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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY | | {{#Wiki_filter:UNITED STATES |
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| COMMISSION | | NUCLEAR REGULATORY COMMISSION |
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| ===OFFICE OF NUCLEAR REACTOR REGULATION===
| | OFFICE OF NUCLEAR REACTOR REGULATION |
| WASHINGTON, D.C. 20555-OpO1 August 21, 1997 NRC INFORMATION
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| 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 |
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| FOR SIGNIFICANT
| | SIGNIFICANT MANIPULATIONS OF THE CONTROLS |
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| MANIPULATIONS
| | FOR POWER REACTOR OPERATOR LICENSING |
| | |
| OF THE CONTROLS FOR POWER REACTOR OPERATOR LICENSING
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| ==Addressees== | | ==Addressees== |
| All holders of operating | | All holders of operating licenses for nuclear power reactors except those who have |
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| licenses for nuclear power reactors except those who have permanently | |
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| ceased operations
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| and have certified | | permanently ceased operations and have certified that fuel has been permanently removed |
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| that fuel has been permanently
| | from the reactor vessel. |
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| removed from the reactor vessel.
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| ==Purpose== | | ==Purpose== |
| The U.S. Nuclear Regulatory | | The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert |
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| Commission (NRC) is issuing this information
| | addressees that operator license applicants are required to perform at least five significant |
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| notice to alert addressees
| | control manipulations on the facility for which a license Is sought (Section 55.31 (a)(5) of Title |
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| that operator license applicants
| | 10 of the Code of Federal Regulations [10 CFR 55.31(a)(5)]). Licensees have erred on the |
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| are required to perform at least five significant
| | interpretation of the requirements of this section of 10 CFR Part 55. It is expected that |
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| control manipulations
| | recipients will review information for applicability to their facilities and consider actions, as |
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| 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 |
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| [10 CFR 55.31(a)(5)]).
| | notice are not NRC requirements; therefore, no specific action or written response is |
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| Licensees
| | required. |
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| have erred on the interpretation | | ==Description of Circumstances== |
| | Operator license applicants are required to provide evidence that they, as trainees, have |
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| of the requirements | | successfully manipulated the controls of the facility for which an operator or senior operator |
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| 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 |
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| will review information
| | manipulations which affect reactivity or power level on the facility for which the license is |
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| for applicability
| | sought (10 CFR 55.31(a)(5)). Controls as defined in 10 CFR 55 are apparatus and |
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| to their facilities
| | mechanisms, the manipulation of which directly affects the reactivity or power level of the |
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| and consider actions, as appropriate, to avoid similar problems.
| | reactor. Licensees have erred on the interpretation of what constitutes a significant control |
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| However, suggestions
| | manipulation. |
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| contained
| | During a review of operator license applications for the Pilgrim facility, NRC inspectors |
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| in this information
| | determined that the requirements for operator and senior operator applicants to perform at |
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| 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
| |
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| of Circumstances
| | licensee incorrectly assumed that a single 30 percent decrease in power with recirculation |
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| Operator license applicants
| | pumps was equivalent to three 10 percent or greater power reductions and counted this as |
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| are required to provide evidence that they, as trainees, have successfully
| | three of the five required significant control manipulations. The licensee contacted other |
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| manipulated
| | licensees regarding the practice at their facilities and reported that there was a wide range of |
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| 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 |
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| must perform five significant
| | _pDp4 rceq -01 1101'2¢ |
| | Q05020 r, . |
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| control manipulations
| | Hills |
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| which affect reactivity
| | 'Y 4 |
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| 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 |
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| Controls as defined in 10 CFR 55 are apparatus
| | until the facility submitted revised applications and provided details of how the applicants |
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| and mechanisms, the manipulation
| | satisfied the requirements to perform the required significant control manipulations. As |
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| 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 |
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| or power level of the reactor. Licensees
| | NRC requirements had occurred because two applicants had not completed the five |
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| have erred on the interpretation
| | significant control manipulations required by 10 CFR 55.31 (a)(5) in an acceptable manner. |
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| of what constitutes
| | Discussion |
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| a significant
| | Before 1987, the operator license application required the licensee to certify that the |
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| control manipulation.
| | applicant had learned to operate the facility and also to provide the details of the training and |
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| During a review of operator license applications
| | experience of the applicant. A 1987 NRC rule changed the requirement to provide the details |
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| |
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| for the Pilgrim facility, NRC inspectors
| | of the applicant's training and experience and requested instead a simple check mark in the |
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| |
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| determined
| | boxes on the application form (NRC-398) to indicate that the applicant has successfully |
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| that the requirements
| | completed an Institute of Nuclear Power Operations (INPO) accredited operator training |
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| for operator and senior operator applicants
| | program that is based on a systems approach to training, and that a certified simulation |
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| to perform at least five significant
| | facility is used in the operator training program. |
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| control manipulations
| | During rule making, the nuclear industry requested clarification of the phrase "leamed to |
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| on the facility were not satisfied.
| | operate" (Federal Register Vol. 52, No. 57 Wednesday, March 25, 1987, page 9456) and |
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| The Pilgrim licensee incorrectly
| | NRC added 10 CFR 55.31 (a)(5) to specify the minimum number of control manipulations that |
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| assumed that a single 30 percent decrease in power with recirculation
| | the applicant had to conduct on the facility. |
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| 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 |
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| to three 10 percent or greater power reductions | | facility during a minimum of five reactivity changes. Every effort should be made to |
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| and counted this as three of the five required significant
| | have a diversity of reactivity changes for each applicant. Startups, shutdowns, large |
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| control manipulations.
| | load changes, and changes in rod programming are some examples and could be |
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| The licensee contacted
| | accomplished by manually using such systems as rod control, chemical shim control, or recirculation flow. |
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| other licensees
| | Additional examples of significant control manipulations include, but are not limited to, items |
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| regarding
| | A-F of 10 CFR 55.59(c)(3) (on-thejob training for requalification): |
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| the practice at their facilities
| | IN 97-67 August 21, 1997 A. Plant or reactor startups to include a range that reactivity |
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| and reported that there was a wide range of interpretations | | feedback from nuclear heat addition is noticeable and heatup |
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| by the other licensees
| | rate is established. |
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| contacted.
| | B. Plant shutdown. |
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| 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 |
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| examinations
| | and shutdown. |
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| to the individuals
| | D. Boration or dilution during power operation. |
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| but did not issue operator licenses until the facility submitted
| | E. Significant ( 10 percent) power changes in manual control or recirculation |
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| revised applications
| | flow. |
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| and provided details of how the applicants
| | F. Reactor power change of 10 percent or greater where load change is |
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| satisfied
| | performed with load limit control or where flux, temperature, or speed control is |
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| the requirements
| | on manual (for HTGR). |
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| 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 |
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| 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 |
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| |
|
| As documented
| | Federal Regulations, Part 55 on Operators' Licenses," dated November 1987, which was |
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| |
|
| 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 |
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| |
|
| 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 |
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| |
|
| that a violation
| | period (i.e., on the same shift) with no diversity of controls would be evaluated as one |
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| of NRC requirements
| | significant control manipulation. The situation in which an applicant reduces power |
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| had occurred because two applicants
| | from 100 percent to 95 percent and then increases power from 95 percent to |
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| had not completed
| | 100 percent would be evaluated as one significant control manipulation. |
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| the five significant
| | The situation when an applicant performs a 50 percent change in power in a short |
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| control manipulations | | period of time with diversity of controls (recirculation flow and control rods, or |
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| required by 10 CFR 55.31 (a)(5) in an acceptable
| | chemical shim and controls rods) can be evaluated as two significant control |
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| manner.Discussion
| | manipulations. The situations when an applicant reduces power by 10 percent then |
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| Before 1987, the operator license application
| | holds there for performance of other work or testing and then later in the shift |
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| required the licensee to certify that the applicant
| | increases power by 10 percent can be evaluated as two significant control |
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| had learned to operate the facility and also to provide the details of the training and experience
| | manipulations. |
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| of the applicant. | | Diversity of significant control manipulations on the plant are expected; however, it is |
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| A 1987 NRC rule changed the requirement
| | not required. If the applicant does not have experience in diverse significant control |
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| to provide the details of the applicant's
| | manipulations, this fact should be noted in the comments section of NRC form 398. |
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| training and experience
| | . I |
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| |
|
| 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
| |
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| |
|
| has successfully
| | Original signed by |
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| |
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| completed
| | Maryle on, Fiting Director |
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| an Institute
| | Division of Reactor Program Management |
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| |
|
| of Nuclear Power Operations (INPO) accredited | | Office of Nuclear Reactor Regulation |
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| |
|
| 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 |
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| Problems Associated
| | 301-415-1096 (817) 860-8159 E-mail: bxhl@nrc.gov E-mail: jlp@nrc. v |
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| 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
| |
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| |
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| Reactivity
| | (630) 829-9705 E-mail: mnl@nrc.gov |
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| |
|
| Addition During Plant Shutdown U.S. Department
| | Attachment: List of Recently Issued N Information Notices |
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| |
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| 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 |
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| |
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| Commission
| | *See previous concurrence / |
| | To receive a copy of this document. Indicate hI the box: *C - Copy without attachmentlenclosure E - Copy with attachment/enclosure |
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| |
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| 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 |
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| Commission
| | NAME BHughes:rc/bh RGallo Cpet'rone kc-hafftee 11slosson |
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| 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 |
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| of medical devices OL = Operating
| | I |
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| License CP = Construction
| | IN 97-XX |
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| Permit
| | July XX. 1997 This information notice requires no specific action or written response. |
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| |
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| 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 |
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| |
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| If you have any questions
| | Nuclear Reactor Regulation (NRR) project manager. |
|
| |
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| about the information
| | Jack Roe. Acting rector |
|
| |
|
| in this notice, please contact one of the technical
| | Division of Rea or Program Management |
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| |
|
| contacts listed below or the appropriate
| | Office of Nuc ar Reactor Regulation |
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| |
|
| 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 |
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| |
|
| 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
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| | |
| kc-hafftee
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| | |
| 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 |
|
| |
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| 'N' -No copy OFFICE HOLB/DRCH
| | TECH/EDITOR PECB/NRR DRPM/NRR |
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| |
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| TECH/EDITOR
| | NAME BHughes:rc/bht. RGallo'fDCalureAd AChaffee JRoe |
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| l PECB/NRR DRPM/NRR NAME BHughes:rc/bht.
| | DATE 08/06/97* 08 /97 07/08/97* 08/ /97 08/ /97 |
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| 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 |
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| |
|
| 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}} |
Failure to Satisfy Requirements for Significant Manipulations of the Controls for Power Reactor Operation LicensingML031050127 |
Person / Time |
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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 |
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Issue date: |
08/21/1997 |
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From: |
Slosson M Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-97-067, NUDOCS 9708150270 |
Download: ML031050127 (8) |
|
Similar Documents at 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 |
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Category:NRC Information Notice
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Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
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
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
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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list | - Information Notice 1997-01, Improper Electrical Grounding Results in Simultaneous Fires in the Control Room and the Safe-Shutdown Equipment Room (8 January 1997, Topic: Safe Shutdown, Emergency Lighting)
- Information Notice 1997-02, Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water Reactors (6 February 1997)
- Information Notice 1997-03, Defacing of Labels to Comply with 10 CFR 20.1904(b) (20 February 1997)
- Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents (24 February 1997, Topic: Backfit)
- Information Notice 1997-05, Offsite Notification Capabilities (27 February 1997, Topic: Earthquake)
- Information Notice 1997-06, Weaknesses in Plant-Specific Emergency Operating Procedures for Refilling the Secondary Side of Dry Once-Through Steam Generators (4 March 1997)
- Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections (6 March 1997, Topic: Hot Short, Safe Shutdown, Weak link)
- Information Notice 1997-08, Potential Failures of General Electric Magne-Blast Circuit Breaker Subcomponents (12 March 1997, Topic: Coatings, Weak link)
- Information Notice 1997-09, Inadequate Main Steam Safety Valve (MSSV) Setpoints and Performance Issues Associated with Long MSSV Inlet Piping (12 March 1997)
- Information Notice 1997-10, Liner Plate Corrosion in Concrete Containments (13 March 1997)
- Information Notice 1997-11, Cement Erosion from Containment Subfoundations at Nuclear Power Plants (21 March 1997)
- Information Notice 1997-12, Potential Armature Binding in General Electric Type Hga Relays (24 March 1997)
- Information Notice 1997-13, Deficient Conditions Associated with Protective Coatings at Nuclear Power Plants (24 March 1997, Topic: Coatings)
- Information Notice 1997-14, Assessment of Spent Fuel Pool Cooling (28 March 1997, Topic: Time to boil, Coatings)
- Information Notice 1997-15, Reporting of Errors and Changes in Large-Break Loss-of-Coolant Accident Evaluation Models of Fuel Vendors and Compliance with 10 CFR 50. 46(a)(3) (4 April 1997, Topic: Coatings, Fuel cladding)
- Information Notice 1997-16, Preconditioning of Plant Structures, Systems, and Components Before ASME Code Inservice Testing or Technical Specification Surveillance Testing (4 April 1997, Topic: Stroke time, Coatings)
- Information Notice 1997-17, Cracking of Vertical Welds in the Core Shroud and Degraded Repair (4 April 1997, Topic: Coatings)
- Information Notice 1997-18, Problems Identified During Maintenance Rule Baseline Inspections (14 April 1997, Topic: Probabilistic Risk Assessment, Coatings, Emergency Lighting)
- Information Notice 1997-19, Safety Injection System Weld Flaw at Sequcyah Nuclear Power Plant, Unit 2 (18 April 1997, Topic: Boric Acid)
- Information Notice 1997-20, Identification of Certain Uranium Hexafluoride Cylinders That Do Not Comply with ANSI N14.1 Fabrication Standards (17 April 1997)
- Information Notice 1997-21, Availability of Alternate AC Power Source Designed for Station Blackout Event (18 April 1997, Topic: Main transformer failure)
- Information Notice 1997-22, Failure of Welded-Steel Moment Resisting Frames During Northridge Earthquake (25 April 1997, Topic: Earthquake)
- Information Notice 1997-23, Evaluation and Reporting of Fires and Unplanned Chemical Reaction Events at Fuel Cycle Facilities (7 May 1997, Topic: Earthquake)
- Information Notice 1997-24, Failure of Packing Nuts on One-Inch Uranium Hexafluoride Cylinder Valves (8 May 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-25, Dynamic Range Uncertainties in the Reactor Vessel Level Instrumentation (9 May 1997, Topic: Earthquake)
- Information Notice 1997-26, Degradation in Small-Radius U-Bend Regions of Steam Generator Tubes (19 May 1997, Topic: Earthquake)
- Information Notice 1997-27, Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction Head (16 May 1997, Topic: Earthquake)
- Information Notice 1997-28, Elimination of Instrument Response Time Testing Under the Requirements of 10 CFR 50.59 (30 May 1997, Topic: Enforcement Discretion)
- Information Notice 1997-29, Containment Inspection Rule (30 May 1997)
- Information Notice 1997-30, Control of Licensed Material During Reorganizations, Employee-Management Disagreements, and Financial Crises (3 June 1997)
- Information Notice 1997-31, Failures of Reactor Coolant Pump Thermal Barriers and Check Valves in Foreign Plants (3 June 1997)
- Information Notice 1997-32, Defective Worm Shaft Clutch Gears in Limitorque Motor-Operated Valve Actuators (10 June 1997)
- Information Notice 1997-33, Unanticipated Effect of Ventilation System on Tank Level Indications and Engineering Safety Features Actuation System Setpoint (11 June 1997)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels In Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (Inc) IR100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (INC) Ir100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-36, Unplanned Intakes by Worker of Transuranic Airborne Radioactive Materials and External Exposure Due to Inadequate Control of Work (20 June 1997)
- Information Notice 1997-37, Main Transformer Fault with Ensuing Oil Spill Into Turbine Building (20 June 1997)
- Information Notice 1997-38, Level-Sensing System Initiates Common-Mode Faulure of High-Pressure-Injection Pumps (24 June 1997, Topic: Hydrostatic)
- Information Notice 1997-39, Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent Fuel Storage Installations (26 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-40, Potential Nitrogen Accumulation Resulting from Backleakage from Safety Injection Tanks (26 June 1997)
- Information Notice 1997-41, Revised - Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers (27 June 1997)
- Information Notice 1997-42, Management Weaknesses Resulting in Failure to Comply with Shipping Requirements for Special Nuclear Material (27 June 1997)
- Information Notice 1997-43, License Condition Compliance (1 July 1997, Topic: Ultimate heat sink)
- Information Notice 1997-44, Failures of Gamma Metrics Wide-Range Linear Neutron Flux Channels (1 July 1997)
- Information Notice 1997-45, Environmental Qualification Deficiency for Cables & Containment Penetration Pigtails (2 July 1997)
- Information Notice 1997-46, Unisolable Crack in High-Pressure Injection Piping (9 July 1997, Topic: Flow Induced Vibration)
- Information Notice 1997-47, Inadequate Puncture Tests for Type B Packages Under 10 CFR 71.73(c)(3) (27 June 1997)
- Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures (9 July 1997, Topic: Safe Shutdown, Unanalyzed Condition, Fire Barrier, Emergency Lighting, Continuous fire watch, Fire Protection Program, Fire Watch)
... further results |
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