Information Notice 1997-67, Failure to Satisfy Requirements for Significant Manipulations of the Controls for Power Reactor Operation Licensing: Difference between revisions

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{{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555-OpO1August 21, 1997NRC INFORMATION NOTICE 97-67: FAILURE TO SATISFY REQUIREMENTS FORSIGNIFICANT MANIPULATIONS OF THE CONTROLSFOR POWER REACTOR OPERATOR LICENSING
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY
 
COMMISSION
 
===OFFICE OF NUCLEAR REACTOR REGULATION===
WASHINGTON, D.C. 20555-OpO1 August 21, 1997 NRC INFORMATION
 
NOTICE 97-67: FAILURE TO SATISFY REQUIREMENTS
 
FOR SIGNIFICANT
 
MANIPULATIONS
 
OF THE CONTROLS FOR POWER REACTOR OPERATOR LICENSING


==Addressees==
==Addressees==
All holders of operating licenses for nuclear power reactors except those who havepermanently ceased operations and have certified that fuel has been permanently removedfrom the reactor vessel.
All holders of operating
 
licenses for nuclear power reactors except those who have permanently
 
ceased operations
 
and have certified
 
that fuel has been permanently
 
removed from the reactor vessel.


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alertaddressees that operator license applicants are required to perform at least five significantcontrol manipulations on the facility for which a license Is sought (Section 55.31 (a)(5) of Title10 of the Code of Federal Regulations [10 CFR 55.31(a)(5)]). Licensees have erred on theinterpretation of the requirements of this section of 10 CFR Part 55. It is expected thatrecipients will review information for applicability to their facilities and consider actions, asappropriate, to avoid similar problems. However, suggestions contained in this informationnotice are not NRC requirements; therefore, no specific action or written response isrequired.
The U.S. Nuclear Regulatory
 
Commission (NRC) is issuing this information
 
notice to alert addressees
 
that operator license applicants
 
are required to perform at least five significant
 
control manipulations
 
on the facility for which a license Is sought (Section 55.31 (a)(5) of Title 10 of the Code of Federal Regulations
 
[10 CFR 55.31(a)(5)]).
 
Licensees
 
have erred on the interpretation
 
of the requirements
 
of this section of 10 CFR Part 55. It is expected that recipients
 
will review information
 
for applicability
 
to their facilities
 
and consider actions, as appropriate, to avoid similar problems.
 
However, suggestions
 
contained
 
in this information
 
notice are not NRC requirements;  
therefore, no specific action or written response is required.Description
 
of Circumstances
 
Operator license applicants
 
are required to provide evidence that they, as trainees, have successfully
 
manipulated
 
the controls of the facility for which an operator or senior operator license is sought. At a minimum, applicants
 
must perform five significant
 
control manipulations
 
which affect reactivity
 
or power level on the facility for which the license is sought (10 CFR 55.31(a)(5)).
 
Controls as defined in 10 CFR 55 are apparatus
 
and mechanisms, the manipulation
 
of which directly affects the reactivity
 
or power level of the reactor. Licensees
 
have erred on the interpretation
 
of what constitutes
 
a significant
 
control manipulation.
 
During a review of operator license applications
 
for the Pilgrim facility, NRC inspectors
 
determined
 
that the requirements
 
for operator and senior operator applicants
 
to perform at least five significant
 
control manipulations
 
on the facility were not satisfied.
 
The Pilgrim licensee incorrectly
 
assumed that a single 30 percent decrease in power with recirculation
 
pumps was equivalent
 
to three 10 percent or greater power reductions
 
and counted this as three of the five required significant
 
control manipulations.
 
The licensee contacted
 
other licensees
 
regarding
 
the practice at their facilities
 
and reported that there was a wide range of interpretations
 
by the other licensees
 
contacted.
 
I I_pDp4 rceq -01 1101'2¢Q05020 Hills r, .'Y 4 IN 97-67 August 21, 1997 The NRC administered
 
examinations
 
to the individuals
 
but did not issue operator licenses until the facility submitted
 
revised applications
 
and provided details of how the applicants
 
satisfied
 
the requirements
 
to perform the required significant
 
control manipulations.
 
As documented
 
in "Pilgrim Examination
 
Report 50-293/97-006 and Notice of Violation," (Accession
 
No. 9707290261), dated July 18, 1997, the NRC determined
 
that a violation
 
of NRC requirements
 
had occurred because two applicants
 
had not completed
 
the five significant
 
control manipulations
 
required by 10 CFR 55.31 (a)(5) in an acceptable
 
manner.Discussion
 
Before 1987, the operator license application
 
required the licensee to certify that the applicant
 
had learned to operate the facility and also to provide the details of the training and experience
 
of the applicant.
 
A 1987 NRC rule changed the requirement
 
to provide the details of the applicant's
 
training and experience
 
and requested
 
instead a simple check mark in the boxes on the application
 
form (NRC-398)
to indicate that the applicant
 
has successfully
 
completed
 
an Institute
 
of Nuclear Power Operations (INPO) accredited
 
operator training program that is based on a systems approach to training, and that a certified
 
simulation
 
facility is used in the operator training program.During rule making, the nuclear industry requested
 
clarification
 
of the phrase "leamed to operate" (Federal Register Vol. 52, No. 57 Wednesday, March 25, 1987, page 9456) and NRC added 10 CFR 55.31 (a)(5) to specify the minimum number of control manipulations
 
that the applicant
 
had to conduct on the facility.Examples of significant
 
control manipulations
 
are contained
 
In Regulatory
 
Guide (RG) 1.8, Revision 2, "Qualification
 
and Training of Personnel
 
for Nuclear Power Plants." Paragraph
 
C.1.h. of RG 1.8 states in part that: Control room operating
 
experience
 
...should include manipulation
 
of controls of the facility during a minimum of five reactivity
 
changes. Every effort should be made to have a diversity
 
of reactivity
 
changes for each applicant.
 
Startups, shutdowns, large load changes, and changes in rod programming
 
are some examples and could be accomplished
 
by manually using such systems as rod control, chemical shim control, or recirculation
 
flow.Additional
 
examples of significant
 
control manipulations
 
include, but are not limited to, items A-F of 10 CFR 55.59(c)(3) (on-thejob
 
training for requalification):
IN 97-67 August 21, 1997 A. Plant or reactor startups to include a range that reactivity
 
feedback from nuclear heat addition is noticeable
 
and heatup rate is established.
 
B. Plant shutdown.C. Manual control of steam generators
 
or feedwater
 
or both during startup and shutdown.D. Boration or dilution during power operation.
 
E. Significant ( 10 percent) power changes in manual control or recirculation
 
flow.F. Reactor power change of 10 percent or greater where load change is performed
 
with load limit control or where flux, temperature, or speed control is on manual (for HTGR).As defined in 10 CFR 55.59(c)(3)(E), a 10 percent or greater power change is considered
 
to be a significant
 
control manipulation.
 
Additional
 
clarification
 
was provided in NUREG-1262,"Answers to Questions
 
at Public Meetings Regarding
 
Implementation
 
of Title 10, Code of Federal Regulations, Part 55 on Operators'
Licenses," dated November 1987, which was transmitted
 
to all licensees
 
on November 12, 1987, as an attachment
 
to Generic Letter 87-16 (Accession
 
No. 8712030029).
 
Some of the guidance included in NUREG 1262 is reiterated
 
below; licensees
 
should refer to NUREG 1262 for additional
 
details.The situation
 
in which an applicant
 
performs a 30 percent change in power in a short period (i.e., on the same shift) with no diversity
 
of controls would be evaluated
 
as one significant
 
control manipulation.
 
The situation
 
in which an applicant
 
reduces power from 100 percent to 95 percent and then increases
 
power from 95 percent to 100 percent would be evaluated
 
as one significant
 
control manipulation.
 
The situation
 
when an applicant
 
performs a 50 percent change in power in a short period of time with diversity
 
of controls (recirculation
 
flow and control rods, or chemical shim and controls rods) can be evaluated
 
as two significant
 
control manipulations.
 
The situations
 
when an applicant
 
reduces power by 10 percent then holds there for performance
 
of other work or testing and then later in the shift increases
 
power by 10 percent can be evaluated
 
as two significant
 
control manipulations.
 
Diversity
 
of significant
 
control manipulations
 
on the plant are expected;
however, it is not required.
 
If the applicant
 
does not have experience
 
in diverse significant
 
control manipulations, this fact should be noted in the comments section of NRC form 398.
 
.I IN 97-67 August 21, 1997 This information
 
notice requires no specific action or written response.
 
If you have any questions
 
about the information
 
in this notice, please contact one of the technical
 
contacts listed below or the appropriate
 
Office of Nuclear Reactor Regulation (NRR) project manager.Original signed by Maryle on, Fiting Director Division of Reactor Program Management
 
===Office of Nuclear Reactor Regulation===
Technical
 
contacts: Brian Hughes, NRR 301-415-1096 E-mail: bxhl@nrc.gov
 
John Pellet, RIV (817) 860-8159 E-mail: jlp@nrc.gov
 
Donald Florek, RI (610) 337-5185 E-mail: djfl@nrc.gov
 
Thomas Peebles, RII (404) 562-4638 E-mail: tap@nrc.gov
 
Mel Leach, Rill (630) 829-9705 E-mail: mnl@nrc.gov
 
Attachment:
List of Recently Issued NRC Information
 
Notices ,5 A ge Tech Editor has reveiwed and concurred
 
on 7/8/97 DOCUMENT NAME: G:ICDPIN95X7A.BXH
 
*See previous concurrence
 
To receive a copy of this document.
 
hIdlcate hI the box: C -Copy without ettachment/enclosure
 
'E -Copy with attachmentfenclosure
 
'N' -No copy OFFICE HOLB/DRCH
 
I HOLB/DRCH
 
I PECB [__ PECB/NRR NAME BHughes:rc/bh
 
RGallo Cpetrone AChaffee G us{DATE 08/06/97*
08/07/97*
08/14/97*
08/14/97*
0819797 lOFFICIAL
 
RECORD COPY
 
I -Attachment
 
IN 97-66 August 20, 1997 LIST OF RECENTLY ISSUED NRC INFORMATION
 
NOTICES Information
 
Date of Notice No. Subject Issuance Issued to 97-66 Failures to Provide 08/20/97 All holders of oDeratir ia licenses Special Lenses for Operators
 
Using Respirator
 
or Self-Contained
 
Breathing Apparatus
 
During Emergency
 
Operations
 
or construction
 
permits for nuclear power and non-power reactors and all licensed reactor operators
 
and senior operators 97-65 Failures of High-Dose- Rate (HDR) Remote After-loading Device Source Guide Tubes, Catheters, and Applicators
 
08/15/97 All high-dose-rate (HDR)remote afterloader
 
licensees 97-64 97-63 97-62 97-61 Potential
 
Problems Associated
 
with Loss of Electrical
 
===Power in Certain Teletherapy===
Units Status of NRC Staff's Review of BWRVIP-05 Unrecognized
 
Reactivity
 
Addition During Plant Shutdown U.S. Department
 
of Health and Human Services Letter, to Medical Device Manu-facturers, on the Year 2000 Problem 08/13/97 08/07/97 08/06/97 08/06/97 All U.S. Nuclear Regulatory
 
Commission
 
medical tele-therapy licensees All holders of OLs or CPs for boiling water reactors All holders of OLs or CPs*for nuclear power reactors All U.S. Nuclear Regulatory
 
Commission
 
medical licensees, veterinarians, and manu-facturers/distributors
 
of medical devices OL = Operating
 
License CP = Construction
 
Permit
 
IN 97-XX August XX, 1997 This information
 
notice requires no specific action or written response.
 
If you have any questions
 
about the information
 
in this notice, please contact one of the technical
 
contacts listed below or the appropriate
 
Office of Nuclear Reactor Regulation (NRR) project manager.Marylee M. Slosson, Acting Dir ctor Division of Reactor ProgramWianagement
 
Office of Nuclear Reactor egulation Technical
 
contacts:
Brian Hughes, NRR John Pellet, RIV 301-415-1096
(817) 860-8159 E-mail: bxhl@nrc.gov
 
E-mail: jlp@nrc. v Donald Florek, RI Thomas P les, RI1 (610) 337-1585 (404) 56 638 E-mail: djfl@nrc.gov
 
E-mailf pnrc.gov Mel Leach, Rill (630) 829-9705 E-mail: mnl@nrc.gov
 
Attachment:
List of Recently Issued N Information
 
Notices DOCUMENT NAME: G:1CDP1lN9pX7A.BXH
 
*See previous concurrence
 
/To receive a copy of this document.
 
Indicate hI the box: *C -Copy without attachmentlenclosure
 
E -Copy with attachment/enclosure
 
N' -No copy 4 A OFFICE HOLB/DRCH
 
' HOLB/DRCH
 
PEC &NAME BHughes:rc/bh
 
RGallo Cpet'rone
 
kc-hafftee
 
DATE 08/06/97*, 08/07/97*
08/)cf/97
08/ #( /97 (A) DRPM 11slosson 08/ /97 UV-VILIAL
 
KtLUUV LUFY'y9'Y% 1V I
 
IN 97-XX July XX. 1997 This information
 
notice requires no specific action or written response.you have any questions
 
about the information
 
in this notice. please c act (one of) the technical
 
contact(s)
listed below or the appropriate
 
ice of Nuclear Reactor Regulation (NRR) project manager.Jack Roe. Acting rector Division of Rea or Program Management
 
===Office of Nuc ar Reactor Regulation===
Technical
 
contact(s):
Brian Hughes. NRR/HOL (301) 415-1096 E-Mail: BXH1@NRC.
 
V Donald Florek, egion I Thomas Peebles. Region II (610) 337-158 (404) 562-4638 E-Mail: DJ @NRC.GOV E-Mail: TAP@NRC.GOV
 
Mel Leac .Region III John Pellet. Region IV (630) 29-9705 (817) 860-8159 E-Mai. MNL@NRC.GOV
 
E-Mail: JLP@NRC.GOV
 
Attachment:
List of Recen y Issued NRC Information
 
Notices*See previous concurrence
 
To receive a copy of this document.
 
Indlicate
 
In the bo C -Copy without attachment/enclosure
 
E -Copy with attachment/enclosure
 
'N' -No copy OFFICE HOLB/DRCH
 
TECH/EDITOR
 
l PECB/NRR DRPM/NRR NAME BHughes:rc/bht.
 
RGallo'f DCalureA d AChaffee JRoe DATE 08/06/97*
08 /97 07/08/97*
08/ /97 08/ /97 I ..INFORMATION
 
NOTICE FORMAT This information
 
notice requires no specific action or written res onse. If you have any questions
 
about the information
 
in this notice, please ntact (one of)the technical
 
contact(s)
listed below or the appropriate
 
fice of Nuclear Reactor Regulation (NRR) project manager.Marylee M. osson, Director Division Reactor Program Management
 
===Office Nuclear Reactor Regulation===
Technical
 
contact(s):
Brian ghes, NRR/HOLB 301- 5-1096 E- 11: BXH1@NRC.GOV
 
onald Florek, Region I Thomas Peebles, Region II 610-337-1585
404-562-4638 E-Mail: DJF1@NRC.GOV
 
E-Mail: TAP@NRC.GOV
 
Mel Leach, Region III John Pellet. Region IV--- --- ----eS no o a 63U-829-9/Ub
 
E-Mail: MNL@NRC.GOV
 
E/-MaJU-iJb
 
G E-Mail: JLP@NRC.GOV
 
Attachment:
List of Recently Issued NRC Information
 
Notices To receive a copy of this document, hIdicate hi the box: 'C -Copy without attachmentlenclosure
 
WE' -Copy with attachment/enclosure
 
'N" -No copy OFFICE HOLB/DRCH
 
I HOLB/DRCH


==Description of Circumstances==
I TECH/EDITOR
Operator license applicants are required to provide evidence that they, as trainees, havesuccessfully manipulated the controls of the facility for which an operator or senior operatorlicense is sought. At a minimum, applicants must perform five significant controlmanipulations which affect reactivity or power level on the facility for which the license issought (10 CFR 55.31(a)(5)). Controls as defined in 10 CFR 55 are apparatus andmechanisms, the manipulation of which directly affects the reactivity or power level of thereactor. Licensees have erred on the interpretation of what constitutes a significant controlmanipulation.During a review of operator license applications for the Pilgrim facility, NRC inspectorsdetermined that the requirements for operator and senior operator applicants to perform atleast five significant control manipulations on the facility were not satisfied. The Pilgrimlicensee incorrectly assumed that a single 30 percent decrease in power with recirculationpumps was equivalent to three 10 percent or greater power reductions and counted this asthree of the five required significant control manipulations. The licensee contacted otherlicensees regarding the practice at their facilities and reported that there was a wide range ofinterpretations by the other licensees contacted. I I_pDp4 rceq -01 1101'2¢Q05020Hills r, .'Y 4 IN 97-67August 21, 1997 The NRC administered examinations to the individuals but did not issue operator licensesuntil the facility submitted revised applications and provided details of how the applicantssatisfied the requirements to perform the required significant control manipulations. Asdocumented in "Pilgrim Examination Report 50-293/97-006 and Notice of Violation,"(Accession No. 9707290261), dated July 18, 1997, the NRC determined that a violation ofNRC requirements had occurred because two applicants had not completed the fivesignificant control manipulations required by 10 CFR 55.31 (a)(5) in an acceptable manner.DiscussionBefore 1987, the operator license application required the licensee to certify that theapplicant had learned to operate the facility and also to provide the details of the training andexperience of the applicant. A 1987 NRC rule changed the requirement to provide the detailsof the applicant's training and experience and requested instead a simple check mark in theboxes on the application form (NRC-398) to indicate that the applicant has successfullycompleted an Institute of Nuclear Power Operations (INPO) accredited operator trainingprogram that is based on a systems approach to training, and that a certified simulationfacility is used in the operator training program.During rule making, the nuclear industry requested clarification of the phrase "leamed tooperate" (Federal Register Vol. 52, No. 57 Wednesday, March 25, 1987, page 9456) andNRC added 10 CFR 55.31 (a)(5) to specify the minimum number of control manipulations thatthe applicant had to conduct on the facility.Examples of significant control manipulations are contained In Regulatory Guide (RG) 1.8,Revision 2, "Qualification and Training of Personnel for Nuclear Power Plants."Paragraph C.1.h. of RG 1.8 states in part that:Control room operating experience ...should include manipulation of controls of thefacility during a minimum of five reactivity changes. Every effort should be made tohave a diversity of reactivity changes for each applicant. Startups, shutdowns, largeload changes, and changes in rod programming are some examples and could beaccomplished by manually using such systems as rod control, chemical shim control,or recirculation flow.Additional examples of significant control manipulations include, but are not limited to, itemsA-F of 10 CFR 55.59(c)(3) (on-thejob training for requalification):
IN 97-67August 21, 1997 A. Plant or reactor startups to include a range that reactivityfeedback from nuclear heat addition is noticeable and heatuprate is established.B. Plant shutdown.C. Manual control of steam generators or feedwater or both during startupand shutdown.D. Boration or dilution during power operation.E. Significant ( 10 percent) power changes in manual control or recirculationflow.F. Reactor power change of 10 percent or greater where load change isperformed with load limit control or where flux, temperature, or speed control ison manual (for HTGR).As defined in 10 CFR 55.59(c)(3)(E), a 10 percent or greater power change is considered tobe a significant control manipulation. Additional clarification was provided in NUREG-1262,"Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code ofFederal Regulations, Part 55 on Operators' Licenses," dated November 1987, which wastransmitted to all licensees on November 12, 1987, as an attachment to Generic Letter 87-16(Accession No. 8712030029). Some of the guidance included in NUREG 1262 is reiteratedbelow; licensees should refer to NUREG 1262 for additional details.The situation in which an applicant performs a 30 percent change in power in a shortperiod (i.e., on the same shift) with no diversity of controls would be evaluated as onesignificant control manipulation. The situation in which an applicant reduces powerfrom 100 percent to 95 percent and then increases power from 95 percent to100 percent would be evaluated as one significant control manipulation.The situation when an applicant performs a 50 percent change in power in a shortperiod of time with diversity of controls (recirculation flow and control rods, orchemical shim and controls rods) can be evaluated as two significant controlmanipulations. The situations when an applicant reduces power by 10 percent thenholds there for performance of other work or testing and then later in the shiftincreases power by 10 percent can be evaluated as two significant controlmanipulations.Diversity of significant control manipulations on the plant are expected; however, it isnot required. If the applicant does not have experience in diverse significant controlmanipulations, this fact should be noted in the comments section of NRC form 398.


.IIN 97-67August 21, 1997 I -AttachmentIN 97-66August 20, 1997 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to97-66 Failures to Provide 08/20/97 All holders of oDeratiria licensesSpecial Lenses forOperators UsingRespirator or Self-Contained BreathingApparatus DuringEmergency Operationsor construction permits fornuclear power and non-powerreactors and all licensed reactoroperators and senior operators97-65Failures of High-Dose-Rate (HDR) Remote After-loading Device SourceGuide Tubes, Catheters,and Applicators08/15/97All high-dose-rate (HDR)remote afterloader licensees97-6497-6397-6297-61Potential ProblemsAssociated with Lossof Electrical Powerin Certain TeletherapyUnitsStatus of NRC Staff'sReview of BWRVIP-05Unrecognized ReactivityAddition During PlantShutdownU.S. Department ofHealth and HumanServices Letter, toMedical Device Manu-facturers, on theYear 2000 Problem08/13/9708/07/9708/06/9708/06/97All U.S. Nuclear RegulatoryCommission medical tele-therapy licenseesAll holders of OLs or CPsfor boiling water reactorsAll holders of OLs or CPs*for nuclear power reactorsAll U.S. Nuclear RegulatoryCommission medical licensees,veterinarians, and manu-facturers/distributors ofmedical devicesOL = Operating LicenseCP = Construction Permit
I PECB/NRR I DRPM/NRR l l INAME BHughes:rc/bh


IN 97-XXAugust XX, 1997 This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact one of the technical contactslisted below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.Marylee M. Slosson, Acting Dir ctorDivision of Reactor ProgramWianagementOffice of Nuclear Reactor egulationTechnical contacts: Brian Hughes, NRR John Pellet, RIV301-415-1096 (817) 860-8159E-mail: bxhl@nrc.gov E-mail: jlp@nrc. vDonald Florek, RI Thomas P les, RI1(610) 337-1585 (404) 56 638E-mail: djfl@nrc.gov E-mailf pnrc.govMel Leach, Rill(630) 829-9705E-mail: mnl@nrc.govAttachment: List of Recently Issued N Information NoticesDOCUMENT NAME: G:1CDP1lN9pX7A.BXH*See previous concurrence /To receive a copy of this document. Indicate hI the box: *C -Copy without attachmentlenclosure E -Copy with attachment/enclosureN' -No copy 4 AOFFICE HOLB/DRCH ' HOLB/DRCH PEC &NAME BHughes:rc/bh RGallo Cpet'rone kc-haffteeDATE 08/06/97*, 08/07/97* 08/)cf/97 08/ #( /97(A) DRPM11slosson08/ /97UV-VILIAL KtLUUV LUFY'y9'Y% 1VI
RGallo DCalure4UPP


IN 97-XXJuly XX. 1997 This information notice requires no specific action or written response.you have any questions about the information in this notice. please c act(one of) the technical contact(s) listed below or the appropriate ice ofNuclear Reactor Regulation (NRR) project manager.Jack Roe. Acting rectorDivision of Rea or Program ManagementOffice of Nuc ar Reactor RegulationTechnical contact(s): Brian Hughes. NRR/HOL(301) 415-1096E-Mail: BXH1@NRC. VDonald Florek, egion I Thomas Peebles. Region II(610) 337-158 (404) 562-4638E-Mail: DJ @NRC.GOV E-Mail: TAP@NRC.GOVMel Leac .Region III John Pellet. Region IV(630) 29-9705 (817) 860-8159E-Mai. MNL@NRC.GOV E-Mail: JLP@NRC.GOVAttachment: List of Recen y Issued NRC Information Notices*See previous concurrenceTo receive a copy of this document. Indlicate In the bo C -Copy without attachment/enclosure E -Copy with attachment/enclosure 'N' -No copyOFFICE HOLB/DRCH TECH/EDITOR l PECB/NRR DRPM/NRRNAME BHughes:rc/bht. RGallo'f DCalureA d AChaffee JRoeDATE 08/06/97* 08 /97 07/08/97* 08/ /97 08/ /97 I ..INFORMATION NOTICE FORMATThis information notice requires no specific action or written res onse. If youhave any questions about the information in this notice, please ntact (one of)the technical contact(s) listed below or the appropriate fice of NuclearReactor Regulation (NRR) project manager.Marylee M. osson, DirectorDivision Reactor Program ManagementOffice Nuclear Reactor RegulationTechnical contact(s): Brian ghes, NRR/HOLB301- 5-1096E- 11: BXH1@NRC.GOVonald Florek, Region I Thomas Peebles, Region II610-337-1585 404-562-4638E-Mail: DJF1@NRC.GOV E-Mail: TAP@NRC.GOVMel Leach, Region III John Pellet. Region IV--- --- ----eS no o a63U-829-9/UbE-Mail: MNL@NRC.GOVE/-MaJU-iJb GE-Mail: JLP@NRC.GOVAttachment: List of Recently Issued NRC Information NoticesTo receive a copy of this document, hIdicate hi the box: 'C -Copy without attachmentlenclosure WE' -Copy with attachment/enclosure 'N" -No copyOFFICE HOLB/DRCH I HOLB/DRCH I TECH/EDITOR I PECB/NRR I DRPM/NRR l lINAME BHughes:rc/bh RGallo DCalure4UPP AChaffee MSlossonDATE 08/6 /97 08/ /97 08/ /97 08/ /97 07/ /97OFFICIAL RECORD COPYIssue Date: 03/21/94E20-50720, Exhibit 20  
AChaffee MSlosson DATE 08/6 /97 08/ /97 08/ /97 08/ /97 07/ /97 OFFICIAL RECORD COPY Issue Date: 03/21/94 E20-5 0720, Exhibit 20}}
}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Revision as of 14:11, 31 August 2018

Failure to Satisfy Requirements for Significant Manipulations of the Controls for Power Reactor Operation Licensing
ML031050127
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant  Entergy icon.png
Issue date: 08/21/1997
From: Slosson M M
Office of Nuclear Reactor Regulation
To:
References
IN-97-067, NUDOCS 9708150270
Download: ML031050127 (8)
v • d • e


UNITED STATES NUCLEAR REGULATORY

COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-OpO1 August 21, 1997 NRC INFORMATION

NOTICE 97-67: FAILURE TO SATISFY REQUIREMENTS

FOR SIGNIFICANT

MANIPULATIONS

OF THE CONTROLS FOR POWER REACTOR OPERATOR LICENSING

Addressees

All holders of operating

licenses for nuclear power reactors except those who have permanently

ceased operations

and have certified

that fuel has been permanently

removed from the reactor vessel.

Purpose

The U.S. Nuclear Regulatory

Commission (NRC) is issuing this information

notice to alert addressees

that operator license applicants

are required to perform at least five significant

control manipulations

on the facility for which a license Is sought (Section 55.31 (a)(5) of Title 10 of the Code of Federal Regulations

[10 CFR 55.31(a)(5)]).

Licensees

have erred on the interpretation

of the requirements

of this section of 10 CFR Part 55. It is expected that recipients

will review information

for applicability

to their facilities

and consider actions, as appropriate, to avoid similar problems.

However, suggestions

contained

in this information

notice are not NRC requirements;

therefore, no specific action or written response is required.Description

of Circumstances

Operator license applicants

are required to provide evidence that they, as trainees, have successfully

manipulated

the controls of the facility for which an operator or senior operator license is sought. At a minimum, applicants

must perform five significant

control manipulations

which affect reactivity

or power level on the facility for which the license is sought (10 CFR 55.31(a)(5)).

Controls as defined in 10 CFR 55 are apparatus

and mechanisms, the manipulation

of which directly affects the reactivity

or power level of the reactor. Licensees

have erred on the interpretation

of what constitutes

a significant

control manipulation.

During a review of operator license applications

for the Pilgrim facility, NRC inspectors

determined

that the requirements

for operator and senior operator applicants

to perform at least five significant

control manipulations

on the facility were not satisfied.

The Pilgrim licensee incorrectly

assumed that a single 30 percent decrease in power with recirculation

pumps was equivalent

to three 10 percent or greater power reductions

and counted this as three of the five required significant

control manipulations.

The licensee contacted

other licensees

regarding

the practice at their facilities

and reported that there was a wide range of interpretations

by the other licensees

contacted.

I I_pDp4 rceq -01 1101'2¢Q05020 Hills r, .'Y 4 IN 97-67 August 21, 1997 The NRC administered

examinations

to the individuals

but did not issue operator licenses until the facility submitted

revised applications

and provided details of how the applicants

satisfied

the requirements

to perform the required significant

control manipulations.

As documented

in "Pilgrim Examination

Report 50-293/97-006 and Notice of Violation," (Accession

No. 9707290261), dated July 18, 1997, the NRC determined

that a violation

of NRC requirements

had occurred because two applicants

had not completed

the five significant

control manipulations

required by 10 CFR 55.31 (a)(5) in an acceptable

manner.Discussion

Before 1987, the operator license application

required the licensee to certify that the applicant

had learned to operate the facility and also to provide the details of the training and experience

of the applicant.

A 1987 NRC rule changed the requirement

to provide the details of the applicant's

training and experience

and requested

instead a simple check mark in the boxes on the application

form (NRC-398)

to indicate that the applicant

has successfully

completed

an Institute

of Nuclear Power Operations (INPO) accredited

operator training program that is based on a systems approach to training, and that a certified

simulation

facility is used in the operator training program.During rule making, the nuclear industry requested

clarification

of the phrase "leamed to operate" (Federal Register Vol. 52, No. 57 Wednesday, March 25, 1987, page 9456) and NRC added 10 CFR 55.31 (a)(5) to specify the minimum number of control manipulations

that the applicant

had to conduct on the facility.Examples of significant

control manipulations

are contained

In Regulatory

Guide (RG) 1.8, Revision 2, "Qualification

and Training of Personnel

for Nuclear Power Plants." Paragraph

C.1.h. of RG 1.8 states in part that: Control room operating

experience

...should include manipulation

of controls of the facility during a minimum of five reactivity

changes. Every effort should be made to have a diversity

of reactivity

changes for each applicant.

Startups, shutdowns, large load changes, and changes in rod programming

are some examples and could be accomplished

by manually using such systems as rod control, chemical shim control, or recirculation

flow.Additional

examples of significant

control manipulations

include, but are not limited to, items A-F of 10 CFR 55.59(c)(3) (on-thejob

training for requalification):

IN 97-67 August 21, 1997 A. Plant or reactor startups to include a range that reactivity

feedback from nuclear heat addition is noticeable

and heatup rate is established.

B. Plant shutdown.C. Manual control of steam generators

or feedwater

or both during startup and shutdown.D. Boration or dilution during power operation.

E. Significant ( 10 percent) power changes in manual control or recirculation

flow.F. Reactor power change of 10 percent or greater where load change is performed

with load limit control or where flux, temperature, or speed control is on manual (for HTGR).As defined in 10 CFR 55.59(c)(3)(E), a 10 percent or greater power change is considered

to be a significant

control manipulation.

Additional

clarification

was provided in NUREG-1262,"Answers to Questions

at Public Meetings Regarding

Implementation

of Title 10, Code of Federal Regulations, Part 55 on Operators'

Licenses," dated November 1987, which was transmitted

to all licensees

on November 12, 1987, as an attachment

to Generic Letter 87-16 (Accession

No. 8712030029).

Some of the guidance included in NUREG 1262 is reiterated

below; licensees

should refer to NUREG 1262 for additional

details.The situation

in which an applicant

performs a 30 percent change in power in a short period (i.e., on the same shift) with no diversity

of controls would be evaluated

as one significant

control manipulation.

The situation

in which an applicant

reduces power from 100 percent to 95 percent and then increases

power from 95 percent to 100 percent would be evaluated

as one significant

control manipulation.

The situation

when an applicant

performs a 50 percent change in power in a short period of time with diversity

of controls (recirculation

flow and control rods, or chemical shim and controls rods) can be evaluated

as two significant

control manipulations.

The situations

when an applicant

reduces power by 10 percent then holds there for performance

of other work or testing and then later in the shift increases

power by 10 percent can be evaluated

as two significant

control manipulations.

Diversity

of significant

control manipulations

on the plant are expected;

however, it is not required.

If the applicant

does not have experience

in diverse significant

control manipulations, this fact should be noted in the comments section of NRC form 398.

.I IN 97-67 August 21, 1997 This information

notice requires no specific action or written response.

If you have any questions

about the information

in this notice, please contact one of the technical

contacts listed below or the appropriate

Office of Nuclear Reactor Regulation (NRR) project manager.Original signed by Maryle on, Fiting Director Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical

contacts: Brian Hughes, NRR 301-415-1096 E-mail: bxhl@nrc.gov

John Pellet, RIV (817) 860-8159 E-mail: jlp@nrc.gov

Donald Florek, RI (610) 337-5185 E-mail: djfl@nrc.gov

Thomas Peebles, RII (404) 562-4638 E-mail: tap@nrc.gov

Mel Leach, Rill (630) 829-9705 E-mail: mnl@nrc.gov

Attachment:

List of Recently Issued NRC Information

Notices ,5 A ge Tech Editor has reveiwed and concurred

on 7/8/97 DOCUMENT NAME: G:ICDPIN95X7A.BXH

  • See previous concurrence

To receive a copy of this document.

hIdlcate hI the box: C -Copy without ettachment/enclosure

'E -Copy with attachmentfenclosure

'N' -No copy OFFICE HOLB/DRCH

I HOLB/DRCH

I PECB [__ PECB/NRR NAME BHughes:rc/bh

RGallo Cpetrone AChaffee G us{DATE 08/06/97*

08/07/97*

08/14/97*

08/14/97*

0819797 lOFFICIAL

RECORD COPY

I -Attachment

IN 97-66 August 20, 1997 LIST OF RECENTLY ISSUED NRC INFORMATION

NOTICES Information

Date of Notice No. Subject Issuance Issued to 97-66 Failures to Provide 08/20/97 All holders of oDeratir ia licenses Special Lenses for Operators

Using Respirator

or Self-Contained

Breathing Apparatus

During Emergency

Operations

or construction

permits for nuclear power and non-power reactors and all licensed reactor operators

and senior operators 97-65 Failures of High-Dose- Rate (HDR) Remote After-loading Device Source Guide Tubes, Catheters, and Applicators

08/15/97 All high-dose-rate (HDR)remote afterloader

licensees 97-64 97-63 97-62 97-61 Potential

Problems Associated

with Loss of Electrical

Power in Certain Teletherapy

Units Status of NRC Staff's Review of BWRVIP-05 Unrecognized

Reactivity

Addition During Plant Shutdown U.S. Department

of Health and Human Services Letter, to Medical Device Manu-facturers, on the Year 2000 Problem 08/13/97 08/07/97 08/06/97 08/06/97 All U.S. Nuclear Regulatory

Commission

medical tele-therapy licensees All holders of OLs or CPs for boiling water reactors All holders of OLs or CPs*for nuclear power reactors All U.S. Nuclear Regulatory

Commission

medical licensees, veterinarians, and manu-facturers/distributors

of medical devices OL = Operating

License CP = Construction

Permit

IN 97-XX August XX, 1997 This information

notice requires no specific action or written response.

If you have any questions

about the information

in this notice, please contact one of the technical

contacts listed below or the appropriate

Office of Nuclear Reactor Regulation (NRR) project manager.Marylee M. Slosson, Acting Dir ctor Division of Reactor ProgramWianagement

Office of Nuclear Reactor egulation Technical

contacts:

Brian Hughes, NRR John Pellet, RIV 301-415-1096

(817) 860-8159 E-mail: bxhl@nrc.gov

E-mail: jlp@nrc. v Donald Florek, RI Thomas P les, RI1 (610) 337-1585 (404) 56 638 E-mail: djfl@nrc.gov

E-mailf pnrc.gov Mel Leach, Rill (630) 829-9705 E-mail: mnl@nrc.gov

Attachment:

List of Recently Issued N Information

Notices DOCUMENT NAME: G:1CDP1lN9pX7A.BXH

  • See previous concurrence

/To receive a copy of this document.

Indicate hI the box: *C -Copy without attachmentlenclosure

E -Copy with attachment/enclosure

N' -No copy 4 A OFFICE HOLB/DRCH

' HOLB/DRCH

PEC &NAME BHughes:rc/bh

RGallo Cpet'rone

kc-hafftee

DATE 08/06/97*, 08/07/97*

08/)cf/97

08/ #( /97 (A) DRPM 11slosson 08/ /97 UV-VILIAL

KtLUUV LUFY'y9'Y% 1V I

IN 97-XX July XX. 1997 This information

notice requires no specific action or written response.you have any questions

about the information

in this notice. please c act (one of) the technical

contact(s)

listed below or the appropriate

ice of Nuclear Reactor Regulation (NRR) project manager.Jack Roe. Acting rector Division of Rea or Program Management

Office of Nuc ar Reactor Regulation

Technical

contact(s):

Brian Hughes. NRR/HOL (301) 415-1096 E-Mail: BXH1@NRC.

V Donald Florek, egion I Thomas Peebles. Region II (610) 337-158 (404) 562-4638 E-Mail: DJ @NRC.GOV E-Mail: TAP@NRC.GOV

Mel Leac .Region III John Pellet. Region IV (630) 29-9705 (817) 860-8159 E-Mai. MNL@NRC.GOV

E-Mail: JLP@NRC.GOV

Attachment:

List of Recen y Issued NRC Information

Notices*See previous concurrence

To receive a copy of this document.

Indlicate

In the bo C -Copy without attachment/enclosure

E -Copy with attachment/enclosure

'N' -No copy OFFICE HOLB/DRCH

TECH/EDITOR

l PECB/NRR DRPM/NRR NAME BHughes:rc/bht.

RGallo'f DCalureA d AChaffee JRoe DATE 08/06/97*

08 /97 07/08/97*

08/ /97 08/ /97 I ..INFORMATION

NOTICE FORMAT This information

notice requires no specific action or written res onse. If you have any questions

about the information

in this notice, please ntact (one of)the technical

contact(s)

listed below or the appropriate

fice of Nuclear Reactor Regulation (NRR) project manager.Marylee M. osson, Director Division Reactor Program Management

Office Nuclear Reactor Regulation

Technical

contact(s):

Brian ghes, NRR/HOLB 301- 5-1096 E- 11: BXH1@NRC.GOV

onald Florek, Region I Thomas Peebles, Region II 610-337-1585

404-562-4638 E-Mail: DJF1@NRC.GOV

E-Mail: TAP@NRC.GOV

Mel Leach, Region III John Pellet. Region IV--- --- ----eS no o a 63U-829-9/Ub

E-Mail: MNL@NRC.GOV

E/-MaJU-iJb

G E-Mail: JLP@NRC.GOV

Attachment:

List of Recently Issued NRC Information

Notices To receive a copy of this document, hIdicate hi the box: 'C -Copy without attachmentlenclosure

WE' -Copy with attachment/enclosure

'N" -No copy OFFICE HOLB/DRCH

I HOLB/DRCH

I TECH/EDITOR

I PECB/NRR I DRPM/NRR l l INAME BHughes:rc/bh

RGallo DCalure4UPP

AChaffee MSlosson DATE 08/6 /97 08/ /97 08/ /97 08/ /97 07/ /97 OFFICIAL RECORD COPY Issue Date: 03/21/94 E20-5 0720, Exhibit 20


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