ML091700603
| ML091700603 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/11/2009 |
| From: | Conte R NRC Region 1 |
| To: | Conte R NRC Region 1 |
| References | |
| FOIA/PA-2009-0070 | |
| Download: ML091700603 (9) | |
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Sunday, January 11, 2009 6:59 PM Richard Conte cover guts OC 2008-07 LRIrev-2A Upfront Guts.doc hifmib' h~fthi e=o~ wasdeleted h wodu hcewi the Freedom of Infbiaft AC.
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([148.184.99.10]) with mapi; Sun, 11 Jan 2009 18:58:53 -0500 Content-Type: application/ms-tnef; name="winmail.dat" Content-Transfer-Encoding: binary From: Richard Conte <Richard.Conte@nrc.gov>
To: Richard Conte <Richard. Conte@nrc.gov>
Date: Sun, 11 Jan 2009 18:58:52 -0500
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Conte Input for Upfront Guts of Report Dear Mr. Pardee On December 23, 2008, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at your Oyster Creek Generating Station. The enclosed repprt documents the inspection results, which were discussed on December 23, 2008, with Mr. T. Rausch, Site Vice President, Mr. M. Gallagher, Vice President License Renewal, and other members of your staff in a telephone conference observed by representatives from the Stateof New Jersey.
Part 50 results With respect to activities authorized by 10 CFR 50, the inspectors found no finoihgs of safety significance.
(b)(5)
Furthdias you well kni an appieal of a licensing board decision regarding the Oyster Creek appllik4t n for a renewedlf..!6eense i piending before the Commission related to the adequacy of the agi rfanagement progiapri for the Oyster Creek drywell.
The midcycl@ijtter of.......
Indicated that the inspections of L
(b)
(5)
The NRC is conducting these inspections using the guidance of Inspection Procedure (IP) 71003 "Post-Approval Site Inspection for License Renewal" as a prudent measure in order to take the opportunity to make observations of Oyster Creek license renewal activities during the last refuel outage prior to entering the period of extended operation. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
(b) (5)
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(b)(5) 54 44,4 4'~'44~4
A-4 (b)(5)
In accordance with 10 CFR 2.790 of the NAC's "Ruies fracti a copy of this letter and its enclosure will be available el.ectoncally fo blhc *..thE NRC Public Document Room or from the PubliclyNAvailable.RecordNj*$RS) comp'&i of NRC's document system (ADAMS). ADAMS is.accessible ft, the NR eb-site at http://www.nrc.qov/NR-C/ADAMS/ini.html (th ublic Electronic Reading Room).
(b) (5)
Sincerely, Darrell Roberts, Director Division of Reactor Safety
A-5 REPORT DETAILS
- 4.
OTHER ACTIVITIES (OA) 40A2 License Renewal Follow-up (IP 71003)
- 1.
Background
Because the application for a renewed license remains under Commission review for final decision, and a renewed license has not been approved for Oister Creek, the standards used to judge the adequacy of selected IP 71003 inspection s$6Tpies do not appiy.
This inspection was conducted in order to observe AierGen's continuing license renewal activities during the last refueling outage prior to. Oyster Creek (OC) entering the extended period of operation.
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Accordingly, the inspectors recorded observations, wi*tlty assessment of implementation adequacy or safety significance.
IP 71003 verifies license conditions add as cense cense renewal commitments, selected aging managemernrIra cllerýftenewal commitments revised after the renewed r
i accordance with Title 10 of the Code of Federal Reg.lat1esOFR) Parf quireme-ts for the Renewal of Operating Licenses for Nuclear Pntr Plants'-.
- 2.
Inspection San erSeleeti.
toes.
Th, A oz eaEIlected a number of inspection samples for review, using the NRC a;¢epdeo gudl.
bapn their importance in the license renewal application pcess, as an & tunityktrnake observations on license renewal activities.
cftsct'ion observati were considered, in light of pending 10 CFR 54 license renewal cor itents and license conditions, as documented in NUREG-1 875, "Safety Evalu'-t,,Report (SEI;) Related to the License Renewal of Oyster Creek Generating Station,'<aell matic performance under on-going implementation of 10 CFR 50 cur.r'nsing basis (CLB) requirements.
The reviewed SER proposed commitments and license conditions were selected based on several attributes including: the risk significance using insights gained from sources such as the NRC's "Significance Determination Process Risk Informed Inspection Notebooks," revision 2; the extent and results of previous license renewal audits and inspections of aging management programs; the extent or complexity of a commitment; and the extent that baseline inspection programs will inspect a system, structure, or component (SSC), or commodity group.
For each commitment and on a sampling basis, the inspectors reviewed supporting
A-6 documents including completed surveillances, conducted interviews, performed visual inspection of structures and components including those not accessible during power operation, and observed selected activities described below. The inspectors also reviewed selected corrective actions taken as a consequence of previous license renewal inspections.
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- 3.
Review Details 3.1 NRC Unresolved Item 10 CFR 50 existing requirements (e.g., current licensing basis (CLB) xxx USE words from PN
- The conclusions of PNO-1-08-012 remain unchanged
- An Unresolved Item (URI) will be opened to evaluate whether existing current licensing basis commitments were adequately performed and, if necessary, assess the safety significance for any related performance deficiency.
e The issues for follow-up include the strippable coating de-lamination, reactor cavity trough drain monitoring, and sand bed drain monitoring.;
- The commitment tracking, implementation, and work.control processes will be reviewed, based on corrective actions resulting from AmerGen's "*!!..w of deficiencies and operating experience, as a Part 50 activity.
3.2 Drywell Floor Trench Inspections