ML20129C392

Forwards Rev 4 to ISI Plan for Braidwood Nuclear Generating Station Units 1 & 2 First Insp Interval

ML20129C392
Person / Time
Site:	Braidwood
Issue date:	10/08/1996
From:	Stanley H COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20129C394	List: ML20129C392 ML20129C401
References
TAC-M92120, TAC-M92121, NUDOCS 9610240014
Download: ML20129C392 (7)

Text

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Osmmonwealth lifiwn Comguny tiraidwood Generating Station Routeal, llox 84 liraces ille. II. (in 1073)619 Tel8144 M 2801 1

October 8,1996 l ,

l United States Nuclear Regulatory Commission ]

Attention: Document Control Desk  !

Washington, D.C. 20555-0001

Subject:

Revision 4 of the Inservice Inspection Plan 1 Braidwood Nuclear Power Station, Units 1 and 2 j Facility Operating Licenses NPF-72 and NPF-77 l NRC Docket Nos. 50-456 and 50-457 l

References:

1. Robert A. Capra (USNRC) letter to D. L. Farrar (Comed), Safety Evaluation of the Inservice Inspection Program Relief Requests Nos. NR-20, NR-21, NR-22 for Braidwood Station Units I and 2 (TAC Nos. M 92120, M92121) dated September 1, 1995.

Ladies and Gentlemen Commonwealth Edison Company's (Comed's) Braidwood Nuclear Power Station, Units I 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 4 Vessel Code through the Summer 1983 Addenda (ASME Code), as required by Title 10, Code of Federal Regulations, Part 50, Section 55a, Paragraph f, Subparagraph 3 [10 CFR 50.55a(f)(3)], except where alternatives have been authorized or relief has been requested and granted by the United States Nuclear Regulatory Commission (USNRC). j Revision 4 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 as a result of the Resistance Temperature Detector (RTD) modification. This modification has caused testing population and condition changes for both units by eliminating numerous welds. Revision 4 will also correct several minor typographical errors. Finally, this j revision will also incorporate existing, approved relief requests, and will submit new relief l requests. A brief discussion of the new relief requests associated with this revision of the l ISI program is included below:

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USNRC Document Control Desk October 8,1995

1. NR-25 - Pressurizer Seismic Lugs: Subsection IWB, Table IWB-2500-1 Examination Category B-H, Item B8.20 requires surface or volumetric examinations ofintegrally welded attachments to the pressurizer.

2. NR Inaccessible Welds of Welded Attachments: Subsection IWC, Table IWC-2500-1, Examination Category C-C, Item C3.20 requires surface examinations ofintegrally welded attachments to piping.

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 Limited Exams Reactor Vessel Nozzle Inner Radius Sections: Subsection IWB, Table IWB-2500-1, Examination Category B-D, item B3.100 requires essentially a 100% volumetric examination of the inner radius region described in figure IWB-2500-7 for reactor vessel nozzle inner radius sections.

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5. NR Use of PDI/ Appendix VIII Y chniques on Reactor Vessel Shell Welds:

Subsection IWB, Table IWB-2500-1, Examination Category B-A, items Bl.11, Bl.21, Bl.30 require volumetric examinations be performed on selected reactor vessel welds. These volumetric examinations are to be performed in accordance with IWA-2232. IWA-2232 states that these inspections shall be conducted in accordance with Article 4 of Section V, as amended by section XI.

6. NR Use of Code Case 522: ASME section XI, Table IWC -2500-1, Examination Category C-H, requires the performance of a visual VT-2 examination during a system pressure test on Code Class 2 pressure retaining components. Note 7 of this table states: "The pressure boundary includes only those portions of the system required to operate or support the safety system function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function of the system is required." {

7. NR-31 Limited volumetric examination of reactor vessel circumferential shell weld: Sub Section IWB, Table IWB-2500-1, Examination Category B-A, Item Number Bl.ll requires a 100% volumetric examination of the reactor vessel circumferential shell welds as detailed in Figure IWB-2500-1.

Comed respectfully requests USNRC review and approval of Relief Requests NR-25, NR-26, NR-27, NR-28, NR-29, NR-30 and NR-31 no later than January 31,1997, such oicisvp)98063 doc m

USNRC Document Control Desk October 8,1995 these requirements can be implemented during the upcoming Unit I and Unit 2,1997 outages. These outages represent the last outages in the first ISI interval for Braidwood Station.

Please address any comments or questions regarding this matter to Mr. Douglas Huston, at (815)458-2801 extension 2511.

Very truly yours,

/ , ,

Y

' / .stanley o.

Site Vice Presi ent -

Braidwood Nuclear Station 1

Attachments (2)

Enclosures (2) cc: B. Beach, Regional Administrator - RIII l R. A. Assa, Braidwood Project Manager - NRR C. Phillips, Senior Resident Inspector - Braidwood Office of Nuclear Facility Safety - IDNS 1

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d Summary of Changes for Revision 4 of the Inservice Inspection Plan:

There are three basic reasons for revising the Inservice Inspection (ISI) Plan. The first is to reflect current plant configuration. Due to the RTD modification for both Units, populations and conditions have changed. The RTD modification has eliminated numerous welds and the Section 5 tables are being updated to reflect the new population. The second reason is to f address minor typo's. Several minor typos will be corrected. The third 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-23 (RHR Heat Exchanger) and NR-24 (Pressurizer Surge Nozzle) Relief Request submittals which have already been approved. Also, Braidwood is submitting new Relief Requests, NR-25 (Pressurizer Seismic Lugs), NR-26 (Inaccessible Welds of Welded Attachments), NR-27 (Limited Exams of Reactor Vessel 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) and NR-31

.i (Limited Exam of Reactor Vessel Shell Welds) for NRC review. A description of the changes )

is provided below: l

1) Cover page revised to reflect revision status, i.e. Revision 4.

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

3) 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-23, NR-24, NR-25, NR-26, NR-27, NR-28, NR-29, NR-30 and NR-31.

b) Typo on NR-7, page 3-13, was corrected. Weld IRC-162 was corrected to 1RC-16-2.

c) Page 3-38, " Approval Status" was updated to reflect the current status of the relief request.

d) Page 3-40, " Approval Status" was updated to reflect the current status of the relief request. i e) Typo on NR-22, page 3-41, was corrected. The description section misplaced the word " pressure", and was corrected to read " Alternate Rules for 10 Year Hydrostatic Pressure Testing for Class 3 Systems". Also, on page 3-42 Page1

" Approval Status" was updated to reflect the current status of the relief request.

f) Relief Request NR-23, " Alternate Examination of Nozzle to Vessel Welds -

Residual Heat Removal Heat Exchangers", pages 3-43 to 3-47 are being incorporated into the ISI Plan, g) Relief Request NR-24, " Pressurizer Surge Nozzle to Vessel Weld and Pressurizer Surge Nozzle Inner Radius Section", pages 3-48 to 3-56 are being incorporated into the ISI Plan.

h) Relief Request NR-25, " Alternate Rules for the Inservice Inspection of the Pressurizer Seismic Lug Welds", pages 3-57 to 3-63 are submitted for NRC review and are being incorporated into the ISI Plan.

i) Relief Request NR-26, " Alternate Rules for the Inservice Inspection of Inaccessible Welds on Welded Attachments", pages 3-64 to 3-71 are submitted for NRC review and are being incorporated into the ISI Plan.  !

j) Relief Request NR-27, " Alternate Rules for the Inservice Inspection of Reactor Vessel Nozzle to Vessel Welds", pages 3-72 to 3-74 are submitted for NRC review and are being incorporated into the ISI Plan.  !

k) Relief Request NR-28, " Alternate Rules for the Inservice Inspection of Reactor i Vessel Nozzle Inner Radius Sections (IRS)", pages 3-75 to 3-78 are submitted for NRC review and are being incorporated into the ISI Plan.

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1) Relief Request NR-29, " Alternate Rules for the Inservice Inspection of Reactor Vessel Circumferential Shell Welds, lower Head Circumferential Weld and Shell to Flange Weld", pages 3-79 to 3-80 are submitted for NRC review and are being incorporated into the ISI Plan.

m) Relief Request NR-30, " Alternate Rules to Table IWC-2500-1, Category C-H:

Pressure Testing of Containment Penetration Piping with Attached Nonclassed Piping", pages 3-81 to 3-82 are submitted for NRC review and are being incorporated into the ISI Plan.

n) Relief Request NR-31, " Limited Volumetric Examination of Reactor Vessel Circumferential Shell Weld", pages 3-83 to 3-86 are submitted for NRC review and are being incorporated into the ISI Plan.

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4) Some pages in Section 4 have been revised or added. Changes to the Technical Approaches and Positions Section are summarized below:

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, a) Within this section, page 4-2 is revised to reflect the addition of Note 18 (Code i

Case N-356) and Note 19 (Code Case N-460).

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b) Note 18 was added (Rev. 4 submittal) to allow the use of Code Case N-356.

i l c) Note 19 was added (Rev. 4 submittal) to allow the use of Code Case N-460.

5) 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 e

weld populations due to plant modifications and references to Relief Requests NR-23, NR-24, NR-25, NR-26, NR-27, NR-28, NR-29 and NR-30.

a) Page 5-2, item numbers Bl.11, Bl.21 and Bl.30, were revised to reflect reference to NR-29 and/or NR-31.

i b) Page 5-5, item numbers B3.90, B3.100, B3.110 and B3.120, were revised to reflect reference to NR-24, NR-27 and NR-28.

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l c) Page 5-6 was revised to provide proper spacing between lines. No information

was changed on this page. >

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! d) Page 5-13, item number B7.50, was revised to reflect new component populations due to the Unit I and 2 RTD modification.

! e) Page 5-14, item number B7.70, was revised to reflect new component j populations due to the Unit I and 2 RTD modification.

i f) Page 5-15, item number B8.20, was revised to reflect new component

. populations and reference to NR-25.

! g) Page 5-16, item numbers B9.21, B9.32 and B9.40 was revised to reflect new component populations due to the Unit I and 2 RTD modification. Also, item j number B9.21 Exam Requirements was revised from "Vol and SUR" to "SUR" ,

to reflect proper code examination requirements, l

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I h) Page 5-17, item number B10.10, was revised to reflect new component populations due to the Unit I aad 2 RTD modification. l i

i) Page 5-22, item number C2.21, Relief Request column was revised to correct a typo and change reference of "NR-20" to "NR-23".

j) Page 5-24, item number C3.20, Relief Request column was revised to reference "NR-26". Also, the " Remarks" column was corrected to reflect the proper  :

number of components selected for inspection, Unit 1 from "26" to "37" and l Unit 2 from "33" to "37".

k) Page 5-26 had its page format corrected. Also, hem number C5.32, was revised to correct typo "3-41" to "3-Ul" and to ado "SUR" to Exam Requirements column.

1) Page 5-27, item numbers C7.30, C7.40, C7.70 and C7.80, were revised to ,

reference "NR-30".

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m) Page 5-28, item number Dl.20, was revised to correct component population of !

Unit I from "46" to "44" and " Remarks" column selected components from l

"35" to "33". Also, correct typo of "VT-3/4" in the Exam Requirements i column to "VT-3". l 1

n) Page 5-29, item number D3.20, was revised to correct component population from "1" to "0" and remove "VT-3/4" in the Exam Requirements column.

o) Page 5-30, Augmented High Energy Main Steam and Feedwater populations revised to correct component population on Unit I from "282" to "314" and on Unit 2 from "297" to "330".

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