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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| 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 | | 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:}} | {{#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== | |||
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}} | |||
{{Information notice-Nav}} | {{Information notice-Nav}} |
Latest revision as of 04:45, 24 November 2019
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
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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
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Leach,
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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