NG-07-0878, Second 10-Year Containment Inspection Plan

Second 10-Year Containment Inspection Plan

ML073320185
Person / Time
Site:	Duane Arnold
Issue date:	11/16/2007
From:	Richard Anderson Duane Arnold
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NG-07-0878
Download: ML073320185 (42)

Text

FPL Energy Duane Arnold, LLC 3277 DAEC Road Palo, Iowa 52324 FPL Energy.

Duane Arnold Energy Center November 16, 2007 NG-07-0878 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket No: 50-331 Op. License No: DPR-49 Second 10-Year Containment Inspection Plan The Duane Arnold Energy Center (DAEC) will begin the second containment inspection interval on May 22, 2008. This interval will continue through February 21, 2014. FPL Energy Duane Arnold, LLC herewith submits the DAEC containment inspection plan for this upcoming interval.

FPL Energy Duane Arnold, LLC intends to use this plan to perform containment inspections during the upcoming refueling outage RFO 21. As discussed in the plan, FPL Energy Duane Arnold, LLC is requesting approval of several relief requests.

The relief requests are contained in Section 11 and 16 of the Enclosure.

Relief requests MC-RO01 and MC-P001 support inspections and testing planned for RFO 21 currently scheduled for the first quarter of 2009. Therefore, approval of these relief requests by November 30, 2008 is requested.

Relief per MC-RO01 is being requested pursuant to 10 CFR 50.55a(a)(3)(i) on the basis that performing inspections as described in MC-RO01 provides an acceptable level of quality and safety. Relief per MC-P001 is being requested pursuant to 10 CFR 50.55a(a)(3)(ii) on performing detailed visual examinations for minor repairs on the basis that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

NG-07-0878 November 16, 2007 Page 2 of 2 Should you have any questions regarding this matter, please contact Steve Catron, Duane Arnold Energy Center Licensing Manager, at (319) 851-7234.

Richard L. Anderson Vice President, Duane Arnold Energy Center FPL Energy Duane Arnold, LLC Enclosure cc: Administrator, Region Ill, USNRC Project Manager, DAEC, USNRC Senior Resident Inspector, DAEC, USNRC

Enclosure to NG-07-0878 Enclosure DAEC Second Interval Containment Inspection Plan for Duane Arnold Energy Center, Palo, IA 39 Pages Follow

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Duane Arnold En~ergy Center SECOND TEN-YEAR INSPECTION INTERVAL CONTAINMENT INSPECTION PLAN FOR DUANE ARNOLD ENERGY CENTER PALO, IOWA

DAEC Station 2nd Interval Containment Inspection Plan 1.0 Containment Inspection Plan Preparation and Approval Statements The DAEC Containment Inspection Plan was reviewed and approved by the following DAEC personnel:

APPROVALS Prepared By:

IWE rfograii wner Reviewed By: Date: /o-/I 07 NDE Level III Reviewed By: Date: Jt a IST'Pro~gram. Owner Reviewed By: Date: -,oý Superviso(, Ins niand Materials Approved By: Date: I- - Z'-1o7 Manag;W, Program Engineering Reviewed By: Date:_________

Authorized Nuclear Inservice Inspector Revision 0 (1-1) Date

DAEC Station 2 nd Interval Containment Inspection Plan TABLE OF CONTENTS Section .. Description Page(s) 1 Table of Contents 1-2 2 Revision Summary Sheet 2-1 3 Introduction and Plan Description 3-.1 to 3-12 4 Application of Exemption Criteria 4-1 5 List of Applicable UFSAR Figures 5-1 6 List of Applicable Isometric Drawings 6-1 7 Containment Inspection Summary Table 7-1 to 7-2 8 Containment Inspection Technical Approach and 8-1 Position Index/Summaries 9 Containment Inspection Technical Approach and 9-Ito 9-3 Positions 10 Containment Inspection Relief Request 10-1 to 10-2 Index/Summaries 11 Containment Inspection Relief Requests 11-1 to 11-2 12 Containment Pressure Testing Summary Table 12-1 13 Containment Pressure Testing Technical Approach and 13-1 Position Index/Summaries 14 Containment Pressure Testing Technical Approach and 14-1 Positions 15 Containment Pressure Testing Relief Request 15-1 Index/Summaries 16 Containment Pressure Testing Relief Requests 16-1 to 16-2 17 Component Examination Summary Listing 17-1 to 17-2 Revision 0 (1-2)

DAEC Station 2nd Interval Containment Inspection Plan REVISION

SUMMARY

SHEET Section Effected Page(s) Revision Date I Table of Contents 00 2 Revision Summary Sheet 00 3 Introduction and Plan Description 00 4 Application of Exemption Criteria 00 5 List of Applicable UFSAR Figures 00 6 List of Applicable Isometric Drawings 00 7 Containment Inspection Summary Table 00 8 Containment Inspection Technical Approach and 00 Position Index/Summaries 9 Containment Inspection Technical Approach and 00 Positions 10 Containment Inspection Relief Request Index/Summaries 00 II Containment Inspection Relief Requests 00 12 Containment Pressure Testing Summary Table 00 13 Containment Pressure Testing Technical Approach and 00 Position Index/Summaries 14 Containment Pressure Testing Technical Approach and 00 Positions 15 Containment Pressure Testing Relief Request 00 Index/Summaries 16 Containment Pressure Testing Relief Requests 00 17 Component Examination Summary Listing 00 Revision 0 (2-1)

DAEC Station 2nd Interval Containment Inspection Plan INTRODUCTION AND PLAN DESCRIPTION 1.0 Introduction 1.1 This Containment Inspection Plan outlines the requirements for the Non-Destructive Examination of Class MC components and their supports at Duane Arnold Energy Center (DAEC). The Primary Containment consists of the drywell, the suppression chamber (torus), and the connecting piping (vent headers). Process piping penetrating primary containment is not addressed in this program.

1.2 This Containment Inspection Plan will be effective from May 22, 2008 through and including February 21, 2014, which represents the second ten-year interval of the Containment Inspection Program for DAEC. The end date corresponds with the current license. This also allows the update to correspond with the ISI Interval dates.

1.3 The key features of this Plan are the Introduction and Plan Description, Relief Requests, Technical Approach and Positions, and Summary Tables. The details of the Containment Inspection Program are addressed in other documents that are available at DAEC.

2. Basis of Containment Inspection Plan 2.1. a. In the Federal Register, dated August 8, 1996 (61 FR 41303), the NRC amended its regulations (rule) to incorporate by reference the 1992 Edition and Addenda of Subsections IWE and *IWL of Section XI of the ASME Code. Subsection IWE and IWL give the requirements for inservice inspection (ISI) of Class MC (metallic containments) and Class CC (concrete containments) of light-water-cooled power plants. The amended rule became effective on September. 9, 1996; it requires the licensees to incorporate the new requirements into their ISI plans and to complete the inspections specified for the first inspection period during the first five years (i.e. no later than September 9, 2001). Any repair or replacement (RJR) activity performed on containments after the effective date of September 9, 1996, shall meet the requirements of Subsection IWE and/or IWL.

b. The end of the First Inspection Interval for the Containment Inspection.

Program was May 21, 2008. This Containment Inspection Plan has been updated to the 2001 Edition with the 2003 Addenda of American Society of Mechanical Engineers (ASME)Section XI.

• IWL is not applicable to the Duane Arnold Energy Center.

Revision 0 (3-1)

DAEC Station 2nd Interval Containment Inspection Plan 2.2 The three inspection periods during the second inspection interval are as follows:

First Period: May 22, 2008 - May 21, 2010 Second Period: May 22, 2010 - May 21, 2012 Third Period: May 22, 2012 - February 21 2014 2.3 This Plan was developed in accordance with the requirements delineated in the 10 CFR 50.55a and the 2001 Edition, 2003 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Subsections IWA and IWE.

2.3.1 The ISI Plan for Subsection IWB, IWC, IWD, and IWF are not included in this Plan. These subsections of Section XI are contained within another document.

2.3.2 As allowed by USNRC Regulatory Guide 1.147, Revision 14, certain ASME Section XI Code Cases have been determined acceptable for application to ISI Programs. Currently there are no Code Cases being adopted by DAEC and incorporated in the Containment Inspection Plan.

However, DAEC may wish to use Code Cases not currently identified in Regulatory Guide 1.147 and will request relief to use specific Code Cases and identify those in Sections 11 and 16. Once approval is obtained for use of these additional Code Cases the Containment Inspection Plan will be revised accordingly.

2.3.3 Inservice pressure testing following repair/replacements by welding for minor repairs on Class MC components will be performed in accordance with Appendix J of 10CFR. (Ref. Relief Request MC-POO1) 3.0 Classifications 3.1 The NRC issued the construction permit for the Duane Arnold Energy Center (DAEC) in June 1968. The plant design was completed when the operating license for DAEC and the Final Safety Analysis Report (FSAR) for the facility was submitted to the NRC in March 1971. This license was issued by the NRC in January 1974. The ASME Code Section III, Class B, 1968 Edition with the Summer 1968 Addenda and Code Cases 1177, 1330, and 1413 were used for the design, fabrication, erection, and testing of the DAEC Primary Containment. At the construction permit stage, the NRC evaluated and found satisfactory the DAEC conforming with the then available July 11, 1967 version of the AEC General Design Criteria (GDC). The Safety Evaluation stated "We have reviewed the applicant's assessment of his conformance to the GDC and the stated DAEC design criteria and we are satisfied that the applicant has met the intent of the July 7, 1971 version of the General Design Criteria". Re-evaluation of the DAEC Torus attached piping was specified by NUREG-0661, "Safety Evaluation Report Revision 0 (3-2)

DAEC Station 2nd Interval Containment Inspection Plan Mark I Containment Long Term Program". This was required because of new loads. These new loads are caused by the Safety/Relief Valve (SRV) discharge and a postulated loss-of-coolant accident (LOCA). This worked was performed and completed in July 1983.

3.2 The primary containment structure is a portion of the GE Mark I Primary Containment Pressure Suppression System. The complete pressure suppression system consists of the drywell which houses the reactor vessel and reactor coolant recirculation loops, the pressure suppression chamber, the connecting vent system between the drywell and pressure suppression chamber, isolation valves, vacuum relief system, and containment cooling systems. The isolation valves and vacuum relief system are not discussed in this document. The containment cooling systems are discussed in detail in other system specific Design Basis Documents.

The drywell, pressure suppression chamber, and the interconnecting vent system (Primary Containment Structure) will be addressed in this document.

3.3 The drywell is a steel pressure vessel (0.75 to 3.0 inches thick), with a spherical lower portion and cylinder upper portion. It is enclosed in reinforced concrete, 4 to 7 feet thick, for shielding, and to provide additional resistance to deformation and buckling over areas where the concrete backs up the steel shell. Above the foundation transition zone, and below the flange, the drywell is separated from the reinforced concrete by a gap of approximately 2 inches to allow for thermal expansion. Shielding over the top of the drywell is provided by removable, segmented, reinforced concrete shield plugs.

The drywell vessel is provided with a removable head to facilitate refueling, one combination double door personnel access lock/equipment lock, one equipment hatch, one personnel access hatch, and one control rod drive removal hatch. The head and hatches are all bolted in place and have double seals and test tap for leak tests.

Special bellows seals are provided between the reactor vessel, the drywell vessel, and the reactor well to form a water tight seal and enable flooding of the upper portion of the drywell during refueling operations. To protect the outer circumference of the bellows a backing plate is provided which has a test tap for leakage monitoring. During normal operation, six watertight hinged covers are opened and removable air supply and return ducts permit circulation of ventilation air in the region above the reactor well seal bulkhead plate.

3.4 The pressure suppression chamber is a steel pressure vessel in the shape of a torus located below and encircling the drywell. The pressure suppression chamber contains the suppression pool and the gas space above the pool. The suppression chamber will transmit seismic loading to the reinforced concrete foundation slab of the Reactor Building. Space is provided outside the chamber for inspection.

Revision 0 (3-3)

DAEC Station 2nd Interval Containment Inspection Plan Access to the chamber is provided at two locations. These are two 4 foot diameter manhole entrances with double gasketed (leak testable) bolted covers connected to the chamber by 4 foot diameter steel pipe inserts. These access ports will be closed when Primary Containment is required and will be opened only when the primary coolant temperature is below 212'F and the pressure suppression capability is no longer required.

The pressure suppression pool serves as a heat sink for postulated transient or accident conditions. Energy is transferred to the pool by either the discharge piping from the reactor pressure safety/relief valves or the drywell vent piping, which discharge below the water level. The pool condenses the steam portion of the flow and collects any water carryover, while non-condensible gases (including any gaseous fission products) are released to the suppression chamber gas space.

The pool also acts as a heat sink for High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) steam exhaust. Energy is removed from the suppression pool when the Residual Heat Removal (RHR) System is operating in the Suppression Pool Cooling Mode.

The suppression pool is also the primary source of water for the Core Spray System and the Low Pressure Coolant Injection (LPCI) mode of the RHR System and the secondary source of water for the RCIC and HPCI Systems. The quantity of water stored in the suppression pool is sufficient to condense the steam from a design basis accident and to provide adequate water for the emergency core cooling systems. The suppression chamber is subject to the pressure associated with the storage of a minimum of 58,900 - 61,500 cubic feet of water distributed uniformly within the vessel during normal operation. Under accident conditions, the suppression chamber is designed for 61,500 cubic feet of water and a maximum containment pressure of 62 psig.

3.5 Eight 4 foot 9 inch diameter vent pipes connect the drywell and the pressure suppression chamber. Jet deflectors are provided in the drywell at the entrance of each vent pipe to prevent possible damage to the vent pipes from jet forces or projectiles which might accompany a pipe break in the drywell. The vent pipes are provided with two-ply expansion bellows to accommodate differential motion between the drywell and suppression chamber. These bellows have test connections which allow for leak testing and for determining that the passages between the two-ply bellows are not obstructed.

The drywell vents are connected to a 3 foot 6 inch diameter vent header in the form of a torus which is contained within the air space of the suppression chamber. Projecting downward from the header are 48 downcomer pipes, 24 inches in diameter and terminating a minimum of 3 feet below the water surface of the pool and approximately 7 feet above the bottom of the Torus.

Revision 0 (3-4)

DAEC Station 2nd Interval Containment Inspection Plan 3.6 Containment penetrations are designed for the same integrity as the primary containment structure itself. They will, therefore not affect the capabilities of the primary containment system to act as radiological barrier before, during, or subsequent to any design basis accident.

3.7 One combination personnel access lock/equipment lock is provided for access to the drywell. The personnel lock has two gasketed doors in series, with each door designed and constructed to withstand the drywell design differential pressure.

The doors are mechanically interlocked to ensure that at least one door is locked at all times when primary containment is required. The locking mechanisms are designed so that a tight seal will be maintained when the doors are subjected to either internal or external pressure. The seals on this access opening are capable to being tested for leakage. The personnel access lock is bolted on to an equipment insert barrel approximately 12 feet in diameter which in turn is provided with double testable seals and is welded to the drywell shell. The personnel access lock can be completely removed by an overhead monorail to increase the size of the opening should a larger access by required.

A personnel access hatch with double, testable seals is provided in the drywell head. This hatch is bolted in place.

One equipment access hatch with double, testable seals is also provided. This hatch is bolted in place.

Personnel and equipment hatches are sized and located with full consideration of service required, accessibility for maintenance, and periodic testing programs. A 2 inch minimum gap is maintained around the barrel of the personnel and equipment hatches as they pass through or enter into the concrete shield wall.

A control rod drive removal hatch with double, testable seals is provided. This hatch is bolted in place, and permits removal of the drive mechanisms when required.

4.0 Containment Inspection Boundaries 4.1 The containment system includes (a) through (c) as follows:

(a) the containment vessel (b) all penetration assemblies or appurtenances attached to the containment vessel (c) all piping, pumps, and valves attached to the containment vessel, or to penetration assemblies out to and including any valves required to isolate the system and provide a pressure boundary for the containment function.

Revision 0 (3-5)

DAEC Station 2nd Interval Containment Inspection Plan 4.2 The inspection boundary shall not be closer to the containment vessel than:

(a) the first circumferential joint in welded connections (the connecting weld shall be considered part of the piping),

(b) the face of the first flange in bolted connections (the bolts shall be considered part of the piping)

(c) the first-threaded joint in screw connections 4.3 The inspection boundary between the containment vessel and attachments shall not be any closer to the pressure retaining portion of the vessel than as defined in (a) through (g) below:

(a) attachments cast or forged with the containment vessel and weld buildup on the vessel surface shall be considered part of the containment vessel (b) attachments, welds, and fasteners having a pressure retaining function shall be considered part of the containment vessel.

(c) except as provided in (d) and (e) below, the boundary between the containment vessel and an attachment not having a pressure retaining function shall be at the surface of the vessel (d) the first connecting weld of a nonpressure-retaining structural attachment to the containment vessel shall be considered part of the vessel unless the weld is more than 2t from the pressure retaining portion of the vessel, where t is the nominal thickness of the pressure retaining material.

Beyond 2t from the pressure retaining portion of the vessel, the first weld shall be considered part of the attachment (e) the first connecting weld of a welded nonstructural attachment to the containment vessel shall be considered part of the attachment. At or within 2t from the pressure retaining portion of the component the first connecting weld shall conform to NE-4450.

(f) mechanical fasteners used to connect a nonpressure-retaining attachment to the containment vessel shall be considered part of the attachment (g) boundary may be located further from the pressure retaining portion of the containment vessel than as defined in (a) through (f) above when specified in the Design Specifications 5.0 Inaccessible Areas Revision 0 (3-6)

DAEC Station 2nd Interval Containment Inspection Plan 5.1 Portions of Class MC containment vessels, parts, and appurtenances that are embedded in concrete or otherwise made inaccessible during construction of the vessel or as a result of vessel repair/replacement activities are exempted from examination, provided:

(a) no openings or penetrations are embedded in the concrete, (b) all welded joints that are inaccessible for examination are double butt welded and are fully radiographed and, prior to being covered, are tested for leak tightness using a gas medium test, such as Halide Leak Detector Test; and (c) the vessel is leak rate tested after completion of construction or repair/replacement activities to the leak rate requirements of the Design Specification.

5.2 Surface areas of Class MC containment vessels, parts and appurtenances may be considered inaccessible if visual access by line of sight with adequate lighting from permanent vantage points is obstructed by permanent plant structures, equipment, or components, provided these surface areas do not require examination in accordance with the inspection plan or IWE- 1240.

5.3 An evaluation of the acceptability of inaccessible areas shall be completed when conditions exist in accessible areas that could indicate the presence of or result in degradation to such inaccessible areas.. The following shall be addressed and included in the ISI Summary Report (ref. IOCFR50.55a(b)(2)(ix)(A)):

(a) A description of the type and estimated extent of degradation, and the conditions that led to the degradation; (b) An evaluation of each area, and the result of the evaluation and the need for additional examinations and; (c) A description of necessary corrective actions 6.0 Augmented Containment Inspection Requirements 6.1 IWE-1241 specifies the requirements in determining the areas that are likely to experience accelerated degradation and aging (ref. Table IWE-2500-1, Category E-C). Such areas include the following:

a) interior and exterior containment surface areas that are subject to accelerated corrosion with no or minimal corrosion allowance or areas where the absence or repeated loss of protective coatings has resulted in Revision 0 (3-7)

DAEC Station 2nd Interval Containment Inspection Plan substantial corrosion and pitting. Typical locations of such areas are those exposed to standing water, repeated wetting and drying, persistent leakage, and those with geometries that permit water accumulation, condensation, and microbiological attack. Such areas may include penetration sleeves, stiffeners, surfaces wetted during refueling, concrete-to-steel shell or liner interfaces, embedment zones, leak chase channels, drain areas, or sump liners.

b) interior and exterior containment surface areas that are subject to excessive wear from abrasion or erosion that causes a loss of protective coatings, deformation, or material loss. Typical locations of such areas are those subject to substantial traffic, sliding pads or supports, pins or clevises, shear lugs, seismic restraints, surfaces exposed to water jets from testing operations or safety relief valve discharges, and areas that experience wear from frequent vibrations.

c) interior and exterior containment surface areas identified in accordance with IWE-2420(b) "Successive Examinations".

6.2 Surface areas requiring augmented examination shall be determined in accordance with IWE-1241 and shall be identified.

7.0 Repair and Replacement Program Requirements 7.1 The DAEC Repair/Replacement program requirements are being implemented under a separate program document not included in this submittal. DAEC's Repair/Replacement program is implemented in accordance with the 2001 Edition of ASME Section XI, as amended by the 2003 Addenda (IWX-4000), and the latest licensing agreements pertaining to these requirements. The ASME Section XI Repair/Replacement program for DAEC will be administered in accordance with the aforementioned rules and maintained in accordance with IWA- 1400, IWA-6200 and available for review on-site.

8.0 Contents of Containment Inspection Plan 8.1 The Containment Inspection Plan addresses the requirements for containment inspection of components and pressure testing separately, although some Sections of the Plan are common to both. The applicability of each of the Sections identified in this Plan is as follows:

8.1.1 Containment Inspection Sections 4, 7, 8, 9, 10, and 11 Revision 0 (3-8)

DAEC Station 2nd Interval Containment Inspection Plan 8.1.2 Pressure Testing Sections 12, 13, 14, 15, and 16 8.2 Section 1 - Table of Contents Provides the organizational format for the Containment Inspection Plan.

8.3 Section 2 - Revision Summary Sheet Provides the revision status of the effected pages in the Containment Inspection Plan.

8.4 Section 3 - Introduction and Plan Description Provides details on the scope, basis and contents of the Containment Inspection Plan, classifications, and augmented containment inspection requirements.

8.5 Section 4 - Application of Exemption Criteria Provides the basis for determining the Class MC exempted components from the examination requirements per IWE-1200.

8.6 Section 5 - List of Applicable UFSAR Figures Provides a listing of UFSAR Figures corresponding to components subject to examination under this Plan.

8.7 Section 6 - List of Applicable Isometric Drawings Provides a listing of piping isometric drawings corresponding to each system that contains components subject to examinations under this Plan.

8.8 Sections 7 - Containment Inspection Summary Tables The DAEC Containment Inspection Summary Tables provide the following information:

8.8.1 Examination Category Provides the examination category as identified in ASME Section XI, Table IWE-2500-1. Only those examination categories applicable to DAEC are identified.

Revision 0 (3-9)

DAEC Station 2nd Interval Containment Inspection Plan 8.8.2 Item Number and Item Description Provides the item number and description as defined in ASME Section XI, Table IWE-2500-1. Only those item numbers applicable to DAEC are identified.

8.8.3 Number of Components Provides the total population of components potentially subject to examination. The number of components actually examined during the inspection interval will be as indicated in Section 17, based upon the Code requirements for the subject item number.

8.8.4 Exam Requirements Provides the examination method(s) required by ASME Section XI, Table IWE-2500-1.

8.8.5 Relief Request Provides a listing of relief requests applicable to the item number. If a relief request number is identified, see the corresponding relief request in Section 11.

8.8.6 Technical Approach and Position Provides a listing of technical approach and positions applicable to the item number. If a technical approach and position number is identified, see the corresponding technical approach and position in Section 9.

8.9 Section 8 - Containment Inspection Technical Approach and Position Index/Summaries Provides a summary and the revision status of all technical approach and positions related to containment inservice inspection. The index includes that date that the technical approach and position is approved internally.

8.10 Section 9 - Containment Inspection Technical Approach and Positions When the requirements of ASME Section XI are not easily interpreted, DAEC has reviewed general licensing/regulatory requirements and industry practice to determine a practical method of implementing the Code requirements. The technical approach and position documents contained in this section have been Revision 0 (3-10)

DAEC Station 2nd Interval Containment Inspection Plan provided to clarify DAEC's implementation of ASME Section XI requirements for containment inspection.

8.11 Section 10 - Containment Inspection Relief Request Index/Summaries Provides a summary and the revision status of all relief requests related to containment inspection. The index includes the date the relief request is approved by the NRC.

8.12 Section 11 - Containment Inspection Relief Requests This section contains relief requests written in accordance with 10 CFR 50.55a(a)(3) and (g)(5) when specific ASME Section XI requirements for containment inspection are considered impractical. The enclosed relief requests are subject to change throughout the inspection interval. If examination requirements are determined to be impractical during the course of the interval, additional or modified relief requests will be submitted in accordance with 10 CFR 50.55a.

8.13 Section 12- Containment Pressure Testing Summary Tables The Containment Pressure Testing is described in the "Performance Based Containment Testing Program Manual" as discussed in Section 12.

8.14 Section 13 - Containment Pressure Testing Technical Approach and Position Index/Summaries Provides a summary and the revision status of all technical approach and positions related to containment pressure testing.

8.15 Section 14 - Containment Pressure Testing Technical Approach and Positions When the requirements of ASME Section XI are not easily interpreted, DAEC has reviewed general licensing/regulatory requirements and industry practice to determine a practical method of implementing the Code requirement. The technical approach and position documents contained in this section have been provided to clarify DAEC's implementation of ASME Section XI requirements for containment pressure testing.

8.16 Section 15 - Containment Pressure Testing Relief Request Index/Summaries Provides a summary and the revision status of all relief requests related to containment pressure testing.

Revision 0 (3-11)

DAEC Station 2nd Interval Containment Inspection Plan 8.17 Section 16 - Containment Pressure Testing Relief Requests This section contains relief requests written in accordance with 10 CFR 50.55a(a)(3) and (g)(5) when specific ASME Section XI requirements for containment pressure testing are considered impractical. The enclosed relief requests are subject to change throughout the inspection interval. If testing requirements are determined to be impractical during the course of the interval, additional or modified relief requests will be submitted in accordance with 10 CFR 50.55a.

8.18 Section 17 - Component Examination Summary Listing This section contains the tables and schedule for selection and examination of components in accordance with the requirements of ASME Section XI.

Revisio n 0 (3-12)

DAEC Station 2 nd Interval Inservice Inspection Plan APPLICATION OF EXEMPTION CRITERIA

1.Section XI Class MC Exemptions:

1.1 Subparagraph IWE-1220 gives specific guidance permitting exemption of components from the examination requirements of IWE-2500 if they are:

(a) vessels, parts, and appurtenances that are outside of the boundaries of containment as defined in the design specifications; (b) embedded or inaccessible portions of containment vessels, parts, and appurtenances that met the requirements of the original Construction Code; (c) portions of containment vessels, parts, and appurtenances that become embedded or inaccessible as a result of vessel repair/replacement activities if the conditions of IWE-1232(a) and (b) and IWE-5220 are met; (d) piping, pumps, and valves that are part of the containment system, or which penetrate, or are attached to the containment vessel. These components shall be examined in accordance with the requirements of IWB or IWC, as appropriate to the classification defined by the Design Specification.

1.2 The concrete biological shield and the shield plugs are not part of the containment design and are, therefore excluded from this program.

1.3 The portion of the drywell below the concrete floor is inaccessible. The welds in the lower head consists of both double and single buttwelded joints. Both were radiographed and pressure tested in accordance with the Construction Code (ASME Section III).

1.4 Integral attachments connected to components which are exempt from examination under IWE-1220 are also exempt from the examination requirements of IWE-2500 and Table IWE-2500-1.

Revision 0 (4-1) Date 10/19/2007

DAEC Station 2 nd Interval Containment Inspection Plan LIST OF APPLICABLE UFSAR FIGURES FIGURE FIGURE TITLE No.

6.2-1 Primary Containment System 6.2-2. Containment Vessels Requirements Drywell Penetrations 6.2-3 ISuppression Pool Penetrations 6.2-4 Typical Piping Penetration/Containment Boundary 6.2-5 Typical Piping Penetration/Containment Boundary 6.2-6 Typical Piping Penetrat ion/Containment Boundary 6.2-7 Typical Instrument Penetration/Containment Boundary 6.2-8 Typical Triple Flued Head Fitting 6.2-9 Typical Electrical Penetration/Containment Boundary 6.2-10 I Drywell Stretchout 6.2-11 Drywell Penetrations Orientation Below the Equator 6.2-12 Drywell Penetrations Orientation Above the Equator 6.2-13 Drywell Penetration Orientation in Cylinder 6.2-14 I Suppression Chamber Penetration Schedule 6.2-15 Drvwell Shell - Field Assembly 6.2-16 D rWeal Shell Field Joint Details 6.2-17 Drywell Vent Penetration 6.2-18 Drywell Vent Jet Deflectors 6.2-19 Drywell Erection Skirt 6.2-20 Drywell Top Flange 6.2-21 Drywell Top Flange Details 6.2-22 I CRD Removal Hatch (Penetration X-6) 6.2-23 12 Ft Equipment Door - Shop and Field Assembly - Penetration X-2 6.2.25 Beam Seat Locations

.6.2-26 Details of Upper Beanm Seats

,6.2-27 IDetailsý of Lower Beam Seats 6.2-28 Male.S~tabiliz~er Asse~mbly, 6.2-29 I Female Stabilizer Assembly 6.2-33 Drywell Control Rod Insert 6.2-34 Drywell Head Access Hatch - Penetration X-4 6.2-35 Suppression Chamber General Arrangement 6.2-36 I Field Assembly-Vent Line and Header 6.2-37 Suppression Chamber Support Girder and Header Supports and Pin Details for Field 6.2-38 Field Assembly Suppression Chamber Columns

.6.2-39 Torus Manway.and Davit Assembly - Penetrations N-200A and B 6.2-40 ISuppression Chamber - Radial Penetrations 6.2-41 Suppression Chamber Radial Penetrations and Strainers 6.2-42 W ppression Chamber Earthquake Ties 6.2-43 Sh 1 General Personnel Lock X- I 6.2-43 Sh 2 General Personnel Lock X- I 6.2-58 I Torus-Drywell Vacuum Breaker Details I

Revision 0 (5-1) Date 10/16/2007

DAEC Station 2 nd Interval Containment Inspection Plan LIST OF APPLICABLE PIPING ISOMETRIC DRAWINGS P&ID No. Description ISI ISOMETRIC DWG. No.

N/A Drywell/Torus Vent Line, Vent Head & 5.1-01 Downcomer N/A Torus Support (Typ.) 5.1-02<1>

N/A Torus Support Location 5.1-02<2>

N/A Torus Support Configuration 5.1-02<3>

+

Revision 0 (6-1) Date 10/16/2007

DAEC Statio.. ,d Interval Containment Inspection Plan CONTAINMENT INSPECTION

SUMMARY

TABLE (Page 1 of 2)

Examination Item Total Exam Relief Technical Category Number Description Number Requirements Request Approach &

of Position Components El.I I Accessible Surface Areas' 25 Areas General Visual TAP-E002 (STP 3.6.1.1- TAP-E003 01)

E-A El. 12 Wetted Surfaces of Submerged Areas' 16 Bays General Visual TAP-E002 El.20 Vent System 8 Vents General Visual TAP-E002 Accessible Surface Areas"'2 (STP 3.6.1.1 -

01)

El.30 Moisture Barriers 3 2 General Visual TAP-E002 NOTES:

(1) Examination shall include all accessible interior and exterior surfaces of Class MC components, parts, and appurtenances, and metallic shell and penetration liners of Class CC components. The following items shall be considered for examination:

a) integral attachments and structures that are parts of reinforcing structure, such as stiffening rings, manhole frames, and reinforcement aroundopenings.

b) surfaces of attachment welds between structural attachments and the pressure retaining boundary or reinforcing structue, except for nonstructural or temporary attachments as defined in NE-4435 and minor permanent attachments as defined in CC,4543.4.

c) surfaces of containment structural and pressure boundary welds, including longitudinalwelds (Category A), circumferentialwelds (Category B), flange welds (Category C), and nozzle-to-shell welds (Category D) as defined in NE-3351 for Class MC and CC-3840 for Class CC; and surfaces of Flued Head and Bellows Seal Circumferential Welds joined to the Penetration.

d) pressure-retaining bolted connections, including bolts, studs, nuts, bushings, washers, and threads in base material and flange ligaments between fastener holes.

Bolted connections need not be disassembled for performance of examinations, and boltingmay remain in place under tension.

(2) Include flow channeling devices within containment vessels (3) Examination shall include moisture barrier materials intended to prevent intrusion of moisture against inaccessible areas of the pressure retaining metal containment shel or liner at concrete-to-metal interfaces and at metal-to-metal interfaces which are not seal-welded. Containment moisture barrier materials include caulking, flashing, and other sealants used for this application.

Revision 0 (7-1) Date 10/19/2007

- %-11-- 1. .........

...... I.,

DAEC Station 2 d Interval Containment Inspection Plan CONTAINMENT INSPECTION

SUMMARY

TABLE (Page 2 of 2)

Examination Item Total Exam Relief Technical Category Number Description Number Requirements Request Approach &

of Position Components E4.11 Visible Surfaces' 16 Bays Detailed Visual MC-R001 TAP-E0O I TAP-E002 E-C E4.12 Surface Area Grid, N/A Ultrasonic TAP-E002 Minimum Wall Thickness Location' Thickness NOTES:

(1) Containment surface areas requiring augmented examination are those identified in 1WE1240.

(2) The extent of examination shall be 100% for each inspection period until the areas examined remain essentiali unchanged for next inspection period- Such areas no longer require augmented examination in accordance with IWE-2420(c).

Revision 0 (7-2) Date 10/19/20f.

DAEC Station 2 nd Interval Containment Inspection Plan CONTAINMENT INSPECTION TECHNICAL APPROACH AND POSITION INDEX/SUMMARIES Position Page(s) Rev. *Date Summary ApprovedI TAP-EOO1 9-1 0 Remote Visual Examinations TAP-E002 9-2 0 Use of General and Detailed Visuals Examination Methods TAP-E003 9-3 0 Examination of disassembled containment bolting connections

• Denotes Internal Approval Date Revision 0 (8-1) Date 10/16/2007

DAEC Station 2nd Interval Containment Inspection Plan TECHNICAL APPROACH AND POSITION NUMBER: TAP-EO01 (Page 1 of 1)

COMPONENT IDENTIFICATION Code Class: MC

Reference:

Table IWA-2210-1 Examination Category: All Item Number: All

==

Description:==

Remote Visual Examinations CODE REQUIREMENT Table IWA-2210-1 specifies the minimum illumination and maximum distance for direct visual examination.

POSITION 10CFR50.55a(b)(2)(ix)(B) allows the following alternative to Table IWA-2210-1:

When performing remotely the visual examination required by Subsection IWE, the maximum direct examination distance specified in Table IWA-2210-1 may be extended and the minimum illumination requirements specified in Table IWA-2210-1 may be decreased provided that the conditions or indications for which the visual examination is performed can be detected at the chosen distance and illumination.

The DAEC has developed a resolution card which contains characters meeting the requirements of the near-distance test chart in IWA-2210 (2001 Edition with the 2003 Addenda). This card will be used to verify that the condition or indications for which the visual examination is being performed can be detected.

Revision 0 (9-1) Date 10/19/2007

DAEC Station 2 nd Interval Containment Inspection Plan TECHNICAL APPROACH AND POSITION NUMBER: TAP-E002 (Page 1 of 1)

COMPONENT IDENTIFICATION Code Class: MC

Reference:

Table IWE-2500- 1 Examination Category: All Item Number: All

Description:

Use of General and Detailed Visual Examination Methods CODE REQUIREMENT Table IWE-2500-1 requires an examination method of General Visual for Examination Category E-A and Detailed Visual Examination for Examination Category E-C.

POSITION 10CFR50.55a(b)(2)(ix)(F) states:

"VT-I and VT-3 examinations must be conducted in accordance with IWA-2200. Personnel conducting examinations in accordance with the VT-I and VT-3 examination method shall be qualified in accordance with IWA-2300. The "owner defined" personnel qualification provisions in IWE-2330(a) for personnel that conduct VT-I and VT-3 examinations are not approved for use."

In addition 10CFR50.55a(b)(2)(ix)(G) specifies:

"The VT-3 examination method must be used to conduct the examinations in Items E 1.12 and E1.20 of Table IWE-2500-1, and the VT-I examination method must be used to conduct the examination in Item E4. 11 of Table IWE-2500- 1. An examination of the pressure retaining bolted connections in Item El. 11 of Table IWE-2500-1 using the VT-3 examination method must be conducted once each interval. The "owner defined" visual examination provisions in IWE-23 10(a) are not approved for use for VT-i and VT-3 examinations."

The DAEC will implement the requirements as stated in the two referenced 10CFR50.55a paragraphs above.

Revision 0 (9-2) Date 10/19/2007

DAEC Station 2 nd Interval Containment Inspection Plan TECHNICAL APPROACH AND POSITION NUMBER: TAP-E003 (Page 1 of 1)

COMPONENT IDENTIFICATION Code Class: MC

Reference:

Table IWE-2500-1 Examination Category: E-A Item Number: EI.ll

==

Description:==

Examination of disassembled containment bolting connections CODE REQUIREMENT Table IWE-2500-1 Category E-A, Item El.11, footnote 1d does not require the disassembly of bolted connections to perform the visual examination and bolting may remain in place under tension.

POSITION I OCFR50.55a(b)(2)(ix)(H) states:

"Containment bolted connections that are disassembled during the scheduled performance of the examination in Item El .11 of Table IWE-2500-1 must be examined using the VT-3 examination method. Flaws or degradation identified during the performance of a VT-3 examination must be examined in accordance with the VT- 1 examination method. The criteria in the material specification or IWB-3 517.1 must be used to evaluate containment bolting flaws or degradation.

As an alternative to performing VT-3 examinations of containment bolted connections that are disassembled during the scheduled performance of Item E 1.11, VT-3 examinations of containment bolted connections may be conducted whenever containment bolted connections are disassembled for any reason."

The DAEC will implement the alternative examination requirements as stated in the referenced 10CFR50.55a paragraph above.

Revision 0 (9-3) Date 10/19/2007

DAEC Station 2 "dInterval Containment Inspection Plan CONTAINMENT INSPECTION RELIEF REQUESTS Section 11 contains relief requests written in accordance with 10CFR50.55a(a)(3) and (g)(5) when specific ASME Section XI requirements for containment inspection are considered impractical or pose an undo burden on the licensee. The relief requests contained in Section 11 are subject to change during the course of the ten year inspection interval as a result of changes in technology, plant design or as a result of installed modifications. If examinations or tests are determined to be impractical, or result in hardship or unusual difficulty without a commensurate increase in the level of quality or safety, during the course of the interval, additional or modified relief requests will be submitted in accordance with IOCFR50.55(a)(3) and (g)(6).

The following Table is an index which summarizes each relief request and provides for sequential numbering to maintain continuity for the remaining inspection intervals at DAEC.

Revision 0 (10-1) Date 10/19/2007

DAEC StationRnd2 Interval Containment Inspection Plan CONTAINMENT I~NSPECTION RELIEF REQUEST INDEX/SUMMARIES Relief Page(s) Rev Date Summary Request 1 1Approvedj MC-RO01 11-1. 0 Periodic Examination of Suppression

___________Chamber Revision 0 (10-2)

DAEC Station 2nd Interval Containment Inspection Plan RELIEF REQUEST NUMBER: MC-RO01 (Page 1 of 1)

COMPONENT IDENTIFICATION Code Class: MC

Reference:

IWE-1240 Examination Category: E-C Item Number: E4.11

Description:

Periodic Examination of Suppression Chamber CODE REQUIREMENT IWE-1241 provides the selection criteria for those areas requiring augmented examinations.

Subparagraph (a) states "interior and exterior containment surface areas that are subject to accelerated corrosion with no or minimal corrosion allowance or areas where the absence or repeated loss of protective coatings has resulted in substantial corrosion and pitting".

IWE-2500-1, Category E-C requires a Detailed Visual (VT-1) every period on 100% of surface areas identified by IWE-1242.

REASON FOR REQUEST The DAEC Torus was initially coated in 1973 with an inorganic zinc protective coating CarboZinc 11 with a four foot wide band epoxy coating Phenoline 368 at the waterline. FPLE Duane Arnold has a very proactive inspection program for the torus interior. The torus has been inspected and coating repairs performed in 1977, 1980, 1981, and 1983. In 1985, all internal surfaces of the torus shell and external surfaces of the vent system were recoated with CarboZinc

11. Additional inspections and repairs to the coating were performed in 1987, 1988, 1990, 1992, and 1993. During the 1993 inspection,. a quantitative inspection was performed on a one square foot evalution area representative of the worst case corrosion observed during the qualitative inspections. A grid was established and the coordinates of each pit in the evaluation area were recorded so that the rate of corrosion (pit depth) could be monitored and trended in the future.

Repairs to the coating are made as necessary. Subsequent inspection performed on the torus immerision zones during 1995, 1996, 1998, 2001 and 2005 found numerous areas of zinc depletion and minor pitting. These areas were repaired with an epoxy coating Brutem 15 and UT-15 (beginning in 2001). The 1995 repairs were performed using Plasite C-790. A total of 14,229 repairs have been performed to the shell since 1995.

The inspection results of the one square foot area evaluation grid established in 1993 indicates that the torus shell corrosion rate to be <0.001" per 12 month cycle. In 1998 due to excessive zinc depletion and surface rusting, pit identification numbers were unattainable; therefore the grid area was repaired with Brutem 15.

Repeated inspections have shown that there is no sign of disbanding or delamination of the torus internal coating. Integrity of the repairs is also not degraded. Although recommended expected life of Carbo Zinc 11 is 15-20 years, a longer life out of inorganic zinc coating due to frequent desludging and coating repairs is expected. To attain further life extension, continued desludging and repairs every other outage to prevent growth of rust nodules will be completed.

Revision 0 (11-1)

DAEC Station 2 ,id Interval Containment Inspection Plan PROPOSED ALTERNATIVE AND BASIS FOR USE FPLE Duane Arnold will continue to perform a general visual examination on 100% of the torus exterior and interior surface (above the water line) each period (Item E1.11). In addition a VT-i visual examination on 100% of the torus interior and exterior surfaces (below the water line)

(Item E4. 11) will be performed twice per interval. Since both sides are accessible (IWE-2500(b)(1) for visual examination, no volumetric examination (Item E4.12) is required.

This examination provides an acceptable way to monitor the coating on the interior surface. of the torus. Areas which are detected to have a "corrosion cell" (small area of uncoated metal, typically 1/4" to 1/2") will be repaired. Performing a general visual of 100% of the exterior and interior surfaces (above the water line), VT-I of 100% of the interior surfaces (below the water line) twice per interval provides an assurance that the structural integrity of the torus is acceptable. Repairs to the coating are performed when necessary.

DURATION OF PROPOSED ALTERNATIVE Relief is requested for the 2 nd 10 year interval of the IWE Program for the DAEC.

Revision 0 (11-2)

DAEC Station 2 nd Interval Containment Inspection Plan PRESSURE TEST

SUMMARY

TABLE Containment testing at the DAEC is conducted in accordance with 10CFR50, Appendix J, Option B. Option B allows licensees to implement a containment testing program which is based on past component performance and risk rather than following the prescriptive requirements of Option A. The DAEC Appendix J, Option B testing program is described in the "Performance Based Containment Testing Program Manual".

Revision 0 (12-1) Date 10/16/2007

DAEC Station 2 d Interval Containment Inspection Plan CONTAINMENT SYSTEM PRESSURE TESTING TECHNICAL APPROACH AND POSITION INDEXISIJMMARIES Poiin Pg~) Rev. *Date [Summary There are no Technical Approach and Positions identified at this time.

__ I___ ii __ I

________ I

• Denotes Internal Approval Date Revision 0 (13-1) Date 10/19/2007

DAEC Station 2 nd Interval Containment Inspection Plan THERE ARE NO TECHNICAL APPROACH AND POSITIONS IDENTIFIED AT THIS TIME Revision 0 (14-1) Date 10/19/2007

DAEC Station 2 dInterv al Containment Inspection PI In SYSTEM PRESSURE TESTING RELIEF REQUEST INDEX/SUMMARIES Relief Page(s) Rev. Date Summary Request I I Approved MC-P001 16-1 to 16-2 0 I Detailed Visual (VT- 1) Examination following Minor Repairs/Replacements/Modifications 4 + +

4 4- -I-1 1- 4 1-4 1 + 1-4 4 4- 4 4 4 4~ 4 4 4 .1 4

+ 4 4 4 4- 4 1- .4. 4 Revision 0 (15-1) Date 10/16/2007

DAEC Station 2 nd Interval Containment Inspection Plan RELIEF REQUEST NUMBER: MC-POO1 (Page 1 of 2)

COMPONENT IDENTIFICATION Code Class: MC

Reference:

IWE-5240 Examination Categories: All Category Numbers Item Numbers: All Item Numbers

==

Description:==

VT-2 Examinations following Repairs/Replacements/

Modifications Component Numbers: All Components CODE REQUIREMENT Paragraph IWE-5240, of the 2001 Edition, 2003 Addenda of ASME Section XI requires a detailed visual examination be performed in conjunction with the pressure testing following all repairs, replacements, or modifications.

Minor repairs as defined in IWE-5222 can be deferred until the next scheduled leakage test, provided nondestructive examination is performed in accordance with the approved repair program. Minor repairs consist of the following:

1) welds of attachments to the surface of the pressure retaining boundary

2) weld cavities, the depth of which does not penetrate the required design wall more than 10%; and

3) welds attaching penetrations that are NPS 1 or smaller BASIS FOR RELIEF Pursuant to IOCFR50.55a(a)(3)(ii), relief is requested on performing detailed visual examinations for minor repairs on the basis that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

10 CFR 50.55a was amended in the Federal Register (61FR41303) to require the use of the 1992 Edition, 1992 Addenda, of Section XI when performing containment examinations. Paragraph IWE-5210 states that except as noted within Paragraph IWE-5240, the requirements of Article IWA-5000 are not applicable to Class MC components. Paragraph IWE-5240 states: "During the pressure test required by IWE-5220, a detailed visual examination (IWE-2310) shall be performed on areas affected by repair/replacement activities." The detailed visual examination (IWE-2310(d)) is conducted to assess, the structural condition of areas affected by repair/replacement activities.

Revision 0 (16-1) Date 10/19/2007

DAEC Station 2nd Interval Containment Inspection Plan RELIEF REQUEST NUMBER: MC-PO01 (Page 2 of 2)

BASIS FOR RELIEF (cont.)

Performing a detailed visual (VT-i as required by 10CFR50.55a(b)(2)(ix)(G)) on minor repair/replacement activities would be a duplicate of the requirement found in IWE-5222 that states: "...may be deferred until the next scheduled leakage test, provided nondestructive examination is performed in accordance with the Repair/Replacement Program and Plan." The nondestructive examinations performed in accordance with the construction code would meet the requirement of IWE-2310 in assessing the structural condition of the area affected by the repair/replacement activity.

IWE-5220 identifies the pressure retaining boundary of Class MC to be subjected to a pneumatic leakage test in accordance with the provisions of Title 10, Part 50 of the Code of Federal Regulations, Appendix J, paragraph IV.A. 10CFR50, Appendix J provides requirements for testing as well as acceptable leakage criteria. These tests are performed by Appendix J "Test" personnel and utilize calibrated equipment to determine acceptability. Additionally, 10 CFR 50.55a(b)(2)(ix)(E) requires a general visual examination of the containment each period that would identify any structural degradation that may contribute to leakage.

A Detailed Visual Examination (VT-1) for minor repairs will not provide additional assurance of safety beyond that of current Appendix J practices. The presence of a VT-1 examiner in addition to Appendix J test personnel for minor repairs could result in unnecessary exposure duplication and violation of "ALARA" good practice without any substantial increase in safety.

It is important to note that all minor repairs will be examined (surface or visual) per the applicable construction code requirements.

ALTERNATE EXAMINATION The requirements of IWE-5240 shall be performed on major repairs on the containment pressure boundary. However for minor repairs, testing shall be conducted in accordance with 10CFR50, Appendix J, in lieu of IWE-5240.

APPLICABLE TIME PERIOD Relief is requested for the second ten year interval of the Containment Inspection Program for the DAEC.

Revision 0 (16-2) Date 10/19/2007

DAEC Station 2 "dInterval Containment Inspection Plan COMPONENT EXAMINATION

SUMMARY

LISTING 1.0 All containment components and containment component supports potentially subject to examination under the 2001 Edition with the 2003 Addenda of Section XI are contained in the attached Table.

2.0 This table identifies the number of containment components selected for examination during the second inspection interval and provides a schedule by period, for the applicable required examinations to be performed. The components selected are those anticipated to be examined during the second interval; however, other components may be substituted based on access, ALARA considerations, and installation of plant design modifications. The total number of components for each Code Category/Item No. is provided in the attached "Section XI Summary Report and Long Term Plan". Deviations from the "Long Term Plan" shall not be considered a change to this Program, provided the "Containment Inspection Examination Summary Table" is satisfied.

3.0 Table 17-1 is sorted by, Code Category/Item No., Examination Description, System Identification, required NDE method, Scheduled Period, and Comments. DAEC will maintain, on site, a controlled comprehensive containment examination plan and schedule and will be made available for review.

Revision 0 (17-1)

DAEC Station 2nd Interval Containment Inspection Plan Containment Inspection Examination Summary Table Examination Item System Exam Period Comments Category Number Examination Description Identification Requirements Scheduled 1 2 3 EL.11 Accessible Surface Areas Drywell/Torus/ General Visual I 1 1 *Examination will be E-A Downcomers performed each period TAP-E002 TAP-E003 El.12 Wetted Surfaces of Submerged Areas Torus General Visual I TAP-E002 E 1.20 BWR Vent System Downcomers General Visual 3 3 2 TAP-E002 Accessible Surface Areas I I El.30 Moisture Barriers Drywell/Torus/ General Visual 1 1 1 TAP-E002 Downcomers Torus Detailed Visual *The number of EA. 11 Visible Surfaces 1 1 components may vary depending on inspection results TAP-EOO1 TAP-E002 MC-ROO E-C E4.12 Surface Area Grid Torus Volumetric L___I___I_ Minimum Wall Thickness Location I I Revision,* .... ...7-2)

Duane Arnold. Nuclear Plant 4th . erval Section Xl Summary Report and Long Term Plan Revision: 0 Period I Period 2 Period 3 Category, DwgllSO No.

Item No., Comp. Desc. ~'0 0 0 Class Summary No.ICompiD/System Scope i Method I Procedure Code Case Iit E-A 504700 ISII/ ISI - b - - b - - - s -

El.11 STP 3.6.1.1-01 ISI// ACCESSIBLE AREAS AUG . . . ... . . ... . . .

C CONTAINMENT ISINVT/STP 3.6.1.1-01 OWN . . . ... . . ... . . .

PRE . . . ... . . ... . . .

E-.A 502800 ISINT/STP 3.6.1.1-01 ISI - S . ... . . ... .

DRYWELL-TORUS VENT #A (301) EXAM E 1.2 0 DW T O TO R U S V E NT #A Z O N E 0 1-4 5: AU G . . . . . . . . . . . . . .

C VS OW N . . . .. . . . .. . . . .

PRE . . . ... . . .

E-A 502900 ISINT/STP 3.6.1.1-01 ISI s . ... . . ... . . .

DRYWELL-TORUS VENT #6 (3301) EXAM E1,20 DW TO TORUS VENT #B ZONE 315:-3601 AUG . . . ... . . ... . . .

C VS OWN . . . ... . . .

PRE . . . ... . . ... . . .

E-A 503000 ISINTISTP 3.6.1.1-01 ISI s- - - -.

DRYWELL-TORUS VENT #C (60:) EXAM E120 DW TO TORUS VENT #C ZONE 451-901 AUG . . . ... . . ... . . .

C VS OWN . . . ... . . ... . . .

PRE E.A 503100 ISINVT/STP 3.6.1.1-01 11 - - s - - -

DRYWELL-TORUS VENT #D (3001) EXAM E1.20 DW TO TORUS VENT #D ZONE 270:-3151 AUG . . . ... . . ... . . .

C VS OWN . . . ... . . ... . . .

PRE . . . ... . . ... . . .

EA 503200 ISI/VT/STP 3.6.1.1-01 ISI . .-.

DRYWELL-TORUS VENT #E (1201) EXAM E1.20 DW TO TORUS VENT #E ZONE 901-135: AUG . . . ... . . ... . . .

C VS OWN . . . ... . . ... . . .

PRE E-A 503300 ISI/VT/STP 3.6.1.1-01 ISI -- -- - ------ -- s - - -

DRYWELL-TORUS VENT #F (240:) EXAM E1.20 DW TO TORUS VENT #F ZONE 2251-270: AUG C VS OWN . . . ... . . ... . . .

PRE . . . ... . . ... . . .

E-.A 503400 ISINT/STP 3.6.1.1-01 ISI - S - -

DRYWELL-TORUS VENT #G (1501) EXAM E1.20 DW TO TORUS VENT #G ZONE 1351-1801 AUG C VS OWN PRE 10/16/2007 ScheduleWorks V. 8.1 Page 1 - 2

........... ue

.oeo k V.... 8. . .. ..Pag 1. 2.........

Duane Arnold. Nuclear Plant 4th. ,erval Section XI Summary Report and Long Term Plan Revision: 0 Period 1 Period 2 Period 3 Dwg/ISO No. 1~

Category, C")

• 1 ('4 04 0 Item No., comp. Qese. U-Summary No.IComn nID/Svstem Scooe / Method I Procedure Code Case L.

E-A 503500 ISIVT/STP 3.6.1.1-01 ISI - - - - -

DRYWELL-TORUS VENT #H (210:) EXAM E 1.2 0 D W T O T O R U S VE N T # H Z O N E 18 0 '-22 5 1 A UG . . . . . . . . . . . . . .

C VS OW N . . . .. . . . .. . . . .

PRE . . . . . . . . . . . . . .

E-A 501160 .SIl

.SI - b - - b - - s - - -

E 1.30 MO IST .BA R .742 ISII MO IST UR E BA R R IE R AT 742 AU G . . . . . . . . . . . . . .

C DW ISINVTISTP 3.6.1.1-01 OWN . . . ... . . ... . . .

PRE . . . . . . . . . . . . . .

E-C 503600 ISI// ISI b S E4.11 TORUS BAY #1-16 ISII/ TORUS BAYS 1-16 (UNDERWATER) AUG C TC OWN PRE 10/16/2007 ScheduleWorks V. 8.1 Page 2 - 2