IR 05000461/2012007
| ML12214A348 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 08/01/2012 |
| From: | Robert Daley Engineering Branch 3 |
| To: | Pacilio M Exelon Generation Co, Exelon Nuclear |
| Mohammad Munir | |
| References | |
| IR-12-007 | |
| Download: ML12214A348 (16) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 August 1, 2012 Mr. Michael Senior Vice-President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville IL 60555 SUBJECT: CLINTON POWER STATIO N EVALUATION S OF CHANGES, TESTS, O R EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000 461/20 1 2007
Dear Mr. Pacilio:
On July 12, 201 2, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications inspection at your Clinton Power Station. The enclosed inspection report documents the inspection results
, which were discussed on July 12, 201 2, with you and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings of significance were identifie d. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/ Robert C. Daley, Chie f Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-461 License Nos. NPF-62
Enclosure:
Inspection Report 05000 461/2012007 w/Attachment: Supplemental Information
REGION III==
Docket No: 50-461 License No
- NPF-62 Report No:
05000 461/20 1 2007 Licensee: Exelon Generation Facility: Clinton Power Station Location: Clinton , IL Dates: June 25 - July 12, 201 2 Inspectors:
M. Munir, Reactor Inspector (Lead) J. Gilliam, Reactor Inspector L. Jones, Reactor Inspector Approved by:
R. Daley, Chief Engineering Branch 3 Division of Reactor Safety 1 Enclosure
SUMMARY OF FINDINGS
IR 05000 461/20 1 2007; 0 6/25/201 2 - 07/12/201 2; Clinton Power Station; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications.
This report covers a two-week announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by Region III based engineering inspectors.
The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG
-1649, "Reactor Oversight Process," Revision 4, dated December 2006.
A. No findings of significance were identified.
N RC-Identified and Self-Revealed Findings B. No violations of significance were identified.
Licensee-Identified Violations
1. REACTOR SAFETY
REPORT DETAILS
Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity 1R17 Evaluation
s of Changes, Tests, or Experiments and Permanent Plant Modifications
.1
a. Evaluation of Changes, Tests, or Experiments From June 2 5, 20 1 2 through July12, 201 2, the inspectors reviewed 7 safety-evaluations performed pursuant to 10 CFR 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 2 2 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if:
Inspection Scope the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required; the safety issue requiring the change, tests or experiment was resolved; the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and the design and licensing basis documentation was updated to reflect the change.
The inspectors used, in part, Nuclear Energy Institute (NEI) 96
-07, "Guidelines for 10 CFR 50.59 Implementation," Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments," dated November 2000. The inspectors also consulted Part 9900 of the NRC Inspection Manual, "10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments."
This inspection constituted 7 samples of evaluations and 2 2 samples of changes as defined in IP 71111.17-04. b. No findings of significance were identified.
Findings
.2 a. Permanent Plant Modifications
From June 25, 201 2 through July 12 , 2012 , the inspectors reviewed 12 permanent plant modifications that had been installed in the plant during the last three years. This review Inspection Scope
3 Enclosure included in
-plant walkdown for a portion of the installed Division 1, 2 and 3 emergency diesel exhaust system and the newly installed Nuclear Steam Supply Protection System inverters 1C71
-S001A & 1C71
-3001B. The modifications were selected based upon risk significance, safety significance, and complexity. The inspectors reviewed the modifications selected to determine if:
the supporting design and licensing basis documentation was updated; the changes were in accordance with the specified design requirements; the procedures and training plans affected by the modification have been adequately updated; the test documentation as required by the applicable test programs has been updated; and post-modification testing adequately verified system operability and/or functionalit y. The inspectors also used applicable industry standards to evaluate acceptability of the modifications. The list of modifications and other documents reviewed by the inspectors is included as an Attachment to this report.
This inspection constituted t welve permanent plant modification samples as defined in IP 71111.17-04. b. No findings of significance were identified.
Findings
OTHER ACTIVITIES
(OA)
4OA2
.1 Identification and Resolution of Problems
a. Routine Review of Condition Reports From June 2 5, 201 2 through July 12 201 2, the inspectors reviewed 21 corrective action process documents that identified or were related to 10 CFR 50.59 evaluations and permanent plant modifications. The inspectors reviewed these documents to evaluate the effectiveness of corrective actions related to permanent pant modifications and evaluations for changes, tests, or experiments issues. In addition, corrective action documents written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problems into the corrective action system. The specific corrective action documents that were sampled and reviewed by the inspectors are listed in the attachment to this report.
Inspection Scope b. No findings of significance were identified.
Findings 4 Enclosure
4OA6
.1 Meetings O n July 12, 201 2 , the inspector
s presented the inspection results to Mr. Noll and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff. Exit Meeting Summary ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
- W. Noll, Site Vice President
Licensee
- B. Taber, Plant Manager
- D. Kemper, Site Engineering Director
- S. Kowalski, Sr. Manager Design Engineering Manager
- J. Smith, Sr. Manager Plant Engineering
- K. Baker, Regulatory Assurance Manager
Nuclear Regulatory Commission
- B. Kemker, Senior Resident Inspector
LIST OF ITEMS
OPENED, CLOSED AND DISCUSS
ED Non eOpened, Closed, and
Discussed
Attachment
LIST OF DOCUMENTS REVIEWED
The following