ML20236X437
| ML20236X437 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/03/1987 |
| From: | Gallo R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Sieber J DUQUESNE LIGHT CO. |
| References | |
| NUDOCS 8712090193 | |
| Download: ML20236X437 (6) | |
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.JDocket No.-
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"Duqueshe'L'ighECompany?
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. Attn:.Mr.lJ.LD.-Sieber
- Vice President '
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' Nuclear, Group 1
,P.0F Box 4
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.Shippingport,.PA 15077 "M
- Gentlemen:
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Subjecti Beaver Valle'y Unit 2. Licensing' Examination
' Several--examination candidates provided:-information which affected the' ' answer -
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- key to: the. Beaver 1 Valley Unit 2' written examin'ation administered ~ on LMay 18, c1987.
Duelto the L changes ' made ' to the_ ' answer key, four additional written 4'
' examinations.Lsre regraded in ~ accordance- -with. lthe. Examiner..-Standards,;
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NUREG-1021, Chapter ES-112. - There.was no change int the licensingt derisiens,-
however, changes 'were made to some sectional and. overall grades. The ; revis@
d-examination results.were provided to' the appropriate individuals via separate correspondence.
The ' chang'es made to the.' answer key' and the. basis for the changes a're provided.
.in Enclosure 1.
Some of the changes to the ' answer key are-the-result of-inac-curacies and inconsistencies in the reference' material provided for examination-
- preparation; It is suggested that you review the enclosure to this letter to determineHthe referen.ce material requiring. revision.
In-addition, Enclosure;l
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- specifies /.those chang'es to. the answer key which were not identified during. the facility; formal examination review process.
. Thank = you for.your cooperation in this matter.
If you have any. questions please; contact'me.at 215-337-5291.
I 5
Sincerely, ROBERT fi A' LO Robert M. Gallo, Chief Operations Branch Division of Reactor Safety
Enclosures:
As-stated 4bN 8712090193 871203 0
PDR ADOCM 05000412 PDR JFFICIAL RECORD COPY OL 50-412 EXAM - 0001.0.0 y
11/12/87
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Duquesne Light Company 2
cc w/ encl:
J. Crockett,; Senior Manager, Nuclear Operations E. Ewing, Quality Assurance Manager R. J. Swiderski, Manager, Startup Group i
l J. P. Thomas, Manager, Engineering i
R. E. Martin, Manager, Regulatory Affairs l
C. O. Richardson, Stone and Webster Engineering Corporation PublicDocumentRoom(POR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector Commonwealth of Pennsylvania bcc w/ enc 1:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encl)
ORP Section Chief-J. Beall, SRI, BV-1 P.-Tam, LPM, NRR
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0FFICIAL RECORD COPY OL 50-412 EXAM - 0001.0.1 1
10/22/87 i
- SEE PREVIOUS CONCURRENCE SHEET
- RI:DRS
- RI:DRS fRI:0RP Dudley Keller Wiggins Ga o 11/ /87 11/ /87 11/ /87 IS/S/87 0FFICIAL RECORD COPY OL 50-412 EXAM - 0002.0.0 11/12/87
G H E ENCLOSURE 1-m REFERENCE MATERIAL INCONSISTENCIES AND ANSWER KEY ERRORS' RESULTING IN CHANGES TO THE. WRITTEN EXAMINATION ANSWER KEY Question 6.01a-The answer. key ~ incorrectly included the diesel loading sequence as a start.
signal to the auxiliary feedwater pump. The diesel loading sequence provides a-start permissive. signal and would not start the pump. The error was not identified by the. facility during the five days. allowed for examination review.
The ' error was identified by candidates after they received their graded
' examinations.
Question 6.03d The answer key for the question "Under what 2 circumstances will the 4160V auto transfer to the alternate supply?" was changed from:
" BUS UV(0.5); Sustained
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bus.UV(0.5)" to:
"No UV and 42C trips open (0.5) sustained bus UV (0,5)."
OM 2.36.1 page 53 states
... a fast. transfer is initiated for a_ fault in the 4160V. source." Lesson plan 2LP-50S-36.1 page 31 states "A fast ~ transfer takes place when a) no under voltage condition exists on the. bus and b) 420 trips open..."'
The answer key was modified to reflect the information in the lesson plan since it provided a more detailed and accurate explanation of the auto-The error ' as not identified by the facility during the matic bus transfer.
w five days allowed for the examination review. The error was identified by candidates after they received their graded examinations.
-Question 6.05b The true or false answer for the statement "The low steamline pressure SI signal may t>e reset if both the hot and cold loop stop vcives in the associated primary loop are shut," was changed from false to true. The hot and cold leg loop'stop valves have no input to the reset permissive logic associated with an SI caused by low steamline pressure as shown on Figure 7.2-1 Function Diagram in the Beaver Valley Power Station Unit 2 Final Safety Analysis Report. The error was not identified by the facility during the five days allowed for examination review. The error was. identified by candidates after they received their grcded examinations.
Question 6.06a The answer key for the question "Under what condition would it be necessary to use the RSS' pumps to supply HHSI. pump" was changed from: "During cold leg recirc phase (0.4) when RCS pressure is above the shutoff head of the LHSI pumps (0.1)" to:
" Extreme Low ievel in RWST (0.3) resulting in cold leg recirculation phase (0.2)."
The statement that RSS is necessary when RCS pressure is above the shutof f head of the LHSI pumps is incorrect.
OFFICIAL RECORD COPY OL 50-412 EXAM - 0006 0.0 11/12/87
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ENCLOSURE 1 y
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I The reference. material is inconsistent as to when the recirculation phase is
. initiated.
Lesson plan 2LP-SQS-13.1 on page 39 states "upon. receipt of a low level RWST signal."
0.M. 2.13.1 page 2 states "on receipt of an extreme low level alarm in.the RWST." Emergency Operating Procedure ES-1.3 states "on low RWST' level."
Q.M. 2.11.1 page 2 states "when the RWST reaches the extreme low level."
0.M. 2.11.1.is the only reference which indicates that a safety
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injection' signal is needed in coincidence with the RWST level signal to initiate the recirculation' mode.
The basis for the RWST low level signal is partially addressed in Lesson Plan 2LP-SQS-13.1 and more fully explained in 0.M. 2.11.1 on page 2.
.The answer key was changed based on the information gained from a search of the reference material.and examiner judgement.
Question 6.09a The answer to the question " List the setpoints and the reason for the Low-Low S/G 1evel. trip'," was changed from: " Protects against a loss of. heat sink'in the event of a sustained steam /feedwater mismatch insufficient to activate the low level trip," to: "provides core protection-by preventing operation with the steam generator level below the minimum volume required for adequate heat removal."
The' original answer is a verbatim quote from page 9 of Operating Manual 0.M. 2.01.1, and indicates that the S/G low low level trip is a backup to the steam /feedwater mismatch trip. The Technical Specifications on page B2-6,.
I states that the steam /feedwater trip is a backup tc the S/G low low level trip.
1 The answer was modified based on information contained in the Technical Speci-fications vice information contained in the operating procedures.
Question 7.01a The true or false answer to " Inching can ONLY be accomplished when the key is set in the 'Run' position and the inching light is illuminated," was changed from true to false. There is no 'Run' position on the inching permissive key switch in accordance with 2LP-FHP-1 page 32 and Technical Manual No. 2502.1 05-001-001 Sterns-Rogers.
Lesson Plan 2LP-FHP-1 page 8 is incorrect when it states ".. the switch is selected to the inching permissive 'RUN' position." The answer was clanged based on the identification of inconsistent information contained in the training material.
OFFICIAL RECORD COPY OL 50-412 EXAM - 0006.1.0 11/12/87
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ENCLOSURE 1 m.
Question 7.01d.
The answer to " Slack cable hoist will not lower if the Dillon Load Cell < 450 lbs,"iwas changed from false'to true. '450 lbs is below the 600 lbs setpoint of circuit #1 which will prevent operation in'the down direction. The error was:
not: identified by:the facility during the five days allowed for. examination
- review. The error was identified by candidates after they. received their
. graded examinations.,
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. Question 7.04a The answer to the' question "What anticipated' operational transient.could cause a continuous bank insertion of the. controlling bank?" was expanded to include
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'" load rejection" based on'various plant transients conducted at the Beaver Valley Unit I simulator.
' Additional-inf.ormation, based on five transients: conducted on the simulator, was'provided by a. candidate in his request for regrade.. From this information it appears that the' intent of-the Continuous Insertion of RCCA Control Bank,-
A0P-2.1.3 ~ was not only.to " Check for Turbine runback," but to check for other valid steam demand events.
.The answer key was' changed based on sufficient evidence that the abnormal procedure intended.other actions to'be taken besides the' actions explicitly stated. Abnormal procedures should be explicit as to what conditions are
-being verified and not left to operator training to provide clarification.
Question 7.08a The answer to the question, "What is the maximum allowable RCS temperature and pressure with RHR in service?" was changed from "350 F, 425 psig" to "350'F, 360 psig".
The reference OM 2.6.2 issue 1, rev. 2, page I shows 425 psig as the setpoint. The reference OM 2.10.1, issue 1, rev. 2, page 1 shows 360 psig as the setpoint. The reference OM 2.10.2, issue 1, rev 2, page 1, also shows 360.psig as.the setpoint.
The answer key was changed based on a complete review of the-reference material and examiner judgement. The error was not identified by the training department during the five days allowed for exami-nation review, but was dentified by a~ candidate in his request for regrade.
Setpoints associated with system operations should be consistent throughout all Operating Manual Chapters.
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OFFICIAL RECORD COPY OL 50-412 EXAM - 0007.0.0 11/12/87
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4 ENCLOSURE 1
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Question.-7.10c-The ans'wer. to' the question concerning a major secondary. steam sistem rupture, "How does.MSIV closure. lessen the consequences of the event.
(2 reasons)" was expanded.to include " Pressure in the containment is-reducsd" based on Technical.
Specifications page B 3/4 7-3 which states that the restriction on operability Lof the main steam line' isolation valves.".... is required to 1) minimize the positive reactivity. effects of the Reactor Coolant System cooldown' associated-Ewith the blowdown, and 2) limit the pressure rise within the containment..."
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The' Final Safety Analysis ' Report (FSAR)l page 10.3 '3 amendment '18 states that-
- for a faulted steam generator "._.. the isolation valve prevents blowdown from the.other steam generator." The FSAR continues that, in addition, the MSIV's
" prevent blowdown through-a ruptured pipe downstream of the isolation valves."
The FSAR,.page 10.3-5, amendment 2, states that the shutting of the MSIV's will check "... the sudder, and large release of energy in the. form of steam, which in turn prevents rapid cooling of the RCS." The FSAR continues that "The closure.also ensures a. supply of steam to the turbine-driven auxiliary feed-1.
water pumps." Beaver Valley E0P, Executive Volume 2.538.4, page 11' states, "The MSIV's are checked to be closed in this step in an attempt. to isolate the
. break' and to isolate the SGs from each other." Lesson Plan 2LP-SQS-21.1 states that the function of the MSIV's is "to isolate the main steam lines in case of
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a main steam line break."
No reference was.found that presented all of these various purposes of'the MSIV closure in a cohesive manner.
f 0FFICIAL RECORD COPY OL 50-412 EXAM - 0008.0.0 11/12/87
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