ML060830167
| ML060830167 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/23/2006 |
| From: | Hironori Peterson Division of Reactor Safety III |
| To: | Christine Lipa NRC/RGN-III/DRP/RPB6 |
| References | |
| Download: ML060830167 (9) | |
See also: IR 05000316/2006003
Text
March 23, 2006
MEMORANDUM TO: Christine Lipa, Chief
Projects Branch 6
Division of Reactor Projects
FROM: Hironori Peterson, Chief /RA/
Operations Branch
Division of Reactor Safety
SUBJECT: D. C. COOK NUCLEAR POWER PLANT
DRS INPUT TO INTEGRATED REPORT 50-315/06-03;
50-316/06-03
Attached is the report input for D. C. Cook Nuclear Power Plant, Inspection
Report 50-315/06-03; 50-316/06-03. I have reviewed this input and have determined it is ready
for distribution to the licensee and dissemination to the public.
Post Inspection Data Input to Inspection Report 50-315/06-03; 50-316/06-03
Procedure Status and Sample Size:
IP 71111.11B (Biennial Licensed Operator Requalification Training Program Inspection)
Status = Not Applicable
Sample size = 0 (None: sample size of 1 entered in odd years for biennial inspections)
Attachment: Input to Inspection Report 50-315/316/2006-03
CONTACT: Bruce Palagi, DRS
(630) 829-9611
DOCUMENT NAME:G:\DRS\Work in Progress\DCCook Input Report 50-316-06-03 BBP.wpd
G Publicly Available G Non-Publicly Available G Sensitive G Non-Sensitive
To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy
OFFICE RIII RIII RIII RIII
NAME BPalagi: ls PPeterson
DATE 03/23/06 03/23/06
OFFICIAL RECORD COPY
Cover Letter
X No Input, no significant findings.
Title Page
Inspectors: B. Palagi, Senior Operations Engineer (Lead Inspector)
C. Moore, Operations Engineer
SUMMARY OF FINDINGS
ADAMS boilerplate - Inspectable Area: Licensed Operator Requalification Program
A. Inspector-Identified and Self-Revealed Findings
Cornerstone: Mitigating Systems
No findings of significance were identified.
B. Licensee-Identified Violations
No findings of significance were identified.
REPORT DETAILS
1. REACTOR SAFETY
Cornerstone: Mitigating Systems
1R11 Licensed Operator Requalification Program (71111.11)
.1 Facility Operating History
a. Inspection Scope
The inspectors reviewed the plants operating history from January 2004 through
January 2006 to identify operating experience that was expected to be addressed by
the Licensed Operator Requalification Training (LORT) program. Then it was verified
that the identified operating experience had been addressed by the facility licensee in
accordance with the stations approved Systems Approach to Training (SAT) program to
satisfy the requirements of 10 CFR 55.59(c), Requalification program requirements.
b. Findings
No findings of significance were identified.
.2 Licensee Requalification Examinations
a. Inspection Scope
The inspectors performed a biennial inspection of the licensees LORT test/examination
program for compliance with the stations SAT program which would satisfy the
requirements of 10 CFR 55.59(c)(4), Evaluation. The operating examination material
reviewed consisted of four operating tests, each containing two dynamic simulator
scenarios and five job performance measures (JPMs). The written examinations
reviewed consisted of four written examinations, each containing 37 questions. The
inspectors reviewed the annual requalification operating test and biennial written
examination material to evaluate general quality, construction, and difficulty level. The
inspectors assessed the level of examination material duplication from week-to-week
during the current year operating test and written examinations. The inspectors
reviewed the methodology for developing the examinations, including the LORT
program 2-year sample plan, probabilistic risk assessment insights, previously identified
operator performance deficiencies, and plant modifications.
b. Findings
No findings of significance were identified.
.3 Licensee Administration of Requalification Examinations
a. Inspection Scope
The inspectors observed the administration of a requalification operating test to assess
the licensees effectiveness in conducting the test to ensure compliance with
10 CRF 55.59(c)(4), Evaluation. The inspectors evaluated the performance of three
crews in parallel with the facility evaluators during six dynamic simulator scenarios and
evaluated various licensed crew members concurrently with facility evaluators during the
administration of several JPMs. The inspectors assessed the facility evaluators ability to
determine adequate crew and individual performance using objective, measurable
standards. The inspectors observed the training staff personnel administer the operating
test, including conducting pre-examination briefings, evaluations of operator performance,
and individual and crew evaluations upon completion of the operating test. The inspectors
evaluated the ability of the simulator to support the examinations. A specific evaluation of
simulator performance was conducted and documented under Section 1R11.8,
Conformance With Simulator Requirements Specified in 10 CFR 55.46, of this report.
b. Findings
No findings of significance were identified.
.4 Examination Security
a. Inspection Scope
The inspectors observed and reviewed the licensees overall licensed operator
requalification examination security program related to examination physical security
(e.g., access restrictions and simulator considerations) and integrity (e.g., predictability
and bias) to verify compliance with 10 CFR 55.49, Integrity of examinations and tests.
The inspectors also reviewed the facility licensees examination security procedure, any
corrective actions related to past or present examination security problems at the facility,
and the implementation of security and integrity measures (e.g., security agreements,
sampling criteria, bank use, and test item repetition) throughout the examination
process.
b. Findings
No findings of significance were identified.
.5 Licensee Training Feedback System
a. Inspection Scope
The inspectors assessed the methods and effectiveness of the licensees processes
for revising and maintaining its LORT Program up to date, including the use of feedback
from plant events and industry experience information. The inspectors reviewed the
licensees quality assurance oversight activities, including licensee training department
self-assessment reports. The inspectors evaluated the licensees ability to assess the
effectiveness of its LORT program and their ability to implement appropriate corrective
actions. This evaluation was performed to verify compliance with 10 CFR 55.59 (c)
Requalification program requirements and the licensees SAT program.
b. Findings
No findings of significance were identified.
.6 Licensee Remedial Training Program
a. Inspection Scope
The inspectors assessed the adequacy and effectiveness of the remedial training
conducted since the previous biennial requalification examinations and the training from
the current examination cycle to ensure that they addressed weaknesses in licensed
operator or crew performance identified during training and plant operations. The
inspectors reviewed remedial training procedures and individual remedial training plans.
This evaluation was performed in accordance with 10 CFR 55.59 (c) Requalification
program requirements and with respect to the licensees SAT program.
b. Findings
No findings of significance were identified.
.7 Conformance With Operator License Conditions
a. Inspection Scope
The inspectors reviewed the facility and individual operator licensees' conformance
with the requirements of 10 CFR Part 55. The inspectors reviewed the facility licensee's
program for maintaining active operator licenses and to assess compliance with
10 CFR 55.53 (e) and (f). The inspectors reviewed the procedural guidance and the
process for tracking on-shift hours for licensed operators and which control room
positions were granted watch-standing credit for maintaining active operator licenses.
The inspectors reviewed the facility licensee's LORT program to assess compliance with
the requalification program requirements as described by 10 CFR 55.59 (c). Additionally,
medical records for 14 licensed operators were reviewed for compliance with
b. Findings
No findings of significance were identified.
.8 Conformance With Simulator Requirements Specified in 10 CFR 55.46
a. Inspection Scope
The inspectors assessed the adequacy of the licensees simulation facility (simulator) for
use in operator licensing examinations and for satisfying experience requirements as
prescribed in 10 CFR 55.46, Simulation Facilities. The inspectors also reviewed a
sample of simulator performance test records (i.e., transient tests, scenario test and
discrepancy resolution validation test), simulator discrepancy and modification records,
and the process for ensuring continued assurance of simulator fidelity in accordance with
10 CFR 55.46. The inspectors reviewed and evaluated the discrepancy process to
ensure that simulator fidelity was maintained. Open simulator discrepancies were
reviewed for importance relative to the impact on 10 CFR 55.45 and 55.59 operator
actions as well as on nuclear and thermal hydraulic operating characteristics. The
inspectors conducted interviews with members of the licensees simulator staff about the
configuration control process and completed the IP 71111.11, Appendix C, checklist to
evaluate whether or not the licensees plant-referenced simulator was operating
adequately as required by 10 CFR 55.46 (c) and (d).
b. Findings
No findings of significance were identified.
9 Annual Operating Test Results
a. Inspection Scope
The inspectors reviewed the pass/fail results of individual written tests, and the operating
and simulator tests (required to be given per 10 CFR 55.59(a)(2)) administered by the
licensee during calender year 2006. The overall written examination and operating test
results were compared with the significance determination process in accordance with
NRC Manual Chapter 0609, Appendix I, Operator Requalification Human Performance
Significance Determination Process.
b. Findings
No findings of significance were identified.
4. OTHER ACTIVITIES
4OA5 Other Activities
(Closed) Violations 05000315/316/200506-01, 02, and 03 Failure to Accurately Report
Completion of Corrective Actions from a Previous Severity Level III Violation, Failure to
Provide Complete and Accurate Information about Operators Health Status, and
Failure to Report a Change in Operator Medical Status
Corrective actions associated with NRC issued Notice of Violation (NOV) EA-05-171
were reviewed. On November 23, 2005, the NRC issued a Notice of Violation EA-05-171
and proposed a Civil Penalty of $60,000 to the Indiana Michigan Power Company
associated with two violations of 10 CFR 50.9, "Completeness and Accuracy of
Information," and one violation of 10 CFR 50.74, Notification of Change in Operator or
Senior Operator Status. The violations were identified during an NRC inspection (NRC
Inspection Report No. 05000315/2005006) conducted at D.C. Cook in the spring and
summer of 2005 to review the plants reactor operator licensing program. NRC
inspectors identified three violations: (1) the utility had provided the NRC with incomplete
and inaccurate information. The utility stated that a complete review of all operator
medical records had been conducted and that no records that would require restrictions
to operator licenses for medical reasons had been found. However, NRC inspectors
identified three licensed operators who had medical conditions that would require their
licenses to be restricted; (2) the utility had failed to notify the NRC about licensed
operators experiencing a permanent illness within 30 days. Two NRC-licensed operators
at the plant were diagnosed with potentially disqualifying medical conditions in 1998 and
2003. However, the NRC was not notified of these facts until 2005; and (3) the utility
also failed to provide the NRC with complete and accurate information on NRC reactor
license applications. Applications submitted to the NRC for new, renewed and amended
NRC licenses did not describe the individuals recently diagnosed medical conditions that
would affect the conditions of these licenses. The licensee has implemented corrective
actions and the NRC evaluated the effectiveness of those corrective actions during this
inspection. The corrective action were evaluated as having been effective based on a
review of current operator training material, medical records, and reporting practices.
Therefore, violations VIO 05000315/316/2005006-01 (Failure of the licensee to
accurately report the completion of corrective actions from a previous SLIII violation in
2004.); VIO 05000315/316/2005006-02 (Failure to provide accurate and complete
information about operators health prior to the NRC performing a licensing action.); and
VIO 05000315/316/2005006-03 (Failure of the licensee to report the change in operator
medical status.) will be closed.
4OA6 Meeting(s)
.1 Interim Exit Meetings
Interim exit meetings were conducted for:
Biennial Operator Requalification Program Inspection with Mr. J. Jensen, Site Vice
President, on March 10, 2006.
Annual Operator Requalification Examination Results Inspection with Mr. T. Vriezema,
Operations Requalification Training Supervisor, on March 20, 2006.
KEY POINTS OF CONTACT
Licensee
L. Bush, Operations Supervisor
R. Gillespie, Operations Training Manager
T. Veirzema, Operations Requalification Training Supervisor
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Closed
05000315/200506-01 VIO Failure to Accurately Report Completion of Corrective
05000316/200506-01 Actions from a Previous Severity Level III Violation
05000315/200506-02 VIO Failure to Provide Complete and Accurate Information
05000316/200506-02 about Operators Health Status
05000315/200506-03 VIO Failure to Report a Change in Operator Medical Status
05000316/200506-03
LIST OF DOCUMENTS REVIEWED
Condition Reports associated with Notice of Violation EA-05-171, CR #s 05109063, 05111059,
05112045,051122049, 05216067,05223020, 05224028, 05322029, 0534276
Lesson Plan RQ-C-3040, LOR Period 3004 Ops Review
TI-TROP-02 Rev. 8, Administrative Requirements for NRC License and Medical Requirements
OHI-2071 Rev. 9, Reporting Reassignment, Yermination, and Conditions Potentially Affecting
Performance of Licensed Duties
TPD-600-LOR Rev. 11, LICENSED OPERATOR REQUALIFICATION TRAINING PROGRAM
DESCRIPTION
LIST OF ACRONYMS USED
CFR Code of Federal Regulations
DRS Division of Reactor Safety
IP Inspection Procedure
LORT Licensed Operator Requalification Training
SAT Systems Approach to Training