ML20207P180
| ML20207P180 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 12/29/1986 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| RTR-NUREG-1002 2554K, 86-02, 86-2, NUDOCS 8701150195 | |
| Download: ML20207P180 (3) | |
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bpt 6
. /'N} Commonweenh Edson
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One Fwat Nabonel Plaza. CNcago, Enois
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Address Reply to: poet Omco Box 767 CNca00. Illinois 6C490 0767 December 29, 1986 I
Mr. James G.
Keppler Regional Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL. 60137
Subject:
Braidwood Station Unit 1 10 CFR 50.55(e) Report No. 86-02 Rejectablo-Indications During Preservice Inspection on the Loop 1 Steam Generator i
i and the Pressurizer NRC Docket No. 50-456
References:
(a)
February 11, 1986 A.D. Miosi letter to J.G.
Keppler (b)
NUREG-1002, Safety Evaluation Report, Supplement 1, dated September, 1986 i
(c)
NUREG-LOO 2, Safety Evaluation Report, Supplement 2, dated October, 1986 i
t
Dear Mr. Keppler:
Reference (a)' fulfilled the thirty (30) day reporting requirement and provided interim information concerning the two (2) rejectable weld indications found during Unit 1 preservice inspection at Braidwood Station.
The purpose of this letter is to inform you that the actions necessary to resolve this item have been completed.
This letter is considered to be a final report.
In reference (a), it was stated that a fracture mechanics analysis had been performed that accepted the indications for the forty (40) year plant life and that the analysis had been submitted to NRR for their concurrence.
Reference (b), Section 5.2.4.4, provided NRR's evaluation of this matter and resulted in the following conclusions:
(1)
"The flaws that exceed the standards of Table IEB-3410-1 of Section XI of the ASME Code in the steam generator and pressurizer are most likely slag inclusions resulting from weld fabrication.
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. (2)
Excavation and weld repair of these flaws would not increase the level of quality and safety of the components.
(3)
The fracture mechanics evaluations illustrated in charts in WCAP-llO63 and WCAP-11064 demonstrate that the flaws will not grow during the life of the plant to a size that will affect the integrity of the vessels.
(4)
The proposed alternative provides an acceptable level of quality.and safety, subject to the following examination and test requirements:
(a)
The areas containing the flaws must be inspected in accordance with the inspection interval requirements of IWB-2420 of Section XI of the ASME Code.
(b)
The loop 1 steam generator secondary side hydrotest and leak tests must be performed at temperatures greater than 1650F and 1500F, respectively.
(c)
The pressurizer primary side hydrotest and leak test must be performed at temperatures greater i
than 1200F.
(5)
After the applicant commits to the inservice examination and test requirements of item (4), the applicant will have demonstrated compliance with the criteria in 10CFR 50.55(a)(3).
Hence, the applicant may be permitted to place the pressurizer and loop 1 steam generator into service without weld repair of the two flaws that exceed the preservice acceptance standard of Section XI of the ASME Code."
l Reference (c) Section 5.2.4.4 addressed and accepted Commonwealth Edison's commitment to examine the areas containing the flaws in accordance with the inspection interval requirements of IWB-2420 of Section XI of the ASME Code; to perform the loop 1 steam generator secondary side hydrotests and leak tests at temperatures greater than 1650F and 1500F, respectively; and perform the pressurizer primary side hydrotests and leak tests at temperatures l
greater than 1200F.
As a result, NRR provided in reference (c) l the following conclusion:
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. "On the basis of the fracture mechanics evaluations and commitment to the examination and test requirements discussed in SSER 1, the applicant has demonstrated compliance with the criteria in 10CFR 50.55(a)(3).
Accordingly, the pressurizer and loop 1 steam generator may be placed into service without weld repair of the two flaws that exceed the preservice acceptance standard of Section XI of the ASME Code.
Therefore, Confirmatory Issue B(15) is considered closed."
Please address any questions concerning this matter to this office.
Very truly yours, b
C S.C. Hunsader Nuclear Licensing Administrator
/klj cc:
NRC Resident Inspector-Braidwood 1
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