ML20235X553
| ML20235X553 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/09/1987 |
| From: | Burdick T, Mark King, Picker B, Reidinger T, Spenser M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20235X498 | List: |
| References | |
| 50-346-OL-87-01, 50-346-OL-87-1, NUDOCS 8710200039 | |
| Download: ML20235X553 (16) | |
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> U.S. NUCLEAR REGULATORY COMMISSION REGION III :
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- Report No. 50-346/0L-87-01 Docket'flo. 50-346 License No. NPF-3 l
Licensee: . Toledo Edison Company J 300 Madison Avenue Toledo, OH 43652 Facility.Name: Davis Besse i Examination Administered.At: Davis Besse Examination Conducted: Weeks of August 17.and 24, 1987 I /h f h Examiners: 'T. D. eidinger,vNRC ,
Date UL Qbl'l
. Picker, EGG S 7 1 D&te
$/ IAA 1 M. Spenser, EGG /d /C')
Date' ;
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M. King, EGG >
/D6te' 9/O I hld ApprovedBy:}T.Burdick, Chief /d Operating Licensing Section Dite' l
Examination Summary Examination administered on weeks of August 17 and 24, 1987 l Report No. 50-346/0L-87-01))
Results: Eight licensed Senior Reactor Operators (SRO) and eight Reactor Operators;(RO) were administered written and operating examinations. Two 1 Reactor Operators and two Senior Reactor Operators failed their examinations.
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h w . REPORT DETAILS 1.- Examiners- d T. D. Reidinger, Chief Examiner, NRC
, ,M. King,-EGG M. Spenser, EGG' B.' Picker, EGG l
- 2. Exit Meeting.
On August 28, 1987, at the conclusion of tne replacement examinations, the chief examiner met with members of the plant staff to discuss generic '
findings made,during the course of the examinations. The following. l personnel attended the exit meeting.
. Attendees Jay Lennartz, NRC Region III Examiner !'
Tim Reidinger,NRC, Chief,. Examiner
. Robert DeFayette', NRC Region III Section Chief, DRP Neal Bonner, Assistant' Plant Manager, Maintenance Paul Byron, NRC, Senior Resident Inspector John Johnson, Operations Engineer Supervisor
. Rich Simpkins, Operations. Training Manager Paul Timmerman, Operations Training Mana Jim Syrowski, 7 raining Director (Acting)ger )
Anthony.Stallard, Operations Training Supervisor i George A. Bradley, Nuclear Specialist II (Nuclear Licensing) i Cindy Blay, Nuclear Licensing Summary of NRC Comments J
The chief examiner presented the following facility strengths. The l
-candidates were well versed in Technical Specifications in regards to )
understanding the action statements, LC0 and surveillance require ants. j The candidates were strong in their overall plant knowledge as 1 demonstrated in the walk through portion of the operating examination.
The candidates exhibited good familiarity with their emergency procedures and abnormal procedures during the operating examination. The candidates i were strong in the administrative areas as demonstrated in the control I room portion of the operating examination. Two administrative deficiencies were identified by the examiners.
In one in3tance, a " Grand Master" C-Tag 3 Key was missing and was not properly signed out or accounted for by the log out procedure in 1 the key locker in the Shift Supervisors office.
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- Td 'inC han En0 4r6:!.dtet AE L2M .J (Lass Of ES V.akeup Pump (s)
(iu : , .,:l;7 .F, . ntML:t ite;;*.![ i states ^:.: n:t >chtnf e powe- t enT , Step 5.7 L. < a o .
stites .Wr4 the paer res. ti# 'M 2M; Ster 3 /3 sti;es commente W ' ', c < ,
c oev er Wdatt.x ' tc.: 23'it . !;ep : .? !s telMnp cperaicles 13Lesmence
.a; pcser radta 1:n 20 25'< ea ter step ? ~ ntaca impies :. paeer f,. -
l ?. ,r! . . ce. d utth.,r,' tis- in p Op ess "hu see,;ecce ; or opertty accions s s is - ;
.; mis,eacini; anc canc.u:mp, fer d e Operators
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i I h m One generic.ceficiency-war icentiS ac 4 the exad ner v .. . . . !
M The and1 dates in eeneral dancastrates a weak apprac'atten in
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,regards ta'the. understanding of:contr:1 room annunciate"s reieting
- to electrical faults, Common electrical faults ,such as dW%rentta7 l
.o trips, evercurrent tr@s on 'the tt.rbine generator or diese*t were,
- n'ot fairly well understood by the candidates'in recards to tneir
. definition o#, these various trips. t i
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4V P RESOLUTION OF COMMENTS.TO DAVIS-BESSE h I
g my ,
REACTOR' OPERATOR EXAMINATION OF-l
- AUGUST 17,.1987 J 4 q.
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'di ' > Question: 1,iO3- ~
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.. NRC'. Resolution:
y;ny e
- W' ' ', cAccept,"Downcomer/Aspuating' Region as an alternative for Feedwater 4 LHe'ating/ Preheating'. region.
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i , Accepted, answer wasDmodified to allow either " remains. the same" or-- ,
g;1 y ."slightlyiincreases" for the Film Boiling Region'. .
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l L'e'ferences:
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- Same ah before and Training Information Manual for OTSG pages 15 & 16.
k Question 1.04-
.NRC Resolution: ,
m
' Accepted, added two possible answers. 1.. Warming up of steamlines before
.m .unisolating.them. . 2. Starting pumps with discharge. valves closed or.
throttled.
References:
Procedure listed:by facility SP 1106.25.
Question 1.05 !
'NRC Resolution:
Accepted. ' Answer modified to read as follows: " Raising the level would
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tend to increase Natural Circulation (0.5), by' raising the effective OTSG j Thermal Center,:thus increasing height difference between heat source and heat sink (0,5) and' increasing the density. difference in primary due to. 'l Lincreased heat transfer between primary and secondary (0.5)." Total. points i j
remain unchanged. 1
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References:
i Same as Question and Lesson Plan HF/FF-LP-23. q 1
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Question 1.06' q
- NRC Resolution: f 1
Partially accepted. Answer will be changed. a. to be " decrease", c. to "No change". 1 m = density x velocity x area and since area of RCS is same and velocity of fluid, due to pump speed is same, then due to heat-up density decreases thus mass flow and head; decrease. Volumetric flow is equal to mass. flow over
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density and since both decrease, volumetric flow remains essentially unchanged.
References:
- Same as Question.
, Question 1.08 NRC Resolution:
Not accepted. This question is a theory question. Asking "why should" imply a theory concept rather than "why would" which would imply.a physical concept. Answer unchanged.
References:
Same as Question.
Question 1.09 NRC Resolution:
Not accepted. Answer was modified. No change to Xeron and Samarium since they hre stated individually. Stuck rods are accounted for in Rod Worth.
Answer key will be modified to show either " Control rod position or Control y rod worth as an answer.
References:
1 Same as Question and Worksheets 3 & 4 of SP 1103.15.
Question 1.12
- f. NRC Resolution:
1.
' Partially accepted. Answer a. changed to 1.85% 1 0.3%. Answer b, changed to 4.2% 1 0.3%.
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References:
s Cycle'5 physics data.
- Question 1.14
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..NRC Resolution: i
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'! ' Accepted. The word " capture" will be: removed from answer key.
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References:
Same as. Question.
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, Question 1.15.
.NRC Resolution:
Not accepted. Overall worth is more. negative and'is supported by-
> references.
References:
Same as Question and R0 curve book.
. Question 2.05 NRC Resol ~ution:
Partially accepted. 480 VAC power to-hydraulic pumps is'not accepted. 120.
j VAC bus YBU is added to station house power as acceptable answer. 125 VOC panel DBP is added to 125 VDC distribution system as acceptable answer.
Refeiences:
Same as Question and SP 1105.12.
i Question 2.06 ]
NRC Resolution:
Accepted._ Added as acceptable: 5. Low oil pressure trip setpoints
- u different. 6. Lead and standby air compressor load and unload setpoints are different.
References:
i Same as. Question and SP 1104.24, 3 )
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{ Question 2.08 NRC Resolution: J I
' Accepted. Answer. key will be modified to the following which provides a better answer. Any 4 acceptable as.before. .)
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'APSR's'have' buttons to hold segment arms q~
- 1. '
- 2. APSR's have no ball checks l
- 3. Bearing surface thicker'(segments) 'I
- 4. Coupling size'different .
- 5. No springs / snubber on APSR
- 6. Poison lengths are different 1
References:
Same as Question.
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l Question 2.09 NRC Resolution:
Partially accepted. Substituted list provided by facility as choices for correct response plus a. Spent fuel pool but will not add as additional-
. answers. ' Points, remain unchanged.
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References:
I SP 1104.66, 1104.80; Drawings M-033, M-035, M-045 l
. Question 2.10
-NRC Resolution:
Accepted..' Answer key changed to the following:
- 1. Prevent contamination.of the BWST
References:
Same as Question.
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7 . Question 2.14at NRC Resolution::
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- Not' accepted. Even though the Emergency Ventilation system does. service the i storage poolias a backup this function.is' covered by the second purpose )
.listedlin;thefanswer. key. Answer is not changed.
References:
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l Same~as Question.. i TQuestion 2.16' NRC Resolution:
Accepted. . Item 2 of Answer Key ~- changed to bus A.
.Not accepted;for item 6. Item 6 is deleted'and question is revalued:to-1.50.
References:
Same as Question.
Question'2.17 NRC Resolution: l Comment ackn'owledged.
Question 3.01
-NRC Resolution: ;
Partially. accepted. 'Added ReactorfCross: Limits and Feedwater Cross limits but will give only half credit for generic term Cross Limits. Therefore, there are now 4 of the 6 items for full credit.
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References:
Same as Question and SP 1105.04.
Quest' ion 3.02 l NRC Resolution:
Accepted;as noted. 1. Added Voltage to answer key. 2. CCW flow to remain unchanged. The.CCW ir.terlock is a common term used on both Drawing and i System Procedure provided. 3. Accept either Core Lift Criteria or Tc > i setpoint. l l
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References:
'Same as Ouestion, SP 11103.06.and P&ID M-040B. ;
Questien 3.03
'NRC Resolution:
Accepted. . Answer key for item 4 FWP Hi disch press changed to 20%/inin rate. i i
References:
. Training Information Manual Volume 3, ICS.
Question 3.05 NRC Resolution:
Not accepted. Manual Emergency Shutdown is not bypassed and therefore is active even though it is not mentioned in the procedure sited.
References:
Same as Question.
Question'3.07 NRC Resolution:
Accepted. Answer key modified to say "Open service water isolation to Aux feed (0.5) then depress open push-buttons for AFW Turbine Steam Supply i (0.5).
References:
Same as Question.
Question 3.08 NRC Resolution:
Not accepted. The alarm is an indicator of trouble, while shutting the valves is an action as result of reaching the alarm point.
References:
Same as Question.
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. ' Question 3.10 NRC Resolution:
i Comment noted. Answer key corrected to show proper valves.
References:
Training Information Manual, Volume 3, ICS, q i
Question 3.17a NRC Resolution:
Not accepted. The actions listed will occur, while the shutdown of the EDG is an operator, time dependent judgement. i
References:
SP 1007.05 4160 Volt Switching Procedure.
Question 4.02 NRC Resolution:
Not accepted. All additional responses desired are subparts of the three answer key responses-as given in the administrative procedure.
References:
Same as Question. ,
-Question 4.03 NRC Re~ solution:
Accepted. Answer key will be modified to list responsibilities per AD 1839.00, Rev. 16, page 9.
References:
Station Operations Administrative Directive 1839.00, Rev. 16.
Question 4.06 NRC Resolution:
Not accepted. Per item 6.3 of Radiation Procedures HP 1601.10 4500 mrem is l
the " Working annual guide limit."
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' .j Same as Question.-
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.NRC:. Resolutions q v L Not' a'ccepteci.' Question was specific'in stating condition.of question..
iR'eferences:'
~ Same as Question.
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, . Question 4.09 ,
NRC Resolution:
' Accepted.
Answer key will:be modified to list. actions of both pr'imary and e secondary operators per references listed.
References:
~C .Same'as Question- .
JQuestion 4.12 NRC Resolution:
'Acce'pted with modification. Answer 3 will be modified to read " Shift MU pump suction to the BWST position of MU3971..."
References:
LSame--as Question.
-Question 4.13 NRCiResolution:
-Comment noted. Due to similarities with previous Question responses, 7Q uestion will-be deleted.
References:
,: . .None t
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i 3 L ' Question 4'.18.2-
.NRC Resolution:
Accepted with changes. Answer key will be changed to "approximately 0.1 DPM" but not both-the present answer and recommended answer.
References:
PP 1102.02 Plant Startup.
i Answer Key Corrections:
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3.03 Error in.FWP discharge pressure runback limit of 55% was discovered and verified during grading. ' Answer changed to proper value of 60%
by grader.
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.4.15 Modified answer - deleted line " Reactor power determines ...
requirement." Deleted the letter designating item 3.a. making this part now answer 3. Deleted answer b. Redistributed points to 0.66 for each answer 1-3.
Editorial Changes:
1.06 Answer point value at end should read (4 0 0.5 ea = 2.0) 1.09 Answer point.value at end should read (5 @ 0.5 ea = 2.5).
3.05 . Answer ~ point value at end should read (4 @ 0.5 ea = 2.0).
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.-'t RESOLUTION OF COMMENTS TO DAVIS-BESSE SENIOR REACTOR OPERATOR EXAMINATION-0F AUGUST'17, 1987 L
At .the conclusion: of the written examination, the examiners provided .
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Mr. Richard, Simpkins with 'a copy of the~ written examination and answer key- q
-for review. The comments made by the facility reviewers are_. included as an j
-enclosure to this' report, the NRC' resolutions to these. comments are listed q
.below.
Three'of 15 (20%)' modifications made to the examination answer key were due
- to inadequate or. insufficient training material. submitted to the NRC for exam
' gene rati on .-
l Question 5.04 Part 1. Facility-comment acknowledged. The question is only worth 0.5 pt, and there are 11 components total. . Answers will be graded commensurate 1y.
Part 2. Agree'with facility comments, will accept answers between 5% - 7%.
Question 5.07 Agree with facility comment. Will also accept recommended additional answers as correct.
' Ques. tion 5.08 Agree with facility comment. Part I accept Beta Core definition provided in reference.
Parts 2 and 3 do not require numerical values. !
Question 5.10 Acknowledge facility comment as constructive. No corrective action required.
Question 5.12 Facility comment acknowledged. Being above and to the left of l the subcooled margin lines only assures greater than 20 degrees !
subcooling. If the candidate addresses the 50 degrees subcooling l required by the procedure in the question, then full credit will i be awarded.
1 Question 5.16 Agree with facility comment. Facility rec 6 emendations 1 will be incorporated into the answer key. !
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-Question '5.17: . Agree with facility comment. For Part 2,.w111 also accept % *.
" increases slightly" as correct.
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Question 5.18 Agree with facility comment. For Part 4 of the answer, will accept a flowpath between heat source'and heat sink.
Also, liquid does not have to be subcooled.
Question 6.01 Acknowledge. typing error.
Question 6.02 Agree with facility comment. 'Will also accept-94% on operate range.
Question 6.04 . Agree with facility comment. Will accept D-ring for Steam Generator secondary shield wall.
Question 6.06 Facility comment. acknowledged. Part 1 answer key did.not ask for setpoints. Setpoints were in parentheses,. indicating' that they.were non-required information.
Part 2 answer key has been corrected to indicate All SFRCS trip now trip ARTS.. Updated information was not available to the NRCLat the time of the exam generation.
Question 6.08'.Will agree with the facilit'y comments, " Moisture carry over
-to the low pressure turbine" as an acceptable answer. Note that this is incorporated into the reference provided by the facility as a handwritten keyword in the margin and is.not part of the text.
Question 6.10 Agree with facility comment. Recommended additional answer, will be added to the key.
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. Question 6.12 Facility comment acknowledged. Recommended answers are .i equivalent to the answer key. No changes required.
Question 6.14 Facility comment acknowledged. Part 1 clearly asks for a' system vice a component and no other answers will be accepted. l It is agreed that valve namas should have been included in '
Part 2, but for this question, it had no impact on providing the correct answer.
' Question 6.15 Agree with facility comment. Will accept loss of NNI power. l 2
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, 7 -Question 6.18 hgree with facility comment. Part 3 will be deleted.
Quln, tion 6,21 Agree with facility comment. Added primary water pump
, , as an additional correct answer.
Question 7.01 Facility comment acknowledged. The point break down based on the candidate emphasizing voids, core uncovery and the earliest point of the kidney curve in his answer. However, since RCPs are tripped immediately if SCM is lost, per the Emergency Procedures, this portion of the answer will not be required and the point value will be adjusted to 1.5.
s
- i. Uuestion 7.03 Agree with facility comment. Will accept RCS average temp.
and OTSG average shell temp. in determining tube to shell
, delta T.
Question 8.02 Facility comment acknowledged. The answer will be modified as recommended except that five correct answers will still be required and only responses relating to control rod assembly inoperability will be accepted.
Question 8.03 Agree with facility comment, question has been deleted.
Question 8.05 Agree with facility comment. Will accept
- 1. Notify Senior Vice President, Nuclear
- 2. Notify Company Nuclear Review Board The admin procedure should reflect the information contained within Tech Specs.
Questi_on 8.06 Agree with facility comment. Will accept a word description of the three (3) schedules.
_l Question 8.07 Facility comment acknowledged. Responses which are equivalent to, or subparts of the original answer key will be accepted.
Question 8.08 Agree with facility comment. Will accept Shift Supervisor as an alternate response.
Quastion 8.12 Agree with facility comment. Will accept 1.25 of interval as an alternate response for Part a.
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> Question 8.15 -Agree with facility comment. Will accept' Emergency Director I as an alternate response for Part 2.
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Question.8.16 Agree with facility comment. WilliacceptOpciationsSupport ' '
l Center as an answer.-
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GENERAL CONCERNS ON SRO EXAM' ., J e,:
A great deal of emphasis has been placed on the E0Ps by the NRC as well as the Nuclear' Industry. lit is important to understand the basis for the p/ocedural ,.
- actions, particularly key. action steps contained within the emergenr;y procedures.
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An operator cannot make full use of the E0Ps unless he understands'the impact i of his actions,-and this information is contained within the ATOG and Technical
- Bases Documents. The: importance of evaluating this knowledge area. is suppohed v. I
' by NUREG-1122, " Knowledge and Abilities Catalogue for PWRs." This information 9 should be'an. integral part of a training program on the emergency procedures.
- POST EXAMINING REVIEW The following modifications were made to the answer key based on post-examination review'by-the examiners: */ -
- 1. Question 5;02, Loca1' power density and average power density will also be accepted as correct per Tech Specs.
- 2. Question 5.13, Part 1. The question was not worded'to elicit the !
desired response and was deleted. l
- 3. Question 6.17, Part 2. RCS pressure will also be accepted as a , , , I correct answer for primary closing force on. the RCP seals, as stated j in'the referenced lesson plan. ,
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