VHEN discharge pressure stabilizes THEN do the following:
__ a Throttle closed 1 SU-6, lA SW Pp Disch to Supply Hdr No 1 Isol Valve.
__ b. Throttle open 1 SW-4
__ c. Repeat substeps a. and b. unc SW 4 is full open AND l-SW-6 is full closed.
__ 3) RETURN TO step in effect.
(STEP 1 CONTINUED ON NEXT PAGE) -
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. NUMBER ATTACHMENT TITLE REVISION
, 0-AP-12 '
'
ALIGNING ONE SW FUMP PER SUPPLY HEADER ATTACHMENT WHEN NO PUMPS ARE RUNNING ON ONE HEADER PACE
2 of 3 I 1. If HQ Service Water Pumps are running on No. 2 (B) Supply Header, IHEH align one pump to No. 2 (B) Supply Header: (continued)
d) II 2-SU-P-1B was selected, IEEE perform the following:
__
1) Throttle open 2-SU-ll, 1B SW Pp Disch to Supply Hdr No 2 Isol Valve, while maintaining SW Pump discharge pressure > 30 psig in the Control Room on 2-SW PI-201B. -
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2) WHEN discharge pressure stabilizes, THEN do the following:
__ a. Throttle closed 2-SU 13, 1B SW Pp Disch to Supply Hdr No 1 Isol Valve.
__ b. Thrcttle open 2 SW-ll.
__
c. Repeat substeps a. and b. until 2-SU-ll is full open AND 2-SU-13 is full closed.
_,,, 3) RETURN TO step in effect.
CAUTION: Discharge pressures for BOTH running Service Water Pumps must be maintained greater than 30 psig (monitored in the Control Room) in order to avoid pump runout.
In order to maintain SW pump discharge pressures above 30 psig, throttling of the SW outlet valve (s) for the CCHX(s) supplied from the No. 1 (A) Supply Header may be necessary.
- 1 2. lE HQ Service Water Pumps are running on No. 1(A) Supply Header,
,
THEN align one pump to No. 1 (A) Supply Header:
I
__ a) Ensure 1-SU-P 1B and 2 SU P-1A are both running. l l'
b) Select either 1 SW-P-1B or 2-SW-P-lA to be aligned:
__
- l-SU-P 1B l :
__
- 2-SW-P-1A (STEP 2 CONTINUED ON NEXT PACE)
)
NUMBER ATTACHMENT TIT 1I REVISION b 0-AP-12 11 ALIGNING ONE SW PUMP PER SUPPLY HEADER
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ATTACMENT PAGE WHEN NO PUMPS ARE RUNNING ON ONE HEADER .
4 3 of 3 Il 2. If HQ Service Water Pumps are running on No. 1(A) Supply Header, IHEH align one pump to No. 1 (A) Supply Header: (continued)
c) If 1-SW-P-1B was selected, IHEN perform the following:
__ 1) Throttle open 1-SW-13,18 SW Pp Disch to Supply Hdr No 1 Isol Valve, while maintaining SW Pump discharge pressure > 30 psig in the Control Room on 1-SW-PI-101B.
=.
2) WHEN discharge pressure stabilizes, IHEN do the following:
__ a. Throttle closed 1-SW-11, 1B SW Pp Disch to Supply Hdr No 2 Isol Valve.
__ b. Throttle open 1-SU-13.
__ c. Repeat substeps a. and b. until 1 SW-13 is full open AND l-SU-ll is full closed.
__ 3) RETURN TO step in effect.
d) II 2 SW-P-1A was selected, THEN perform the following:
__ 1) Throttle open 2-SW-6, lA SW Pp Disch to Supply Hdr No 1 Isol Valve, while maintaining SW Pump discharge pressure > 30 psig in the Control Room on 2-SW-PI-201A.
2) WHEN discharge pressure stabilizes, THEN do the following:
__ a. Throttle closed 2-SU-4, lA SW Pp Disch to Supply Hdr No 2 Isol valve.
__ b. Throttle open 2 SW-6.
__ c. Repeat substeps a. and b. until 2-SW 6 is full open AND 2-SU-4
.is full closed.
__ 3) RETURN T0 step in effect.
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- NER ATTACHMENT 78TLE REVISION 0-AP-12 SECURING COMMON CC LOADS ATTACHMENT IACE
1 of 3 1. _ Secure the Boron Evaporators by pushing the INTERLOCK OFF pushbuttons.
.
2. Verify stopped or stop both Spent Fuel Fool Cooling Pumps:
_
- 1-PC-P-1A
_ * 1-FC-P-1B
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3. Secure SG Blowdown by closing the following Unit 1 SG Blowdown Trip Valves:
__ 1-BD-TV-100A
_
1-BD-TV-100B
_ * 1-BD TV-100C
__
- 1-BD-TV-100D
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- 1-BD-TV-100E
__.* 1-BD-TV-100F
Secure SC Blowdown by closing the following Unit 2 SC Blowdown Trip Valves:
_
2-BD-TV-200A
__
2 BD TV-200B
__ * 2-BD-TV-200C
_
- 2-BD TV-200D
__
- 2-BD TV-200E
_ * 2-BD TV-200F
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NER ATTACHMEN1 T!TLE REV1SS'ON 0-AP-12 11 ATTACHMENT PAGE 5 2 of 3 Il 5. Secure steam to the gas strippers by closing the following valves:
__ * 1-BR-TCV-103A
__ * 1-BR-TCV-103B
__ * 1-BR-PCV-159A a
__ * 1-BR-PCV-159B
=
6. Secure Gas Stripper Discharp Pumps:
__ * 1-BR-P-10A
__
- 1-BR-P-10B 7. Secure Gas Stripper Compressors:
__
- l-BR-C-1A
__
- l-BR-C-1B 8. Secure Waste Cas Compressors:
__
- 1-GU C-1A
__
- 1-GW-C-1B 9. __ Secure 1-BR-P-8, Boron Evaporator Bottums Cooler Pump.
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- NER ATTACHMENT TITLE REV2S20N
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0-AP-12
SECURING COMMON CC LOADS ;
ATTACHMENT IACE '
3 of 3 10. Close the following Unit 1 and Unit-2 RCS Sample Trip Valves:
_
- 1-SS-TV-100A
_
1-SS-TV-103A
1-SS-TV-112A
_
- 1-SS-TV-101A
.-
_
- 1-SS-TV-104A
_ * 14S-TV-106A
_
- 1-SS-TV-102A
_
- 1-SS-TV-100B
- 1-SS-TV-103B
_
- 1-SS-TV-112B
- 1-SS-TV-101B
-
_. * 1-SS-TV-104B
_ * 1-SS-TV-106B
_ * 1-SS-TV-102B
_ * 2-SS-TV-200A
_ * 2-SS-TV-203A
_.
2-SS-TV-212A
__. 2-SS-TV-201A-
_
2-SS-TV 204A
_
2-SS-TV-206A
_ * 2-SS-TV-202A
2-SS-TV-200B
_
2-SS-TV-203B
_ * 2-SS-TV-212B
_ 2-SS-TV-201B
2 SS-TV-204B i. _ * 2-SS-TV 206B
._
2-SS-TV-202B-
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I I I NUMBER ATTACHMENT TITLE REVISION 0-AP-12 11
"A" SERVICE WATER HEADER RUPTURE ATTACHMENT PACE 6 1 of 5
'l EDIE: * This Attachment provides instructions to align the Unit 1 CC Heat Exchangers to the "B" Service Water Header and secure the Servi:e Water System crossties.
9teps may be performed in any order or together to expedite isolation of the ruptured Service Water Header.
This Attachment may be modified as necessary by the Unit SRO to ensure break isolation from the "B" Service Water Header.
=
1. Stop the following Service Water Pumps:
__
- l-SU-P-1A
__
- 2-SW-P-1B l 2. Close the following valves to prevent header siphoning:
__
l-SU-6, lA SW Pp Disch to Supply Header No 1 Isol Valve
__
1-SW-13, 1B SW Pp Disch to Supply Header No 1 Isol Valve l __
2-SU-6, lA SW Pp Disch to Supply Header No 1 Isol Valve
__ * 2-SU-13, 1B SW Pp Disch to Supply Header No 1 Isol Valve 3. _, Start a second Service Water Pump on the "B" Service Water Header as directed by the Unit SRO.
i
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4 Do the following to align the 1-CC-E-1A to the "B" Service Water Header:
__ a) Close 1-SW-223, lA Component Cooling Hx SW Sply Hdr No 1 Isol Vv.
__ r) Open 1-SW 222, IA Component Cooling Hx SW Sply Hdr No 2 Isol Vv.
__ c) Close 1-SU 230, lA Component Cooling Hx SV Ret Hdr No 4 Isol Vv.
.
__ d; Throttle open 1 SW-231 lA Component Cooling Hx SW Ret Hdr No 3 l Isol Vv, as directed by the Unit SRO.
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. NUMBER ATTACHKENT T1T12 REVISION 0-AP-12
"A" SERVICE WATER HEADER RUPTURE ATTACHMENT PACE
2 of 5 5. Do the following to align the 1-CC-E 1B to the "B" Service Water Header:
__ a) Close 1-SW-233, 1B Component Cooling Hx SW Sply Hdr No 1 Isol Vv.
__ b) Open 1-SU-232, 1B Compcnent Cooling Hx SW Sply Hdr No 2 Isol Vv.
__ c) Close 1-SU-241, 1B Component Cooling Ex SV Ret Hdr No 4 Isol Vv.
__ d) Throttle open 1-SU 240, 13 Component Cooling Hx SU Ret Hdr No 3 I mel Vv , as directed by the Unit SRO.
6.
Close the following Service Water Supply Valves to the CC System:
__ l-SW-MOV-10BA
__ = 1-SU-MOV-108B 7. __ Close 1-SU-247, Service Water Return Hdr No 4 Isolation Valve.
8. Close the following valves to isolate Charging Pumps and Instrument Air Compressors from the "A" Service Water Header:
__
1-SU-681, CH Pumps Gear Box Clrs SW Supply Hdr No 1 Isol Vv (located in Auxiliary Building 244 foot level behind 2-CC-E-1A)
__ * 1-SU-678, CH Pumps Cear Box Clrs SW Return Hdr No 4 Isol Vv (located in Auxiliary Building 244 foot level west of 1-CC-E-1B)
__ = 1-SW-251, Inst Air Ht Exchs SW Sply Header No 1 Isol Valve (located in Auxiliary Building 259 foot level north of Cardox Tank)
__ * 1 SW-286, Inst Air Ht Exchs SW Ret Header No 4 Isol Valve (located in Auxiliary Building 259 foot level north of Cardox Tank)
9. Secure the Service Water crosstie through 1-SW-RM-107 as follows:
__ a) In the Control Room, stop 1 SU-P 9B.
b) In the Auxiliary Building Basement, close the following valves:
__
l-SW 249 SW Radiation Monitor 107 to Ret tdr No 4 Isol Vv
__
1 SW-504, 9B SW Rad Monitor Pump suction Isolation Valve
.
- - - _ - - _ _
_ _
NUMBER ATTACHMENT TXTLE REVISION 0-AP-12 11
"A" SERVICE WATER HEADER RUPTURE ATTACHMENT PAGE 6 3 of 5 Il EDIE. Unit 1 "A" and "C" Control Room Chillers are normally supplied from the "B" Service Water Header. Unit 1 "B" Control Room Chiller is normally supplied from the "A" Service Water Header.
10. In the Unit 1 Chiller Room, do the following:
__ a) Close 1-SU-287, Heat And Vent Chillers SW Sply Hdr No 1 Isol Vv.
__ b) Close 1-SW-290, Heat And Vent Chillers SW Ret Hdr No 4 Isol Vv.
=.
__ c) Open 1-SU-385, Heat And Vent Chiller 4C SW Outlet Hdr Isol Valve.
__ d) Open 1-SU-405, Heat And Vent Chiller 4C SW Outlet Hdr Isol Valve.
__ e) Open 1-SU-362, Heat And Vent Chiller 4C SW Inlet Hdr Isol Valve.
__ f) Open 1-SU-418, Heat And Vent Chiller 4C SW Inlet Hdr Isol Valve.
__ g) If 1-HV-E-4B was running prior to the event, THEN start 1-HV-E-4B as directed by the Unit SRO.
NOTE: Unit 2 "B" Control Room Chiller is normally supplied from the "B" Service Water Header. Unit 2 "A" and "C" Control Room Chillers are normally supplied from the ' A Service Water Header.
11. In the Unit 2 Chiller Room, do L e following:
__ a) Close 2-SU-224, SW Sply Hdr No 1 to Cont Room HV Chlrs Isol Valve.
__ b) Close 2-SW-227, SW Ret Hdr No 4 to Cont Room HV Chlrs Isol Valve.
__ c) Open 2-SW-302, Heat And Vent Chiller 4C SW Outlet Hdr Isol Valve.
__ d) Open 2-SU-357, Heat And Vent Chiller 4C SW Outlet Hdr Isol Valve.
__ e) Open 2-SW-305, Heat And Vent Chiller 4C SW Inlet Hdr Isol Valve.
__ f) Open 2-SW-335, Heat And Vent Chiller 4C SW Inlet Hdr Isol Valve.
__ g) If 2-HV-E-4A or 2-HV-E-4C were running prior to the event, THEN start 2-HV-E-4A or 2 HV E-4C as directed by the Unit SRO.
. NUMBER ATTACHMENT TITLE REVISION 0-AP-12
"A" SERVICE WATER HEADER RUPTURE
'
ATTACHMENT PAGE
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12. In the Control Room, verify the following valves are closed:
__ l-SW-MOV-105C, "A" SV Return Hdr From RSHX Isol Valve
__ e 1-SU-MOV-105D, "A" SW Return Hdr From RSHX Isol Valve
__ * l-SU-MOV-101A, "A" SW Supply Header To RSHX Isol Valve i
-
__ * 1-SU-MOV-101B, "A" SW Supply Header To RSHX Isol Valve
=
__ l-SU-MOV-ll5A, Aux SW Pp Disch Hdr Iso Vv
=
__
1-SU-MOV-ll3B, Fuel Pit Coolers Supply Hdr (normally de-energized closed)
__ = 1-SU-MOV-110B, Recire Air Cooler Supply From "A" Header (normally de-energized closed)
__ e 1-SU-MOV-ll4B, Recire Air Cooler Return To "A" Header (normally de-energized closed)
__ = 2-SU-MOV-205C, "A" SV Return Hdr From RSHX Isol Valve
__ = 2-SW-MOV-205D. "A" SU Return Hdr From RSHX Isol .21ve
__
__
2-SU-MOV-201B, "A" SV Supply Header To RSHX Isol Valve l
__ 2-SW MOV-215B, Aux SW Pp Disch Hdr Iso Vv i
__
2-SU-MOV-213A, Fuel Pit Coolers Return Hdr (normally de-energized closed)
__ = 2-SW-MOV-210A, Recire Air Cooler Supply From "A" Header (normally de-energized closed)
__ * 2-SV-MOV-214B, Recire Air Cooler Return To "A" Header (normally de-energized closed)
.. ..-. . . . . .- - ~. . - . . - - . . _ _ _ . - . - . - _. .- - - - - - - ...
- - . . . . - . . . _ - - . . - _ . . _ .
NUMBER ATTACHMENT TITLE REVIS' ION 0-AP-12 11 .
"A" SERVICE WATER HEADER RUPTURE !
ATTACHMENT PAGE l 6 5 of 5 !
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13. . Secure the Service Water crosstie through 1-SU-P-10 as follows: }
!
_ a) In the Control Room, stop 1-SU-P-10. I t
b) In the Service Water Pit in the Unit 1 Turbine Building Basement, close the following valves- {
i e' 1-SU-31, SV Ret Hdr No 4 to SW Rad Mon Pump 10 Suet Isol Vv
_ !
!
_ *=1-SW-35, SV Rad Mon Pump 10 Disch to Ret Hdr No 4 Isol Vv l
e HQIg: 0-MOP-49.08. REMOVING NO. 1 SUPPLY (A) AND NO 4 RETURN-(A) HEADERS t FROM SERVICE AND RETURNING TO SERVICE, provides instructions to i drain the "A" Service Water Header to the lake. If the Service i Water rupture is above 252 foot elevation, then this method could ,
stop the Service Water leakage into the plant.
f 14 CO TO 0-MOP-49.08, REMOVING NO. 1 SUPPLY (A) AND NO. 4 RETURN (A) HEADERS [
FROM SERVICE AND RETURNING TO SERVICE, to complete isolation and tagout of !
the "A" Service Water Header as directed by the Shift Supervisor, t
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NUMBER ATTACHMI.NT T171.E REVISION
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0-AP-12
"B" SERVICE WATER HEADER RUPTURE ATTACHKENT PACE
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EOIg: *
This Attachment provides instructions to align the Unit 2 CC
- Heat Exchangers to the "A" Service Water Header and secure the i
Service Water System crossties.
Steps may be performed in any order or together to expedite isolation of the ruptured Service Water Header.
This Attachment may be modified as nedessary by the Unit SRO to ensure break isolation from the "A" Service Water Header.
=
t 1. Stop the following Service Water Pumps:
__ * 1-SU-P-1B
__
- 2-SW-P-1A 2. Cimse the following valves to prevent header siphoning:
__
l-SU-4, lA SW Pp Disch to Supply Header No 2 Isol Valve ;
__ * l-SU-ll, 1B SW Pp Disch to Supply Header No 2 Isol Valve I
__
2-SW-4, lA SW Pp Disch to Supply Header.No 2 Isol Valve
,
__ * 2-SU-ll, 1B SW Pp Disch to Supply Header No 2 Isol Valve i
3. __ Start a second Service Water Pump on the "A" Service Water Header as
- ' directed by the Unit SRO.
4 Do the following to align the 2-CC-E-1A to the "A" Service Water Header:
__ a) Close 2 SW-176, IA Component Cooling Hx SW Sply Hdr No 2 Isol Vv
__ b) Open 2-SU-177, lA Component Cooling Hx SW Sply Hdr No 1 1 sol Vv
__ c) Close 2-SU-184, lA Component Cooling Hx SW Ret Hdr No 3 Isol Vv
__ d) Throttle open 2-SW-185, lA Component Cooling Hx SW Ret Hd: No 4 Isol Vv, as directed by the Unit SRO.
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NUMBER' ATIACHMENT TITLE REVIS' ION 0-AP-12 11
"B" SERVICE WATER HEADER RUPTURE ATTACHMENT PAGE 7 2 of 5
'l 5. Do the following to align the 2-CC-E-1B to the "A" Service Water Header:
__ a) Close 2-SW-187, 1B Component Cooling Hx SW Sply Hdr No 2 Isol Vv
__ b) Open 2-SU-186, 1B Component Cooling Hx SW Sply Hdr No 1 Isol Vv
__ c) Close 2-SU-194, 1B Component Cooling Ex SW Ret Hdr No 3 Isol Vv
__ d) Throttle open 2-SU-195, 1B Component Cooling Hx SW Ret Hdr No 4 Isod Vv, as directed by the Unit SRO.
6. Close the following Service Water Supply Valves to the CC System:
^
__
- 2-SU-MOV-208A r
__
- .2 SU MOV-208B l
!
7. __ Close 1-SW-250, Service Water Return Hdr No 3 Isolation Valve. ,
,
I 8. Close the following valves to isolate Charging Pumps and Instrument Air Compressors from the "B" Service Water Header: ,
__
l-SU-694, CH Pumps Gear Box Clrs SW Supply Hdr No 2 Isol Vv l (located in Auxiliary Building 244 foot level behind 2-CC-E-1A)
!
__
(located in Auxiliary Building 244 foot level west of 1-CC-E-1B) ;
__ * 1-SU-254, Inst Air Ht Exchs SW Sply Header No 2 Isol Valve (located in Auxiliary Building 259 foot level north of Cardox Tank)
__
+ 1-SU-285, Inst Air Ht Exchs SV Ret Header No 3 Isol Valve (located in Auxiliary Building 259 foot level north of Cardox Tank)
i 9. Secure the Service Water crosstie through 1 SW-RM-107 as follows:
__ a) In the Control Room, stop 1-SW P-9A. i
-
b) In the Auxiliary Building Barement, close the following valves: I
__ l-SW-246 SW Radiation Monitor 107 to Ret Hdr,No 3 Isol Vv
__
1-SU-503, 9A SW Rad Honitor Pump Suction Isolation Valve
.
m -- - - - ,,e - - ._ _ _ _ _ __ _._ _ __ __ _ ___.- _- . _ _ _ _ _ _ _ _ _ _ - _ _ _ -
_ _ _ . _ . . _ - ._ _ _ _ , . _ _ _ _ _ . _ _ .
. _ . _ _ . _ _ _ _ _ _ _ ._ _ ;
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NUMBER _ ATTACHMENT TITLE REVISION I l , 0-AP-12 11 ;
--
"B" SERVICE WATER HEADER RUPTURE
,
i ATTACHMENT i PAGE i 7 t 3 of 5 i
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E2IE: Unit 1 "A" and "C" Control Room Chillers are normally supplied from l the "B" Service Water Header. Unit 1 "B" i i
normally supplied from the "A" Service Water Control Room Chiller is Header.
10. In the Unit 1 Chiller Room, do the following:
__ a) Close 1-SU-288 Heat and Vent Chillers SW Sply Hdr No 2 Isol Vv.
- 1
! __ b) Close 1-SU-289, Heat and Vent Chillers SV Ret Hdr No 3 Isol Vv.
__ c)- Op n 1-SU-385, Heat and Vent Chiller 4C SW Outlet Hdr Isol Valve.
! __ d) Open 1-SU-405, Heat _and Vent Chiller 4C SW Outlet Hdr Isol Valve.
!
__ e) Open 1-SU-362, Heat and Vent Chiller 4C SW Inlet Hdr Isol Valve.
__ f) Open 1-SU 418, Heat and Vent Chiller 4C SW Inlet Hdr Isol Valve.
[
__ g) If 1-HV-E-4A or 1-HV-E-4C were running prior to the event. THEN start j. 1-HV-E-4A or 1-HV-E-4C as directed by the Unit SRO.
i NOTE: Unit 2 "B" Control Room Chiller is norrally supplied from the "B" Service Water Header. Unit 2 "A" and "C" Control Room Chillers are i normally supplied from the "A" Service Water Header.
11. In the Unit 2 Chiller Room, do the following:
__ a) Close 2-SW-225, SW Sply Hdr No 2 to Cent Room HV Chlrs Isol Valve. l
!
I
__ b) Close 2-SU-226, SV Ret Hdr No 3 to Cont Room HV Chlrs Isol Valve.
__ c) Open 2-SU-302, Heat and Vent Chiller 4C SU Outlet Hdr Isol Valve.
__ d) Open 2-SW-357, Heat and Vent Chiller 4C SW Outlet Hdr Isol Valve.
__ e) Open 2-SU-305, Heat and Vent Chiller 4C SW Inlet Hdr Isol Valve.
__ f) Open 2-SW-335. Heat and Vent Chiller 4C SW Inlet Hdr Isol Valve.
__ g) If 2-HV-E-4B was running prior to the event. THEN start 2-HV-E-4B as directed by the Unit SRO.
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-- 1 I NUMBER ATTACHMENT T2TLE REVISION 0-AP-12 11
"B" SERVICE WATER HEADER RUPTURE ATTACHMENT PAGE 7 4 of 5 l
12. In the Control Room, verify the following valver are closed:
__
__
l-SW-MOV-105B. "B" SW Return Hdr From RSHX Isol Valve ,
__
- ;
__
- =
__
- 1-SW-MOV-115B Aux SW Pp Disch Hdr Iso Vv
l l __
l-SW-MOV-113A, Fuel Pic Coolers Return Hdr (normally ;
de-energized closed)
,
__ = 1-SW-MOV-110A, Recire Air Cooler Supply From "B" Header (normally de-energized closed)
__ = 1-SU-MOV-114A, Recire Air Cooler Return To "B" Header (normally ;
de-energized closed) '
r
__
__
- 2 SW-MOV-205B, "B" SU Return Hdr From RSHX Isol Valve f i
__
!
__
'
__
2-SU-MOV-215A, Aux SW Pp Disch Hdr Iso Vv l
__ 2-SW-MOV-213B, Fuel Pit Coolers Supply Hdr (normally '
de-energized closed)
__ 2-SU-MOV-210B, Recire Air Cooler Supply From "B" Header (normally de-energized closed) l
__
2-SW-MOV-214A, Recirc Air Cooler Return To "B" Header (normally l
de-energized closed)
'.
!
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- . . - . _ - _ _ - . . - _ - -
. . - . . _ __ _ . . ~ . _ . _ . _ _ _ _ . . . . _ _ . _ _ _ _ __. __ . . _ _ . . _ _ _ _ _ . _ _ _ .
- NUMBER ;
ATTACHMENT TITLE REV1SION
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- 0-AP-12
i .-
"B" SERVICE WATER HEADER RUPTURE
..
ATTACHMENT i P/.GE ;
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5 of 5
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13. Secure the Service Water crosstie through 1-SW-P-10 as follows:
__ a) in the control Room, stop 1-SW-P-10.
( b) In the Service Water Pit in the Unit 1 Turbine Building Basement, I close the following valves:
__
1-SW-28, SW Ret Hdr No 3 to SV Rad Mon Pump 10 Suct Isol Vv I:
i
,_
- =-1-SW-34, SW Rad Mon Pump 10 Disch to Ret Hdr No 3 Isol Vv HOIE:
-
0-MOP-49.09, REMOVING No.2 SUPPLY (B) AND No. 3 RETURN (B) HEADERS i
FROM SERVICE AND RETURNING TO SERVICE, provides instructions to drain l the B" Service Water Header to the lake.
l-If the Service Water
'
rupture is above 252 foot elevation, then this method could stop the Service Water leakage into the plant.
14. ,_ CO TO 0-MOP-49.09 REMOVING NO.2 SUPPLY (B) AND NO. 3 RETURN (B) HEADERS FROM SERVICE AND RETURNING TO SERVICE, to complete isolation and tagout of the "B" Service Water Header as directed by the Shift' Supervisor.
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NUMBER ATTACHMENT TITLE REVISION 0 AP-12 11 .
OPERATION OF AUXILIARY SERVICE WATER PUMPS 8 1 of 3 d
EQIg: This Attachment provides instructions for aligning the Auxiliary Service Water Pumps for Service Water Makeup and for Lake-To-Lake Operation.
1. Send an Operator to put the following Service Water Overboard Discharge Valves in DEFEAT (located in the Service Water Logic Cabinet):
-
"A" HEADER
_
- 1 -sW-MOV- 120A
_
- 2-SU-MOV-220A
"B" HEADER
_
- l-SW-MOV-120B
_
- 2-SU-MOV-220B 2. Verify the following Screen Wash Pumps are stopped:
_
- 1-CW-P-2B
_
- 2-CW P-2A 3. Close the following valves:
_,
- l-SU-MOV-118
_
- 1-SU-MOV-119
_
- 2 SU-MOV-219 4 lg 1-sW.P-4 will be started THEN open the following valves:
_
- l-SU MOV-ll5A
._
2 SU-MOV-215B
- l-SW-MOV-ll?
.
.
-
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. MER (
l 0-AP-12 ATTACHMENT TITLE REVISION
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l ATTACHMENT PERATION OF AUXILIARY SERVICE WATER PUMPS f PAGE t 8 2 of 3 l
S. II 2-SW-P-4 will be started..IHEH open the following valves:
- 2-SW-MOV-215A
__
__ * 1-SU-MOV-115B.
__ * 2-SW-MOV-217
6. Start =the desired Auxiliary Service Water Pumps:
__
- 1-SU-P-4
__
- 2-SU-P-4 7. If Service Water Reservoir makeup is desired, THEN do the following:
a. Open all Service Water Spray Valves:
__
l-SW-MOV-121A
-
__
l-SU-MOV-122A
__ 1-SU-MOV-121B
- 1-SW-MOV-122B
__
__ 2-SU-MOV-221A
__ = 2-SU-MOV 222A
__ * 2-SU-MOV-221B
__ 2-SU-MOV-222B b. Close the following Service Water Overboard Discharge valves:
__ * 1-SW-MOV-120A
__ * l-SU-MOV-120B i
i __ 2-SW-MOV-220A
? --
l- *
2-SU-MOV 220B
__
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- .. . .- ~. . . . . . . . - - .. . - ~ . - - . - = . ~ . . .. . . . . .. ._ - _ - - . . . . .
WMBER ATTACHMENT TITLE REVISION 0-AP-12 g3 . ,
l OPERATION OF AUXILIARY SERVICE WATER PUMPS ATTACHMENT PAGE L
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8. JI Lake-To-lake operation is desired. THEM do che following:
a. Open the following Service Water Overboard Discharge Valves:
"A" HEADER ,
'
- 1-SW-MOV-120A
~
- ,
._
- 2-SU-MOV-220A
=
"B" HEADER
!
- 1-SU-MOV-120B ,
_
_ * 2-SU-MOV-220B b. Close all Service Water Spray Valves:
'
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,___ * 1-SU-MOV-121A
_ * l-SU-MOV-122A
- 1-SW-MOV-121B
_ j l
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,_
- 1-SU-MOV-122B
,
_
- 2-SW-MOV-221A
,
I
_
- 2-SW MOV-222A !
_ * 2 SU-MOV-221B ;
.
_ * 2-SW-MOV-222B l
!
9. RETURN TO step in effect,
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_ . _-__ __ __ _ ._- _. . _ _ _ _ . . _ _ _ . - _ _ _ _ . - _ _ . _ _ _ ,
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. REFUELING OPERATIONS 02-27-96 CONTAINMENT BUILDING PENE 1 RATION _S LIMITING CONDITION FOR OPERATION 3.9.4 a. The containment building penetrations shall be in the followin b.
The equipment door closed and held in place by a minimum ,
A minimum of one door in each airlock is closed, * and c. j outside atmosphere shall be either:Each penetration o the 1. Closed by an isolation valve, blind flange, or manual valve or ,
2. and BeExhaust capable of being closed by an OPERABLE isolation valve.
automatic urge APPLICABILITY: !
During CORE ALTERATIONS or movement ofirradiated containment ACTION:
I With the requirements of the above specification , not satisfied imme uspend all operations i
involving CORE ALTERATIONS or movement ofirradiated fuel in th
'
The provisions of Specification 3.0.3 are not applicable.e containment building.
SURVEILLANCE REQUIREMENTS
'
4.9.4 either in its closed / isolated condition or capable automatic o be Containment Purge and Exhaust isolation valve within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior t of and at least building by:once per 7 days during CORE ALTERATIONS or movement of 1
.e containment a.
Verifying the penetrations are in their closed / isolated condition ** o
.
b. l Testing the Containment Purge and Exhaust isolation valve applicable portions of Specifications 4.6.3.1.2 and 4.9.9.
Both a. doors of the containment personnel airlock may be open provided bl. closed and that an individual is designated to There is at least 23 feet of water above the top of the reactor press b2. flange during movement of fuel assemblies within the containment, or There is at least 23 feet of water above the top ofirradiated fuel asse within the reactor pressure vessel during CORE ALTERATION movement of fuel assemblies.
"
If both doors of the containment personnel airlock are open pursua 3.9.4.b above, one door shall be verified to be capable of being closed surveillance frequency.
NORTH ANNA - UNIT 1 3/4 9-4 Amendment No.198
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qqqqw M O N W
SRO Ansuu Key
[a] [b] [c] $Q 1.
[] [b] [c] [d] 26.
[a] M [c] [d] 2. [a] [b] g [d] 27.
M [b] [c] [d] 3.
[a] [b] m [d] 28.
M [b] [c] [d] 4.
M Ib] [c] [d] 29.
[a] [b] M [d] 5. [a] [b] [g [d] 30.
[a] M [c] [d] 6. [a] g [c] [d] 31.
M [b] [c] [d] 7. -
M [b] [c] [d] 32.
[a] [b] [c] [q 8. [a] [b] rg [d] 33.
[a] [b] M [d] 9. [a] [b] [c] M 34. 1
[a] [b] [c] [qi 10. [a] [b] lilq [d] 35.
[a] [iq [c] [d] 11. [a] M [c] [d] 36.
[a] [b] [c] [4 12. [a] [b] [c] M 37.
(4 [b] [c] [d] 13. [a] [b] [g [d] 38.
[a] [b] N [d] 14. [Es [b] [c] [d] 39.
[a] [b] [c] [4 15. [a] M [c] [d] 40.
[a] M [c] [d] 16. [a] [b] [c] [4 41.
[a] [b] M [d] 17. [a] [b] [c] gj 42.
M [b] [c] [d] 18. [a [b] [c] [d] 43.
[a] [b] [c] [4 19. [W] [b] [c] [d] 44.
M [b] [c] [d] 20. M [b] [c] [d] 45.
[a] [b] [4 [d] 21. [a] M [c] [d] 46.
M [b] -[c] [d] 22. [a] [b] [c] 5] 47.
[a] M [c] [d] 23. [a] M [c] [d] 4S.
[a] [b] [c] M 24. [a] [b] iW [d] 49.
[a] M [c] [d] 25. (W [b] [c] [d] 50. _
? SRO Answer Key
[a] [b] [c] g 51. [a] [b] $ [d] 76.
[a] [g [c] [d] 52. [a] u [c] [d] 77.
[a] [b] [c] [4 53. [a] [b] M [d] 78.
[a] [b] [c] M 54. [a] [b] M [d] 79.
[a] [b] [c] [4 55. [a] [b] [c] [4 80.
M [b] [c] [d] 56. [a] [b] [c] M 81.
[a] [b] [c] M 57. [a] [b] M [d] 82.
-
i
[a] [q [c] [d] 58. [a] [q [c] [d] 83. l
[a] [b] [q [d] 59. [a] [4 [c] [d] 84.
[a] [b] [c] [4 60. W [b] [c] [d] 85.
[a] [b] [c] m 61. [a] M [c] [d] 86.
M [b] [c] [d] 62. M [b] [c] [d] 87.
l [a] m [c] [d] 63. [a] [b] [c] m 88.
[a] [b] [c] [4 64. M [b] [c] [d] 89.
M [b] [c] [d] 65. [a] [b] M [d] 90. ;
l (W [b] [c] [d] 66. [a] $ [c] [d] 91. i
[a] [b] [( [d] 67. [a] M [c] [d] 92. !
l
[a] lg [c] [d] 68. [a] M [c] [d] 93. i
- '
[a] [b] M [d] 69. [a] [b] [c] M 94.
M [b] [c] [d] 70. [a] M [c] [d] 95.
i
'
M [b] [c] [d] 71. [a] [b] [W [d] 96.
!
[a] [M [c] [d] 72. [a] M [c] [d] 97.
[a] [b] M [d] 73. [a] [b] M [d] 98.
[a] [b] [c] [E 74. [a] [b] M [d] 99.
[a] [M [c] [d] 75. M [b] [c] [d] 100.