ML091700699

E-mail from J. Richmond of USNRC to M. Modes of USNRC, Regarding Oc Lt 2008-07

ML091700699
Person / Time
Site:	Oyster Creek
Issue date:	01/13/2009
From:	Richmond J NRC Region 1
To:	Modes M NRC Region 1
References
FOIA/PA-2009-0070
Download: ML091700699 (31)

Text

Elizabeth Keightey From: John Richmond ,.F.

Sent: Tuesday, January 13, 2009 8:03 PM To: Michael Modes Cc: Doug Tifft

Subject:

0( LR 2008-07 Attachments: OC 2008-07 LRI rev-7.doc Michael - I think this is very near a finished product [except cover letter] & [except final reviewer comments]

One more sanity review Please!

Mb* Inltsem ls was detited in aIIrordance wlth.the Freedom of Information Aet Exemptions 1

J-./4-ý

Received: from R1CLSTRO1 .nrc.gov ([148.184.99.7]) by R1 MSO0 .nrcgov

([148.184.99.10]) with mapi; Tue, 13 Jan 2009 20:03:10 -0500 Content-Type: application/ms-tnef; name="winmail.dat" Content-Transfer-Encoding: binary From: John Richmond <John.Richmond@nrc.gov>

To: Michael Modes <Michael.Modes@nrc.gov>

CC: Doug Tifft <Doug.Tifft@nrc.gov>

Date: Tue, 13 Jan 2009 20:03:08 -0500

Subject:

OC LR 2008-07 Thread-Topic: OC LR 2008-07 Thread-Index: Acd1491AHKdoq+ijShSU6SF6H8xRlg==

Message-ID:

<2856BC46F6A308418F033D973BBOEE72AA61375D28@R1CLSTRO1.nrc.gov>

Accept-Language: en-US Content-Language: en-US X-MS-Has-Attach: yes X-MS-Exchange-Organization-SCL: -1 X-MS-TNEF-Correlator:

<2856BC46F6A308418F033D973BBOEE72AA61375D28@R1 CLSTRO1 nrc.gov>

MIME-Version: 1.0

Mr. Charles G. Pardee Chief Nuclear Officer (CNO) and Senior Vice President Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348

SUBJECT:

OYSTER CREEK GENERATING STATION - NRC LICENSE RENEWAL FOLLOW-UP INSPECTION REPORT 05000219/2008007 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 report 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.

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.

Particular focus occurred on the inservice inspection of the drywell containment. Based on the P results of the NRC's inspection, the NRC staff identified that there were no safety significant conditions with respect to the drywell containment that effected current operations.

With respect to 10 CFR 54 activities and the NRC staff's Final Safety Evaluation Report (SER) for License Renewal - NUREG 1845 (Volume 1 ml 071290023 & Volume 2 ml 071310246), we observed that you are implementing the proposed license conditions of that document and the associated regulatory commitments as though they were in effect. As you well know, an appeal of a licensing board decision regarding the Oyster Creek application for a renewed license is pending before the Commission related to the adequacy of the aging management program for the Oyster Creek drywell. The NRC's Reactor Oversight Process mid-cycle letter of September 2, 2008 indicated that we would be conducting inspections (outage and non-outage) related to license renewal prior to the period of extended operations. 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 such observations of Oyster Creek license renewal activities during the last refuel outage prior to entering the period of extended operations.

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. The enclosed report records the inspector's observations only. We are doing this because the proposed license conditions and associated regulatory commitments made as a part of the 10 CFR 54 application are not in effect. These conditions and commitments are not in effect because the application for a renewed license remains under Commission review for

C. Pardee 2 final decision, and a renewed license has not been approved for Oyster Creek

C. Pardee 2 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 (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web-site at http://www.nrc.-ov/readinq-rm/adams.html (the Public Electronic Reading Room).

We appreciate your cooperation. Please contact me at (610) 337-5183 if you have any questions regarding this letter. (b)(5)

Sincerely, Darrell Roberts, Director Division of Reactor Safety Docket No. 50-219 License No. DPR-16

Enclosure:

Inspection Report No. 05000219/2008007 w/

Attachment:

Supplemental Information C. Crane, President and Chief Operating Officer, Exelon Corporation M. Pacilio, Chief Operating Officer, Exelon Nuclear T. Rausch, Site Vice President, Oyster Creek Nuclear Generating Station J. Randich, Plant Manager, Oyster Creek Generating Station J. Kandasamy, Regulatory Assurance Manager, Oyster Creek R. DeGregorio, Senior Vice President, Mid-Atlantic Operations K. Jury,Vice President, Licensing and Regulatory Affairs P. Cowan, Director, Licensing B. Fewell, Associate General Counsel, Exelon Correspondence Control Desk, AmerGen Mayor of Lacey Township P. Mulligan, Chief, NJ Dept of Environmental Protection R. Shadis, New England Coalition Staff E. Gbur, Chairwoman - Jersey Shore Nuclear Watch E. Zobian, Coordinator - Jersey Shore Anti Nuclear Alliance P. Baldauf, Assistant Director, NJ Radiation Protection Programs

C. Pardee 2 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 (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web-site at http://www.nrc.-ov/readinq-rm/adams.html (the Public Electronic Reading Room).

We appreciate your cooperation. Please contact me at (610) 337-5183 if you have any questions regarding this letter.

Li (b)(5) 73 Sincerely, Richard Conte, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-219 License No. DPR-16

Enclosure:

Inspection Report No. 05000219/2008007 w/

Attachment:

Supplemental Information Distribution w/encl:

S. Collins, RA M. Dapas, DRA D. Lew, DRP J. Clifford, DRP R. Bellamy, DRP S. Barber, DRP C. Newport, DRP M. Ferdas, DRP, Senior Resident Inspector J. Kulp, DRP, Resident Inspector J. DeVries, DRP, Resident OA S. Williams, RI OEDO H. Chernoff, NRR R. Nelson, NRR G. Miller, PM, NRR J. Hughey, NRR, Backup ROPreportsResource@nrc.gov (All IRs)

Region I Docket Room (with concurrences)

SUNSI Review Complete: _ (Reviewer's Initials) Adams Accession No.

DOCUMENT NAME: G:\DRS\Engineering Branch 1\Richmond\OC 2008-07 LR\_Report\OC 2008-07 LRIrev-6a.doc After declaring this document "An Official Agency Record" it will ' be released to the Public.

To receive a copy of this document, indicate in the box:"C" = Copy without attachment/enclosure E" = Copy with attachment/enclosure "N"= No copy OFFICE RI/DRS E RI/DRS RI/DI RI/DRS NAME JRichmond/ RConte/ RBellamy/ DRoberts/

DATE 01/ /09 01/ /09 01/ /09 01/ /09 OFFICIAL COEY

C. Pardee 2 4

U. S. NUCLEAR REGULATORY COMMISSION REGION I Docket No.: 50-219 License No.: DPR-16 Report No.: 05000219/2008007 Licensee: Exelon Generation Company, LLC Facility: Oyster Creek Generating Station Location: Forked River, New Jersey Dates: October 27 to November 7, 2008 (on-site inspection activities)

November 13, 15, and 17, 2008 (on-site inspection activities)

November 10 to December 23, 2008 (in-office review)

Inspectors: ,J. Richmond, Lead M. Modes, Senior Reactor Engineer G. Meyer, Senior Reactor Engineer T. O'Hara, Reactor Inspector J. Heinly, Reactor Engineer J. Kulp, Resident Inspector, Oyster Creek Approved by: Richard Conte, Chief Engineering Branch 1 Division of Reactor Safety ii

SUMMARY

OF FINDINGS IR 05000219/2008007; 10/27/2008 - 12/23/2008; Exelon, LLC, Oyster Creek Generating Station; License Renewal Follow-up The report covers a multi-week inspection of license renewal follow-up items. It was conducted by five region based engineering inspectors and the Oyster Creek resident inspector. The inspection was conducted in accordance with Inspection Procedure (IP) 71003 "Post-Approval Site Inspection for License Renewal." In accordance with the NRC's memorandum of understanding with the State of New Jersey, Department of Environmental Protection, Bureau of Nuclear Engineering, state engineers observed portions of the NRC inspection activities.

2 REPORT DETAILS Summary of Plant Status The Oyster Creek Generating Station was in a scheduled refueling outage during the on-site portions of this inspection.

At the time of the inspection, AmerGen Energy Company, LLC was the licensee for Oyster Creek Generating Station. As of January 8, 2009, the OC license was transferred to Exelon Generating Company, LLC by license amendment No. 271 (ML082750072).

4. OTHER ACTIVITIES (OA) 40A5 License Renewal Follow-up (IP 71003) 1.1 Purpose of Inspection An appeal of a licensing board decision regarding the Oyster Creek application for a renewed license is pending before the Commission related to the adequacy of the aging management program for the Oyster Creek drywell. The NRC's Mid Cycle Performance Review And Inspection Plan for Oyster Creek, dated September 2, 2008 (ML082470569), indicated we would conduct two inspections (outage and non-outage) related to license renewal prior to the period of extended operation. The NRC conducted this inspection using the guidance of Inspection Procedure (IP) 71003 "Post-Approval Site Inspection for License Renewal." This inspection was considered a Ay prudent measure in order to make observations of Oyster Creek license renewal activities during the last refuel outage prior to entering the period of extended operation.

Inspection observations were considered, in light of pending 10 CFR 54 license renewal commitme'nts and license conditions, as documented in NUREG-1875, "Safety Evaluation Report (SER) Related to the License Renewal of Oyster Creek Generating Station" (ML071290023 & ML071310246), as well as programmatic performance under on-going implementation of 10 CFR 50 current licensing basis (CLB) requirements.

Normally IP 71003 verifies that license renewal activities are implemented in accordance with 10 CFR 54, "Requirements for the Renewal of Operating Licenses for Nuclear Power Plants." The license renewal inspection activities are generally related to:

• License conditions added as part of a renewed license 9 Selected aging management programs and implementing procedures e License renewal commitments revised after the renewed license was granted e Updated Final Safety Analysis Report (UFSAR) revision

• Newly identified structures, systems, and components (SSCs)

Because the OC license has not been renewed, not all areas of the the inspection guidance was applicable, such as UFSAR revision or review of newly identified SSCs.

For 10 CFR 54 activities, the report documents the inspector observations. This was done because the proposed license conditions and associated regulatory commitments made as a part of the 10 CFR 54 application are not in effect. These conditions and commitments are not in effect because the application for a renewed license remains under Commission review for final decision, and a renewed license has not been approved for Oyster Creek.

1.2 Sample Selection Process The SER proposed commitments and proposed 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 selected commitment and on a sampling basis, the inspectors reviewed supporting 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 result of previous license renewal inspections.

2. Assessment of Current License Basis Performance Issues Based on the NRC's evaluation of the drywell shell ultrasonic test (UT) thickness measurements, direct observation of drywell shell conditions both inside the drywell, including the floor trenches, and outside the drywell, in the sand bed regions, condition and integrity of the drywell shell epoxy coating, and condition of the drywell shell moisture barrier seals, the NRC determined Exelon provided an adequate basis to conclude the drywell primary containment will remain operable throughout the period to the next scheduled examination, in the 2012 refueling outage.

As noted in the details of sections 3.1, 3.2, 3.3, and 3.4 below, a few current license basis issues were observed that may require licensee corrective action. Because the following issues may be associated with performance deficiencies, an Unresolved Item (URI) is being openedfor NRC tracking. After the licensee has had sufficient time to evaluate the issues and determine appropriate corrective actions, the NRC will review the available information to determine if any performance deficiency is potentially more (

than minor. The specific items for follow-up include:

91 (b)(5)i-of the strippable coating, applied to the liner of the refueling cavity, and

• [ (b)(5)2 to monitor the entire length of former sand bed drain lines, visible from the torus room, and the subsequent discovery that two of the drain lines were not directly attached to the portion of the drain line exiting the concrete structure below the former sand bed, and

• Discovery by boroscopic examination that the reactor vessel refueling cavity trough drain line valve was in the closed position during a portion of time while the drain flow was being monitored and the refuel cavity was flooded, L (b)(5)

(b)(5)

IP 71003 consists of a number of site visits to determine the status of license renewal commitment implementation. During the next site visit, the NRC will follow up on Exelon's evaluation and the repair of four small blisters in sand bed bay 11. Exelon stated that some blistering was expected, and would be identified during routine visual examinations. The NRC staff will review Exelon's cause evaluation after it is completed.

The drywell shell epoxy coating and the moisture barrier seal, both in the sand bed region, are barrier systems used to protect the drywell from corrosion. The problems identified and corrected with these barriers had a minimal impact on the drywell steel shell. The projected shell corrosion rate remains very small, as confirmed by the NRC staff review of Exelon's technical evaluations of the 2008 UT data. Based on the NRC's direct observation of the blisters, review of Exelon's repair, and direct observation of drywell shell conditions both inside the drywell and outside the drywell, in the sand bed regions, and the over all condition and integrity of the drywell shell epoxy coating, the NRC determined Exelon provided an adequate basis to conclude the likelihood of additional blisters will not impact the containment safety function during the period until the next scheduled examination, in the 2012 refueling outage. (URI 0500021912008007-01: License Renewal Follow-up)

3. Detailed Review of License Renewal Activities 3.1 Reactor Refuel Cavity Liner Strippable Coatinq

a. Scope of Inspection Proposed SER Appendix-A Item 27, ASME Section XI, Subsection IWE Enhancement

.'(2)', stated, in part:

A strippable coating will be applied to the reactor cavity liner to prevent water intrusion into the gap between the drywell shield wall and the drywell shell during periods when the reactor cavity is flooded. Refueling outages prior to and during the period of extended operation.

The inspector reviewed work order R2098682-06, "Coating application to cavity walls and floors."

b. Observations From Oct. 29 to Nov. 6, the cavity liner strippable coating limited cavity seal leakage into the cavity trough drain at less than 1 gallon per minute (gpm). On Nov. 6, in one localized area of the refuel cavity, the liner strippable coating started to de-laminate.

Water puddles were subsequently identified in sand bed bays 11, 13, 15, and 17 (see section 3.4 below for additional details). This issue was entered into the corrective action program as Issue Report (IR) 841543. In addition, this item was included in a

common cause evaluation as part of IR 845297. Exelon's initial evaluations identified several likely or contributing causes, including:

• A portable submerged water filtration unit was improperly placed in the reactor cavity, which resulted in flow discharged directly on the strippable coating.

" ALb)(5)oil spill into the cavity may have affected the coating integrity.

• No post installation inspection of the coating had been performed.

3.2 Reactor Refuel Cavity Seal Leakage Monitoring

a. Scope of Inspection Proposed SER Appendix-A Item 27, ASME Section XI, Subsection IWE Enhancement (3), stated, in part:

The reactor cavity seal leakage trough drains and the drywell sand bed region drains will be monitored for leakage, periodically.

The inspectors observed Exelon's cavity seal leakage monitoring activities, performed by work order R2095857. The inspectors independently checked the cavity trough drain flow immediately after the reactor cavity was filled, and several times throughout the outage. The inspectors also reviewed the written monitoring logs.

b. Observations Exelon monitored reactor refuel cavity seal leakage by monitoring and recording the flow in a 2 inch drain line from the cavity concrete trough to a plant radwaste system drain funnel which, in turn, drained to the reactor building sump.

On Oct. 27, Exelon isolated the cavity trough drain line to install a tygon hose to allow drain flow to be monitored. On Oct. 28, the reactor cavity was filled. Drain line flow was monitored frequently during cavity flood-up, and daily thereafter. On Oct. 29, a boroscope examination of the drain line identified that the isolation valve had been left closed. When the drain line isolation valve was opened, about 3 gallons of water drained out. The drain flow then subsided to about an 1/8 inch stream (less than 1 gpm).,' This issue was entered into the corrective action program as Issue Report (IR) 37647.

3.3 Drywell Sand Bed:Region Drain Monitoring

a. Scope of Inspection Proposed SER Appendix-A Item 27, ASME Section Xl, Subsection IWE Enhancement (3), stated, in part:

The sand bed region drains will be monitored daily during refueling outages.

The inspectors observed Exelon's activities to monitor sand bed drains, performed by work order R2095857. The inspectors independently checked drain line poly bottles and

accompanied Exelon personnel during routine daily checks. The inspectors also reviewed the written monitoring logs.

b. Observations There is one sand bed drain line for every two sand bed bays (i.e., total of five drains for 10 bays). Exelon remotely monitored the sand bed drains by checking poly bottles attached via tygon tubing to a funnel hung below each drain line. The tygon tubing which connected a poly bottle to the funnel under the drain line was about 50 foot long.

The sand bed drains were not directly observed and were not visible from the outer area of the torus room, where the poly bottles were located.

On Nov. 10, Exelon found 2 of the 5 tygon tubes disconnected from their funnels and laying on the floor (bays 3 and 7). Exelon personnel could not determine when the tubing was last verified to be connected to the funnel. Both tubes were reconnected.

This issue was entered into the corrective action program as Issue Report (IR) 843209.

xxx need IR ##

On Nov. 15, during a daily check of sand bed bay 11 drain poly bottle, Exelon found the poly bottle full (greater than 4 gallons). Exelon sampled the water, but could not positively determine the source based on radiolytic or chemical analysis. The inspectors noted that Exelon had found the poly bottle empty during each check throughout the outage, until Nov 15 (cavity was drained on Nov 12). The inspectors also noted that the funnel, to which the tygon tubing was connected, had a capacity of about 6 gallons.

Exelon entered bay 11 within a few hours, visually inspected it, and found it dry. This issue was entered into the corrective action program as Issue Report (IR) xxx.

3.4 Reactor Cavity Seal Leakage Action Plan for 1 R22

a. Scope of Inspection Proposed SER Appendix-A Item 27, ASME Section XI, Subsection IWE Enhancement (3), stated, in part:

If leakage is detected [flow out of a sand bed drain], procedures will be in place "to determine the source of leakage and investigate and address the impact of leakage on the drywell shell.

The inspectors reviewed Exelon's pre-approved cavity seal leakage action plan.

b. Observations For the reactor cavity seal leakage, Exelon established an administrative limit of 12 gpm flow in the cavity trough drain, based on a calculation which indicated that cavity trough drain flow of less than 60 gpm would not result in trough overflow into the gap between the drywell concrete shield wall and the drywell steel shell.

The inspectors noted that Exelon's pre-approved action plan, in part, directed the following actions to be taken:

e If the cavity trough drain flow exceeded 5 gpm, then increase monitoring of the cavity drain flow from daily to every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

e If the cavity trough drain flow exceeded 12 gpm, then increase monitoring of the sand bed poly bottles from daily to every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• If the cavity trough drain flow exceeded 12 gpm and any water is found in a sand bed poly bottle, then enter and inspect the sand bed bays.

On Nov. 6, the reactor cavity liner strippable coating started to de-laminate (see section 3.1 above). The cavity trough drain flow took a step change from less than 1 gpm to approximately 4 to 6 gpm. Exelon increased monitoring of the trough drain to every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and monitoring of the sand bed poly bottles to every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The cavity trough drain flow remained at about 4 to 6 gpm until the cavity was drained on Nov. 12, when the drain flow subsided to zero.

On Nov 8, personnel working in sand bed bay 11 identified dripping water. Water puddles were subsequently identified in sand bed bays 11, 13, 15, and 17. These issues were entered into the corrective action program as Issue Report (IR) 842333. In addition, these items were included in a common cause evaluation as part of IR 845297.

The inspectors noted that all sand bed bay work was originally scheduled to have been completed and to have the bays closed out by Nov. 2.

On Nov 12, the cavity was drained. All sand bed bays were dried and inspected for any water or moisture damage; no deficiencies were identified. Exelon stated follow-up ultrasonic test (UT) examinations will be performed to evaluate the drywell shell during the next refuel outage.

On Nov. 15, water was found in the sand bed bay 11 poly bottle (see section 3.3 above).

The inspectors observed that Exelon's pre-approved action plan was inconsistent with the actual actions taken in response to increased cavity seal leakage. The plan did not direct increased sand bed poly bottle monitoring, and would not have required a sand bed entry or inspection until Nov 15, when water was first found in a poly bottle. The inspectors also noted that water had entered the gap between the drywell shield wall and the drywell shell at a much lower value of cavity seal leakage than Exelon had predicted.

3.5 Reactor Cavity Trough Drain Inspection for Blockage

a. Scope of Inspection Proposed SER Appendix-A Item 27, ASME Section XI, Subsection IWE Enhancement (13), stated, in part:

The reactor cavity concrete trough drain will be verified to be clear from blockage once per refueling cycle. Any identified issues will be addressed via the corrective action process.

The inspector reviewed a video recording record of a boroscope inspection of the cavity

trough drain line, performed by work order R2102695.

b. Observations See observations in section 3.2 above.

3.6 Moisture Barrier Seal Inspection (inside sand bed bays)

a. Scope of Inspection Proposed SER Appendix-A Item 27, ASME Section XI, Subsection IWE Enhancements (12 & 21), stated, in part:

Inspect the [moisture barrier] seal at the junction between the sand bed region concrete [sand bed floor] and the embedded drywell shell. During the 2008 refueling outage and every other refueling outage thereafter.

The purpose of the moisture barrier seal is to prevent water from entering a gap below the concrete floor in the sand bed region. Exelon performed a 100% visual test (VT) inspection of the seal in the sand bed region (total of 10 bays). The inspectors directly observed as-found conditions in portions of 6 sand bed bays, and as-left conditions in 4 sand bed bays.

The inspectors reviewed VT inspection records for each sand bed bay, and compared their direct observations to the recorded VT inspection results. The inspectors reviewed Exelon VT inspection procedures, interviewed non-destructive examination (NDE) supervisors and technicians, and observed field collection and recording of VT inspection data. The inspectors also reviewed a sample of NDE technician visual testing qualifications.

The inspectors observed Exelon's activities to evaluate and repair the moisture barrier seal in sand bed bay 3.

b. Observations The inspectors observed that NDE visual inspection activities were conducted in accordance with approved procedures. The inspectors verified that Exelon completed the inspections, identified condition(s) in the moisture barrier seal which required repair, completed the se al repairs in accordance with engineering procedures, and conducted appropriate re-inspection of repaired areas.

The VT inspections identified moisture barrier seal deficiencies in 7 of the 10 sand bed bays, including surface cracks and partial separation of the seal from the steel shell or concrete floor. Exelon determined the as-found moisture barrier function was not impaired, because no cracks or separation fully penetrated the seal. All deficiencies were entered into the corrective action program and repaired (IRs are listed in the Attachment). In addition, these items were included in a common cause evaluation as part of IR 845297.

xxx ADD IR ## for bay 3 seal The VT inspection for sand bed bay 3 identified a seal crack and a surface rust stains below the crack. When the seal was excavated, some drywell shell surface corrosion was identified. A laboratory analysis of removed seal material determined the epoxy seal material had not adequately cured, and concluded it was an original 1992 installation issue. The seal crack and surface rust were repaired.

The inspectors compared the 2008 VT results to the 2006 results and noted that in 2006 no seal deficiencies were identified in any sand bed bay.

3.7 Drywell Shell External Coatingqs Inspection (inside sand bed bays)

a. Scope of Inspection Proposed SER Appendix-A Item 27, ASME Section XI, Subsection IWE Enhancements (4 & 21), stated, in part:

Perform visual inspections of the drywell external shell epoxy coating in all 10 sand bed bays. During the 2008 refueling outage and every other refueling outage thereafter.

The inspectors observed portions of Exelon's activities to perform a 100% visual inspection of the epoxy coating in the sand bed region (total of 10 bays). In addition, the inspectors directly observed as-found conditions of the epoxy coating in portions of 6 sand bed bays, and the as-left condition in sand bed bay 11, after coating repairs. The inspectors also observed field collection, recording, and reporting of visual inspection data.

The inspectors reviewed VT inspection records for each sand bed bay and compared their direct observations to the recorded VT inspection results. The inspectors reviewed Exelon VT inspection procedures, interviewed non-destructive examination (NDE)

Supervisors and technicians, and observed field collection and recording of VT inspection data. The inspectors also reviewed a sample of NDE technician visual testing qualifications, The inspectors directly observed Exelon's activities to evaluate and repair the epoxy coating in sand bed bay 11. In addition, the inspectors reviewed Technical Evaluation 330592.27.46, "Coating Degradation in Sand Bed bay 11 ."

b. Observations The inspectors observed that NDE visual inspection activities were conducted in accordance with approved procedures. The inspectors verified that Exelon completed the inspections, identified condition(s) in the exterior coating which required repair, completed the coating repairs in accordance with engineering procedures, and conducted appropriate re-inspection of repaired areas.

In sand bed bay 11, the NDE inspection identified one small broken blister, about 1/4 inch in diameter, with a 6 inch surface rust stain, dry to the touch, trailing down from the

blister. During the initial investigation, three additional smaller surface irregularities (initially described as surface bumps) were identified within a 1 to 2 square inch area near the broken blister. The three additional bumps were subsequently determined to be unbroken blisters. This issue was entered into the corrective action program as IR 838833 and 839053. In addition, this item was included in a common cause evaluation as part of IR 845297. All four blisters were evaluated and repaired.

On Nov. 13, the inspectors conducted a general visual observation (i.e., not a qualified VT inspection) of the repaired area and the general condition in bay 11. The inspectors verified that Exelon's inspection data reports appeared to accurately describe the conditions observed by the inspectors.

To confirm the adequacy of the coating inspection, Exelon re-inspected 4 sand bed bays (bays 3, 7, 15, and 19) with a different NDE technician. No additional deficiencies were identified. In Technical Evaluation 330592.27.46, Exelon determined, by laboratory analysis using energy dispersive X-ray spectroscopy, that the removed blister material contained trace amounts of chlorine. Exelon also determined that the presence of chlorine, in a soluble salt as chloride, can result in osmosis of moisture through the epoxy coating. The analysis also concluded there were no pinholes in the blister samples. In addition, the analysis determined approximately 0.003 inches of surface corrosion had occurred directly under the broken blister. Exelon concluded that the corrosion had taken place over approximately a 16 year period. In addition, UT dynamic scan thickness measurements under the four blisters, from inside the drywell, confirmed the drywell shell had no significant degradation as a result of the corrosion. On Nov. 13, the inspectors conducted a general visual observation (i.e., not a qualified VT inspection) of the general conditions in bay 5 and 9. The inspectors observed that Exelon's inspection data reports adequately described the conditions observed by the inspectors.

xxx ADD IR ###

In follow-up, Exelon reviewed a 2006 video of the sand beds, which had been made as a general aid, not as part of an NDE inspection. The 2006 video showed the same 6 inch rust stain in bay 11. The inspectors compared the 2008 VT results to the 2006 results and noted that in 2006 no coating deficiencies were identified in any sand bed bay. This apparent deficiency with the 2006 coating inspection was entered into the corrective action program as Issue Report (IR) xxx.

During the final closeout of bays 3, 5, and 7, minor chipping in the epoxy coating was identified, and described as incidental mechanical damage from personnel entry for inspection or repair activities. All deficiencies were entered into the corrective action program and repaired (IRs are listed in the Attachment).

During the final closeout of bay 9, an area approximately 8 inches by 8 inches was identified where the color of the epoxy coating appeared different than the surrounding area. Because each of the 3 layers of the epoxy coating is a different color, Exelon questioned whether the color difference could have been indicative of an original installation deficiency. This issue was entered into the corrective action program as IR 844815, and the identified area was re-coated with epoxy.

3.8 Drywell Floor Trench Inspections

a. Scope of Inspection Proposed SER Appendix-A Item 27, ASME Section XI, Subsection IWE Enhancements (5, 16, & 20), stated, in part:

Perform visual test (VT) and ultrasonic test (UT) examinations of the drywell shell inside the drywell floor inspection trenches in bay 5 and bay 17 during the 2008 refueling outage, at the same locations that were examined in 2006. In addition, monitor the trenches for the presence of water during refueling outages.

The inspectors observed non-destructive examination (NDE) activities and reviewed UT examination records. In addition, the inspectors directly observed conditions in the trenches on multiple occasions during the outage. The inspectors compared UT data to licensee established acceptance criteria in Specification IS-318227-004, revision 14, "Functional Requirements for Drywell Containment Vessel Thickness Examinations,"

and to design analysis values for minimum wall thickness in calculations C-1 302-187-E310-041, revision 0, "Statistical Analysis of Drywell Sand Bed Thickness Data 1992, 1994, 1996, and 2006," and C-1302-187-5320-024, revision 2, "Drywell External UT Evaluation in the Sand Bed." In addition, the inspectors reviewed Technical Evaluation 330592.27.43, "2008 UT Data of the Sand Bed Trenches."

The inspectors reviewed Exelon UT examination procedures, interviewed NDE supervisors and technicians, reviewed a sample of NDE technician UT qualifications.

The inspectors also reviewed records of trench inspections performed during two non-refueling plant outages during the last operating cycle.

b. Observations In Technical Evaluation 330592.27.43, Exelon determined the UT thickness values satisfied the general uniform minimum wall thickness criteria (e.g., average thickness of an area) and the locally thinned minimum wall thickness criteria (e.g., areas 2 inches or less in diameter), as applicable. For UT data sets, such as 7x7 arrays, the TE caiculated statistical parameters and determined the data set distributions were acceptable. The TE also compared the data set values to the corresponding 2006 values and concluded there were no significant differences and no observable on-going corrosion. The inspectors independently verified that the UT thickness values satisfied applicable acceptance criteria.

During two non-refueling plant outages during the last operating cycle, both trenches were inspected for the presence of water and found dry by Exelon's staff and by NRC inspectors (NRC Inspection Reports 05000219/2007003, 05000219/2007004, and memorandum ML071240314).

During the initial drywell entry on Oct. 25, the inspectors observed that both floor trenches were dry. On subsequent drywell entries for routine inspection activities, the inspectors observed the trenches to be dry. On one occasion, Exelon observed a small amount of water in the bay 5 trench, which they believed was from water spilled nearby

on the drywell floor; the trench was dried and the issue entered into the corrective action program as IR 843190. On Nov. 17, during the final drywell closeout inspection, the inspectors observed the following:

• Bay 17 trench was dry and had newly installed sealant on the trench edge where concrete meets shell, and on the floor curb near the trench.

xxx ADD IR ##

• Bay 5 trench had a few ounces of water in it. The inspector noted that within the last day there had been several system flushes conducted in the immediate area. Exelon stated the trench would be dried prior to final drywell closeout.

• Bay 5 trench had the lower 6 inches of grout re-installed and had newly installed sealant on the trench edge where concrete meets shell, and on the floor curb near the trench.

3.9 Drywell Shell Thickness Measurements

a. Scope of Inspection Proposed SER Appendix-A Item 27, ASME Section XI, Subsection IWE Enhancements (1, 9, 14, & 21), stated, in part: -

Perform full scope drywell inspections [in the sand bed region], including UT thickness measurements of the drywell shell, from inside and outside the drywell.

During the 2008 refueling outage and every other refueling outage thereafter.

Proposed SER Appendix-A Item 27, ASME Section XI, Subsection IWE Enhancements (7, 10, & 11) stated, in part:

Conduct UT thickness measurements in the upper regions of the drywell shell.

Prior to the period of extended operation and two refueling outages later.

The inspectors directly observed non-destructive examination (NDE) activities and the drywell shell conditions both inside the drywell, including the floor trenches, and in the sand bed bays (drywell external shell). The inspectors reviewed UT examination records and compared UT data results to licensee established acceptance criteria in Specification IS-318227-004, revision 14, "Functional Requirements for Drywell Containment Vessel Thickness Examinations," and to design analysis values for minimum wall thickness in calculations C-1302-187-E310-041, revision 0, "Statistical Analysis of Drywell Vessel Sand Bed Thickness Data 1992, 1994, 1996, and 2006," and C-1302-187-5320-024, revision 2, "Drywell External UT Evaluation in the Sand Bed." In addition, the inspectors reviewed the Technical Evaluations (TEs) associated with the UT data, as follows:

• TE 330592.27.42, "2008 Sand Bed UT data - External"

• TE 330592.27.45, "2008 Drywell UT Data at Elevations 23 & 71 foot"

• TE 330592.27.88, "2008 Drywell Sand Bed UT Data - Internal Grids"

The inspectors reviewed UT examination records for the following:

" Sand bed region elevation, inside the drywell

" All 10 sand bed bays, drywell external

" Various drywell elevations between 50 and 87 foot elevations

• Transition weld from bottom to middle spherical plates, inside the drywell

• Transition weld from 2.625 inch plate to 0.640 inch plate (knuckle area), inside the drywell The inspectors reviewed Exelon UT examination procedures, interviewed NDE supervisors and technicians, and observed field collection and recording of UT data.

The inspectors also reviewed a sample of NDE technician UT qualifications.

b. Observations The inspectors observed that NDE UT examination activities were conducted in accordance with approved procedures.

In Technical Evaluations 330592.27.42, 330592.27.45, and 330592.27.88, Exelon determined the UT thickness values satisfied the general uniform minimum wall thickness criteria (e.g., average thickness of an area) and the locally thinned minimum wall thickness criteria (e.g., areas 2 inches or less in diameter), as applicable. For UT data sets, such as 7x7 arrays, the TEs calculated statistical parameters and determined the data set distributions were acceptable. The TEs also compared the data set values to the corresponding 2006 values and concluded there were no significant differences and no observable on-going corrosion. The inspectors independently verified that the UT thickness values satisfied applicable acceptance criteria.

3.10 Moisture Barrier Seal Inspection (inside drywell)

a. 'Scope of Inspection Proposed SER Appendix-A Item 27, ASME Section XI, Subsection IWE Enhancement (17),..stated, in part:

Perform visual inspection of the moisture barrier seal between the drywell shell and the concrete floor curb, installed inside the drywell during the October 2006 refueling outage, in accordance with ASME Code.

The inspector reviewed structural inspection reports 187-001 and 187-002, performed by work order R2097321-01 on Nov 1 and Oct 29, respectively. The reports documented visual inspections of the perimeter seal between the concrete floor curb and the drywell steel shell, at the floor elevation 10 foot. In addition, the inspector reviewed selected photographs taken during the inspection

b. Observations

No noteworthy observations.

3.11 One Time Inspection Program

a. Scope of Inspection Proposed SER Appendix-A Item 24, One Time Inspection Program, stated, in part:

The One-Time Inspection program will provide reasonable assurance that an aging effect is not occurring, or that the aging effect is occurring slowly enough to not affect the component or structure intended function during the period of extended operation, and therefore will not require additional aging management.

Perform prior to the period of extended operation.

The inspector reviewed the program's sampling basis and sample plan. Also, the inspector reviewed ultrasonic test results from selected piping sample locations in the main steam, spent fuel pool cooling, domestic water, and demineralized water systems.

b. Observations No noteworthy observations.

3.12 "B" Isolation Condenser Shell Inspection

a. Scope of Inspection Proposed SER Appendix-A Item 24, One Time Inspection Program Item (2), stated, in part:

,,,..To confirm the effectiveness of the Water Chemistry program to manage the f material and crack initiation and growth aging effects. A one-time UT losg6*!io inspection of the "B" Isolation Condenser shell below the waterline will be conducted looking for pitting corrosion. 'Perform prior to the period of extended operation.

The inspector observed NDE examinations of the "B" isolation condenser shell performed by work order C2017561-11. The NDE examinations included a visual inspection of the shell interior, UT thickness measurements in two locations that were previously tested in 1996 and 2002, additional UT tests in areas of identified pitting and corrosion, and spark testing of the final interior shell coating. The inspector reviewed the UT data records, and compared the UT data results to the established minimum wall thickness criteria for the isolation condenser shell, and compared the UT data results with previously UT data measurements from 1996 and 2002

b. Observations No noteworthy observations.

3.13 Periodic Inspections

a. Scope of Inspection Proposed SER Appendix-A Item 41, Periodic Inspection Program, stated, in part:

Activities consist of a periodic inspection of selected systems and components to verify integrity and confirm the absence of identified aging effects. Perform prior to the period of extended operation.

The inspectors observed the following activities:

• Condensate expansion joints Y-2-1 1 and Y-2-12 inspection (WO R2083515)

• 4160 V Bus lC switchgear fire barrier penetration inspection (WO R2093471)

b. Observations No noteworthy observations.

3.14 Circulating Water Intake Tunnel & Expansion Joint Inspection

a. Scope of Inspection Proposed SER Appendix-A Item 31, Structures Monitoring Program Enhancement (1),

stated, in part:

Buildings, structural components and commodities that are not in scope of maintenance rule but have been determined to be in the scope of license renewal. Perform prior to the period of extended operation.

On Oct. 29, the inspector directly observed the conduct of a structural engineering inspection of the circulating water intake tunnel, including reinforced concrete wall and floor slabs, steel liners, embedded steel pipe sleeves, butterfly isolation valves, and tunnel expansion joints. The inspection was conducted by a qualified structural engineer. After the inspection was completed, the inspector compared his direct observations with the documented visual inspection results.

b. Observations No noteworthy observations.

3.15 Buried Emergency Service Water Pipe Replacement

a. Scope of Inspection Proposed SER Appendix-A Item 63, Buried Piping, stated, in part:

Replace the previously un-replaced, buried safety-related emergency service water piping prior to the period of extended operation. Perform prior to the period of extended operation.

The inspectors observed the following activities, performed by work order' C2017279:

• Field work to remove old pipe and install new pipe

• Foreign material exclusion (FME) controls

• External protective pipe coating, and controls to ensure the pipe installation activities would not result in damage to the pipe coating

b. Observations No noteworthy observations.

3.16 Electrical Cable Inspection inside Drywell

a. Scope of Inspection Proposed SER Appendix-A Item 34, Electrical Cables and Connections, stated, in part:

A representative sample of accessible cables and connections located in adverse localized environments will be visually inspected at least once every 10 years for indications of accelerated insulation aging. Perform prior to the period of extended operation.

The inspector accompanied electrical technicians and an electrical design engineer during a visual inspection of selected electrical cables in the drywell. The inspector observed the pre-job brief which discussed inspection techniques and acceptance criteria. The inspector directly observed the visual inspection, which included cables in raceways, as well as cables and connections inside junction boxes. After the inspection was completed, the inspector compared his direct observations with the documented visual inspection results.

b. Observations No noteworthy observations.

3.17 Drywell Shell Internal Coatings Inspection (inside drywell)

a. Scope of Inspection Proposed SER Appendix-A Item 33, Protective Coating Monitoring and Maintenance Program, stated, in part:

The program provides for aging management of Service Level I coatings inside the primary containment, in accordance with ASME Code.

The inspector reviewed a vendor memorandum which summarized inspection findings for a coating inspection of the as-found condition of the ASME Service Level I coating of the drywell shell inner surface. In addition, the inspector reviewed selected photographs taken during the coating inspection and the initial assessment and disposition of

identified coating deficiencies. The coating inspector was also interviewed. The coating inspection was conducted on Oct. 30, by a qualified ANSI Level III coating inspector.

The final detailed report, with specific elevation notes and photographs, was not available at the time the inspector left the site.

b. Observations No noteworthy observations.

3.18 Inaccessible Medium Voltage Cable Test

a. Scope of Inspection Proposed SER Appendix-A Item 36, Inaccessible Medium Voltage Cables, stated, in part:

Cable circuits will be tested using a proven test for detecting deterioration of the insulation system due to wetting, such as power factor or partial discharge.

Perform prior to the period of extended operation.

The inspector observed field testing activities for the 4 kV feeder cable from the auxiliary transformer secondary to Bank 4 switchgear and independently reviewed the test results. A Doble and power factor test of the transformer, with the cable connected to the transformer secondary, was performed, in part, to detect deterioration of the cable insulation. The inspector also compared the current test results to previous test results from 2002. In addition, the inspector interviewed plant electrical engineering and maintenance personnel.

b. Observations No noteworthy observations.

3.19 Fatigue Monitoring Program

a. Scope of Inspection Proposed SER Appendix-A Item 44, Metal Fatigue of Reactor Coolant Pressure Boundary, stated, in part:

The program will be enhanced to use the EPRI-licensed FatiguePro cycle counting and fatigue usage factor tracking computer program.

The inspectors interviewed the fatigue program manager and determined that the FatiguePro program, although in place and ready-to-go, has not been implemented.

Exelon stated the FatiguePro program will be implemented after final industry resolution of a concern regarding a mathematical summation technique used in FatiguePro. The FatiguePro program was evaluated by the inspectors in March of 2006 (Report 05000219/20006007). The inspectors determined that Exelon's proposed implementation had not changed in the interim.

b. Observations The inspectors determined that Exelon's proposed implementation had not changed the since the NRC reviewed it in March of 2006.

4. Proposed Conditions of License

a. Scope of Inspection SER Section 1.7 contained two outage related proposed conditions of license:

The fourth license condition requires the applicant to perform full scope inspections of the drywell sand bed region every other refueling outage.

The fifth license condition requires the applicant to monitor drywell trenches every refueling outage to identify and eliminate the sources of water and receive NRC approval prior to restoring the trenches to their original design configuration.

Proposed SER Appendix-A Item 27, ASME Section XI, Subsection IWE Enhancements (1, 4, 9, 12, 14, & 21) implement the proposed license condition associated with a full scope drywell sand bed region inspection.

Proposed SER Appendix-A Item 27, ASME Section XI, Subsection IWE Enhancements (5, 16, & 20) implement the proposed license condition associated with the drywell trenches.

b. Observations For observations, see the applicable sections above.

5. Commitment Management Progiram

a. Scope of Inspection The inspectors evaluated current licensing basis procedures used to manage and revise regulatory commitments to determine whether they were consistent with the requirements of 10 CFR 50.59, NRC Regulatory Issue Summary 2000-17, "Managing Regulatory Commitments," and the guidance in Nuclear Energy Institute (NEI) 99-04, "Guidelines for Managing NRC Commitment Changes." In addition, the inspectors reviewed the procedures to assess whether adequate administrative controls were in-place to ensure commitment revisions or the elimination of commitments altogether would be properly evaluated, approved, and annually reported to the NRC. The inspectors also reviewed Exelon's current licensing basis commitment tracking program to evaluate its effectiveness. In addition, the following commitment change evaluation packages were reviewed:

• Commitment Change 08-003, OC Bolting Integrity Program

• Commitment Change 08-004, RPV Axial Weld Examination Relief

b. Observations The inspectors observed that the commitment change activities were conducted in accordance with approved procedures, which required an annual update to the NRC with a summary of each change.

40A6 Meetinqs, IncludinQ Exit MeetincI Exit Meeting Summary The inspectors presented the results of this inspection to Mr. T. Rausch, Site Vice President, Mr. M. Gallagher, Vice President License Renewal, and other members of Exelon's staff on December 23, 2008. NRC Exit Notes from the exit meeting are located in ADAMS within package ML090120726.

No proprietary information is present in this inspection report.

A-1 ATTACHMENT SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT Licensee Personnel C. Albert, Site License Renewal J. Cavallo, Corrosion Control Consultants & labs, Inc.

M. Gallagher, Vice President License Renewal C. Hawkins, NDE Level III Technician J. Hufnagel; Exelon License Renewal J. Kandasamy, Manager Regulatory Affairs S. Kim, Structural Engineer M. McDermott, NDE Supervisor R. McGee, Site License Renewal D. Olszewski, System Engineer F. Polaski, Exelon License Renewal R. Pruthi, Electrical Design Engineer S. Schwartz, System Engineer P. Tamburro, Site License Renewal Lead C. Taylor, Regulatory Affairs NRC Personnel S. Pindale, Acting Senior Resident Inspector, Oyster Creek J. Kulp, Resident Inspector, Oyster Creek L. Regner, License Renewal Project Manager, NRR D. Pelton, Chief - License Renewal Projects Branch 1 M. Baty, Counsel for NRC Staff J. Davis, Senior Materials Engineer, NRR Observers R. Pinney, New Jersey State Department of Environmental Protection R. Zak, New Jersey State Department of Environmental Protection M. Fallin, Constellation License Renewal Manager R. Leski, Nine Mile Point License Renewal Manager

- a A-2 LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Opened/Closed None.

Opened 05000219/2008007-01 URI License Renewal Follow-up (Section 2.0)

Closed None.

.. Sý A-3 LIST OF DOCUMENTS REVIEWED License Renewal Proaram Documents Drawings Plant Procedures and Specifications Incident Reports (IRs)

• = IRs written as a result of the NRC inspection Maintenance Requests (ARs) & Work Orders (WOs)

Ultrasonic Test Non-destructive Examination Records Visual Test Inspection Non-destructive Examination Records NDE Certification Records Miscellaneous Documents NRC Documents Industry Documents

• documents referenced within NUREG-1 801 as providing acceptable guidance for specific aging management programs

A-4 LIST OF ACRONYMS ASME American Society of Mechanical Engineers EPRI Electric Power Research Institute NDE Non-destructive Examination NEI Nuclear Energy Institute SSC Systems, Structures, and Components SDP Significance Determination Process TE Technical Evaluation UFSAR Updated Final Safety Analysis Report UT Ultrasonic Test VT Visual Testing