ML20217A233

Forwards Rev 5 to ISI Plan for Braidwood Nuclear Power Station.Brief Discussion of New Relief Requests Associated W/Rev of ISI Program,Listed

ML20217A233
Person / Time
Site:	Braidwood
Issue date:	03/05/1998
From:	Tulon T COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20217A240	List: ML20217A233 ML20217A267
References
NUDOCS 9803240330
Download: ML20217A233 (6)

Text

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Commonwealth than Company Braidwood Generating 5tation knute *l. Ikix H4 Hracesille, 11.60407 9619 Tel H154 W2801 O du s- 'p \

March 5,1998 United States Nuclear Regulatory Commission Attention: Document Control Desk 3 Washington, D.C. 20555-0001 l

Subject:

Revision 5 of the Inservice Inspection Plan )

Braidwood Nuclear Power Station, Units 1 and 2  ;

Facility Operating Licenses NPF-72 and NPF-77 I NRC Docket Nos. 50-456 and 50-457 Ladies and Gentlemen: l l

Commonwealth Edison Company's (Comed's) Braidwood Nuclear Power Station, Units 1 l and 2 (Braidwood), performs inservice inspections (ISI) in accordance with Section XI of the 1983 Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code through the Summer 1983 Addenda (ASME Code), as required by Title 10, j Code of Federal Regulations, Part 50, Section 55a, Paragraph g, Subparagraph 3 [10 CFR '

50.55a(g)(3)], except where alternatives have been authorized or relief has been requested and granted by the United States Nuclear Regulatory Commission (USNRC).

Revision 5 of the Braidwood ISI Program is provided in Enclosure 1. Attachment A provides a summary of all of the changes associated with this revision. These changes are briefly discussed below.

The ISI program is being revised to reflect changes in current plant configuration and to correct minor typographical errors. Plant modifications have caused testing population and condition changes for both units. Finally, this revision will also incorporate existing, approved relief requests, and will submit new relief requests. A brief discussion of the new relief requests associated with this revision of the ISI program is included below:

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1. NR Limited volumetric examination of reactor vessel circumferential shell

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weld: Sub Section IWB, Table IWB-2500-1, Examination Category B-A, Item Number Bl.11 requires a 100% volumetric examination of the reactor vessel ~%f circumferential shell welds as detailed in Figure IWB-2500-1. / ;

2. NR-36 10CFR50.55a(g)(ii)(A)(2) requires that all licenses shall augment their Reactor Pressure Vessel (RPV) examination by implementing once, as part of the 98032'40330 980305 PDR ADOCK 05000456 O PDR g N t'nicom company

r m USNRC Document Con $rol Desk March 5,1998 inservice inspection interval in effect on September 8,1992, the examination requirements for the RPV shell welds specified in Item Bl.10.of Examination Category B-A, " Pressure Retaining Welds in Reactor Vessel", in Table IWB-2500-l

' 1 of Subsection IWB of the 1989 Edition of Section XI, Division 1, of the ASME Boiler and Pressure Vessel Code. For the purpose of this augmented examination,

" essentially 100%" as used in Table IWB-2500-1 means more than 90% of the examination volume of each weld, where. the reduction in coverage is due to-interference by another component, or part geometry.

3. NR Limited Exams of Reactor Vessel Welds: Subsection IWB, Examination Category B-D,~ Item B3.90 requires essentially a 100% volumetric examination of the region described in Figure IWB-2500-7 for reactor vessel nozzle-to-vessel welds.

4. NR Subsection IWB, Table IWB-2500-1, Examination Category B-A, Item Number Bl.21 requires essentially 100% volumetric examination of the accessible length of the Reactor Pressure Vessel (RPV) Lower Head Circumferential weld as detailed.in Figure IWB-2500-3.

Comed respectfully requests USN'RC review and approval of Relief Requests NR-35, NR-36, NR-37 and NR-38.

Please address any comments or questions regarding this matter to T. W. Simpkin, at (815)458-2801 extension 2980.

Sincerely, I

i thy J. Tulon te Vice President Braidwood Nuclear Generating Station Attachments cc: A. B. Beach, Regional Administrator - RIII S. N. Bailey, Braidwood Project Manager - NRR

. C. Phillips, Senior Resident Inspector - Braidwood

. Office of Nuclear Facility Safety - IDNS

- o:LnrcW8017yt. doc o

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- ATTACHMENT A Summary of Changes for Revision 5 of the Inservice Inspection Program

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Summary of Changes for Revision 5 of the Inservice Inspection Plan:

There are two basic reasons for revising the Inservice Inspection (ISI) Plan. The first reason is to correct minor typographical errors. The second reason is to incorporate existing and new Relief Requests into the ISI Program Plan. The ISI Plan tables and sections were updated to reflect NR-25 (Pressurizer Seismic Lugs), NR-26 (Inaccessible Welds of Welded Attachments), NR-27 (Limited Exams of Reactor Nozzles Welds), NR-

- 28 (Limited Exams Reactor Vessel Nozzle Inner Radius Sections), NR-29 (Use of PDI/ Appendix VIII techniques on Reactor Vessel Shell Welds), NR-30 (Use of Code Case 522), NR-31 (Volumetric Exam of Reactor Vessel Shell Welds), NR-32 (ASME IWE/IWL Repeir and Replacements), NR-33 (Repair of Concrete Containments) and NR-34 (Volumetric Exam of Reactor Vessel Shell Welds) Relief Request which have already been submitted to or approved by the NRC. Also, Braidwood is submitting new Relief Requests, NR-35 (Volumetric Exam of Reactor Vessel Shell Weld), NR-36 (Volumetric Exam of Reactor Vessel Shell Welds), NR-37 (Volumetric Examination of Reactor

' Nozzle Welds) and NR-38 (Volumetric Exam of Reactor Vessel Lower Head Circumferential Weld) for NRC review. A description of the changes is provided below:

1) Cover page revised to reflect revision status, i.e. Revision 5.

2) Revision Summary sheet revised, page (i). Each page revision status is reflected on this summary sheet.

3) Revision Summary sheet added, page (ii). This is a continuation of the Revision Summary sheet

4) Table of Contents sheet revised, page (iii). Page was renumbered from (ii) to (iii).  !

5) List of Tables sheet revised, page (iv). Page was renumbered from (iii) to (iv). j

6) Some pages in Section 3 have been revised or added. Changes to the relief request section are summarized below; a) Within this section, page 3-3 was revised to reflect the inclusion of relief requests NR-31, NR-32, NR-33, NR-34, NR-35, NR-36, NR-37, and NR-38.

b) Page 3-57 to 3-106, are being incorporated into the ISI Plan to include previously submitted or approved relief requests NR-25, NR-26, NR-27, NR-28, NR-29, NR-30, NR-31, Nk-32, NR-33, NR-34. ,

c): Relief Request NR-35, " Volumetric Examination of Reactor Pressure  ;

Vessel (RPV) Circumferential Shell Weld", pages 3-107 to 3-112 are  !

submitted for NRC review and are being incorporated into the ISI Plan.

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i) Page 5-25, item numbers C5.12,' C5.21 and C5.22, were revised to reflect proper component populations.

j) Page 5-26, item numbers C5.31 and C5.32, were revised to reflect proper component populations.

k) Page 5-28, item numbers DI.10 and D2.10, were revised to reference NR-22.

n) - Page 5-29, item number D2.20, was revised to correct component population. Item number D3.10, was revised to reference NR-22.

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d) Relief Request NR-36, " Volumetric Examination of Reactor Pressure Vessel (RPV) Circumferential Shell Welds", pages 3-113 to 3-118 are submitted for NRC review and are being incorporated into the ISI Plan.

e) - ' Relief Request NR-37, " Volumetric Examination of Reactor Pressure Lower Head Circumfereutial Weld", pages 3-119 to 3-124 are submitted for NRC review and are being incorporated into the ISI Plan.

f) Relief Request NR-38, " Volumetric Examination of Reactor Pressure Vessel Nozzle to Vessel Welds", pages 3-125 to 3-128 are submitted for NRC review and are being incorporated into the ISI Plan.

4) Section 5 contains the ISI Plan Summary. This section contains information on Code Category, Item and total number of welds. This section was revised to reflect new weld populations due to plant modifications or typo's, and references to Relief Requests NR-31, NR-32, NR-33, NR-34, NR-35, NR-36, NR-37, and NR-38.

a) Page 5-2, item numbers Bl.11 and Bl.21, were revised to reflect reference to NR-34,35,36 and/or NR-38.

b) Page 5-5, item numbers B3.90, was revised to reflect reference to NR-37.

.c) Page 5-11, item B6.200, was revised to reflect the proper population of components.

d) Page 5-12, item number B6.230, spacing in " Technical Approach and Position" and " Remarks" column was revised to reflect proper alignment of" Note 2" and "1 Valve", respectively.

e) Page 5-16, item number B9.40, was revised to reflect proper component populations.

f) Page 5-17, item number B10.10, was revised to reflect new component populations.

g) Page 5-19, item number B13.50, was revised to reflect proper component populations.

H h) Page 5-24, item number C3.20, was revised to reflect proper component populations.

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