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

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(3 intermediate revisions by the same user not shown)
Line 3: Line 3:
| issue date = 08/21/1997
| issue date = 08/21/1997
| title = Failure to Satisfy Requirements for Significant Manipulations of the Controls for Power Reactor Operation Licensing
| title = Failure to Satisfy Requirements for Significant Manipulations of the Controls for Power Reactor Operation Licensing
| author name = Slosson M M
| author name = Slosson M
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
Line 14: Line 14:
| page count = 8
| page count = 8
}}
}}
{{#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==
==Description of Circumstances==
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):
Operator license applicants are required to provide evidence that they, as trainees, have
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 39 .IIN 97-67August 21, 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.Original signed byMaryle on, Fiting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts:Brian Hughes, NRR301-415-1096E-mail: bxhl@nrc.govJohn Pellet, RIV(817) 860-8159E-mail: jlp@nrc.govDonald Florek, RI(610) 337-5185E-mail: djfl@nrc.govThomas Peebles, RII(404) 562-4638E-mail: tap@nrc.govMel Leach, Rill(630) 829-9705E-mail: mnl@nrc.gov
 
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.                                   II
 
_pDp4                                rceq       -01 1101'2¢
Q05020                                                                                  r, .
 
Hills
 
'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                John Pellet, RIV
 
301-415-1096                      (817) 860-8159 E-mail: bxhl@nrc.gov              E-mail: jlp@nrc.gov
 
Donald Florek, RI                 Thomas Peebles, RII
 
(610) 337-5185                    (404) 562-4638 E-mail: djfl@nrc.gov              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 oDeratiria licenses
 
Special Lenses for                            or construction permits for
 
Operators Using                              nuclear power and non-power
 
Respirator or Self-                          reactors and all licensed reactor
 
Contained Breathing                          operators and senior operators
 
Apparatus During
 
Emergency Operations
 
97-65          Failures of High-Dose-            08/15/97    All high-dose-rate (HDR)
                  Rate (HDR) Remote After-                      remote afterloader licensees
 
loading Device Source
 
Guide Tubes, Catheters, and Applicators
 
97-64          Potential Problems                08/13/97    All U.S. Nuclear Regulatory
 
Associated with Loss                          Commission medical tele- of Electrical Power                          therapy licensees
 
in Certain Teletherapy
 
Units
 
97-63          Status of NRC Staff's            08/07/97    All holders of OLs or CPs
 
Review of BWRVIP-05                          for boiling water reactors
 
97-62          Unrecognized Reactivity          08/06/97    All holders of OLs or CPs
 
Addition During Plant                        *for nuclear power reactors
 
Shutdown
 
97-61          U.S. Department of                08/06/97    All U.S. Nuclear Regulatory
 
Health and Human                              Commission medical licensees, Services Letter, to                          veterinarians, and manu- Medical Device Manu-                          facturers/distributors of
 
facturers, on the                            medical devices
 
Year 2000 Problem
 
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                                                                                                    A4 OFFICE        HOLB/DRCH              '          HOLB/DRCH                PEC            &                                    (A)DRPM
 
NAME          BHughes:rc/bh                      RGallo                    Cpet'rone                kc-hafftee                  11slosson
 
DATE          08/06/97*,                        08/07/97*                08/)cf/97              08/ #( /97                  08/ /97 UV-VILIAL KtLUUV LUFY'
                                                                                                y9          'Y%  10S  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                                                        l
 
TECH/EDITOR            PECB/NRR                    DRPM/NRR
 
NAME            BHughes:rc/bht.                    RGallo'fDCalureAd                              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. Ifyou
 
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                eS noPellet.
 
John            o a Region IV
 
63U-829-9/Ub                                E/-MaJU-iJb                G
 
E-Mail: MNL@NRC.GOV                          E-Mail: JLP@NRC.GOV
 
Attachment: List of Recently Issued NRC Information Notices
 
To receive a copy of this document, hIdicate hithe box: 'C  - Copy without attachmentlenclosure  WE'- Copy with attachment/enclosure 'N" - No copy


===Attachment:===
OFFICE        HOLB/DRCH I HOLB/DRCH I                             TECH/EDITOR I              PECB/NRR I           DRPM/NRR ll
List of Recently Issued NRC Information Notices ,5 A geTech Editor has reveiwed and concurred on 7/8/97DOCUMENT NAME: G:ICDPIN95X7A.BXH*See previous concurrenceTo receive a copy of this document. hIdlcate hI the box: C -Copy without ettachment/enclosure 'E -Copy with attachmentfenclosure'N' -No copyOFFICE HOLB/DRCH I HOLB/DRCH I PECB [__ PECB/NRRNAME BHughes:rc/bh RGallo Cpetrone AChaffee G us{DATE 08/06/97* 08/07/97* 08/14/97* 08/14/97* 0819797lOFFICIAL RECORD COPY 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 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.gov


===Attachment:===
INAME          BHughes:rc/bh RGallo                                 DCalure4UPP              AChaffee            MSlosson
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 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.GOV


===Attachment:===
DATE          08/6 /97                   08/       /97             08/     /97             08/     /97           07/     /97 OFFICIAL RECORD            COPY
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.GOV


===Attachment:===
Issue Date:           03/21/94                                E20-5                                    0720, Exhibit 20}}
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}}


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

Latest revision as of 04:45, 24 November 2019

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
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. II

_pDp4 rceq -01 1101'2¢

Q05020 r, .

Hills

'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 John Pellet, RIV

301-415-1096 (817) 860-8159 E-mail: bxhl@nrc.gov E-mail: jlp@nrc.gov

Donald Florek, RI Thomas Peebles, RII

(610) 337-5185 (404) 562-4638 E-mail: djfl@nrc.gov 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 oDeratiria licenses

Special Lenses for or construction permits for

Operators Using nuclear power and non-power

Respirator or Self- reactors and all licensed reactor

Contained Breathing operators and senior operators

Apparatus During

Emergency Operations

97-65 Failures of High-Dose- 08/15/97 All high-dose-rate (HDR)

Rate (HDR) Remote After- remote afterloader licensees

loading Device Source

Guide Tubes, Catheters, and Applicators

97-64 Potential Problems 08/13/97 All U.S. Nuclear Regulatory

Associated with Loss Commission medical tele- of Electrical Power therapy licensees

in Certain Teletherapy

Units

97-63 Status of NRC Staff's 08/07/97 All holders of OLs or CPs

Review of BWRVIP-05 for boiling water reactors

97-62 Unrecognized Reactivity 08/06/97 All holders of OLs or CPs

Addition During Plant *for nuclear power reactors

Shutdown

97-61 U.S. Department of 08/06/97 All U.S. Nuclear Regulatory

Health and Human Commission medical licensees, Services Letter, to veterinarians, and manu- Medical Device Manu- facturers/distributors of

facturers, on the medical devices

Year 2000 Problem

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 A4 OFFICE HOLB/DRCH ' HOLB/DRCH PEC & (A)DRPM

NAME BHughes:rc/bh RGallo Cpet'rone kc-hafftee 11slosson

DATE 08/06/97*, 08/07/97* 08/)cf/97 08/ #( /97 08/ /97 UV-VILIAL KtLUUV LUFY'

y9 'Y% 10S 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 l

TECH/EDITOR PECB/NRR DRPM/NRR

NAME BHughes:rc/bht. RGallo'fDCalureAd 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. Ifyou

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 eS noPellet.

John o a Region IV

63U-829-9/Ub E/-MaJU-iJb G

E-Mail: MNL@NRC.GOV E-Mail: JLP@NRC.GOV

Attachment: List of Recently Issued NRC Information Notices

To receive a copy of this document, hIdicate hithe 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 ll

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


Retrieved from "https://kanterella.com/w/index.php?title=Information_Notice_1997-67,_Failure_to_Satisfy_Requirements_for_Significant_Manipulations_of_the_Controls_for_Power_Reactor_Operation_Licensing&oldid=2201440"