ML20217H836
| ML20217H836 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 04/17/1998 |
| From: | Tulon T COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20013H719 | List: |
| References | |
| NUDOCS 9804300102 | |
| Download: ML20217H836 (6) | |
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Commonwealth Filiv>n Company
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liraidwood Generating.%tation Route el, ik)x M 6 liraces ille, IL 60 607-9619 Tcl 81 S45H-2801
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April 17,1998 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Subject:
Braidwood Nuclear Power Station Units 1 and 2 Second Interval Inservice Inspection Program Plan
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Facility Operating Licenses NPF-72 and NPF-77 j
NRC Docket Nos. 50-456 and 50-457 Pursuant to Title 10, Code of Federal Regulations, Part 50, Section 55a, Paragraph g, Subparagraph (4)(ii) [10CFR50.55a(g)(4)(ii)], Commonwealth Edison (Comed) g proposes to revise the Braidwood Nuclear Power Station, Units I and 2 Inservice L
Inspection (ISI) program for the Second Ten Year Interval.
in accordance with 10CFR50.55a(g), Comed is required to update the ISI program per the ASME Section XI (the Code) for Braidwood Station once every ten years or interval. The ISI program is required to comply with the latest edition and addenda of the Code incorporated by reference in 10CFR50.55a one year prior to the start of the m
interval per 10CFR50.55a(g)(4)(ii).
The next inteival for Braidwood Unit I is currently scheduled to commence July 29,1998 and be completed July 28,2008, 1
year Interval extension as allowed by paragraph (d) of IWA-2430. The next interval for Braidwood Unit 2 is currently scheduled to commence October 17,1998 and be completed October 16,2008, i 1 year Interval extension as allowed by paregraph (d) of IWA-2430. Accordingly, the 1989 Edition of ASME Section XI is the Code that Braidwood must meet for the second ten year interval ISI Program.
Braidwood will be performing the replacement of the Unit i Steam Generators during the upcoming September,1998 refueling outage (AIR 07). As such, the current submittal was developed to reflect component populations and required inspections after Steam Generator Replacement. This information was obtained for Braidwood i
from the review of modification, engineering design change, and work package documentation. Section 2, Table 2.5-1 identifies the revised isor.:etric drawings for
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U nit 1, These drawings are part of the steam generator replacement modification l[
package and are not finalized, and therefore are not included in the appendices to the submittal.
In addition to the ISI Program, Braidwood is also submitting the Containment ISI (gl) Program with the Second interval ISI Program Plan. Per the requirements of 9504500102980417 4/l.
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USNRC Document Control Desk 4/15/98 the Code Of Federal Regulations, Title 10, Part 50, Section 55a, (10 CFR 50.55a), this Containment ISI Program Plan was developed in accordance with the requirements delineated in the 1992 Edition,1992 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Subsections IWE and IWL, as modified by 10 CFR 50.55a(b)(2)(ix) and 10 CFR 50.55a(b)(2)(x) and inspection Program B of IWE-2412 and IWL-2410. This Program Plan is effective from July 29,1998 to July 28,2008 for Unit 1, and from October 17,1998 to October 16,2008 for Unit 2, i 1 year Interval extension as allowed by paragraph (d) of IWA-2430. This is the First Interval inspection Plan for IWE/lWL. Since the dates given in 10CFR 50.55(a)(g)(6)(ii)(B) for Implementation of the First Interval Containment Inservice Inspection Program Plan (ClSI) coincide with the Second Interval inservice Inspection Program Plan (ISI), the CISI Program is incorporated into, and is considered part of the Second Interval ISI Program Plan.
Braidwood is submitting for review the Controlled portion of the Second Interval inservice Inspection Program Plan (Attachment C). The key features of Braidwood's Controlled ISI Program Plan are the introduction and Brckground (Section 1), Basis for ISI Program (Section 2), Component ISI Program Plan (Section 3), Component Support ISI Program Plan (Section 4), System Pressure Testing ISI Program Plan (Section 5), CISI Plan (Section 6), ISI Summary Tables (Section 7), Relief Requests (Section 8), ISI Prviram Plan Notes (Section 9), and References (Section 10).
To assist in the review of the Controlled portion of the Second Interval ISI Program Plan, Braidwood has supplied 6 appendices (Attachment D) with the submittal. The key features of these Appendices are Unit I and 2 ISI Program Boundary and Isometric / Component Drawings, Unit I and 2 Component Listing / Examination Schedule, Second Interval Schedule Status report, Calibration Block Listing, and Component / Component Support Selection Documents.
Where the implementation of certain Code requirements has been determined to be impractical because of configuration of components, radiation level, or other valid reasons, specific Relief Requests have been included in Section 8 of the controlled portion of the Second Interval ISI Program Plan. Of these requests, approval of12R-05, 12 R-07, 12 R-l l, 12 R-12, 12 R-13, 12 R-14, 12 R-15, 12 R-17, 12 R-25, 12 R-26, 12 R-27,12R-30, and 12R-31 is requested by September 1,1998. Several of these Relief Requests deal with either System Pressure testing (12R-05,11,12,13, 30 and 31) or Containment inspection Program (12R-25,26, and 27) requirements, and are needed to support the Steam Generator Replacement Outage which is schedule to begin in September,1998. The remainder of the Relief Requests (12R-07,14,15 and 17) deal with the implementation of certain ISI Program requirements which affects the population scheduled for the September,1998 refueling outage.
Please note that Relief request 12R-30 references EPRI Report TR-109668-SI, WO4382-01, " Materials Handbook for Nuclear Plant Pressure Boendary Applications." This report, included in the submittal, contains information proprietary to EPRI and is supported by an aflidavit signed by EPRI, the owner of the information
USNRC Document Control Desk 4/ /98 (Attachment B). The aflidavit sets for the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in Paragraph (b)(4) of section 2.790 of the Commission's regulations. Accordingly, it is respectfully requested that the information, which is proprietary to Comed, be withheld from public disclosure in accordance with 10 CFR 2.790 of the Commission's regulations.
It should be noted that a limited number of Relief Requests presented in Braidwood's ISI Program were similr.r to previously approved requests under the First Ten Year Inspection Interval ISI Program. A cross reference between the old Relief Request numbers and the new Relief Request numbers is presented in Attachment A.
Please address any comments or questions regarding this matter to Richard L.
Scliessmann, at (815)458-2801 extension 2038.
Sincerely, f
JSt?4 Timothy J. Tulo Site Vice President Braidwood Nuclear Station TTI,FiroMdnust mei980289t. doe Attachments A - Relief Request Cross Reference B - Proprietary Aflidavit for EPRI Report TR-109668-SI, WO4382-01 C - Inservice inspection Program Plan D -ISI Program Appendices (6) cc:
B. Beach, Regional Administrator - Rill (with Attachments A, C)
S. N. E J'ey, Braidwood Project Manager - NRR (with Attachments A,B,C,D)
C. Phillips, Senior Resident inspector - Braidwood (without Attachments)
OtTice of Nuclear Facility Safety - IDNS (with Attachments A,B,C,D) 1 I
Attachment A Relief Request Cross Reference Second Interval #
First Interval #
Summarv 12R-01 NR-1 Alternative examination for branch pipe connections designed with reinforcement saddles. NR-01 approved via SER Dated 10/04/91.12R-01 was modified to included Rfi to SI piping branch connections.
12R-02 NR-15 Limited surface examination of CV, Rii, and CS pump integral attachment welds. NR-15 approved via SER Dated 10/04/91.12R-02 was modified to included CS pump lugs.
12R-03 NR-18 Limited examination of RC system piping weld due to whip restraint obstructions. NR-18 approved via SER Dated 10/04/91.
12R-04 NR-16 Limited Volumetric examination of MS and FW welds due to ultrasonic scanning obstructions. NR-16 approved via SER Dated 10/04/91.
12R-05 NR-21 Alternative hydrostatic pressure test requirements for ASME Class 1,2 and 3 Repaired / Replaced components, use of Code Case N-416-1. NR-21 approved via SER Dated 9/01/95. No changes for second interval.
12R-06 NR-22 Alternative rules for hydrostatic pressure testing of Class 3 components, use of Code Case N-498-1.
NR-22 approved via SER Dated 9/01/95. No changes for second interval 12R-07 NR-12 RiiR lleat Exchanger Nozzle inside Radius Section.
NR-12 was partially approved on SER Dated 10/04/91 for the inside Radius Section NR-23 RiiR licat Exchanger Nozzle to Vessel weld volumetric exam. NR-23 approved via SER Dated 2/29/96.
12R-08 NR-24 Volumetric examination of the Pressurizer Surge Nozzle-to-Vessel 11ead weld and Surge Nozzle Inside Radius Section. NR-24 approved via SER Dated 5/03/96. No changes for second interval.
Attachment A Relief Request Cross Reference Sgcond I'nterval #
First Interval #
Summarv 12R-09 NR-25 Limited surface examination of the Pressurizer Seismic Lug welds. NR-25 approved via SER Dated 12/1 !/9~/. No changes for second interval.
12R-10 NR-26 Limited surface examinatior. of the piping penetration integral attachment welds. NR-26 approved via SER Dated 12/11/97.12R-10 includes additional penetrations due new inspection boundaries for the second interval.
12R-11 NR-30 Alternate rules to Table IWC-2500-1, Category C-11, pressure testing of containment penetration piping with attached nonclassed piping. NR-30 approved via SER Dated 12/11/97. No changes for second interval.
12R-18 NR-09,38 Limited volumetric examination of the RPV Circumferential Shell welds and Lower Head q
Circumferential welds. NR-09 approved via SER Dated 10/04/91, NR-38 pending review and approval. No changes for second interval.
12R-20 NR-09 Limited volumetric examination of RPV Head-to-Flange weld. NR-09 approved via SER Dated 10/04/91. No changes for second interval.
12R-22 NR-27,37 Limited volumetric examination of the RPV Nozzle-to-Vessel welds. NR-27 approved via SER Ced 12/11/97, ~NR-37 pending review and approval. No changes for second interval
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O Attachment B Proprietary Affidavit for EPRI Report TR-109668-SI, WO4382-01 Material llandbook for Nuclear Plant Pressure Houndary Applications i
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