IR 05000289/1987025
| ML20149G494 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 02/10/1988 |
| From: | Dudley N, Keller R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20149G463 | List: |
| References | |
| 50-289-87-25OL, NUDOCS 8802180282 | |
| Download: ML20149G494 (30) | |
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.U.S. NUCLEAR REGULATORY COMMISSION REGION I-OPERATOR. LICENSING EXAMINATION REPORT e
Examination Report No. 87-25 (OL)
Facility Docket N .
Facility License N DPR-50 Licensee: GPU Nuclear Corporation P.O. Box 480 Middletown, Pennslyvania 17057 Facility Name: Three Mile Island, Unit 1 -
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Examination Dates: December 8-11, 1987 Chiei Examiner A I' $who, 1 ~ f$if N. Dudley, Se/ior perations Engineer date Approved By: ) .
2.//0/M Robert M. Keller,'Ch'ief, PWR Section
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date Summary: Written examinations and operating tests were administered to two (2)
senior reactor operator and five (5) reactor operator candidates. One reactor
. operator candidate did not pass the written examination. All other candidates passed the examination Numerous individual deficiencies were noted during the operating test which may be indi:ative of a weakness in the training program.
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! <# 8802180282 880210 FDR ADOCK 05000289 D C D .;2
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TYPE OF. EXAMS: 1 Replacement N
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-EXAM RESULTSi
- . R0- : - 'S R0 :
- Pass / Fail : - Pass / Fail :
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- Written Exam : '4/1 : 2/0 :
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- Operating : 5/0 : 2/0 .:
- Exam : : :
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- Overall : 4/1 : 2/0 :
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CHIEF EXAMINER AT SITEi N. Dudley, Senior 0perations Engineer
. OTHER EXAMINERS: B. Picker, EG&G M. King, EG&G The.following is a summary of generic strengths or deficiencies noted on operating-tests. -This information is being provided to aid the licensee in upgrading license and requalification training programs. No licensee response is require Strength: Due to the limited number of contaminated areas within the auxiliary building, supervisory and operations personnel are allowed access to most equipment without the requirement of donning protec-tive clothing.
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Weaknesses: Candidates did not identify the root cause of plant transients which in most cases were instrument failure The simulator has not incorporated major plant modifications such as the Heat Sink Protection System.
L The simulator malfunction cause and effect book did not clearly define the ramping time or severity of some faults such as steam line break and fuel element failure.
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2. The following is a summary of generic strengths or deficiencies noted from the writing and grading of the written examinations. This information is being provided to aid the licensee in upgrading license and requalification training programs. No licensee response is require Strength: Learning objectives provided at the beginning of each-chapter of the Operations Plant Manual were adequately written and
' defined the information in the chapter for which the candidates were held responsibl Weaknesses: Operations Plant Manuals were not up to date. For example, the chapter on the OSTG did not reflect the instrumentation which has been added by the Heat Sink Protection Syste Ope itions Plant Manuals are not useful for understanding integrated sys+ ems response nor for initially understanding system operation The Operations Plant Manuals are useful as a source of technical details of isolated system informatio Senior Reactor Operator candidates were not familiar with the details of radiological controls procedures. For example: the requirements for initiating liquid waste release (question 8.01) and the title of the person to whom a radiological deficiency report should be for-warded (question 8.07.b)
Reactor Operator candidates showed knowledge weaknesses in the fol-lowing areas.
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Interlock between the Reactor Building Cooling Pumps and EF-V-4 and 5. (Question 2.076)
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The effect of the Thot signal on other systems and component (Question 2.10)
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The effect on BTU limits of varying input parameter (Question 3.02)
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The procedures for correcting log entrie (Question 4.11)
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The effect of the Heat Sink Protection System on feedwater valves during a steam line rupture. (Question 4.13)
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- 3 .' Exit Interview
' NRC Personnel present: N. Dudley, Senior Operations Engineer Number: Facility Personnel present:
T. Broughton, TMI-1 Operations and Maintenance'Otrector D. Hassler,-Licensing Engineer W. Thompson, TMI-1 Operator Training Manage L. Ritter, TMI-1 Plant' Operations Administrator
- Summary of comments:
-The number of types of examinaticns administered during the week.was summarized by the examiner. The examiner noted the ease of access through-security check points and the cleanliness of the radiological controlled area The examiner thanked the training staff for their assistance in operating the simulator during the evaluation The examiner stated that an attempt would be made to provide examinations results within 30 days. The examiner stated that discussions of individual candidate weaknesses had been held with the licensee training staff and that questions on plant equipment problems had been discussed with the licensee operations staff and the resident inspecto Attachments:
' Written Examination and Answer Key (SRO) Written Examination and Answer Key (RO) Facility Comments on Written Examinations made after Exam Review with NRC Response to Facility Comment ,
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ENCLOSURE 3 TMI REACTORLOPERATOR. EXAMINATION-RESOLUTION OF COMMENTS.0F EXAMINATION ADMINISTERED ON f12/8/87 FACILITY COMMENT:
ANSWER 1.07 Correct answer should be HIGHER The point of adding heat (POAH) will be higher if temperature is highe If the ambient temperature is higher than some reference condition, it will require-higher power generation for the heat input from f i ssi on to raise fuel temperature significantl Also the doppler. coefficient becomes lens negative as t emper atur e increase Reference: OPM section N-7 page 70, item F. page 100, item page 101, figure 43
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NRC RESOLUTION:
Comment Accepte Answer will be changed to HIGHE . . _ , . . _ _ . _ . , . . _ . . - _. - _ - _ _
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. FACILITY COMMENT -
ANSWERcl.'12 ,
Also acceptable. response should bes Reactor Coolant' Flow
< Further away from minimum DNBR O . Re f'er en c e : OPM ~ secti on ' N'-2, pages 177,'178 & 179 NRC RESOLUTION:
' Comment Accepte Answer key will be modified to accept Reactor Coolant Flow wi th minimum DNBR being f urther awa I h
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FACILITY COMMENT:
ANSWER 1.13 The correct answer for "Effective" is as'follows:
Effective because as one' group is reaching'the top of its travel, it is' moving through a low flux region of,the core, the next group is beginning to travel also in a low flux regio The two groups moving through a low flux region has approximately the same worth uns one group moving through a high flux regio Reference: OPM section N-7 page 161, item Tech Spec section 3.5.2.7 bases, pages 3-35, 35a, 35b & 36 (Note paragraph of interest on top of page 3-36)
NRC RESOLUTION:
Comment Accepte Answer key will be changed to reflect that both groups are moving through an area of lower flux resulting in nearl y the same worth as one group moving in a high flux are ,
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FACILITYiCOMMENT .
ANSWER-1.14 A.L ' Acceptable answer should be as follows (30. gal / inch) (10. inches) (1.6 hot vol. to cold'vol.)
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= 20 i (24 gal / inch)
OR (30 gal / inch) (10 inches) /' (15 gal / inch) = 20 i The_ physical. size,of the pressurizer is such.th/At one inch of.leve1Lis equal to 24 gallons. The rule of thumb for-the pressurizer is that 15 gallons of cold (room temperature) water wl!1texpand at RCS temperature to fill-those 24 gallon (Note that 24/1.6 = 15)
.Ref er ence: OPM section B-1 page 14, figure 4 NRC RESOLUTION:
Comment Accepte Answer Key will be modified to show an answer of 20 inches.
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FACILITY COMMENT:
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~ ANSWER 1.16 The new Inconel APSRs are-LESS capable of controlling imbalance than the old APSR The correct-responsefto the question is than as follows:
Because of "gr ay"-_ poi son , which extends over longer portions of the APSR, imbalance response is more linear with rod motion:and there is no'"foldover" at low APSR positio Woldover is defined as driving imbalance less positive by inserting APSRs)
Reference: Lesson Plan 11.2.01.309, Objecti ves E L G-NRC RESOLUTION:
Comment Accepte Second sentence of answer changed to state: "The APSRs imbalance response is more linear and there i s no "foldover."" [0.5]
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FACILITY COMMENT:
ANSWER 2.03
, Should be "4" psig RB not 3 psig as stated in the' ke Reference - ~OPM.section F-6 page B
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D.- .Shouldfbe "30"'psig RB not'10 psig as stated.in the ke >
Reference: OPM section F-6 page B NRC RESOLUTION:
Comments Accepted for both 2.03.C and Answer Key A
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FACILITY COMMENT:
ANSWER 2.04 Clarification to the' answer key is suggested for the f oll owing:
-'"Waste Liquid" ref ers to isolation of the RB sump and RCDT and should be acceptable as a alternate respons (Valves WDL-V-303,304,534 & 535 close)
-. "Wast e- Gas" refers to isolation of the Vent Header to-the RB,.which connects to the RCDT and-should be acceptable as an alternate respons (Valves WDG-V-3 & 4 Close)
'I Also the f oll owing other systems not included in the answer key are systems i sol ated from the RB:
- "RMS" which refers to the isolation of RM-A-2 by the closing of valves CM-V-1,2,3 & "RB Normal Cooling" which refers to the closing of RB-V-2A and RB-V- Ref er ence: OPM secti on F-6 page 44 NRC RESOLUTION:
l Comment noted and Accepted as note The request for alternate answer for waste liquid and waste gas will not be accepted because they are referring to individual components and not to the syste Additional systems will be added to the key for "RMS/ Containment Radiation Monitoring" and "RB Normal Cooling".
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FACILITY ~ COMMENT:
ANSWER.2.09'
-- A . Acceptable alternate. response should.be'"Permit the core'tcrbe. rapidly reflooded following a postulated cold line break". The flow path description should be'as follows,L"Steam generated in the -core flows up and through the internal vent' valves and f1ows out.to the 1eak".
Reference: OPM section B-3 page 10 NRC RESO..UTION:
Comments Accepte Both answers.A. and B. will be modified to allow the above as alternate answers.
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FACILITY COMMENT: ,
ANSWER 2.'10 Response 4t2 states "ICS".as an.affected item,-a more ,
specific answer of BTU. Limits"'should also.be acceptabl ' Reference: OPM.section F-3 page 49, figure 12 and page.54 NRC RESOLUTION:
Comment partially Accepte The BTU limits will be accepted but-the ICS answer will be stricke l t-l l
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. FACILITY' COMMENT:
ANSWER 2.11 The answer key correctl y . states that MU-V-2A/28 would'
close, but those val ves isolate 'the letdown flow path ~from
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the RCS not tne.RCP seal retur This is done to minimize the activity in the auxiliary building.as the answer key state Reference: OPM section B-5 page 25 & 26, item page 49, figure 6 NRC RESOLUTION:
Comment Accepte Answer key modified to state the closure of the MU-V-2A/2B isolates letdow .-.
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FACILITY? COMMENT: <
J l ANSWER'2.14
, 10 the.c'andidate assumed a:1600#-ESAS actuation the-followin'g' valves will reposition and. pumps receive.La start signal:
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-MU-V-2A/2B-MU-V-14A/14B-MU-P-1A/1C
' -MU-V-36/37
' MU-V-16A/168/16C/16D
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If the candidate assumed a 4# ESAS actuation-the following
~>- :addi t i onal valve would repositon:
-MU-V-3'
Reference: OPM section r-6 page 44
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' NRC RESOLUTION:
Comment Note MU-V-3 is already-part 'oI the answer ke f
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FACILITY COMMENT:'
ANSWER 3.06
, The question.ask's "What is the function..." andlthe proper response should be "The function is to isolate the affected components from their circuits in the control and relay rooms". The response in the answer key' addresses the "EFFECTS"'of operating the. Transfer Switche Reference: OPM sec ti on F-9 pages 3 & 4- (ref er to.the last paragraph on pg. 4)
NRC RESOLUTION:
Comment Accepte Answer key changed to "to isolate the affected components from their circuits in the control and relay room .
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FACILITY, COMMENT:
' ANSWER 3.13 The correct response should be as follows:
To de+ eat RBIC only 2 channels of 'the 3 can be bypassed f ollowing actuatio ' (Bypassing all 3 channels on-a train would cause-the system to re-actuate) On the Reactor Trip Isolation all 3 channels per train are_
bypasse Reference: OPM section F-6, pages 39 & 42 NRC-RESOLUTION:
Comment Accepte The fact'ity comment is added as an addi ti onal required answer s follows: "Bypassing all 3 channels on a train would c4 se the system to re-actuate
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FACILITY COMMENT:
ANSWER 4.06 Answer key should be~ expanded to allow additional correct answer s based on ATP 1210-1 (Reactor / Turbine Trip), which are as follows '
. Generator field and output breakers open-Generator stop valves close
- ICS runs main feedwater back
- Turbine bypass valves control OTSG pressure.to allow the plant to achieve the post trip window Reference: ATP 1210-1 pages 2,3 & 4 NRC RESOLUTION:
Comment partially accepte ICS operation of feedwater will be added, but the remaining three items are already part of the present answer and will not be added to the answer.
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FACILITY COMMENT:-
ANSWER 4.13 Two combinations of correct responses are possible for this question based on the candidates assumption Those answers are as follows:
Case 1: Assume that only the "A" OTSG depressurizes Same as answer _ key FW-V-17B will not close automatically and the ICS will c on t r ol it's position automaticall FW-V-5B will only close automatically if FW-V-16B cl oses t o < 70%- ope FW-V-92B will not close automaticall Reference: OPM section F-3 page SB, figure 16 OPM section F-10 page 3 section III.5 and page 50 & 51 f i gur es 4 and 4A Case 2: Assume that both OTSGs depressurize Same as answer key FW-V-17B goes closed when OTSG pressure is <600 psig however, ICS does not control position automaticall The HSPS system shuts the valve independently of the IC FW-V-59 goes cl osed when OTSG is <600 psig, however it will not reopen if FW-V-16B gets to the 90 tc 95 percent open positio The HSPS acts to remove the air si gnal to the val ve downstream of the ICS signal, causing the valve to remain shut unless the operator bypasses that portion of the HSPS syste Same as answer key Reference: OPM section F-lO page 3, section III.5 and page 50 & 51 figures 4 & 4A NOTE the reference quoted in the question is out of date for current plant condition NRC RESOLUTION:
Comment cartially accepte Case 2 not possible due to the design of MSIV Therefore Case 1 can appl The phrase
"Cl oses automaticall y" will be removed from part b. and points moved to second sentence in answe Will add the words "when Startup MFRV reaches 70%" to first line in answer Will change answer d. to read "remains open C O. B 3. "
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CHANGES MADE BY THE EXAMINER:
Question 4.0 Deleted part d due to insufficient guidance provided to candidates.in stem of the question.concerning the possibility of using an answer more than onc ~
Question value dropped to 1.50 and.section value dropped.to 24.50 and Total for exam dropped.to'99.5 $-
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.TMIJSENIOR REACTOR OPERATOR EXAMINATION
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' RESOLUTION OF-COMMENTS OF EXAMINATION ADMINISTERED ON'12/8/87 FACILITY COMMENT:
ANSWER 5.04 Key' answer is incorrect -(calcul at. .inal ~ error made 'used . 1xE-10 vice 10xE-10)
The correct response-should be "C"
- P=Po E((SUR)(t))
P=(10xE-10)E((.75 DPM)(2 min.))
P=3.16 E-OD
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Note: Etx) - Raise 10 to the power x References: None r equir ed calcuiational error in the answer ke NRC RESPONSE:
Accept facility comment. Answer key modifie .
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FACILITY COMMENT:
ANSWER 5.10 The correct ~ response should be "REMAIN THE SAME," the delta pressure across the tubes stays constan (Primary side pressure 92155 psig with secondary pressure.D925 psig)
(The delta _ pressure ALONG the tubes does decrease)
Reference: OPM section B-4, page 13, figure 5 The correct response should be "DECREASES," feedwater temperature decreases as power decrease Reference: OPM section F-3, page 51, figure 13 Not RESPONEE:
Acccot facility commen Answer key modifie .
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F A C I L !.T Y C O'M M E N T : -
ANSWER 6.02-(Note the answer key"for.-questions 6.01'and 6.02 are reversed).
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-The correct. response to the question should be " D " , - B ' 8r - C breakers open plus "E" electronic tri Reference: OPM section F-1 page 62 NRC-RESPONSE:
Accept facility commen Answer key modified.
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' FACILITY COMMENT:
ANSWER 6.04-
' The correct answer should bet NaOH is added to the RCS f ollowing an ESAS actuation of 4# RB pressure. .The NaOH tank would than be lined up to the suction, header of the LPI pumps (DH-P-1A/1B) and the Building ~ Spray pumps (BS-P-1A/18). From this line up it would than.be possible to inject.NaOH into the RC The_deborating demins are not part of the RCS. NaOH is used to regenerate the demins following exhaustion, while they are isolated.from'the syste Reference: OPM section B-6, page 36, figure 9 OPM section B-9, pages 3 & 5 OPM section F-6, page 16 NRC RESPONSE:
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Accept facility commen Answer key modified.
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'9 FACILITY COMMENT: .
ANSWER 6'06- ,
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~ valves will reposition and pumps receive.a start signal:
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'-MU-V-2A/2B-MU-V-14A/14B-
-MU-P-1A/1C-
-MU-V-36/37-
-MU-V-16A/168/16C/16D-MU-V-18
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'- If the candidate assumed a'4# ESAS actuation'the following addi ti onal valve would reposition '
-MU-V-3 Reference: OPM section F-6 page 44 I
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NRC RESoONSE:-
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racility comment is note Question will be graded based on
. appl i can t 's ; assumpt i o H-t i
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' FACILITY COMMENT:
ANEWER:6.10'
- The correct response should be as follows:
J Leak rate is more than 4%
1200 GPM; % of signal equal s 35%
with 5% error flow is *1250 GPM Flow differential is 1250-1200 GPM = 50.GPM 50/1200 = 4.16% (+ or - b2 sed on tolerance band)
Reference: OPM section D-4, page 43
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NRC RESPONSE:
Design flow was changed from 2100 gpm to 1200 gpm in the answer ke All other facility values are within the tolerances in the-answer key and the key was not change ,
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FACILITY COMMENT'
ANSWER 7.04 . Val ves RC-V-2 and/or RC-V-3.are only required to:be cycled if they have bGen close Should: accept the above respcnse fromLthe candidate or'the response in-the answer: key _for full credi Reference OP 1102-11 page 5, item 10 OPM section B-1 page 36 item 21
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The cuestion asked for a reason for cycling the spray valves
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and did not a r.k when the valves needed to be cycled. -The answer Ley was modified to accept discussion of damage or binaing due to-thermal transien .
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! FACILITY COMMENT:
ANSWER 7.05 Alternate acceptable response should be as f ollows:
Throttle EFW: flow'to stabilize,the plant since the EFW
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throttling' criteria.are me Reference: ATP 1210-10, page 5~
JNRC RESPONSE:
Accept facilit commen Answer key modifie ..-i
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FACILITY COMMENT:
ANSWER 7.06- Answer should be "Damage may occur ~due to movement cf the
' Carriage Upender mechanism.(due to system interlocks being
. deenergi z ed).
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. Reference: 1507-3, page 6 OPM section M-1, page 24 e
NRC RESPONSE:
Accept fa:ility commen Answer key modifie I L
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FACILITY COMMENT:
ANSWER 7.101
-_ Al ternate acceptable response should be "Operations at power may be continued if no abnormal vibration and increased #2 seal leakage can be handled.
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Reference AP 1203-16, page 3, paragraph'1. NRC RESPONSCs The fi.cility's' suggested response is contained in the f ollow up actions in AD 1203-16, which'are not required to be known for full-credi The answer key contains the actions ~ required by,the immedi ate acti ons 'i n AP 1203-16, which are required for full credit.'
NO change made to the answer ke " :-Q ,
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FACILITY COMMENT:
ANSWER 7.11 Two combinations of_ correct responses are possible for this question based on the candidates assumptions. Those answers are as follows:
Case la Assume that only the "A" OTSG depressurires A. Same as answer key B. FW-V-178 will not close automatically and the ICS will control it's position automaticall C. FW-V-5B will only close automatically if FW-V-168 closes to (70*/. ope D. FW-V-928 will not close automaticall Reference: OPM section F-3 page 58, figure 16 OPM section F-10 page 3 section III.5 and *
page 50 & 51 figures 4 & 4A Cace 0: Assume that both OTSGs depressurice A. Same as answer key B. FW-V-17B goes closed when OTSG pressure is <600 psig however, ICS does not control position automaticall The HSPS system shuts the valve independently of the IC C. FW-V-5B goes closed when OTSG is <600 psig, however it will not reopen if FW-V-16B gets to the 90 to 95'
percent open positio The HSPS acts to remove the air signal to the valve downstream of the ICS signal, causing the valve to remain shut unless the operator bypasses that portion of the HSPS syste Same as answer key Reference: OPM section F-10 page 3, section III.5 and page 50 & 51 figures 4 L 4A NOTE the reference quoted in the question is out of date for current plant condition NRC RESPONSC: ,
Accepted facility commen Question graded based on candidates' ,
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FACIL'ITY COMMENTt'
ANSWER 8.01 There are.two'possible correct answers to the question,'.they are:
A and C, based on' Tech Spec table 3.21.1, action 20 t
Reference: Tech Spec section 3.21.1,-action 20, pages'3-97, 98, 9 NRC RESOLUTION:
The question was developed f rom a licensing event report _(LER)-
that was caused by operators initiating a release prior to-taking an initial grab sampl No change made to the answer key.
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JACILITY COMME'NT -
= ANSWER'8.09-B...NOT ALLOWED i s ' the ' corearct answer to the' question.
"~ Reference Tech Spec 3.'1.3.4.2.(b)'on'page 3-6 & 6a NR'C RESPONSE:
' Accept facility commen Answer' key modifie i
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FACILITY COMMENT:
ANSWER.B.13 Level of emergency declaration should be UNUSUAL. EVENT or ALERT based on paragraph OR Declaration of up to SITE AREA emergency based on the SS/ED's judgement per paragraph NOTE: Plant makeup capabilities still exist using MU-P-1 Reference: 6410-!MP-13OO.01
'NRC RESPONSE:
Accept Unusual Event ~or Aler The question examines on the candidates' ability to classify an event using the information pr ovi ded and the facility's procedure Candidates' classification of-events at higher levels based on shift supervisor judgement does not demonstrate an ability to use the procedures, i
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