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 STATES NUCLEAR REGULATORY
{{#Wiki_filter:UNITED STATES


COMMISSION
NUCLEAR REGULATORY COMMISSION


===OFFICE OF NUCLEAR REACTOR REGULATION===
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-OpO1 August 21, 1997 NRC INFORMATION


NOTICE 97-67: FAILURE TO SATISFY REQUIREMENTS
WASHINGTON, D.C. 20555-OpO1 August 21, 1997 NRC INFORMATION NOTICE 97-67: FAILURE TO SATISFY REQUIREMENTS FOR


FOR SIGNIFICANT
SIGNIFICANT MANIPULATIONS OF THE CONTROLS


MANIPULATIONS
FOR POWER REACTOR OPERATOR LICENSING
 
OF THE CONTROLS FOR POWER REACTOR OPERATOR LICENSING


==Addressees==
==Addressees==
All holders of operating
All holders of operating licenses for nuclear power reactors except those who have
 
licenses for nuclear power reactors except those who have permanently
 
ceased operations


and have certified
permanently ceased operations and have certified that fuel has been permanently removed


that fuel has been permanently
from the reactor vessel.
 
removed from the reactor vessel.


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert


Commission (NRC) is issuing this information
addressees that operator license applicants are required to perform at least five significant


notice to alert addressees
control manipulations on the facility for which a license Is sought (Section 55.31 (a)(5) of Title


that operator license applicants
10 of the Code of Federal Regulations [10 CFR 55.31(a)(5)]). Licensees have erred on the


are required to perform at least five significant
interpretation of the requirements of this section of 10 CFR Part 55. It is expected that


control manipulations
recipients will review information for applicability to their facilities and consider actions, as


on the facility for which a license Is sought (Section 55.31 (a)(5) of Title 10 of the Code of Federal Regulations
appropriate, to avoid similar problems. However, suggestions contained in this information


[10 CFR 55.31(a)(5)]).
notice are not NRC requirements; therefore, no specific action or written response is


Licensees
required.


have erred on the interpretation
==Description of Circumstances==
Operator license applicants are required to provide evidence that they, as trainees, have


of the requirements
successfully manipulated the controls of the facility for which an operator or senior operator


of this section of 10 CFR Part 55. It is expected that recipients
license is sought. At a minimum, applicants must perform five significant control


will review information
manipulations which affect reactivity or power level on the facility for which the license is


for applicability
sought (10 CFR 55.31(a)(5)). Controls as defined in 10 CFR 55 are apparatus and


to their facilities
mechanisms, the manipulation of which directly affects the reactivity or power level of the


and consider actions, as appropriate, to avoid similar problems.
reactor. Licensees have erred on the interpretation of what constitutes a significant control


However, suggestions
manipulation.


contained
During a review of operator license applications for the Pilgrim facility, NRC inspectors


in this information
determined that the requirements for operator and senior operator applicants to perform at


notice are not NRC requirements;
least five significant control manipulations on the facility were not satisfied. The Pilgrim
therefore, no specific action or written response is required.Description


of Circumstances
licensee incorrectly assumed that a single 30 percent decrease in power with recirculation


Operator license applicants
pumps was equivalent to three 10 percent or greater power reductions and counted this as


are required to provide evidence that they, as trainees, have successfully
three of the five required significant control manipulations. The licensee contacted other


manipulated
licensees regarding the practice at their facilities and reported that there was a wide range of


the controls of the facility for which an operator or senior operator license is sought. At a minimum, applicants
interpretations by the other licensees contacted.                                   II


must perform five significant
_pDp4                                rceq      -01 1101'2¢
Q05020                                                                                  r, .


control manipulations
Hills


which affect reactivity
'Y    4


or power level on the facility for which the license is sought (10 CFR 55.31(a)(5)).
IN 97-67 August 21, 1997 The NRC administered examinations to the individuals but did not issue operator licenses


Controls as defined in 10 CFR 55 are apparatus
until the facility submitted revised applications and provided details of how the applicants


and mechanisms, the manipulation
satisfied the requirements to perform the required significant control manipulations. As


of which directly affects the reactivity
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


or power level of the reactor. Licensees
NRC requirements had occurred because two applicants had not completed the five


have erred on the interpretation
significant control manipulations required by 10 CFR 55.31 (a)(5) in an acceptable manner.


of what constitutes
Discussion


a significant
Before 1987, the operator license application required the licensee to certify that the


control manipulation.
applicant had learned to operate the facility and also to provide the details of the training and


During a review of operator license applications
experience of the applicant. A 1987 NRC rule changed the requirement to provide the details


for the Pilgrim facility, NRC inspectors
of the applicant's training and experience and requested instead a simple check mark in the


determined
boxes on the application form (NRC-398) to indicate that the applicant has successfully


that the requirements
completed an Institute of Nuclear Power Operations (INPO) accredited operator training


for operator and senior operator applicants
program that is based on a systems approach to training, and that a certified simulation


to perform at least five significant
facility is used in the operator training program.


control manipulations
During rule making, the nuclear industry requested clarification of the phrase "leamed to


on the facility were not satisfied.
operate" (Federal Register Vol. 52, No. 57 Wednesday, March 25, 1987, page 9456) and


The Pilgrim licensee incorrectly
NRC added 10 CFR 55.31 (a)(5) to specify the minimum number of control manipulations that


assumed that a single 30 percent decrease in power with recirculation
the applicant had to conduct on the facility.


pumps was equivalent
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


to three 10 percent or greater power reductions
facility during a minimum of five reactivity changes. Every effort should be made to


and counted this as three of the five required significant
have a diversity of reactivity changes for each applicant. Startups, shutdowns, large


control manipulations.
load changes, and changes in rod programming are some examples and could be


The licensee contacted
accomplished by manually using such systems as rod control, chemical shim control, or recirculation flow.


other licensees
Additional examples of significant control manipulations include, but are not limited to, items


regarding
A-F of 10 CFR 55.59(c)(3) (on-thejob training for requalification):


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


and reported that there was a wide range of interpretations
feedback from nuclear heat addition is noticeable and heatup


by the other licensees
rate is established.


contacted.
B.      Plant shutdown.


I I_pDp4 rceq -01 1101'2¢Q05020 Hills r, .'Y 4 IN 97-67 August 21, 1997 The NRC administered
C.     Manual control of steam generators or feedwater or both during startup


examinations
and shutdown.


to the individuals
D.      Boration or dilution during power operation.


but did not issue operator licenses until the facility submitted
E.      Significant ( 10 percent) power changes in manual control or recirculation


revised applications
flow.


and provided details of how the applicants
F.      Reactor power change of 10 percent or greater where load change is


satisfied
performed with load limit control or where flux, temperature, or speed control is


the requirements
on manual (for HTGR).


to perform the required significant
As defined in 10 CFR 55.59(c)(3)(E), a 10 percent or greater power change is considered to


control manipulations.
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


As documented
Federal Regulations, Part 55 on Operators' Licenses," dated November 1987, which was


in "Pilgrim Examination
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


Report 50-293/97-006 and Notice of Violation," (Accession
below; licensees should refer to NUREG 1262 for additional details.


No. 9707290261), dated July 18, 1997, the NRC determined
The situation in which an applicant performs a 30 percent change in power in a short


that a violation
period (i.e., on the same shift) with no diversity of controls would be evaluated as one


of NRC requirements
significant control manipulation. The situation in which an applicant reduces power


had occurred because two applicants
from 100 percent to 95 percent and then increases power from 95 percent to


had not completed
100 percent would be evaluated as one significant control manipulation.


the five significant
The situation when an applicant performs a 50 percent change in power in a short


control manipulations
period of time with diversity of controls (recirculation flow and control rods, or


required by 10 CFR 55.31 (a)(5) in an acceptable
chemical shim and controls rods) can be evaluated as two significant control


manner.Discussion
manipulations. The situations when an applicant reduces power by 10 percent then


Before 1987, the operator license application
holds there for performance of other work or testing and then later in the shift


required the licensee to certify that the applicant
increases power by 10 percent can be evaluated as two significant control


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


of the applicant.
Diversity of significant control manipulations on the plant are expected; however, it is


A 1987 NRC rule changed the requirement
not required. If the applicant does not have experience in diverse significant control


to provide the details of the applicant's
manipulations, this fact should be noted in the comments section of NRC form 398.


training and experience
. I


and requested
IN 97-67 August 21, 1997 This information notice requires no specific action or written response. If you have any


instead a simple check mark in the boxes on the application
questions about the information in this notice, please contact one of the technical contacts


form (NRC-398)  
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
to indicate that the applicant


has successfully
Original signed by


completed
Maryle                  on,    Fiting Director


an Institute
Division of Reactor Program Management


of Nuclear Power Operations (INPO) accredited
Office of Nuclear Reactor Regulation


operator training program that is based on a systems approach to training, and that a certified
Technical contacts:            Brian Hughes, NRR                John Pellet, RIV


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


facility is used in the operator training program.During rule making, the nuclear industry requested
Donald Florek, RI                Thomas Peebles, RII


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


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
Mel Leach, Rill


that the applicant
(630) 829-9705 E-mail: mnl@nrc.gov


had to conduct on the facility.Examples of significant
Attachment: List of Recently Issued NRC Information Notices                                ,5                      A    ge


control manipulations
Tech Editor has reveiwed and concurred on 7/8/97 DOCUMENT NAME: G:ICDPIN95X7A.BXH


are contained
*See previous concurrence
 
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
To receive a copy of this document. hIdlcate hI the box: C - Copy without ettachment/enclosure 'E - Copy with attachmentfenclosure


in diverse significant
'N' - No copy


control manipulations, this fact should be noted in the comments section of NRC form 398.
OFFICE        HOLB/DRCH                  I      HOLB/DRCH        I      PECB [__                    PECB/NRR


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


notice requires no specific action or written response.
I        -
                                                                      Attachment


If you have any questions
IN 97-66 August 20, 1997 LIST OF RECENTLY ISSUED


about the information
NRC INFORMATION NOTICES


in this notice, please contact one of the technical
Information                                      Date of


contacts listed below or the appropriate
Notice No.            Subject                    Issuance    Issued to


Office of Nuclear Reactor Regulation (NRR) project manager.Original signed by Maryle on, Fiting Director Division of Reactor Program Management
97-66          Failures to Provide              08/20/97    All holders of oDeratiria licenses


===Office of Nuclear Reactor Regulation===
Special Lenses for                            or construction permits for
Technical


contacts: Brian Hughes, NRR 301-415-1096 E-mail: bxhl@nrc.gov
Operators Using                              nuclear power and non-power


John Pellet, RIV (817) 860-8159 E-mail: jlp@nrc.gov
Respirator or Self-                           reactors and all licensed reactor


Donald Florek, RI (610) 337-5185 E-mail: djfl@nrc.gov
Contained Breathing                          operators and senior operators


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


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


Attachment:
97-65          Failures of High-Dose-            08/15/97    All high-dose-rate (HDR)
List of Recently Issued NRC Information
                  Rate (HDR) Remote After-                      remote afterloader licensees


Notices ,5 A ge Tech Editor has reveiwed and concurred
loading Device Source


on 7/8/97 DOCUMENT NAME: G:ICDPIN95X7A.BXH
Guide Tubes, Catheters, and Applicators


*See previous concurrence
97-64          Potential Problems                08/13/97    All U.S. Nuclear Regulatory


To receive a copy of this document.
Associated with Loss                          Commission medical tele- of Electrical Power                          therapy licensees


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


'E -Copy with attachmentfenclosure
Units


'N' -No copy OFFICE HOLB/DRCH
97-63          Status of NRC Staff's            08/07/97    All holders of OLs or CPs


I HOLB/DRCH
Review of BWRVIP-05                          for boiling water reactors


I PECB [__ PECB/NRR NAME BHughes:rc/bh
97-62          Unrecognized Reactivity          08/06/97    All holders of OLs or CPs


RGallo Cpetrone AChaffee G us{DATE 08/06/97*  
Addition During Plant                        *for nuclear power reactors
08/07/97*
08/14/97*
08/14/97*
0819797 lOFFICIAL


RECORD COPY
Shutdown


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


IN 97-66 August 20, 1997 LIST OF RECENTLY ISSUED NRC INFORMATION
Health and Human                              Commission medical licensees, Services Letter, to                          veterinarians, and manu- Medical Device Manu-                          facturers/distributors of


NOTICES Information
facturers, on the                            medical devices


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
Year 2000 Problem


Using Respirator
OL = Operating License


or Self-Contained
CP = Construction Permit


Breathing Apparatus
IN 97-XX


During Emergency
August XX, 1997 This information notice requires no specific action or written response. If you have any


Operations
questions about the information in this notice, please contact one of the technical contacts


or construction
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.


permits for nuclear power and non-power reactors and all licensed reactor operators
Marylee M. Slosson, Acting Dir ctor


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


08/15/97 All high-dose-rate (HDR)remote afterloader
Office of Nuclear Reactor egulation


licensees 97-64 97-63 97-62 97-61 Potential
Technical contacts:            Brian Hughes, NRR                  John Pellet, RIV


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


with Loss of Electrical
Donald Florek, RI                  Thomas P            les, RI1
                              (610) 337-1585                      (404) 56 638 E-mail: djfl@nrc.gov              E-mailf pnrc.gov


===Power in Certain Teletherapy===
Mel Leach, Rill
Units Status of NRC Staff's Review of BWRVIP-05 Unrecognized


Reactivity
(630) 829-9705 E-mail: mnl@nrc.gov


Addition During Plant Shutdown U.S. Department
Attachment: List of Recently Issued N                        Information Notices


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
DOCUMENT NAME: G:1CDP1lN9pX7A.BXH


Commission
*See previous concurrence                      /
To receive a copy of this document. Indicate hI the box: *C - Copy without attachmentlenclosure E - Copy with attachment/enclosure


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
N' -No copy                                                                                                    A4 OFFICE        HOLB/DRCH              '          HOLB/DRCH                PEC            &                                    (A)DRPM


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


medical licensees, veterinarians, and manu-facturers/distributors
DATE          08/06/97*,                         08/07/97*                08/)cf/97              08/ #( /97                  08/ /97 UV-VILIAL KtLUUV LUFY'
                                                                                                y9          'Y%  10S  1V


of medical devices OL = Operating
I


License CP = Construction
IN 97-XX


Permit
July XX. 1997 This information notice requires no specific action or written response.


IN 97-XX August XX, 1997 This information
you have any questions about the information in this notice. please c act


notice requires no specific action or written response.
(one of) the technical contact(s) listed below or the appropriate                                                ice of


If you have any questions
Nuclear Reactor Regulation (NRR) project manager.


about the information
Jack Roe. Acting rector


in this notice, please contact one of the technical
Division of Rea or Program Management


contacts listed below or the appropriate
Office of Nuc ar Reactor Regulation


Office of Nuclear Reactor Regulation (NRR) project manager.Marylee M. Slosson, Acting Dir ctor Division of Reactor ProgramWianagement
Technical contact(s):                    Brian Hughes. NRR/HOL


Office of Nuclear Reactor egulation Technical
(301) 415-1096 E-Mail: BXH1@NRC. V


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


E-mailf pnrc.gov Mel Leach, Rill (630) 829-9705 E-mail: mnl@nrc.gov
Mel Leac . Region III                  John Pellet. Region IV


Attachment:  
(630) 29-9705                          (817) 860-8159 E-Mai. MNL@NRC.GOV                      E-Mail: JLP@NRC.GOV
List of Recently Issued N Information


Notices DOCUMENT NAME: G:1CDP1lN9pX7A.BXH
Attachment:            List of Recen y Issued NRC Information Notices


*See previous concurrence
*See previous concurrence


/To receive a copy of this document.
To receive a copy of this document. Indlicate In the bo  C - Copy without attachment/enclosure E - Copy with attachment/enclosure 'N' - No copy
 
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
OFFICE          HOLB/DRCH                                                        l


'N' -No copy OFFICE HOLB/DRCH
TECH/EDITOR            PECB/NRR                    DRPM/NRR


TECH/EDITOR
NAME            BHughes:rc/bht.                    RGallo'fDCalureAd                              AChaffee                    JRoe


l PECB/NRR DRPM/NRR NAME BHughes:rc/bht.
DATE            08/06/97*                          08    /97              07/08/97*              08/        /97              08/      /97


RGallo'f DCalureA d AChaffee JRoe DATE 08/06/97*
I   .
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
INFORMATION NOTICE FORMAT


about the information
This information notice requires no specific action or written res onse. Ifyou


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


contact(s)  
Reactor Regulation (NRR) project manager.
listed below or the appropriate


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


===Office Nuclear Reactor Regulation===
Division          Reactor Program Management
Technical


contact(s):
Office            Nuclear Reactor Regulation
Brian ghes, NRR/HOLB 301- 5-1096 E- 11: BXH1@NRC.GOV


onald Florek, Region I Thomas Peebles, Region II 610-337-1585
Technical contact(s):                      Brian ghes, NRR/HOLB
404-562-4638 E-Mail: DJF1@NRC.GOV


E-Mail: TAP@NRC.GOV
301- 5-1096 E- 11: BXH1@NRC.GOV


Mel Leach, Region III John Pellet. Region IV--- --- ----eS no o a 63U-829-9/Ub
onald Florek, Region I                    Thomas Peebles, Region II


E-Mail: MNL@NRC.GOV
610-337-1585                                404-562-4638 E-Mail: DJF1@NRC.GOV                        E-Mail: TAP@NRC.GOV


E/-MaJU-iJb
Mel


G E-Mail: JLP@NRC.GOV
---
                                                                Leach,
                                                                ---    ----
                                                                            Region III                eS noPellet.


Attachment:
John            o a Region IV
List of Recently Issued NRC Information


Notices To receive a copy of this document, hIdicate hi the box: 'C -Copy without attachmentlenclosure
63U-829-9/Ub                                E/-MaJU-iJb                G


WE' -Copy with attachment/enclosure
E-Mail: MNL@NRC.GOV                          E-Mail: JLP@NRC.GOV


'N" -No copy OFFICE HOLB/DRCH
Attachment: List of Recently Issued NRC Information Notices


I HOLB/DRCH
To receive a copy of this document, hIdicate hithe box: 'C  - Copy without attachmentlenclosure  WE'- Copy with attachment/enclosure 'N" - No copy


I TECH/EDITOR
OFFICE        HOLB/DRCH I HOLB/DRCH I                             TECH/EDITOR I              PECB/NRR I            DRPM/NRR ll


I PECB/NRR I DRPM/NRR l l INAME BHughes:rc/bh
INAME         BHughes:rc/bh RGallo                                DCalure4UPP              AChaffee            MSlosson


RGallo DCalure4UPP
DATE          08/6 /97                  08/      /97            08/      /97              08/    /97          07/      /97 OFFICIAL RECORD            COPY


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}}
Issue Date:           03/21/94                                 E20-5                                   0720, 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

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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


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