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{{#Wiki_filter:UNITED STATES
{{#Wiki_filter:UNITED STATES
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    %e...+/                                           April 21, 1999 MEMORANDUM TO:           Marc L. Dapas, Deputy Director, DRP THRU:                     Thomas J. Kozak, Chief, Reactor Projects Branch 4, DRP FROM:                     Troy W. Pruett, Senior Resident inspector, Clintorf/[d 4
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April 21, 1999 MEMORANDUM TO:
Marc L. Dapas, Deputy Director, DRP THRU:
Thomas J. Kozak, Chief, Reactor Projects Branch 4, DRP FROM:
Troy W. Pruett, Senior Resident inspector, Clintorf/[d 4


==SUBJECT:==
==SUBJECT:==
CLOSURE OF NRC 0350 CASE SPECIFIC CHECKLIST ITEMS 11.1, IV.4, AND VI.3 FOR CLINTON POWER STATION This memorandum documents completion of inspection activities performed during the week of April 12,1999, to assess the licensee's implemented and planned corrective actions associated with NRC Manual Chapter 0350 Case Specific Checklist (CSC) Restart item 11.1, " Establish and implement Continuing Operator Training Emphasizing Technical Specification Adherence / Knowledge and Recognition of Degraded Conditions," CSC Restart item IV.4,             .
CLOSURE OF NRC 0350 CASE SPECIFIC CHECKLIST ITEMS 11.1, IV.4, AND VI.3 FOR CLINTON POWER STATION This memorandum documents completion of inspection activities performed during the week of April 12,1999, to assess the licensee's implemented and planned corrective actions associated with NRC Manual Chapter 0350 Case Specific Checklist (CSC) Restart item 11.1, " Establish and implement Continuing Operator Training Emphasizing Technical Specification Adherence / Knowledge and Recognition of Degraded Conditions," CSC Restart item IV.4,
            " Resolve Degraded Voltage and Electrical Distribution Concerns," and CSC Restart item VI.3,
" Resolve Degraded Voltage and Electrical Distribution Concerns," and CSC Restart item VI.3,
            " Validate the Adequacy of the Setpoint Program." The inspection findings will be documented in NRC Inspection Report 50-461/99011.
" Validate the Adequacy of the Setpoint Program." The inspection findings will be documented in NRC Inspection Report 50-461/99011.
The resident inspector staff closed CSC Restart item 11.1. Case Specific Checklist item II.1 was initially reviewed in NRC Inspection Report 50-461/99006. One aspect remained unreviewed which involved an assessment of the work control to operations interface. The inspectors reviewed the licensee's root cause analyses, apparent cause analyses; self-assessments, and corrective actions for issues involving the use of coordination plans, system impact statements,   i development and performance of post-maintenance testing, equipment status control, and awareness of operations personnel. The inspectors determined that the planned corrective           ;
The resident inspector staff closed CSC Restart item 11.1. Case Specific Checklist item II.1 was initially reviewed in NRC Inspection Report 50-461/99006. One aspect remained unreviewed which involved an assessment of the work control to operations interface. The inspectors reviewed the licensee's root cause analyses, apparent cause analyses; self-assessments, and corrective actions for issues involving the use of coordination plans, system impact statements, i
actions appeared adequate for closure of CSC Restart item II.1. However, inspection Follow-up       '
development and performance of post-maintenance testing, equipment status control, and awareness of operations personnel. The inspectors determined that the planned corrective actions appeared adequate for closure of CSC Restart item II.1. However, inspection Follow-up Item 50-461/99011-01 was initiated to assess the effectiveness of the planned corrective actions at a later date.
Item 50-461/99011-01 was initiated to assess the effectiveness of the planned corrective actions
        ,  at a later date.                                                                                   ;
The Division of Reactor Safety (DRS) staff closed CSC Restart item IV.1. Case Specific Checklist item IV.1 was initially reviewed in NRC Inspection Report 50-461/99003. One aspect remained unreviewed which involved an assessment of degraded voltage modification testing results. The inspectors evaluated engineering personnel acceptance reviews of the static var compensator verification tests and concluded that the electrical distribution system design changes would resolve the degraded voltage concems at Clinton. Therefore, CSC Restart item IV.1 is considered closed.
The Division of Reactor Safety (DRS) staff closed CSC Restart item IV.1. Case Specific Checklist item IV.1 was initially reviewed in NRC Inspection Report 50-461/99003. One aspect remained unreviewed which involved an assessment of degraded voltage modification testing results. The inspectors evaluated engineering personnel acceptance reviews of the static var compensator verification tests and concluded that the electrical distribution system design changes would resolve the degraded voltage concems at Clinton. Therefore, CSC Restart item IV.1 is considered closed.
The DRS staff closed CSC Restart item VI.1. Case Specific Checklist Item VI.3 was initially reviewed in NRC Inspection Report 50-461/99003. One aspect remained unreviewed which involved an assessment of Technical Specification required instrument setpoints. The inspectors reviewed the adequacy of setpoint operability determinations, operability evaluations, L     9905060052 990427 PDR     ADOCK 05000461 Q                       PDR
The DRS staff closed CSC Restart item VI.1. Case Specific Checklist Item VI.3 was initially reviewed in NRC Inspection Report 50-461/99003. One aspect remained unreviewed which involved an assessment of Technical Specification required instrument setpoints. The inspectors reviewed the adequacy of setpoint operability determinations, operability evaluations, L
9905060052 990427 PDR ADOCK 05000461 Q
PDR


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<*      M. Dapas                                                   and instrument setpoint review packages. The inspectors determined that the evaluations performed by engineering personnel addressed all modes of plant operation with current setpoint field settings. Additionally, sufficient margin existed between the field settings and their respective allowable value and analytical limit. Therefore, CSC Restart item VI.3 is considered closed, i
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and instrument setpoint review packages. The inspectors determined that the evaluations performed by engineering personnel addressed all modes of plant operation with current setpoint field settings. Additionally, sufficient margin existed between the field settings and their respective allowable value and analytical limit. Therefore, CSC Restart item VI.3 is considered
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Latest revision as of 01:32, 7 December 2024

Documents Completion of Insp Activities Performed During Week of 990412,to Assess Licensee Implemented & Planned Corrective Actions Associated with NRC Manual Chapter 0350 Case Specific Checklist Restart Item II.1
ML20206F236
Person / Time
Site: Clinton Constellation icon.png
Issue date: 04/21/1999
From: Troy Pruett
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Dapas M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20206F217 List:
References
50-461-99-03, 50-461-99-06, 50-461-99-11, 50-461-99-3, 50-461-99-6, NUDOCS 9905060052
Download: ML20206F236 (2)
v • d • e


Text

UNITED STATES

[pu mcg%

NUCLEAR REGULATORY COMMi$SION

  • y

~Ik' REGloN I!!

,,j 801 WARRENVILL E noAD g

USLE. ILLINOIS 6053N3M

%e...+/

April 21, 1999 MEMORANDUM TO:

Marc L. Dapas, Deputy Director, DRP THRU:

Thomas J. Kozak, Chief, Reactor Projects Branch 4, DRP FROM:

Troy W. Pruett, Senior Resident inspector, Clintorf/[d 4

SUBJECT:

CLOSURE OF NRC 0350 CASE SPECIFIC CHECKLIST ITEMS 11.1, IV.4, AND VI.3 FOR CLINTON POWER STATION This memorandum documents completion of inspection activities performed during the week of April 12,1999, to assess the licensee's implemented and planned corrective actions associated with NRC Manual Chapter 0350 Case Specific Checklist (CSC) Restart item 11.1, " Establish and implement Continuing Operator Training Emphasizing Technical Specification Adherence / Knowledge and Recognition of Degraded Conditions," CSC Restart item IV.4,

" Resolve Degraded Voltage and Electrical Distribution Concerns," and CSC Restart item VI.3,

" Validate the Adequacy of the Setpoint Program." The inspection findings will be documented in NRC Inspection Report 50-461/99011.

The resident inspector staff closed CSC Restart item 11.1. Case Specific Checklist item II.1 was initially reviewed in NRC Inspection Report 50-461/99006. One aspect remained unreviewed which involved an assessment of the work control to operations interface. The inspectors reviewed the licensee's root cause analyses, apparent cause analyses; self-assessments, and corrective actions for issues involving the use of coordination plans, system impact statements, i

development and performance of post-maintenance testing, equipment status control, and awareness of operations personnel. The inspectors determined that the planned corrective actions appeared adequate for closure of CSC Restart item II.1. However, inspection Follow-up Item 50-461/99011-01 was initiated to assess the effectiveness of the planned corrective actions at a later date.

The Division of Reactor Safety (DRS) staff closed CSC Restart item IV.1. Case Specific Checklist item IV.1 was initially reviewed in NRC Inspection Report 50-461/99003. One aspect remained unreviewed which involved an assessment of degraded voltage modification testing results. The inspectors evaluated engineering personnel acceptance reviews of the static var compensator verification tests and concluded that the electrical distribution system design changes would resolve the degraded voltage concems at Clinton. Therefore, CSC Restart item IV.1 is considered closed.

The DRS staff closed CSC Restart item VI.1. Case Specific Checklist Item VI.3 was initially reviewed in NRC Inspection Report 50-461/99003. One aspect remained unreviewed which involved an assessment of Technical Specification required instrument setpoints. The inspectors reviewed the adequacy of setpoint operability determinations, operability evaluations, L

9905060052 990427 PDR ADOCK 05000461 Q

PDR

I l

io j

o.

M. Dapas <*

and instrument setpoint review packages. The inspectors determined that the evaluations performed by engineering personnel addressed all modes of plant operation with current setpoint field settings. Additionally, sufficient margin existed between the field settings and their respective allowable value and analytical limit. Therefore, CSC Restart item VI.3 is considered

closed, i

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