ML070670343

Containment Inservice Inspection (CII) Program, Evaluation of Aging Management Programs, 01/25/2006

ML070670343
Person / Time
Site:	Vermont Yankee
Issue date:	01/25/2006
From:	Entergy Nuclear Operations
To:	Office of Nuclear Reactor Regulation
References
LRPD-02, Rev 1
Download: ML070670343 (68)

Text

LRPD-02 VYNPS License Renewal Project Revision 1 Aging Management Program Evaluation Results Page 162 of 275 Containment Inservice Inspection (CII) Program 4.14.2 Containment Inservice Inspection (CII) Program A. Proaram DescriDtion The WNPS Containment Inservice Inspection (CII) Program is a plant-specific program encompassing the requirements for the inspection of Class MC pressure-retaining components (Primary Containment) and their integral attachments in accordance with the requirements of 10CFR50.55a(b)(2) and the 1998 Edition of ASME Section XI with 2000 Addenda, Inspection Program B. Subarticle IWA-4540 of the 2003 Addenda of the 2001 Edition of ASME Section XI has also been adopted.

i l (Ref. Section 1.3, PP 7024)

This program is credited in the following.

AMRC-01, Primary Containment

6. Evaluation

1. Scope of Program The CII Program, under ASME Section XI Subsection IWE, manages loss of material and cracking for the primary containment and its integral attachments.

The primary containment is a General Electric Mark I pressure suppression containment system. The system consists of a drywell (housing the reactor vessel and reactor coolant recirculation loops), a pressure suppression chamber (housing a water pool), and the connecting vent system between the drywell and the water pool, isolation valves, and containment cooling systems. The code of construction for the containment structure is the ASME Section Ill, 1965 with winter addenda.

(Ref. Section 1.2, PP 7024) i

2. Preventive Actions The CII Program is a monitoring program that does not include preventive actions.

3. Parameters Monitorednnspected The primary containment and its attachments are inspected for evidence of cracks, wear, and corrosion.

(Ref. Section 5.1.2, ENN-EP-S-001 and Section 4.2, PP 7024)

4. Detection of Aging Effects The CII Program manages loss of material and cracking for the primary containment and its integral attachments.

(Ref. AMRC-01)

LRPD-02 VYNPS License Renewal Project Revision 1 Aging Management Program Evaluation Results Page 163 of 275 Containment lnservice Inspection (CII) Program The primary inspection method for the primary containment and its integral attachments is visual examination. Visual examinations are performed either directly or remotely with sufficient illumination and resolution suitable for the local environment to assess general conditions that may affect either the containment structural integrity or leak tightness of the pressure retaining component. The program includes augmented ultrasonic exams to measure wall thickness of the containment structure.

(Ref. Section 5.1.1, ENN-EP-S-001 and Sections 1.3 and 4, PP 7024)

5. Monitoring and Trending Results are compared, as appropriate, to baseline data and, other previous test results. If indications are accepted for continued use by analytical evaluation, the areas containing such flaws are monitored during successive inspection periods.

(Ref. Section 5.1.5, ENN-EP-S-001)

6. Acceptance Criteria Results are compared, as appropriate, to baseline data, other previous test results, and acceptance criteria of the ASME Section XI, Subsection IWE for evaluation of any evidence of degradation.

(Ref. Section 5.2, ENN-EP-S-001) 7 . Corrective Actions Subsection IWE states that components whose examination results indicate flaws or areas of degradation that do not meet the acceptance standards are acceptable if an engineering evaluation indicates that the flaw or area of degradation is nonstructural in nature or has no effect on the structural integrity of the containment. Except as permitted by 10 CFR 50.55a(b)(ix)(D),

components that do not meet the acceptance standards are subject to additional examination requirements, and the components are repaired or replaced to the extent necessary to meet the acceptance standards.

(Ref. Section 5.2, ENN-EP-S-001 and Section 4.2.4, PP 7024)

0. Confirmation Process This attribute is discussed in Section 2.0, Background.

9. Administrative Controls This attribute is discussed in Section 2.0, Background.

10. Operating Experience Operating experience provides assurance that the program will be effective in managing effects of aging so that components crediting this program can perform their intended function consistent with the current licensing basis during the period of extended operation. For more information on applicable operating

LRPD-02 VYNPS License Renewal Project Revision 1 Aging Management Program Evaluation Results Page 164 of 275 Containment lnservice Inspection (CII) Program experience, see VYNPS Report LRPD-05, Operating Experience Review Results.

C. References ENN-EP-S-001, Rev. 00, ENN Engineering Standard - IWE General Visual 1 .

Containment Inspection PP 7024, Rev. 04, LPC 01, Containment Inservice Inspection Program (IWE)

D. Summarv The Containment lnservice Inspection Program provides reasonable assurance that effects of aging will be managed such that applicable components will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Vermont Yankee Nuclear Power Station License Renewal Application Technical Information In addition, wall thickness evaluations of fire protection piping are periodically performed on system components using non-intrusive techniques (e.g., volumetric testing) to identify evidence of loss of material due to corrosion.

A sample of sprinkler heads will be inspected using the guidance of NFPA 25 (2002 Edition) Section 5.3.1.1.1, which states, Where sprinklers have been in place for 50 years, they shall be replaced or representative samples from one or more sample areas shall be submitted to a recognized testing laboratory for field service testing. This sampling will be repeated every 10 years after initial field service testing.

I A.2.1.44 Flow-Accelerated Corrosion Program

..J The Flow-Accelerated Corrosion Program applies to safety-related and nonsafety-

&I related carbon steel components carrying two-phase or single-phase high-energy fluid 2 2% of plant operating time.

I The program, based on EPRl recommendations for an effective flow-accelerated corrosion program, predicts, detects, and monitors FAC in plant piping and other pressure retaining components. This program includes (a) an evaluation to determine critical locations, (b) initial operational inspections to determine the extent of thinning at these locations, and (c) follow-up inspections to confirm predictions. The program specifies repair or replacement of components as necessary.

A.2.1 .I5 Heat Exchanger Monitoring Program u

The Heat Exchanger Monitoring Program inspects heat exchangers for degradation. If degradation is found, then an evaluation is performed to evaluate its effects on the heat exchangers design functions including its ability to withstand a seismic event.

Representative tubes within the population of heat exchangers are eddy current tested at a frequency determined by internal and external operating experience to ensure that effects of aging are identified prior to loss of intended function. Along with each eddy current test, visual inspections are performed on accessible heat exchanger heads, covers and tube sheets to monitor surface condition for indications of loss of material.

The population of heat exchangers includes the HPCl gland seal condenser, HPCl lube oil cooler, RClC lube oil cooler, CST steam reheat coil, drywell atmospheric cooling units (RRU-I , 2, 3 & 4), reactor recirculation pump seal water coolers, reactor recirculation pump motor upper and lower bearing oil coolers, and reactor recirculation pump motor air coolers.

A.2.1 .I6 lnservice Inspection-Containment lnservice Inspection (Cll) Program The WNPS Containment lnservice Inspection (CII) Program is a plant-specific program encompassing the requirements for the inspection-ofCkss MC pressure-retaining Appendix A Updated Final Safety Analysis Report Supplement Page A-15

Vermont Yankee Nuclear Power Station License Renewal Application Technical Information components (primary containment) and their integral attachments in accordance with the requirements of 10CFR50.55a(b)(2) and the 1998 Edition of ASME Section XI with 2000 Addenda, Inspection Program B.

The primary inspection method for the primary containment and its integral attachments is visual examination. Visual examinations are performed either directly or remotely with sufficient illumination and resolution suitable for the local environment to assess general conditions that may affect either the containment structural integrity or leak tightness of the pressure retaining component. The program includes augmented ultrasonic exams to measure wall thickness of the containment drywell shell.

I A.2.1 .17 Inservice Inspection-Inservice Inspection (ISI)Program 1 The WNPS lnservice Inspection (ISI) Program is based on ASME Inspection Program B (IWA-2432), which has 10-year inspection intervals. Every 10 years the program is

.f updated to the latest ASME Section XI code edition and addendum approved by the Nuclear Regulatory Commission in 10CFR50.55a. On September 1, 2003 VYNPS entered the fourth IS1 interval. The Code Edition and Addenda used for the fourth interval is the 1998 Edition with 2000 addenda.

The program consists of periodic volumetric, surface, and visual examination of components and their supports for assessment, signs of degradation, flaw evaluation and corrective actions.

u A.2.1.18 Instrument Air Quality Program n The Instrument Air Quality Program ensures that instrument air supplied to components is maintained free of water and significant contaminants, thereby preserving an environment that is not conducive to loss of material. Dewpoint, particulate contamination, and hydrocarbon concentration are periodically checked to verify the instrument air quality is maintained.

1 A.2.1 .I9 Non-EQ Inaccessible Medium-Voltage Cable Program In the Non-EQ Inaccessible Medium-Voltage Cable Program, in-scope medium-voltage cables, not designed for, but exposed to significant moisture and voltage are tested at least once every ten years to provide an indication of the condition of the conductor insulation. The specific test performed is a proven test for detecting deterioration of the insulation system due to wetting, such as power factor, partial discharge, polarization index, or other testing that is state-of-the-art at the time the test is performed.

Significant moisture is defined as periodic exposures that last more than a few days.

Significant voltage exposure is defined as being subjected to system voltage for more than 25% of the time.

~

Appendix A Updated Final Safety Analysis Report Supplement Page A-I 6

Vermont Yankee Power Station License Renewal Application Technical Information B.l .I 5.1 Containment Inservice Inspection Proaram Descrir>tion The VYNPS Containment Inservice Inspection (CII) Program is a plant-specific program encompassing the requirements for the inspection of Class MC pressure-retaining components (Primary Containment) and their integral attachments in accordance with the requirements of IOCFR50.55a(b)(2) and the 1998 Edition of ASME Section XI with 2000 Addenda, Inspection Program B.

Evaluation

1. Scope of Program The CII Program, under ASME Section XI Subsection IWE, manages loss of material and cracking for the primary containment and its integral attachments. The primary containment is a General Electric Mark I pressure suppression containment system.

The system consists of a drywell (housing the reactor vessel and reactor coolant recirculation loops), a pressure suppression chamber (housing a water pool), and the connecting vent system between the drywell and the water pool, isolation valves, and containment cooling systems. The code of construction for the containment structure is the ASME Section Ill, 1965 with winter addenda.

2. Preventive Actions The CII Program is a monitoring program that does not include preventive actions.

3. Parameters Monitoredllnspected The primary containment and its attachments are inspected for evidence of cracks, f wear, and corrosion.

4. Detection of Aging Effects The CII Program manages loss of material for the primary containment and its integral attachments.

The primary inspection method for the primary containment and its integral attachments is visual examination. Visual examinations are performed either directly or remotely with sufficient illumination and resolution suitable for the local environment to assess general conditions that may affect either the containment structural integrity or leak tightness of the pressure retaining component. The program includes augmented ultrasonic exams to measure wall thickness of the containment structure.

Appendix B Aging Management Programs and Activities Page 8-53

Vermont Yankee Nuclear Power Station License Renewal Application Technical Information

5. Monitoring and Trending Results are compared, as appropriate, to baseline data and other previous test results. If indications are accepted for continued use by analytical evaluation, the areas containing such flaws are monitored during successive inspection periods.

6. Acceptance Criteria Results are compared, as appropriate, to baseline data, other previous test results, and acceptance criteria of the ASME Section XI, Subsection IWE for evaluation of any evidence of degradation.

7. Corrective Actions i

Subsection IWE states that components whose examination results indicate flaws or areas of degradation that do not meet the acceptance standards are acceptable if an engineering evaluation indicates that the flaw or area of degradation is nonstructural in nature or has no effect on the structural integrity of the containment. Except as permitted by 10 CFR 50.55a(b)(ix)(D), components that do not meet the acceptance standards are subject to additional examination requirements, and the components are repaired or replaced to the extent necessary to meet the acceptance standards.

8. Confirmation Process 3 This attribute is discussed in Section B.0.3.

3 9. Administrative Controls This attribute is discussed in Section B.0.3.

IO. Operating Experience RFO 21 inspections found only two areas of potential age-related degradation; the drywell floor to metal containment moisture barrier had missing paint, cracked paint, and areas of corrosion on the base metal in the seal area; and corrosion was found in the area of the X-5G penetration. Engineering evaluation was performed and no significant wall loss was identified. Base metal was prepared, primed and painted to protect it from further corrosion, and the moisture barrier was replaced. RFO 22 inspections found two more areas of potential age-related degradation; surface pitting of primary containment vent headers and vent pipe bowls; and corrosion on torus penetrations X-207A-H. Evaluation determined that the components have significant margin to code minimum wall thickness and that the rate of corrosion is low due to the inerted containment environment during operation. Augmented inspections were not necessary since none of the identified corrosion was significant. RFO 24 inspections revealed flaking coating and rust staining on the bay 3 inner torus wall. Subsequent Appendix B Aging Management Programs and Activities Page 8-54

Vermont Yankee Power Station License Renewal Application Technical Information ultrasonic examination revealed no material loss. Also, visual inspection of drywell head exterior surface revealed areas of localized missing coating and primer with light corrosion, but no material loss. Resolution of these issues prior to loss of component intended function provides evidence that the program is effective at managing aging effects for primary containment and its integral attachments.

RFO 24 visual inspections of drywell interior surfaces, stabilizer assembly interior surfaces, torus penetrations, and drywell penetrations revealed areas of localized missing coating where the primer is intact, but no corrosion or material loss. Visual inspection of new drywell moisture barrier resulted in no recordable indications.

Absence of aging effects on these components provides evidence that the program is effective at managing aging effects for primary containment and its integral attachments.

QA surveillance during RFO 24 revealed a problem with program administrative controls. The issue was addressed and closed. The program was revised to require that engineering evaluations of indications that do not meet acceptance criteria be completed before the containment is declared operable. QA surveillance revealed an issue that could impact effectiveness of the program. Resolution of this issue provides evidence that the program remains effective at managing aging effects for primary containment and its integral attachments.

A recent engineering system health report revealed no issues or findings that could impact effectiveness of the program.

u Conclusion A

The CII Program has been effective at managing aging effects. The CII Program provides reasonable assurance that effects of aging will be managed such that applicable components will

.I i continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

f I

1 B.1.I5.2 Inservice Inspection Proaram DescriDtion The VYNPS Inservice Inspection (19) Program is a plant-specific program encompassing ASME Section XI Subsection IWA, IWB, IWC, IWD and IWF requirements.

The VYNPS IS1 Program is based on ASME Inspection Program B (IWA-2432), which has 10-year inspection intervals. Every 10 years the program is updated to the latest ASME Section XI code edition and addendum approved by the Nuclear Regulatory Commission in 10CFR50.55a.

On September 1, 2003 VYNPS entered the fourth IS1 interval. The Code Edition and Addenda used for the fourth interval is the 1998 Edition with 2000 addenda. The current program ensures Appendix B Aging Management Programs and Activities Page B-55

0perating Experience Rev nca u La 1 ~age45of122 J Item Issue OE Evaluation QA During RFO 23,QA surveillances QA surveillances revealed no issues Surveillances confirmed personnel qualifications, or findings that could impact VY SR-2002- test equipment, testing methods, and effectiveness of the program.

41C,and QS- documentation are consistent with 2004-VY-079 program.

Program QA performs audits and surveillances QA audits and surveillances Owner of the program almost every cycle - revealed no issues or findings that Interview no significant findings have been could impact effectiveness of the Result: IS1 identified. QA audit and surveillances program.

Program are positive. (e.g., Audit Report AR-2003-22).

Program NRC monitors IS1 Program each NRC inspections revealed no issues Owner outage. NRC has nothad findings in or findings that could impact Interview past 2 inspections, e.g., NVY-04-075. effectiveness of the program.

Result: 1st Program Engineering Program status in 1st quarter of 2004 Engineering program health report Program was "Green" indicating site revealed no issues or findings that Health compliance with program objectives. could impact effectiveness of the Report: program.

Inservice Inspection Program Section 4.4.15 presents conclusions regarding the effectiveness of this program for managing I

3.4.16. Containment Inservice Inspection Program 1 The VYNPS Containment Inservice Inspection Program is a plant specific condition monitoring program encompassing the requirements of ASME Section XI Subsection IWE. The program f implements the requirements of Code of Federal Regulations IOCFR50.55a pertaining to inspection and testing of the primary containment. The attributes of this program are described

,j in LRPD-02 (Ref. 5.17).

The results of OE reviews described in Section 2.0 are as follows.

LRPD-05 W N P S License Renewal Project Revision 0 Operating Experience Review Results Page 46 of 122 Item Issue OE Evaluation Program Owner Inspections of the drywell floor to Resolution of this issue provides Interview Result: metal containment moisture barrier evidence that the program is Containment IS1 identified missing paint, cracked effective at managing aging effects WE) paint, and areas of corrosion on the for primary containment and its base metal in the seal area. integral attachments.

Engineering evaluation was performed, the base metal was prepared, primed and painted to protect it from further corrosion, and the moisture barrier was replaced.

(CR-VTY-I 999-1954)

ISI-IWE RFO-21 Inspection of drywell surfaces Resolution of this issue provides Inspection revealed corrosion in the area of the evidence that the program is Results X-5G penetration. No significant wall effective at managing aging effects loss was identified. Area was for primary containment and its prepared, primed and painted to integral attachments.

protect it from further corrosion.

ISI-IWE RFO-21 Inspection of 43% of the drywell Absence of aging effects on drywell Inspection penetrations resulted in noage- penetrations provides evidence that ResuI ts related degradation. the program is effective at managing aging effects for primary containment and its integral attachments.

ISI-IWE RFO-22 inspection of 57% of the drywell Absence of aging effects on drywell Inspection penetrations resulted in no age- penetrations provides evidence that Results related degradation. the program is effective at managing aging effects for primary containment and its integral attachments.

ISI-IWE RFO-22 Inspection of torus penetrations Resolution of this issue provides Inspection identified corrosion on penetrations evidence that the program is Results X-207A-H. More than the minimum effective at managing aging effects required wall thickness remains, so for primary containment and its penetrations were acceptable for integral attachments.

continued use.

VYNPS License Rene ' - ' -'

I LRPD-05 7 Item Issue OE Evaluation ISI-IWE RFO-22 Inspections identified general Resolution of this issue provides Inspection corrosion and surface pitting of evidence that the program is Results primary containment vent headers effective at managing aging effects and vent pipe bowls. Evaluation for primary containment and its determined that primary containment integral attachments.

has significant margin to code minimum wall thickness and that the rate of corrosion is low due to the inerted containment environment during operation. Augmented inspections were not necessary since none of the identified corrosion was sianificant.

ISI-IWE RFO-24 Visual inspection of interior surfaces Resolution of this issue provides Inspection of 16 torus bays revealed flaking evidence that the program is Results coating and rust staining on the bay 3 effective at managing aging effects inner torus wall. Subsequent for primary containment and its ultrasonic examination revealed no integral attachments.

material loss.

ISI-IWE RFO-24 Visual inspection of drywell interior Absence of aging effects on drywell Inspection surfaces revealed areas of localized interior surfaces provides evidence Results missing coating where the primer is that the program is effective at intact, but no corrosion or material managing aging effects for primary loss. containment and its integral attachments.

ISI-IWE RFO-24 Visual inspection of drywell head Absence of aging effects on drywell Inspection exterior surface revealed areas of interior surfaces provides evidence Results localized missing coating where the that the program is effective at primer is intact. There are also areas managing aging effects for primary of missing primer with light corrosion, containment and its integral but no material loss. attachments.

ISI-IWE RFO-24 Visual inspection of stabilizer Absence of aging effects on Inspection assembly A-H interior surfaces stabilizer interior surfaces provides Results revealed areas of localized missing evidence that the program is coating where the primer is intact, but effective at managing aging effects no corrosion or material loss. for primary containment and its integral attachments.

ISI-IWE RFO-24 Visual inspection of torus and-drywell Absence of aging effects on torus Inspection penetrations revealed areas of and drywell penetrations provides Results localized missing coating where the evidence that the program is primer is intact, but no corrosion or effective at managing aging effects material loss. for primary containment and its integral attachments.

1 VYNPS License Renewal Project Operating Experience R=VWV A.A-... D-r.mICe C \ G ~ U I L ~

1I LRPD-05 Revision 0 Page 48 of 122 Item Issue ISI-IWE RFO-24 Visual inspection of new (see Absence of aging effects on the Inspection Program Owner Interview Result, moisture barrier provides evidence Results above) drywell moisture barrier that the program is effective at resulted in no recordable indications. managing aging effects for primary containment and its integral attachments. Actions to preclude recurrence of identified conditions are effective.

Quality QA surveillance during RFO 24 QA surveillance revealed an issue Assurance revealed that the program had that could impact effectiveness of Surveillance deficient administrative controls. The the program. Resolution of this QS-2004-W- program was revised to require that issue provides evidence that the 110 engineering evaluations of indications program remains effective at CR-VTY-2004- that do not meet acceptance criteria managing aging effects for primary 01526 be completed before the containment containment and its integral is declared operable. attachments.

Engineering Program status in 1st quarter of 2004 Engineering program health report Program Health was Green indicating site revealed no issues or findings that Report: Primary compliance with program objectives. could impact effectiveness of the Containment program.

Inspection (IWE)

Program Section 4.4.1 6 presents conclusions regarding the effectiveness of this program for managing aging effects.

3.4.17. Instrument Air Quality Program Under the VYNPS Instrument Air Quality Program, air quality is monitored and maintained within specified limits to ensure that instrument air supplied to components is maintained free of water and significant contaminants, thereby preventing loss of material. The attributes of this program are described in LRPD-02 (Ref. 5.17).

The results of OE reviews described in Section 2.0 are as follows.

Issue OE Evaluation Program Owner Vendor (ATC Associates, Inc.) reviews Absence of findings indicates Interview Result: instrument air system quality every 6 that acceptance criteria have Instrument Air months. No findings have resulted been met. Therefore, the Quality Program from reviews. program is effective at ensuring that instrument air supplied to (Ref. Semi-Annual Analysis of components is maintained free Instrument Air, dated June 16-17, of water and significant 2003, dated December 17-18, 2002, contaminants, thereby and August 20-21, 2001). preventing loss of material.

LRPD-05 W N P S License Renewal Project Revision 0 Operating Experience Review Results Page 72 of 122 4.4.14. Flow-Accelerated Corrosion Program Recent inspection results (RFO 23) revealed that repairs or replacements were not necessary.

Turbine cross-around piping inspections found that 1995 repairs mitigated the rate of erosion and that wall thickness is acceptable. Absence of loss of material due to flow-accelerated corrosion provides evidence that the program is effective for managing loss of material for carbon steel lines containing high-energy fluids. Also, past repairs, replacements, and modifications have been effective in mitigating FAC.

QA surveillances and self-assessments from 1999 to 2004 revealed no issues or findings that could impact effectiveness of the program.

The Flow Accelerated Corrosion Program has been effective at managing aging effects. The Flow Accelerated Corrosion Program provides reasonable assurance that the effects of aging will be managed such that the applicable components will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

4.4.1 5. Inservice Inspection Program Pressure boundary components, including bolting, are evaluated using non-destructive examinations and visual inspections. Deviations from acceptance criteria are properly resolved.

Inspections since 2001 revealed erosion of valve body internals, weld indications, recirculation pump bolting corrosion and RHR valve bolting corrosion. The scope of welding inspections was expanded when rejectable indications were identified. Condition reports were used to document indications and ensured resolution of those conditions. Corrective actions included repair and replacement of components. These actions provide evidence that the program is effective at managing aging effects for applicable components.

QA audits, QA surveillances, engineering system health reports, and NRC inspections from 2001 to 2004 revealed no issues or findings that could impact effectiveness of the program.

The lnservice Inspection Program has been effective at managing aging effects. The Inservice Inspection Program provides reasonable assurance that the effects of aging will be managed such that the applicable components will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

4.4.16. Containment Inservice Inspection Program RFO 21 inspections found only two areas of potential age-related degradation; the drywell floor to metal containment moisture barrier had missing paint, cracked paint, and areas of corrosion on the base metal in the seal area; and corrosion was found in the area of the X-5G penetration.

Engineering evaluation was performed and no significant wall loss was identified. Base metal was prepared, primed and painted to protect it from further corrosion, and the moisture barrier was replaced. RFO 22 inspections found two more areas of potential age-related degradation; surface pitting of primary containment vent headers and vent pipe bowls; and corrosion on torus penetrations X-207A-H. Evaluation determined that the components have significant margin to code minimum wall thickness and that the rate of corrosion is low due to the inerted containment environment during operation. Augmented inspections were not necessary since

I LRPD-05 WNPS License Renewal Project Revision 0 Operating Experience Review Results none of the identified corrosion was significant. RFO 24 inspections revealed flaking coating and rust staining on the bay 3 inner torus wall. Subsequent ultrasonic examination revealed no material loss. Also, visual inspection of drywell head exterior surface revealed areas of localized missing coating and primer with light corrosion, but no material loss. Resolution of these issues prior to loss of component intended function provides evidence that the program is effective at managing aging effects for primary containment and its integral attachments.

RFO 24 visual inspections of drywell interior surfaces, stabilizer assembly interior surfaces, torus penetrations, and drywell penetrations revealed areas of localized missing coating where the primer is intact, but no corrosion or material loss. Visual inspection of new drywell moisture barrier resulted in no recordable indications. Absence of aging effects on these components provides evidence that the program is effective at managing aging effects for primary containment and its integral attachments.

QA surveillance during RFO 24 revealed that the program had deficient administrative controls.

The program was revised to require that engineering evaluations of indications that do not meet acceptance criteria be completed before the containment is declared operable. QA surveillance revealed an issue that could impact effectiveness of the program. Resolution of this issue provides evidence that the program remains effective at managing aging effects for primary containment and its integral attachments.

A recent engineering system health report revealed no issues or findings that could impact effectiveness of the program.

The Containment lnservice Inspection Program has been effective at managing aging effects.

The Containment lnservice Inspection Program provides reasonable assurance that the effects of aging will be managed such that the applicable components will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

4.4.17. Instrument Air Quality Program Recent analyses revealed all parameters are maintained within acceptance criteria. Absence of degradation of instrument air quality provides evidence that the program is effective at ensuring that instrument air supplied to components is maintained free of water and significant contaminants, thereby preventing loss of material.

The Instrument Air Quality Program has been effective at managing aging effects. The Instrument Air Quality Program provides reasonable assurance that the effects of aging will be managed such that the applicable components will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

4.4.18. Oil Analysis Program A negative trend was noted in the lube oil analysis report for the P-40-1A diesel fire pump. Oil was drained, flushed, and refilled. A lube oil sample taken on the B emergency diesel generator indicated an abnormally high silicon level. Cause was determined to be gasket sealant materials used during the last EDG overhaul causing a temporarily high non-abrasive silicon level in the oil. Although acceptance criteria do not include an upper threshold for silicon, re-

ENN 2 .

ENGINEERING STANDARD ENN-EP-S-001 Rev. 0 Effective Date: 3/19/04 IWE General Visual Containment Inspection Applicable Site(s):

IP1 0 IP2 Ix] IP3 IxI JAF IxI PNPS [x1 VY IxI LPI Safety Related: X Yes No c

Prepared by: Glen Smith I

Approved by: Robert Pennv hdr Engineering Standar Date: 3/g/7

aEntwgy ENN NUCLEAR Engineering Standard ENN-EP-S-001 Revision 0 MANAGEMENT IWE General Visual Page -2 of MANUAL Containment Inspection Requirements and Revision Summary Revision No. Date Changes 0 Original issue t

ENN NUCLEAR MANAGEMENT Engineering Standard IWE General Visual I ENN-EP-S-001

-3 Revision 0 of 18 I MANUAL Containment Inspection TABLE OF CONTENTS Section -

Title 1.o PURPOSE .................................................................................... 4

2.0 REFERENCES

............................................................................. 4 3.0 DEFINITIONS ............................................................................... 5 I 4.0 RESPONSIBILITIES .................................................................... 7 1 5.0 DETAILS ...................................................................................... 7 6.0 RECORDS.................................................................................. I1 7.0 ATTACHMENTS ........................................................................ 12 ATTACHMENT 7.1, GENERAL VISUALEXAMINATION CHECKLIST FOR COATED ANDUNCOATED SURFACES ............13 A~ACHMEN 7.2,T IWE GENERAL VISUALEXAMINATION EVALUATION FORM ....................................... 14 ATTACHMENT 7.3, QUALIFICATION OF EQUIPMENT. .................... .I5 u

ATTACHMENT 7.4, PERSONNEL QUALIFICATION FORM.................... 16 3 A~ACHMEN 7.5, T GENERALVISUAL EXAMINATION CHECKLIST FOR BOLTINGASSEMBLIES .................................. 17 ATTACHMENT 7.6, GENERAL VISUAL EXAMINATION CHECKLIST FOR CONTAINMENT SUPPORTS ............................ 18

a Entwgy ENN NUCLEAR Engineering Standard ENN-EP-S-001 Revision 0 MANAGEMENT MANUAL IWE General Visual Page -4 of 18 Containment Inspection 1.0 PURPOSE 1.I This engineering standard is written to document the requirements to perform the IWE visual containment examination. The visual examination is performed to assess the general condition of the containment and to detect evidence of degradation that may affect structural integrity or leak tightness. This examination satisfies the requirements of the ASME Boiler and Pressure Vessel Code, 1992 Edition, 1992 Addenda,Section XI, Subsection IWE examination Category E-A, Item No. E l .I 1 and 1998 Edition up to 2000 Addenda,Section XI, Subsection IWE Examination Category E-A, Item No. E1.lO.

1.2 This engineering standard applies to personnel examining components identified in the site specific Containment In-service Inspection Program Plan (CIIPP) identified in references 2.14, 2.15, 2.21,2.22 and 2.23.

1.3 This procedure applies to class MC components consisting of the containment structure and connecting penetrations, appurtenances and parts that form the containment leak tight boundary. The components in the boundary includes:

1.3.1 Drywell and Drywell head 1.3.2 Suppression Chamber (Torus) exterior surface 1.3.3 Suppression Chamber vapor phase surface 1.3.4 Containment surfaces (including reinforcing structures such as stiffening rings, manhole frames, and reinforcement around openings)

E .Y 1.3.5 Suppression Chamber submerged surfaces (at Pilgrim for Detailed Visual Examination only) P e

1.3.6 Drywell vent system including vent piping, vent header, and downcomers (at Pilgrim Detailed Visual Examination only) 1.3.7 Drywell exterior and penetrations 1.3.8 Containment dome/wall/basement liner 1.3.9 Penetration sleeves 1.3.10 Personnel Air IocklEquipment Hatch 1.3.11 Fuel Transfer Tube

2.0 REFERENCES

2.1 10CFR50 Appendix J 2.2 ASME Boiler and Pressure Vessel Code,Section XI, Rules for In-service Inspection of Nuclear Power Plant Components, Subsection IWE and IWL, 1992 Edition, 1992 Addenda.

2.3 IP2 RR-49; NRC SER TAC NO. MA6949, dated 2/4/00 2.4 IP2 RR-43 and RR-48; NRC SER TAC NO. MA6235, dated 10/7/99 2.5 10 CFR50.55a, Codes and Standards 2.6 ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWE, Rules for In-service Inspection of Nuclear Power Plant Components, 1998 Edition, up to 2000 Addenda

Engineering Standard ENN-EPS-001 Revision 0 ENN NUCLEAR MANAGEMENT MANUAL IWE General Visual Page -5 of 18 Containment Inspection 2.7 IP3 RR-3-24; NRC SER TAC NO. MA 9757, dated 5/17/2001 2.8 American Society of Testing Material (ASTM) D 610-95, Standard Test Method for Evaluating Degree of Rusting on Painted Steel Surfaces.

2.9 ASTM D 660-93, Standard Test Method for Evaluating Checking of Exterior Paints.

2.10 ASTM D 661-93, Standard Test Method for Evaluating Degree of Cracking of Exterior Paints.

2.1 1 ASTM D 714-87, Standard Test Method for Evaluating Degree of Blistering of Paints.

2.12 ASTM D 772-86, Evaluating Degree of Flaking (scaling) of Exterior Paints.

2.13 Appendix A to Document ID #9.1450.044-S-001, Design Margins of the IP2 Containment STEEL LINER RAYTHEON Engineers & Constructors 2.14 2-RPT-00003, Rev. 0, IP2 Containment In-service Inspection Program, First Containment Interval (09/09/96-05/09/08).

2.1 5 IP3-RPT-VC-03071, Rev. 4, IP3 Containment In-service Inspection First Ten Year Class MC and CC Program 2.1 6 IP3-CALC-VC-03067, Reactor Containment-Minimum Liner Thickness 2.17 IP3-RPT-STR-03398, Rev. 0,ASME Section XI, IWE MC and Metallic Liners of Class CC Components Inspection

$1 2.1 8 EP-ML-2002-054, IWE Remote Visual Equipment Qualification, 7/17/02 2.1 9 Appendix E to Report SL-5408, Rev. 0, IS1Acceptance Criteria for Containment Liner B Thickness 2.20 ENN-DC-105; Configuration Management 2.21 PP 7024, VYContainment In-service Inspection Program (IWE) 2.22 JAF-RPT-PC-04088, JAF First Containment In-service Inspection Interval Program Plan 3 2.23 QA 20.03, PNPS First Ten Year Interval IWE Containment Inspection Program 2.24 QA IT1 50.90, Visual Examination of IWE Components 2.25 QA IT1 50.91, IWE Augmented Examinations 2.26 ENN-AD-103, Records management and Document Control Activities 3.0 DEFINITIONS 3.1 Accessibility - Visual access by line of sight with adequate lighting from permanent plant structures, equipment, or components, provided these surface areas do not require augmented examination.

3.2 -

Arc strike A loss or displacement of base metal, caused by the introduction of an electric current of sufficient intensity to change phase from solid to liquid. Arc strikes are rounded depressions in the base metal with some discoloration.

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Entwgy NUCLEAR MANAGEMENT MANUAL IWE General Visual Page -6 of 18 Containment Inspection 3.3 Blisters - Large or small, round or hemispherical projections of the coating from the surface and are either dry or liquid filled. The usual cause of the condition is the penetration of moisture through an area of poor adhesion.

3.4 Chalking - A surface phenomenon that appears soft or powdery. The cause is a breakdown in coating binder, which disintegrates, leaving the surface covered with pigment.

3.5 Checking - Small breaks in coating surfaces that are formed as coating ages and becomes harder and more brittle. Checking, for the most part, is a formulation related reaction, where the resins and pigments do not properly combine.

3.6 Chipping - Small void in coating system, caused by impact from foreign object.

3.7 Class MC components - This term applies to pressure retaining metallic components (including their integral attachments) within the boundaries established in the site specific CllPP for inspection under requirements of ASME Section XI, Subsection IWE as modified by 10 CFR 50.55a. For the purpose of this procedure, all metallic components subject to examination under IWE by 10 CFR 50.55a shall be referred to as Class MC components regardless of the design classification of the component.

3.8 Corrosion - The degradation of a substance (usually metal) or its properties because of a reaction with the environment.

3.9 Cracking (coating) - A non-linear line running through the coating system. Cracking is caused by expansion or contraction throughout the film (layer) and the film and the substrate (primer or metal surface).

3.10 Cracking (metal) - A base metal indication, fissure or separation, either linear or non-linear.

The crack will have length and depth.

3.11 Dent - The movementldisplacement of the base material from its original plane, without signs of metal stress or paintkoating distress.

3.12 Discoloration - Change in color of the coating, fading. Cause could be age, heat, dye or pigment bleeding or surface contamination (dye penetrant, grease, dirt, etc.).

3.13 Engineering Evaluation - An evaluation done for a reportable condition to determine if the structural integrity or leak tightness of the containment is jeopardized.

3.14 Flaking - (Also referred to as scaling or peeling) -the detaching of one layer of a coating from another or from the base metal. Flaking is generally preceded by cracking, checking, or blistering and is the result of loss of adhesion, usually due to stress strain factors.

3.15 General corrosion - An approximately uniform wastage of a surface of a component, through chemical or electrochemical action, free of deep pits or cracks.

3.16 General Visual Exam - A visual examination performed either directly or remotely to assess the general condition of the accessible primary containment surfaces and to detect evidence of degradation that may affect structural integrity or leak tightness.

3.17 Gouge - A loss of base metal caused by impact with a foreign object. Base metal may have sharp edges or be pushed to the far edge of the area of impact.

3.18 Integral attachments - Those structural attachments that have a containment pressure retaining function or are in the containment vessel's support load path and are welded, cast, or forged integrally to the inside or outside surface of the containment pressure boundary.

a Enter- ENN NUCLEAR Engineering Standard ENN-EP-S-001 Revision 0 MANAGEMENT MANUAL IWE General Visual Page -7 of @

Containment inspection 3.19 Leak-tightness - Ability of a component to maintain a prescribed maximum leakage rate under service conditions.

3.20 Non-integral attachment - (Also referred to as nonstructural, temporary or minor permanent attachments) those structural attachments that do not perform a containment pressure retaining function nor are in the containment vessels support load path. Non-integral attachments include such items as insulation supports, nameplates, locating and lifting lugs, lighting supports, shear plates or rings, retainer rings, and walkway supports.

3.21 corrosion that generally produces sharply defined open or closed cavities in a metal surface.

3.22 Relevant Condition - A condition observed during a visual examination that requires supplemental examination, corrective measure, and correction by repaidreplacement, or analytical evaluation.

3.23 Responsible Individual - Individual responsible for implementation of the containment IWE inspection program as described in the program plan, references 2.14, 2.15, 2.21, 2.22, and 2.23.

3.24 Rusting - The presence of oxidation in the form of iron oxide on steel.

3.25 Structural Integrity - The ability of a structure of component to withstand prescribed design loads.

3.26 Undercutting (coating) - Appears as a raised coated rust bloom. Undercutting is actually rust forming under the coating and acting as a wedge to push the coating off the metal surface. The undercutting may crack the coating surface.

3.27 Wear - A gradual removal of a substance caused by friction. In paint or coating the wear may appear as a different color or thickness. In base metal the wear areas may appear brighter in appearance or as a low area.

4.0 RESPONSIBILITIES 4.1 WPO Enaineerina Prosrams or Site Enaineerinq has the responsibility to develop and maintain the Containment IWE program. This may include establishing basis for program content, issuing inspection scope and providing implementation support (scheduling, coordination of inspection, maintaining inspection procedures, etc.). The examination will be performed at intervals specified in the site specific CIIPP.

4.2 The Responsible Individual (RI), or designee, from the Engineering Programs group or Site Engineering has the responsibility to evaluate the examination results. The individual is experienced in evaluating the condition of Class MC components.

4.3 Enaineerina Personnel and/or Certified Inspectors shall perform the examination in accordance with the requirements of Table IWE-2500-1 as delineated in the site specific CIIPP. Inspectors shall be qualified in accordance with site-specific requirements.

5.0 DETAILS 5.1 General Instructions

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ENN NUCLEAR Engineering Standard ENN-EP-S-001 Revision 0 MANAGEMENT 18 MANUAL

\WE General Visual Page -8 of Containment Inspection 5.1.1 The General Visual examination shall be performed either directly or remotely with sufficient illumination and resolution to assess the general condition of the accessible Containment surfaces (inside and outside). The examination shall be documented using Attachments 7.1, 7.5, and 7.6 or site-specific documentation.

Equipment demonstration and validation reports should be maintained or referenced in the work order; in the inspection report identified in section 6.0 or other appropriate site process.

5.1. I.1 Inaccessible areas are not required to be examined unless specifically 1  :

identified as an inaccessible area requiring examination by either the site specific CllPP or the RI. I I

5.1.1.2 Accessible areas requiring examination are defined in the site specific CIIPP.

5.1.1.3 ISI-IWE drawings in the site specific CllPP define the components and boundaries for inspection.

5.1.2 Examiners shall visually examine non-coated and coated surface areas to be inspected and document the examination results, which require evaluation on the IWE General Visual Examination Evaluation Form (Attachment 7.2).

5.1.2.1 Painted or coated areas shall be examined for evidence of flaking, blistering, peeling, discoloration, and other signs of distress.

5.1.2.2 Non-coated areas shall be examined for evidence of cracking, discoloration, wear, pitting, excessive corrosion, gouges, surface discontinuities, dents, and other signs of surface irregularities.

PY Note: Bolted connections need not be disassembled for performance of general Visual examination.

5.1.2.3 Pressure retaining bolting (if required in site CIIPP) shall be examined for defects that may cause the bolted connection to violate either leak tightness or structural integrity.

5.1.3 If no indications exceeding the inspection criteria of Sections 5.3, 5.4, 5.5 and 5.6 are noted, the examination is complete. The closeout of the General Visual examinations will be documented in the form of Work Orders written expressly for the performance of the General Visual examinations or other site-specific documentation.

Following completion of the examinations the detailed results should be documented in an inspection report or other site-specific process. This report will contain a summary of the inspection, including Attachments 7.1 through 7.6 and any pictures, videotapes, CR's, etc. It will cover the IWE examinations performed during the period.

5.1.4 If the examiners note indications which need further evaluation:

5.1.4.1 The IWE General Visual Examination Evaluation Form (Attachment 7.2) shall be completed. The forms shall be immediately brought to the Rl's attention.

The RI shall evaluate the results and determine acceptability; or request a

Engineering Standard ENN-EP-S-001 Revision 0 ENN NUCLEAR MANAGEMENT MANUAL IWE General Visual Page -9 of 18 Containment Inspection detailed visual, VT-1, examination (or additional examinations as determined by the RI, i.e. UT).

Note: The objective of this examination is to provide sufficient data to the RI to conduct an evaluation. When a detailed visual, VT-1, (or additional examinations) are required, access to the area to be examined must be sufficient to allow for valid measurements of the dimensional data reauired for the evaluation.

5.1.5 At the direction of the RI, the examination personnel will note the condition of the surfaces requiring examination. Areas of specific interest may be photographed and/or videotaped. This will serve as a reference condition to be compared with the results of the next inspection.

5.2 Evaluation of Results Note: The inspection criteria are presented as a guide for IWE examination personnel to determine when an existing condition is acceptable or requires further evaluation. The guide is not intended to be all-inclusive. It relies upon the inspectors' general knowledge of material conditions. When a questionable condition is encountered, the IWE examination personnel should always be conservative and request an evaluation.

5.2.1 The inspection criteria (Sections 5.3, 5.4, 5.5 and 5.6) form the basis for accepting existing conditions in plants. These inspection criteria have been evaluated and acceptable by calculation or code and do not deter or compromise the structural integrity of the primary containment pressure boundary.

5.2.2 Indications which do not exceed the inspection criteria are not required to be reported and are considered acceptable without the Rl's review.

5.2.3 The RI will determine if the conditions exceeding the inspection criteria are acceptable. A Condition Report (CR) shall be generated for all unacceptable conditions.

5.2.4 Acceptance evaluation for conditions exceeding the inspection criteria will be in accordance with site-specific requirements. Reference drawings and previous examination results should be utilized as necessary. The RI shall document the results of the acceptance review of the General Visual and, if required, detailed visual, VT-1, examination results.

5.3 Uncoated Surface Areas 5.3.1 If any of the relevant conditions listed below are present, further evaluation may be required. Initiate a CR as required by section 5.2.3. The condition must be recorded on the IWE General Visual Examination Evaluation Form (Attachment 7.2) or other site-specific document and forwarded to the RI for acceptance review.

5.3.1.1 Cracking in base metal

aEntwgy ENN NUCLEAR Engineering Standard ENN-EP-55-00? Revision 0 MANAGEMENT MANUAL IWE General Visual Page -

IO of 9 Containment Inspection 5.3.1.2 Discoloration resulting from age, heat, of corrosion 5.3.1.3 Wear that could exceed 10% of the nominal wall thickness 5.3.1.4 Pits, dents, or gouges of the base metal with depth that could exceed 10% of the nominal wall thickness of the material (e.g. 0.025 inches for a 0.25 inch nominal thickness) 5.3.1.5 Corrosion, which results in discernable, base metal loss that could exceed 10 of the nominal wall thickness.

Oh i

5.3.1.6 Discernable bulges 5.3.1.7 Arc strikes I

5.3.1.8 Other conditions such as mechanical damage causing discernable 1 .

degradation of the base metal f .

5.4 Coated Surface Areas 5.4.1 If any of the relevant conditions listed below are present, further evaluation may be required. Initiate a CR as required by section 5.2.3. The condition must be recorded on the IWE General Visual Examination Evaluation Form (Attachment 7.2) or other site-specific document and forwarded to the RI for acceptance review.

5.4.1.1 Any of the conditions listed in Section 5.3.1 for uncoated surfaces 5.4.1.2 Absence of coating 5.4.1.3 Blisters equal to or greater than size No. 6 as specified in ASTM D 714-87 5.4.1.4 Checking equal to or greater than standard No. 2 as specified in ASTM D 660-93 5.4.1.5 Cracking equal to or greater than standard No. 6 as specified in ASTM D 661-93 5.4.1.6 Flaking equal to or greater than standard No. 6 as specified in ASTM D 772-86 5.4.1.7 Rusting equal to or greater than Rust Grade 7 as specified in ASTM 0 610 -

95 5.4.1.8 Other distress to the coating that may indicate degradation of the underlying base metal 5.5 Bolting Assemblies (As required in site CIIPP) 5.5.1 If any of the relevant conditions listed below are present, further evaluation may be required. Initiate a CR as required by section 5.2.3. The condition must be recorded on the IWE General Visual Examination Evaluation Form (Attachment 7.2) or other site-specific document and forwarded to the RI for acceptance review.

5.5.1.1 Bending, twisting, stretching or deforming of bolts or studs 5.5.1.2 Missing or loose bolts, studs, nuts, or washers

m "Entergv ENN NUCLEAR Engineering Standard ENN-EP-S-001 Revision 0 MANAGEMENT MANUAL IWE General Visual Page -I1 of 18 Containment Inspection 5.5.1.3 Fractured bolts, studs, or nuts 5.5.1.4 Degradation of protective coatings on bolting surfaces 5.5.1.5 Evidence of coolant leakage near bolting 5.5.1.6 Bolting degradation 5.5.1.7 Localized excessive corrosion 5.5.1.8 Misalignment of connection or bolting 5.6 Containment Supports (As required in site CIIPP) 5.6.1 If any of the relevant conditions listed below are present, further evaluation may be required. Initiate a CR as required by section 5.2.3. The condition must be recorded on the IWE General Visual Examination Evaluation Form (Attachment 7.2) or other site-specific document and forwarded to the RI for acceptance review.

5.6.1 .I Any signs of surface irregularities 5.6.1.2 Deformations or structural degradations of fasteners, clamps or other support items, and loss of integrity at bolted or welded connections.

5.6.1.3 Missing, detached, or loose support parts and bolting.

5.6.1.4 Arc strikes, weld spatter, paint, scoring, roughness, or general corrosion on close tolerance, machined or sliding surfaces.

5.6.1.5 Misalignment of supports 5.6.1.6 Improper clearances of guides and stops 5.6.1.7 Wear which visibly reduces the cross-sectional area of the support 5.6.1.8 Abnormal corrosion which reduces the load bearing capacity of the support 5.6.1.9 Crack like or linear sulface flaws 5.6.1 . I O Evidence of clamp or non-integral attachment movement, damage, or movement of component insulation due to support movement 6.0 RECORDS An ASME,Section XI, IWE MC Components Inspection Report or other site-specific process shall be used to document all examinations, findings, and evaluations. If a report is written, it shall be referenced in the Work Orders used to implement the examinations.

The report shall include Attachments 7.1 through 7.6.

The ASME,Section XI, IWE MC Component Inspection Report is a controlled record, and is transmitted to Administrative Services in accordance with ENN-AD-103C-105, "Document Control and Configuration Management Activities".

Engineering Standard ENN-EP-S-001 Revision 0 ENN NUCLEAR MANAGEMENT IWE General Visual Page 12 of 18 MANUAL Containment Inspection

~

Note: Site approved equivalents are acceptable for use in lieu of the following attachments.

7.1 General Visual Examination Checklist for Coated and Uncoated Surfaces 7.2 IWE General Visual Examination Evaluation Form 7.3 Qualification of Equipment 7.4 Personnel Qualification Form i

7.5 General Visual Examination Checklist for Bolting Assemblies 7.6 General Visual Examination Checklist for Containment Supports I

mEnterggy AITACHMENT7.1 ENN NUCLEAR MANAGEMENT MANUAL GENERAL 1 Engineering standard IWE General Visual Containment Inspection VISUALEXAMINATION CHECKLIST ENN-EP-S-001 Page -

13 FORCOATEDAND UNCOATED Revision 0 of 18 SURFACES Sheet 1 of 1 Yes = exceeds the recording criteria No = does not exceed the recording criteria Examination performed by: Date:

Quality Record

I Engineering Standard ENN-EP-S-001 Revision 0 ENN NUCLEAR MANAGEMENT MANUAL IWE General Visual Page -

14 of 18 Containment Inspection ATTACHMENT 7.2, IWE GENERAL VISUALEXAMINATIONEVALUATION FORM Sheet 1 of 1 Component Number or Zone Number (*)

Existing Condition Being Evaluated Evaluation of Existing Condition .'L 1 Evaluation Performed By:

Evaluation Approved By:

Quality Record

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ENN NUCLEAR MANAGEMENT I Engineering Standard ENN-EP-S-001 Revision 0 I MANUAL IWE General Visual Containment Inspection 1 Page 15 of 18 ATTACHMENT 7.3 QUALIFICATIONOF EQUIPMENT I

Introduction:

Demonstration of remote examination equipment is required to be performed prior to executing General Visual examinations when the use of remote equipment is required. This demonstration needs to be i.-f performed once at the beginning of this examination to qualify the light source and the remote equipment used. The commitments of each site specific Relief Request or Technical Position are to be utilized when

'I qualifying the equipment.

Performance Qualification:

Type of equipment used:

Maximum examination distance:

Description of demonstration:

Demonstration distance:

Demonstration performed by: Date:

Demonstration witnessed by (ANII): Date:

Quality Record

Engineering Standard ENN-EP-S-004 Revision 0 ENN NUCLEAR MANAGEMENT MANUAL IWE General Visual Page -

16 of Containment Inspection z

ATTACHMENT p___I 7.4

- P - PERSONNEL QUALIFICATION FORM Inspection Personnel Qualification Form for General Visual Examination Name:

Education:

Experience:

Eye Exam:

On the basis of the above, I have determined that the subject individual is capable of performing General Visual Examinations at IP2, IP3, JAF, Pilgrim, and/or Vermont Yankee as required by ASME Section XI .I .

1992 Edition, 1992 Addenda, or 1998 Edition, no Addenda, Subsection IWE, Subparagraph IWE-3510.1 This qualification expires one year from the date of the eye examination.

Responsible Individual Date Quality Record

Engineering Standard ENN-EP-S-001 Revision 0 ENN NUCLEAR MANAGEMENT MANUAL IWE General Visual Page -

17 of 18 Containment Inspection ATTACHMENT 7.5 GENERAL VISUAL EXAMINATION CHECKLIST FOR BOLTING ASSEMBLIES Yes = exceeds the recording criteria Examination performed by: Date:

Quality Record

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• I -

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18 of 18 Containment Inspection I I I 1

-ATTACHMENT 7.6 - GENERAL VISUAL EXAMINATION I__

CHECKLIST FOR CONTAINMENT SUPPORTS Yes = exceeds the recording criteria Comments Examination performed by: Date:

Ref. Drawings for JAF: 3.72-6C, 3.72-9E, and 3.72-17 Quality Record

VERMONT YANKEE NUCLEAR POWER STATION PROGRAM PROCEDURE PP 7024 REVISION 4 CONTAINMENT INSERVICE INSPECTION PROGRAM W)

USE CLASSIFICATION: INFORMATION RESPONSIBLE PROCEDURE OWNER: Manager, Systems Engineering REQUIRED REVIEWS I Yes/No E-Plan I 10CFRSO.

1 ILPC No.

Effective Date I Affected Pages n 1 01/24/06 3,4, & 12 of 13; Table 1 Pgs 5 , 6 & 7 of 21 I ImDlementation Statement: NIA I Effective Date: 0712 1/05 PP 7024 Rev. 4 Page 1 of 13

TABLE OF CONTENTS 1.0 PURPOSE, SCOPE, AND DISCUSSION ................................................................................... 3 2.0 DEFINITIONS ................,..- ............................................. ,.................. ............ 6 3.0 PRIMARY RESPONSIBILITIES ................................................................................................. 7 4.0 PROCEDURE............... .,................................................................................. ............... 8

5.0 REFERENCES

AND COMMITMENTS .................................................................................. 11 6.0 FINAL CONDITIONS ..,,............................................................................................................ 12 7.0 ATTACHMENTS .........-, ............................................................................................................. 13 8.0 QA REQUIREMENTS CROSS REFERENCE........................................................................ 13 1

PP 7024 Rev. 4 Page 2 of 13

1.o PURPOSE, SCOPE, AND DISCUSSION 1.1. Purpose ENN-DC-120, ASME Section XI Code Promams, in concert with PP 7024 implements the requirements for the Fourth Ten-Year Interval Containment Insavice Inspection Program (Program) in accordance with Title 10 Code of Federal Regulations, Part 50, Section 50.55a, Codes and Standards (10CFR50.55a) dated September 26,2002, pertaining to inspection and testing of the Primary Containment for the three periods of the Interval.

1.2. Scope The Primary Containment System is a GE Mark I Pressure Suppression Containment System.

The system consists of a Drywell (housing the reactor vessel and reactor coolant recirculation loops), a Pressure Suppression Chamber (housing a water reservoir), and the connecting vent system between the Drywell and the water pool, isolation valves, and containment cooling systems. The code of construction for the containment structure is the ASME Section 111, 1965 WNinter Addenda.

fi f 1.3. Discussion The Code of Record (Code) for the Program is the American Society for Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components (ASME Section XI - 1998 Edition with the 2000 Addenda). The utilization of a single code edition ensures a uniform application of the Code requirements by the synchronizing the four implementing programs (i.e., PP 7015, PP 7034, AP 0070, and PP 7024).

The Code of Record was modified by the adoption of subsubarticle IWA-4540 of the 2003 Addenda of the ASME Section XI - 2001 Edition. The adoption was approved by the NRC Safety Evaluation (NVY 05-094) dated July 25,2005.

ENVY developed PP 7024, Containment Inservice Inspection Promam CITE) (i.e., the Program) to comply with the September 9,1996 mandate of 1 OCFR50.55a requiring licensees to incorporate Subsection IWE of ASME Section XI 1992 with the 1992 Addenda into the Inservice Inspection Program. The Initial IWE Interval ran concurrent with the Third Ten-Year Inservice Inspection Interval. Both the Initial TWE Interval and the Third Ten-Year Inservice Inspection Interval schedules and fkequencies are based on IWA-2432 of the Code, Inspection Program Byconsisting of four ten-year intervals with three periods per interval.

August 3 1,2003 ends the Third Ten-Year Inservice Inspection Interval and has been established as the end of the Initial W E Interval, midway though the Second Period. As of September 1, 2003, the Program is aligned with the Fourth Ten-Year Inservice Inspection Interval (Fourth ISI).

PP 7024 Rev. 4 Page 3 of 13 LPC #I

The Program continuity (periodicity and frequency) has been maintained by aligning the remaining Initial IWFi Interval Second Period (RFO 24) with the Fourth IS1 First Period (RFO 24). During the Initial IWE Interval First Period,100% of the required examinations were completed. Additionally, no examinations were scheduled or conducted during the first portion of the Second Period (RFO 23) of the Initial IWE Interval. The relative interval and period starting and ending dates are outlined in the following matrix:

Period 1 Period 2 I Period3 1

Interval 2'd May 1, 1983 S e p 1,1986 sep 1, 1990 Initial IWEInterval Interval to to to Aug 31,1986 Aug 31,1990 Aug 31, 1993 Period 1 Period 2 Period 3 3'd Sep 1,1993 S e p 1, 1996 sep 1,2000 S e p 9,1998 S e p 9,2001 Sept 9,2005 Interval to Aug 31, 1996 I to Aug 31,2000

[FWO 19,20,21]

I to to Aug 31,2003 S e p 8,2001 to S e p 8,2005

[RFO 22,233 [RFO 21,223 [RFO 23,24,25] [RFO 26,271 to S e p 8,2008 4'b Sep 1,2003 Sep 1,2006 sep 1,2010 Interval to to to Aug 31,2006 Aug 31,2010 Aug 31,2013 '

[RFO 24,251 [RFO 26,27,28] [RFO 29,301 1

The 1" IS1 Interval was five years long, due to the delay in the development and implementation of ASME Section XI.

2 The end date of the lstIS1 Interval was extended by five months, in accordance with IWA-2430(c), to permit inspections concurrent with a plant reheling outage. Consequently, the subsequent intervals and periods were adjusted forward five months.

3 The end date of 2"d IS1 Interval - Period 1 was extended by four months to reflect the 1985-86 pipe replacement and reheling outage (9 months duration) in accordance with IWA-2430(e). Consequently, the subsequent intervals and periods were adjusted forward four months.

4 The Initial IWEInterval ended on August 3 1,2003 in order to align the Program with the other ASME Section XI programs.

5 ENVY'S operating license expires March 21,2012.

The Program scope has been adjusted as required to comply with the Code. Two (2)

Examination Categories have been retained from the Initial IWEi Interval Program: containment surfaces (E-A) and containment surfaces requiring augmented examination (E-C).

Parts scheduled for examination by percentage to complete for each period in the qfhInterval are PP 7024 Rev. 4 Page 4 of 13 LPC #1

The Program incorporates the following specified limitations and modifications listed in 10CFR50.55a dated Sept. 26,2002:

VT-1 and VT-3 visual examinations must be conducted in accordance with IWA-2200.

Personnel conducting VT-1 or VT-3 visual examination meth&hall be qualified in accordance with TWA-2300.

VT-1 visual examinations will be conducted in lieu of the Detailed Visual examinations of IWE-23 1O(c) for Examination Category E-C Item E4.11.

VT-3 visual examinations will be conducted in lieu of the General Visual examinations of IWE-23 lo@) for Examination Category E-A Items El. 12 and E l .20 and specifically for the bolting of Item E l . 11.

i i e Flaws or degradation identifieadwing the conduct of the VT-3 visual examination of iI Containment bolting, must be examined in accordance with the VT-1 visual examination method. The criteria in the material sDecification or IWT3-3517.1 must be used to 1..3 evaluate the Containment bolting or degradation.

An evaluation of the acceptability of inaccessible areas shall be conducted when conditions exist in accessible areas that could indicate the presence of or result in degradation to such inaccessible areas. For each inaccessible area identified, the following shall be included in the IS1 Summary Report as required by IWA-6000:

1. A description of the type, estimated extent, and conditions that led to the d

degradation;

2. An evaluation of each area, including the result of the evaluation;

3. A description of the corrective actions, if necessary.

The Program incorporates the alternative requirements for containment inspection and testing as outlined in Regulatory Guide 1.147, as needed. Presently, the following Code Cases are being implemented:

N-532-1 , Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission The Program additionally incorporates the alternative requirements for containment inspection and testing, or corrective measures as outlined in relief requests. Presently, the following relief requests are being implemented:

None The Program does not have to be submitted to the NRC staff for approval. However, the program elements and the required documentation must be maintained on site for audit.

PP 7024 Rev. 4 Page 5 of 13

2.0 DEFINITIONS 2.1. Accessible Surface Area: An area capable of direct or remote visual examination from existing vantage points.

2.2. Aumented Examination Area: Surface areas likely to experience accelerated degradation and aging.

2.3. A u x i l i Lwhting:

~- An artificial light source used as a visual aid to improve viewing conditions and visual perception.

2.4. Coating

Materials (including paints) applied that are used to protect an ASME Code Class MC component against corrosion.

2.5. Component

Metallic vessels, liners, appurtenances, etc. that have been classified as ASME Code Class MC. i I

i 2.6. Containment Non-Structural and Temporary Attachments: Attachments that do not perform a pressure retaining function nor are in the component's supports load path including such items as i insulation supports, nameplates, locating and lifting lugs, lighting supports, walkway supports, etc.

2.7. (Containment Structural) Intearal

Attachment:

Attachments that have a containment pressure retaining function or are in the containment vessel support load path that are welded, cast, or forged integrally to the inside or outside surface of the containment pressure retaining component.

2.8. Defect

A flaw (imperfection or unintentional discontinuity) of such size, shape, orientation, 8':

location, or properties as to be unacceptable.

2.9. Inaccessible Surface Areas: Those areas that are embedded or otherwise obstructed from direct or remote visual examination. Some examples include but are not limited to areas:

e that are permanently embedded in concrete 0 that are covered and permanently sealed by insulation to prevent the intrusion of moisture L 0 that are sealed by a moisture barrier that is designed to prevent intrvsion of moisture i 0 that access (to conduct the visual examination) is permanently obstructed for the examination personnel and/or equipment PP 7024 Rev. 4 Page 6 of 13

3.0 PRIMARY RESPONSIBILITIES This procedure defines the organizational responsibilities as are currently being implemented at Vermont Yankee. As part of the transition to the ENN programs and procedures, the ISI-IWE program ownership responsibilities will be assumed by PJPO Engineering Programs in accordance with ENN-DC-120, ASME Section XI Code Programs. When the transition plan is developed, in accordance with ENN-PL155, Change Management Policy, PP 7024 will be revised accordingly.

3.1. Manager, System Engineering, is responsible to ensure:

3.1.1. Implementation of AP 0098, Appendix A, for the Program.

3.1.2. The Program is defined and maintained per the requirements of 10CFR50.55a,in accordance with ASME Section XI - 1998 Edition through the 2000 Addenda, in compliance with Regulatory Guide 1.147 and approved relief requests.

3.1.3. The assignment of the Containment Inservice Inspection (rWE)Coordinator, the Program owner and Responsible Individual of IWE-2320.

3.1.4. Approval of changes to the Program (Le., PP 7024 and implementing procedures).

3.2. Manager, Design Engineering, is responsible to ensure:

3.2.1. Control of the Design Basis documentation that affects the Program.

3.2.2, Design compliance with the requirements of the Program.

61 3.3. Manager, Planning and Scheduling Outage, is responsible to ensure:

ra 3.3.1. Work Order planning complies with the requirements of the Program.

P 3.3.2. Outage planning complies with the requirements of the Program.

F 3.4. Inservice Inspection (ISI) Coordinator is responsible to assimilate VT-1 and VT-3 visual examination results for inclusion, as needed, in the N I S I Summary Reports or the Owner's 1 Activity Report Form OAR-1.

3.5. ASME Section XI Repair and Replacement Program (RRP) Coordinator is responsible to assimilate VT-1 , VT-2, and VT-3 visual examination results for inclusion, as needed, in the NIS-2 or MS-2A Summary Reports.

3.6. Primary Containment Leak Rate Testing Program Coordinator is responsible to conduct the requisite testing in accordance with 10CFR50 Appendix J.

PP 7024 Rev. 4 Page 7 of 13

IP I

-Y I -

3.7. Containment Inservice Inspection Coordinator (IWECoordinator and Responsible Individual of IWE-2320) is responsible to ensure:

3.7.1. Implementation and administration of the Program including the maintenance and revision of Containment Inservice Inspection Program (IWE), PP 7024.

E 3.7.2. Coordination of the periodic and interval required General, VT-1 and VT-3 visual examinations.

3.7.3. Evaluations, as required, by the Program.

3.7.4. Provide VT-1, VT-3, and the pressure testing with VT-2 visual examination results as input to the IS1 and RRP Coordinators for the development of the NIS-1, NIS-2, NIS-2A or OAR-1 Summary Reports.

i 3.7.5. Assignment of certified examiners for conducting General, VT-1, VT-2, and VT-3 visual examinations. Examiners are certified in accordance with ENN-NDE-2.12, Certification of Visual Testing (VT) Personnel, or other ENVY approved procedures.

1 I

3.7.6. Define areas for augmented examination and revise Table 2 as necessary.

3.7.7. Evaluate components whose examination results reveal flaws or areas of degradation that do not meet the acceptance standards.

4.0 PROCEDURE 4.1. Administration I

The Program provides for two processes: the first is for the performance of Code required I periodic and interval examinations for Category E-A components; the second is for the examination for Category E-C augmented components as required by IWE-1240.

4.1.1. Program Procedure e The Program text contains general information common to the functions.

e Appendix A - Containment Inservice Inspection Program (WE) Relief Requests e Table 1 - Examination Category E-A e Table 2 - Examination Category E-C - presentIy blank PP 7024 Rev. 4 Page 8 of 13

4.1.2. Implementing Procedures ENN-EP-001, IWEGeneral VisuaI Containment Inspection, is used to execute the examination process for Category E-A, Items El. 1 1 and El .30.

ENN-NDE-10.01, VT-1 Examination, is used to e x e c u t e e examination process for Category E-C, Item E4.11.

0 EW-NDE-10.03, VT-3 Examination, is used to execute the examination process for Category E-A, Items E l . l l (bolting), E1.12, andE1.20.

I 4.1.3. Records The Program administrative and implementing procedures, analyses, evaluations, calculations, visual examination results, and other records required to define and execute the Program are retained per AP 6806 and AP 6807. Copies of selected records shall be retained in the IWE Coordinator files.

'1

.-. 4.1.4. Reports Reports will be generated as required per the Code. A copy of the report shall be retained in the IWE Coordinator files.

4.1.5. Reportability Conditions adverse to Technical Specifications must be assessed for Emergency Notification System reporting under 10CFR5O.?2(b)( l)(ii) and (b)(2)(i), and for a Licensee Event Report under lOCF'RSO.73(a)(2)(ii).

4.1.6. Evaluations The Program requires evaluations for various reasons (e.g., for the requisite Post Modification and Maintenance Testing requirements, etc.). These evaluations shall be documented and a copy retained in the IWE Coordinator files.

PP 7024 Rev. 4 Page 9 of 13

4.1.7. Examinations 0 General visual examinations will be conducted in accordance with the criteria of ENN-EP-001 at the frequency specified in Table 1.

0 VT-3 Examination will be conducted in accordance wit.-ENN-NDE-10.03 at the frequency specified in Table 1.

0 VT-1 Examinations will be conducted in accordance with ENN-NDE-10.01 at the frequency specified in Table 2.

0 Examination results that exceed the acceptance criteria shall be documented in I accordance with EN-LI- 102.

4.2. Program Positions i

4.2.1. The Program excludes process piping and systems penetrating the Primary Containment.

The excluded process piping and systems are addressed in PP 7015, Vermont Yankee I I

Inservice Inspection Program; PP 7034, Inservice Inspection Pressure Test Program; AP 0070, ASMB Section XI Repair and Replacement Procedure, andor PP 7006, i

(

b Primary Containment Leak Rate testing Program. Boundary between the containment and piping is:

0 The first circumferential joint exclusive of the connecting weld in welded connections 0 The face of the first flange in bolted flange connections 0 The first threaded joint in mechanical connections 4.2.2. The Primary Containment System is a GE Mark I Pressure Suppression Containment System consisting of a Drywell, a Pressure Suppression Chamber (Torus), and the connecting Vent System between the Drywell and the Torus.

The Primary Containment System is subject to Table Iw)3-2500-1 Examination Category E-A. Table IWE 2500-1 is further divided into:

0 Item El. 11, Accessible Surface Areas - applicable to the Drywell and Torus e Item E1.12, Wetted Surfaces of Submerged Areas - applicable to the Torus 0 Item E1.20, BWR Vent System Accessible Surface Areas - applicable to the eight circular pipes connecting the Drywell to the Torus; the eight Jet Deflectors; the Vent Header interconnecting piping; the ninety-six downcorners; and the ten Vacuum Breakers including the interconnecting piping from the Torus to the Vent S ystem 0 Item E1.30, Moisture Barriers - applicable to the Drywell shell to Concrete floor intersection at elevation 238' PP 7024 Rev. 4 Page 10 of 13

4.2.3. Paint and coating inspections for removal and replacement of coating or paint are included in the Program inspection requirements. An examination of painted or coated surfaces is requited to indicate the condition of the substrate. The examinations shall be included in the applicable work documents for the paint or coating surface preparation and application. Following the application of new paint or coatings the area must be rebase-lined to establish the condition of the substrate in the area-ofnew application.

0 Surfaces subject to general visual and VT-3 Examinations will be examined with paint and coatings in an "as is" condition of lWE-2600(a).

a Surfaces subject to VT-1 Examinations will be examined with paint and coatings in an "as is" condition of WE-2600 (a) or if required in accordance with IWE-2600@)

4.2.4. Repair and replacement activities shall be conducted in accordance with A p 0070 and inspected and documented per the requirements of the Code.

4.2.5. During the implementation of the program, the moisture barrier required per drawing 5920-233 at the intersection of the interior of the drywell shell and the concrete floor at elevation 238' was determined to have been degraded and effective reconfiguration of the seal was not performed (ER 99-1954). A minor modification was developed (MM2000-010) to install a replacement seal. The drywell shell and the concrete floor were stripped of all paint, coatings, and sealant for approximately a six inch band either side of the intersectingjoint. The drywell shell was examined by VT-3, VT-1, and ultrasonic measurement processes. The shell was determined to be satisfactory in accordance with the criteria of VYC-2043. The drywell shell was coated and the seal was replaced. Though not required by the Code of Record, the moisture barrier will be m examined each refueling outage until RFO 27. Table 1 has been annotated to reflect this

!4J program position.

4.2.6. Inaccessible Areas will be listed in Table 1, as identified

5.0 REFERENCES

AND COMMITNENTS 5.1. Technical Specifications and Site Documents 5.1.1. Technical Specification Section 3.6.EI4.6.E 5.2. Administrative Limits 5.2.1. None PP 7024 Rev. 4 Page 11 of 13

5.3. Codes, Standards, and Regulations 5.3.1. ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through 2000 Addenda 5.3.2. Code of Federal Regulations, 10CFR50.2 Definitions 5.3.3. Code of Federal Regulations, 10CFR50.55a dated September 26,2002 5.3.4. Code of Federal Regulations, IOCFRSO Appendix J 5.3.5. Regulatory Guide 1.147, Inservice Inspection Code Case Applicability 5.3.6. Regulatory Guide 1.26, Rev 3, Quality Group Classifications and Standards for Water-,

Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants 5.3.7. NS-22, Draft 4, Rev 1, Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants 5.3.8. Safety Evaluation by the Office Nuclear Reactor Regulation,

Subject:

Safety Evaluation of Request to use Later Addenda of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (Code) - Vermont Yankee Nuclear Power Station CNVy 05-094 dated July 25,2005) 5.4. Commitments 5.4.1. None 5.5. Supplemental References 5.5.1. EN-AD-103, Document Control and Records Management Activities 5.5.2. EN-LI-102, Corrective Action Process 5.5.3. ENN-EP-001, W E General Visual Containment Inspection 5.5.4. ENN-NDE-2.12, Certification of Visual Testing (VT) Personnel 5.5.5. ENN-NDE-10.01, VT-1 Examination 5.5.6. ENN-NDE-10.03, VT-3 Examination 5.5.7. AP 0095, Plant Procedures 5.5.8. AP 0098, Procedure Writers Guide 5.5.9. AP 6806, Transfer of Quality Assurance Records to RIMS 5.5.10. PP 7006, Primary Containment Leak Rate Testing Program 6.0 FINAL CONDITIONS 6.1. The Program Owner shall ensure that the required information from the Containment Inservice Inspection Program (WE) is included in the NIS-1 ,NIS-2, NIS-2A Reports or OAR-1.

6.2. QA records shall be collected, stored and processed in accordance with PP 7801, Quality Assurance Records Program, requirements for QA record handling and storage.

PP 7024 Rev. 4 Page 12 of 13 LPC #1 I .

7.0 ATTACHMENTS 7.1. Appendix A - Containment Inservice Inspection Program (lWE) Relief Requests 7.2. Table 1 - ASME Code Class MC Examination Category E-A 7.3. Table 2 - ASME Code Class MC Examination Category E-C 8.0 QA REQUIREMENTS CROSS REFERENCE Source Document Section Procedure Section 8.1 QMM B.1.c All 8.2 QMM B.3.c All 8.3 QMM B .8.a-f All I

8.4 QMM 3.9.b 4.1.7 1 1 It i I.r I '

R A

PP 7024 Rev. 4 Page 13 of 13

APPENDIX A Containment Inservice Inspection Program (IWE) Relief Requests 10CFR50.55a Request Number:

Page Intentionally Left Blank Appendix A PP 7024 Rev. 4 Page 1 of 1

TABLE 1 ASME CODE CLASS MC EXAMINATION CATEGORY E-A RFO TORUS and TORUS PENETRATIONS s c m m EXAMINATlON ITEM DRAWING EXAMINATION, PERIOD' CATEGORY E-A NUMBER DESCRlIYTION NUMBER METHOD 1 2 3 REMARKS El.ll Bay 1 6202-200 General 24 27 29 Accessible areas of E1.12 I 5920-42 I Visual VT-3 I l l 27i interior and exterior surfaces.

Wetted surfaces of submerged areas.

El.ll Bay 2 6202-200 General 24 27 29 Accessible areas of 5920-42 Visual interior and exterior I surfaces.

~ ~.

El. 12 VT-3 27i Wetted surfaces of I submerged areas.

El.ll Bay 3 6202-200 General 24 27 29 Accessible areas of 5920-42 Visual interior and exterior I surfaces.

E1.12 VT-3 27i Wetted surfaces of

, submerged areas.

El.ll Bay 4 6202-200 General 24 27 29 Accessible areas of I 5920-42 Visual interior and exterior I

surfaces.

E1.12 VT-3 27i Wetted surfaces of t

submerged areas.

El.ll Bay 5 6202-200 General 24 27 29 Accessible areas of 592042 Visual interior and exterior I

surfaces.

E1.12 VT-3 27i Wetted surfaces of submerged areas.

EL11 Bay 6 6202-200 General 24 27 29 Accessible areas of 592042 Visual interior and exterior I surfaces.

El. 12 VT-3 27i Wetted surfaces of submerged areas.

El.ll Bay 7 6202-200 General 24 27 29 Accessible areas of 5920-42 Visual interior and exterior I I I surfaces.

E1.12 VT-3 I 27i Wetted surfaces of submerged areas.

Table 1 PP 7024 Rev. 4 Page 1 of 21

TABLE 1 (Continued)

RFO TORUS and TORUS PENETRATIONS SCHEDULE EXAMINATION ITEM DRAWING EXAMINATION PERIOD' CATEGORY E-A WMBER DESCRIPTION NUMBER METHOD 1 2 3 REMARKS 31.11 Bay 8 6202-200 General 24 27 =29 Accessible areas of I 5920-42 1 Visual VT-3 27i interior and exterior surfaces.

Wetted surfaces of

!1.12 submerged areas.

1.11 6202-200 General Accessible areas of 5920-42 Visual interior and exterior surfaces.

31.12 Wetted surfaces of submerged areas.

31.11 Bay 10 6202-200 General Accessible areas of 5920-42 Visual interior and exterior surfaces.

~

31.12 Wetted surfaces of submerged areas.

21.11 Bay 11 6202-200 General 24 27 29 Accessible areas of 5920-42 Visual interior and exterior surfaces.

31.12 VT-3 27i Wetted surfaces of submerged areas.

fi1.11 Bay 12 6202-200 General 24 27 29 Accessible areas of 5920-42 Visual interior and exterior surfaces.

91.12 Wetted surfaces of submerged areas.

El.ll Accessible areas of 5920-42 Visual interior and exterior surfaces.

E l . 12 VT-3 27i Wetted surfaces of submerged areas.

El.ll Bay 14 6202-200 General 24 27 29 Accessible areas of 5920-42 Visual interior and exterior surfaces.

El. 12 Wetted surfaces of submerged areas.

El.ll Accessible areas of 5920-42 Visual interior and exterior surfaces.

E l . 12 VT-3 27i Wetted surfaces of i submerged areas.

Table 1 PP 7024 Rev. 4 Page 2 of 21

TABLE 1 (Continued)

RFO TORUS and TORUS PENETRATIONS EXAMINATION ITEM DRAWTNC EXAMINATION PERIOD^ CATEGORY E-A NUMBER DESCRIPTION NUMBER METHOD 1 2 -3 REMARKS El.ll Bay.16 6202-200 General 24 27 29 Accessible areas of 5920-42 Visual interior and exterior surfaces.

E1.12 VT-3 27i Wetted surfaces of I 5920-42 General Visual VT-3 General Visual VT-3 24 24 27 27i 27 27i 29 29 submerged areas.

Accessible areas of interior and exterior surfaces.

Bolting Accessible areas of interior and exterior surfaces.

Bolting General 24 27 29 Accessible areas of Visual interior and exterior I surfaces.

El.ll X-206B 5920-42 General 24 27 29 Accessible areas of Visual interior and exterior surfaces.

El.ll X-206C 5920-42 General 24 27 29 Accessible areas of Visual interior and exterior surfaces.

El.ll X-206D 5920-42 General 24 27 29 Accessible areas of Visual interior and exterior surfaces. Bottom 1/3 is inaccessible.

El.ll X-206E 5920-42 General 24 27 29 Accessible areas of Visual interior and exterior surfaces.

El.ll X-206F 5920-42 General 24 27 29 Accessible areas of Visual interior and exterior surfaces.

El.ll X-209A 5920-42 General 24 27 29 Accessible areas of Visual interior and exterior surfaces.

El.11 X-209B 5920-42 General 24 27 29 Accessible areas of Visual interior and exterior surfaces.

5920-42 General 24 27 29 Accessible areas of Visual interior and exterior surfaces.

Table 1 PP 7024 Rev. 4 Page 3 of 21

TABLE 1 (Continued)

RFO TORUS and TORUS PENETRATIONS SCHEDULE EXAMINATION ITEM W E R DESCRIPTION NUMBER El.ll X-209D 5920-42 1

DRAWING EXAMINATION METHOD General 1

PERIOD' 2

27 CATEGORY E-A REMARKS Accessible areas of visual interior and exterior surfaces. Bottom

- 1/3 is inaccessible.

El.ll X-2 1OA 5920-42 General 27 Accessible areas of Visual exterior surfaces.

Piping covered with

- insulation.

E1.12 27i Wetted surfaces of

- submerged areas.

El.ll X-210B 27 Accessible areas of Visual exterior surfaces.

Piping covered with

- insulation.

E l . 12 27i Wetted surfaces of

- submerged areas.

El.ll X-211A 5920-42 General 24 27 29 Accessible areas of Visual interior and exterior surfaces. Exterior piping covered with insulation.

El.11 X-211B 5920-42 General 24 27 29 Accessible areas of Visual interior and exterior gr.;

surfaces. Exterior piping covered with

-- insulation.

El.ll x-212 5920-42 General 24 27 29 Accessible areas of Visual interior and exterior i

surfaces.  !

El.ll X-2 13A 5920-42 General 24 27 29 Accessible areas of Visual exterior surfaces.

Piping covered with

--- insulation.

~~

E1.12 VT-3 27i Wetted surfaces of submereed areas.

El.ll X-213B 5920-42 General 24 27 29 Accessible areas of Visual - - exterior surfaces.

E1.12 I VT-3 27i Wetted surfaces of submerged areas.

Table 1 PP 7024 Rev. 4 Page 4 of 21

TABLE 1 (Continued)

RFO ORUS and TORUS PENETW 'IONS

~ ~

SCHEDULE EXAMINATION ITEM XAMINATION PERIOD' CATEGORY E-A-NUMBER METHOD 1 2 3 REMARKS Eli1 1 GeIleral 24 27 29 Accessible areas of Visual interior and exterior surfaces.

El.ll General 24 27 29 Accessible areas of Visual interior and exterior surfaces.

El.ll G3leral 24 27 29 Accessible areas of I Visual interior and exterior surfaces.

El.ll X-2 17 5920-42 General 24 27 29 Accessible areas of Visual interior and exterior sufaces.

El.ll El.ll X-2 18 X-2 19 I

I 5920-42 I 5920-42 General Visual General 24 27 29 Accessible areas of interior and exterior surfaces.

24 27 29 Accessible areas of Visual interior and exterior surfaces.

El.ll General 24 27 29 Accessible areas of Visual interior and exterior surfaces.

El.ll x-22 1 5920-42 General 24 27 29 Accessible areas of Visual interior and exterior surfaces. Exterior piping covered with insulation.

El.11 General 24 27 29 Accessible areas of

'1 E ,

LPC Visual exterior surfaces.

Exterior piping 1 wvered with 1 insulation. Interior is inaccessible

-blocked by 24" -

HPCI-3.

El.ll X-223 5920-42 General Accessible areas of Visual interior and exterior surfaces.

Table 1 PP 7024 Rev. 4 Page 5 of 21 LPC #1

TABLE 1 (Continued)

RFO 3 PENETRATIONS ITEM DR AW-NUMBER DESCRIPTION NUMBER METHOD 1 2 3 REMARKS El.ll X-224A 5920-42 General 24 27 29 Accessible areas of Visual I / / / exterior surfaces.

Piping covered with insulation.

VT-3 27i Wetted surfaces of II II II II Isuhmereedareas.

- -- __ - - - o - -

I 1 27 I 29 IAccessibleareasof

~

-224B 5920-42 I General 24 Visual exterior surfaces.

Piping covered with insulation.

El. 12 VT-3 27i Wetted surfaces of submerged areas.

El.ll <-225 5920-42 General 27 29 Accessible areas of Visual I I :xterior surfaces.

E1.12 Netted surfaces of I 1 iubmerged areas.

El.ll c226A 5920-42 I General I 24 27 29 kcessible areas of

1.12 +I Visual 27i

xterior surfaces.

Wetted surfaces of submerrred areas.

31.1 1 Y-226B 5920-42 General 27 29 4ccessible areas of Visual Zxterior surfaces.

z1.12 27i Wetted surfaces of submerged areas.

31.11 X-227 5920-42 General 24 27 29 Accessible areas of Visual exterior surfaces.

E1.12 VT-3 271 Wetted surfaces of submerged areas.

El.ll X-228 5920-42 General 24 27 29 Accessible areas of Visual exterior surfaces.

Interior is inaccessible -

internal to X-202E branch line.

El.11 X-229 5920-42 General 24 27 29 Accessible areas of Visual exterior surfaces.

Interior is inaccessible -

internal to X-202C branch line.

Table 1 PP 7024 Rev. 4 Page 6 of 21 LPC #1

TABLE 1 (Continued)

RFO TORUS and TORUS PENETRATIONS SCHEDULE EXAMINATION I

1 ITEM DRAWING EXAMINATION -

RIO CATEGORY E-A NUMBER DESCRIPTION NUMBER METHOD - 2 3 REMARKS E1.11 X-230 5920-42 General 24 27 29 Accessible areas of Visual exterior surfaces.

Interior is inaccessible -

internal to X-2023 El.ll X-23 1A 5920-42 General 24 27 Visual interior and exterior

- surfaces.

El.ll X-23 1B 5920-42 1 General 1 24 27 29 Accessible areas of Visual - exterior surfaces.

E1.12 El.ll I X-23 1C VT-3 27i 27 Wetted surfaces of submerged areas.

29 Accessible areas of Visual interior and exterior

- surfaces.

I I El.ll E1.12 X-231D 5920-42 General Visual VT-3 24 27 27i I

29 Accessible areas of exterior surfaces.

I Wetted surfaces of I I El.ll X-23 1E 5920-42 General 24 27 m Visual interior and exterior surfaces El.ll X-23 1F 5920-42 General Visual E1.12 1 submerged areas.

I I I I El.ll (X-231G 5920-42 1 General visual 24 I1 II 27 29 Accessible areas of interior and exterior surfaces.

I+-++

I I I I El.11 I X-231H 5920-42 I General 24 27 Visual E1.12 I Wetted surfaces of submeraed areas.

Table 1 PP 7024 Rev. 4 Page 7 of 21 LPC #I

TABLE 1 (Continued)

RFO TORUS and TOR1 S PENETRATIONS SCHEDULE EXAMINATION DRAWING EXAMINATION, PERIOD' CATEGORY E-A NUMBER METHOD 1 2 3 REMARKS 5920-42 General 24 27 ' 7 9 Accessible areas of exterior surfaces.

Interior is inaccessible -

internal to X-202E branch line.

27 29 Accessible areas of exterior surfaces.

Interior is inaccessible -

internal to X-202G branch line.

Table 1 PP 7024 Rev. 4 Page 8 of 21

TABLE 1 (Continued) 1 DEn I ITEM DRAWING EXAMINATION PERIOD r-NUMBER D E S C m O N NUMBER METHOD - -

1 2 - El.ll Drywell 6202-1 General 24 2 39 elevation 238 to 6202-2 Visual interior surfaces.

elevation 25 1

- ~

29 Accessible areas of

~

interior surfaces.

From 251' floor to 269' floor at 150" for 3' CW; 160"for 22.5' CW, and 206" for 3' CW are inaccessible due to permanent shielding.

Table 1 PP 7024 Rev. 4 Page 9 of 21

I -

TABLE 1 (Continued)

RFO I 1

-- DRYWELL and DRYWELL PENETRATIONS D R A ~ E SCHEDULE E

EXAMINATION CATEGORY E-A ITEM

+UMBER D E S C m I O N NUMBER METHOD 1 1 1 2 3 REMARKS 31.11 Stabilizer 6202-25 General 1 24 I 27 2 9 - Accessible areas of Assembly B Visual interior surfaces (and exterior surfaces if I

disassembled). I VT-3 27i Bolting z1.11 Stabilizer 6202-25 General 24 27 29 Accessible areas of Assembly C Visual interior surfaces (and exterior surfaces if

~ ~

disassembled).

VT-3 27i Bolting 31.11 Stabilizer 6202-25 General 24 27 29 Accessible areas of Assembly D Visual interior surfaces (and I exterior surfaces if I

disassembled).

VT-3 27i Bolting El.ll Stabilizer 6202-25 General 24 27 29 Accessible areas of Assembly E Visual interior surfaces (and exterior surfaces if disassembled).

VT-3 27i Bolting E1.11 Stabilizer 6202-25 General 24 27 29 Accessible areasof Assembly F Visual interior surfaces (and a exterior surfaces if disassembled),

VT-3 27i Bolting El.ll Stabilizer 6202-25 General 24 27 29 Accessible areas of Assembly G Visual interior surfaces (and exterior surfaces if disassembled).  !

VT-3 27i Bolting  !

E1.11 Stabilizer 6202-25 General 24 27 29 Accessibleareas of Assembly H Visual interior surfaces (and exterior surfaces if disassembled).

I VT-3 27i Bolting El.11 x-1 5 920-4 1 General 24 27 29 Accessible areas of Visual interior and exterior I surfaces.

Table 1 PP 7024 Rev. 4 Page 10 of 21

TABLE 1 (Continued)

I FWO DR WELL and DRY ELL PENETRATIONS SCHEDULE EXAMINATION ITEM DRAWING I EXAMINATION PERIOD' CATEGORY E-A NUMBER DESCRIPTION 2 3 REMARKS E1.11 x-2 5920-41 General 27 29- Accessible areas of Visual interior and exterior surfaces.

El.11 x-3 5920-41 General 24 27 29 AccessibIe areas of Visual interior and exterior surfaces, includes external flange bellows area.

Majority of the interior is blocked b!

duct work.

VT-3 27i Bolting El.ll X-4 5920-41 General 24 27 29 Accessible areas of Visual exterior surfaces (and interior surfaces if disassembled).

VT-3 27i Bolting El.ll X-6 5920-4 1 General 24 27 29 Accessible areas of Visual interior and exterior El.ll El.ll X-7A X-7B P

G-191179 5920-41 5920-41 General Visual Visual I

27i surfaces.

Bolting 27 29 Accessible areas of interior and exterior surfaces.

27 29 Accessible areas of interior and exterior surfaces. I El.ll x-7c G-191179 General 24 27 29 Accessible areas of 5920-4 1 Visual interior and exterior surfaces.

El.ll X-7D G- 191179 General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll X-8 G-191179 General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll X-9A G-191179 General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior I I surfaces.

Table 1 PP 7024 Rev. 4 Page 11 of 21

TABLE 1 (Continued)

I RFO

'ELL PENETRATIONS SCHED EXAMINATION ITEM DRAWING I EXAMINATION PERK CATEGORY E-A NUMBER DESCRIPTION NUMBER1 METHOD E REMARKS El.ll X-9B G-191179 General 24 Accessible areas of 5920-41 Visual interior and exterior surfaces.

E1.11 x-10 G-191179 General 24 29 Accessible areas of 5920-41 Visual interior surfaces.

Exterior of penetration and piping covered with

- insulation.

El.ll x-11 G-191179 General 24 29 Accessible areas of 5920-41 Visual interior and exterior

- surfaces.

El.ll x-12 G- 191179 General 24 29 Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll El.ll X- 13B X-13A 5920-41 G-191179 G-191179 I General Visual General I 24 24 29 29 Accessible areas of interior and exterior surfaces.

Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll X- 14 G-191179 General 24 29 Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll X-15 G-191179 General 24 29 Accessible areas of 5920-41 Visual interior and exterior

- surfaces.

El.ll X- 16A G-191179 General 24 29 Accessible areas of 5920-41 Visual interior and exterior

- surfaces.

El.ll X- 16B G-191179 General 24 29 Accessible areas of 5920-41 Visual interior and exterior

- surfaces.

E1.11 X-17 G-191179 General 24 29 Accessible areas of 5920-41 Visual interior and exterior

- surfaces.

El.ll X-18 G-191179 General 24 29 Accessible areas of 5920-41 Visual interior and exterior

- surfaces.

Table 1 PP 7024 Rev. 4 Page 12 of 21

TABLE 1 (Continued)

RFO DR WELL and DRY ELL PENETRATIONS s c m JLE EXAMINATION ITEM DRAWING 1 EXAMINATIOfi PEN( D' - CATEGORY E-A NUMBER DESCRIPTION NUMBER I METHOD 1 2 3 REMARKS El.ll x-19 G-19 1179 General 24 27 ?9 Accessible areas of 5920-41 Visual interior and exterior

- surfaces.

E1.11 x-20 G-191179 General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior

- surfaces.

El.ll x-21 G-191179 General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior x-22 G-191179

- surfaces.

EL11 General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior

- surfaces.

El.ll x-23 G-191179 General 24 27 29 Accessible areas of 592041 Visual interior and exterior surfaces.

El.ll X-24 G- 191179 General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior G-191179

- surfaces.

EL11 X-25 General 24 27 29 Accessible areas of 5920-4 1 Visual interior and exterior surfaces.

3 EL11 X-26 G-191179 General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior M surfaces.

El.ll X-27 G-191179 General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior

- surfaces.

El.ll X-28 G-191179 General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior El.ll X-29 G-191179

- surfaces.

General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior

- surfaces.

E1.11 X-30 G- 191179 General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior El.ll X-31

- surfaces.

24 27 29 Accessible areas of 5920-41 Visual interior and exterior

- surfaces.

Table 1 PP 7024 Rev. 4 Page 13 of 21

I -

TABLE 1 (Continued)

ITEM DRYWELL and DRYWELL PENETRATIONS I DRAWING I EXAMINATION NUMBER DESCRIPTION NUMBER METHOD ~

zq PERIOD EXAMINATION CATEGORY E-A El.ll Y-32 G-191179 General 5920-41 Visual I interior and exterior surfaces.

El.ll K-33 G-191179 General Accessible areas of 5920-41 Visual interior and exterior surfaces.

E1.11 x-34 G-191179 General Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll X-35A G-191179 General Accessible areas of i 5920-41 visual interior and exterior surfaces.

VT-3 Bolting E1.11 X-3 5B G-191179 General Accessible areas of 5 920-4 1 Visual interior and exterior surfaces.

VT-3 Bolting El.ll x-35c G-191179 General Accessible areas of 5920-41 Visual interior and exterior L

surfaces.

VT-3 Bolting El.ll X-35D G-191179 General Accessible areas of 5920-41 Visual interior and exterior surfaces. c VT-3 Bolting E1.11 X-35E G-191179 General Accessible areas of 5920-41 Visual interior and exterior surfaces.

Bolting '

VT-3 El.ll X-36 G- 191179 General Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll X-37A G-191179 General 24 27 29 Accessible areas of X-38A 5920-41 Visual interior and exterior surfaces.

El.ll X-37B G-191179 General 24 27 29 Accessible areas of X-38B 5920-4 1 Visual interior and exterior surfaces.

El.ll x-37c G-191179 General 24 27 29 Accessible areas of X-38C 5920-4 1 Visual interior and exterior surfaces.

Table 1 PP 7024 Rev. 4 Page 14 of 21

TAEKE 1 (Continued)

DR i EXAMINATION ITEM DRAWING EXAMINATION ~ CATEGORYE-A NUMBER DESCRIPTION NUMBER METHOD 1 2 3 REMARKS EL11 X-37D G-191179 General 24 27 29 I Accessible areas of X-38D 5920-4 1 Visual interior and exterior El.11 X-39A G-191179 General 24 27 29

' surfaces.

Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll X-39B G-191179 General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll X-40A G-191179 General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll X-40B G-191179 General Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.11 x4oc 1 G-191179 General Accessible areas of

~ 5920-41 Visual interior and exterior surfaces.

El.ll X-4OD G-191179 General Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll x-41 G-191179 General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.11 X-42 G-191179 General 24 27 29 Accessibleareasof 5920-41 Visual interior and exterior surfaces.

El.ll x-43 G-191179 General 24 27 29 Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll X-44 G- 191179 General 24 27 29 Accessible areasof 5920-41 I Visual I I I Iinteriorandexterior surfaces.

El.ll x-45 G-191179 General 24 27 29 Accessibleareasof 5920-41 I Visual I I I Iinteriorandexterior surfaces.

El.ll X-46 24 27 29 Accessibleareasof 5920-41 Visual I I I interior and exterior I I surfaces.

Table 1 PP 7024 Rev. 4 Page 15 of 21

~

L- .

TABLE 1 (Continued)

RFO DRYWELL and DRY ELL PENE XATIONS SCHEDULE EXAMINATION ITEM DRAWING EXAMINATION PERIOD' CATEGORY E-A NUMBER DESCRIPTION NUMBER METHOD REMARKS El.ll x-47 G-191179 General Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll X-48 G-191179 General Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll x-49 G- 191179 General Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll X-50 G-191179 General Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.11 X-5 1 G-191179 General Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll X-52 G-191179 General Accessible areas of 5920-41 Visual interior and exterior surfaces.

El.ll X-100A 5920-41 General Accessible areas of Visual interior and exterior surfaces. Both surfaces have restricted access due to junction box

~

mounting.

El.11 X- lOOB 5920-41 General Accessible areas of Visual interior and exterior surfaces. Both surfaces have restricted access due to junction box mounting.

El.ll x-1ooc 5920-41 General Accessible areas of Visual interior and exterior surfaces. Both surfaces have restricted access due to junction box mounting.

Table 1 PP 7024 Rev. 4 Page 16 of 21

TABLE 1 (Continued)

I RFO DR WELL and DRYWELL PENETRATIONS EXAMINATION ITI'EM CATEGORY E-A NUMBER DESCRIPTION NUMBER I REMARKS El.11 General I 24 I 27 Accessible areas of Visual interior and exterior i surfaces. Both surfaces have restricted access due to junction box mounting.

El.11 General 24 27 Accessible areas of Visual exterior surfaces.

Interior is inaccessible El.ll X-1O1B 5920-41 General 24 27 29 Accessible areas of Visual interior and exterior

- surfaces.

El.ll x-I01C 592041 General 24 27 29 Accessible areas of Visual exterior surfaces.

Interior is inaccessible El.ll General 24 27 29 Accessible areas of Visual interior and exterior surfaces.

El.ll x-102 5920-41 General 24 27 29 Accessible areas of Visual exterior surfaces.

Interior is inaccessible El.11 X-103 5920-41 General 24 27 29 Accessible areas of exterior surfaces. Top half exterior is restricted and the interior is inaccessible due to junction box El.ll X-104A I 5920-41

- mounting.

29 Accessible areas of interior and exterior surfaces. Both surfaces have restricted access due to junction box mounting.

Table 1 PP 7024 Rev. 4 Page 17 of 21

TABLE 1 (Continued)

RFO DR WELL and DRYWELL PENE7 UTIONS SCHEDuL;E EXAMINATION ITEM 1 I DRAWING ZXAMINATION - PI uc

- )1 CATEGORY E-A NUMBER METHOD _

1 -

2 3 REMARKS El.ll Y- 104B 5920-41 General 24 27 -29 Accessible areas of Visual interior and exterior surfaces. Exterior is restricted and the interior is inaccessible due to junction box El.ll Y- 104C I 5920-41 General Visual

-I---

24 27 29 Accessible areas of interior and exterior surfaces. Exterior is restricted and the interior is inaccessible due to junction box

-- mounting.

El.ll K-105A 5920-41 General 24 27 29 Accessible areas of Visual interior and exterior surfaces. Interior has restricted access due to junction box

- - mounting.

El.ll X-105B 5920-41 General 24 27 Accessible areas of Visual exterior surfaces.

Interior is

- - inaccessible.

El.ll X-105C 5920-41 General 24 27 29 Accessible areas of Visual interior and exterior surfaces. Interior has restricted access due to junction box

-- mounting.

El.11 X-105D 5920-4 1 General 24 27 29 Accessible areas of Visual interior and exterior surfaces. Interior has restricted access due to junction box

-- mountin E.

Table 1 PP 7024 Rev. 4 Page 18 of 21

TABLE 1 (Continued)

RFO DR WELL, and DRYWELL PENETRATIONS SCHEDULE EXAMINATION ITEM 1 DRAWING EXAMINATION PERIOD CATEGORY E-A NUMBER METHUD 1 2 3 REMARKS El.ll General 24 27 5 3 Accessible areas of Visual interior and exterior surfaces.

El.ll General 24 27 29 Accessible areas of Visual interior and exterior surfaces.

E1.30 General 24 26 29 The interface is from Visual 25 27 the Containment Plate Weld Joint left of X-5B to the Containment Plate Weld Joint right of Penetration X-5E and from the concrete metal interface up -1 I foot.

Table 1 PP 7024 Rev. 4 Page 19 of 21

TABLE 1 (Continued)

I RFO 1 EXAMINATION VENT SYSTEM ASSEMBLIES SCHEDULE ITEM 1 IDRAWING I EXAMlNATION PERIOD CATEGORY E-A NUMBER DESCRIPTION NUMBER METHOD 1 2 9- REMARKS E l .20 Bay 2 Vent Line; 5920-13 VT-3 27i Accessible areas of Vacuum Breaker 6202-200 interior and exterior Lines; Vent 6202-211 surfaces.

Header in Bays 2

& 3; and Downcomers E l .20 Bay 4 Vent Line; 5920-13 VT-3 27i Accessible areas of Vacuum Breaker 6202-200 interior and exterior Lines; Vent 6202-211 surfaces.

Header in Bays 4

& 5; and Downcomers E1.20 Bay 6 Vent Line; 5920-13 VT-3 27i Accessible areas of Vacuum Breaker 6202-200 interior and exterior Lines; Vent 6202-2 11 surfaces.

Header in Bays 6

& 7; and Downcomers E l .20 Bay 8 Vent Line; 5920-13 VT-3 27i Accessible areas of Va&mn Breaker 6202-200 interior and exterior Lines; Vent 6202-211 surfaces.

Header in Bays 8

& 9; and Downcomers E1.20 Bay 10 Vent 5920- 13 VT-3 27i Accessible areas of Line; Vacuum 6202-200 interior and exterior Breaker Lines; 6202-211 surfaces.

Vent Header in Bays 10 & 11; and Downcomers E l .20 Bay 12 Vent 5920-13 VT-3 27i Accessible areas of Line; Vacuum 6202-200 interior and exterior Breaker Lines; 6202-211 surfaces.

Vent Header in Bays 12 & 13; 1

and Downcomers Table 1 PP 7024 Rev. 4 Page 20 of 21 I

TABLE 1 (Continued)

-~ ~

RFO SCHEDW EXAMINATION ITEM DRAWING EXAMINATION PERIOD CATEGORY E-A NUMBER DESCRJPTION NUMBER METHOD 1 2 3 REMARKS E l .20 Bay 14 Vent 5920-13 VT-3 27i Accessible areas of Line; Vacuum 6202-200 interior and exterior Breaker Lines; 6202-211 Vent Header in Bays 14 & 15; and Downcomers El .20 Bay 16 Vent 5920-13 VT-3 Line; Vacuum 6202-200 Breaker Lines; 6202-2 11 Vent Header in Bays 16 Br 1; and Downcomers ~-

i Indica .es refueling outage when an Interval test should?

Table 1 PP 7024 Rev. 4 Page 21 of 21

TABLE 2 ASME CODE CLASS MC EXAMINATION CATEGORY E-C ITEM <

NUMBER DESCRIPTION NUMBER METHOD PERIOD 777 CATEGORY E-C REMARKS E4.11 None VT- 1 Visible Surfaces m.12 None VOLUMETRIC Surface Area Grid, Minimum Wall Thickness Location Table 2 PP 7024 Rev. 4 Page 1 of 1