ML20071G370
| ML20071G370 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 07/06/1994 |
| From: | Saccomando D COMMONWEALTH EDISON CO. |
| To: | Russell W NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20071G374 | List: |
| References | |
| NUDOCS 9407120213 | |
| Download: ML20071G370 (6) | |
Text
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/ Commonwealth Edison
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( Downers Grove, Illiros 60515 July 6,1994 Mr. William Russell, Director Office of Nuclear Reactor Regulation U.S. Nuclear Pogulatory Commission Washington, D.C. 20555 Attention: Document Control Desk
Subject:
Application for Amendment to Facility Operating Licenses:
Byron Station Units 1 and 2 (NPF-37/66; NRC Docket Nos. 50-454/455)
Braidwood Station Units 1 and 2 (NPF 72/77; NRC Docket Nos. 50-456/457)
" Steam Generator Tube Sleeving Methodology"
Reference:
R. Assa letter to D. Farrar transmitting Safety Evaluation for Steam Geriorator Tube Sleeving dated March 4,1994
Dear Mr. Russell,
Pursuant to 10 CFR 50.90, Commonwealth Edison Company (Comed) proposes to amend Appendix A, Technical Specifications of Facility Operating Licenses NPF-37, NPF-66, NPF-72, and NPF 77. The proposed amendment request revises Technical Specification 3/4.4.5, " Steam Generators", and the associated bases. In the Reference letter, Byron and Braidwood were granted amendments to their Technical Specification which authorized the use of the sleeving process. That amendment cited specific references to NRC approved technical reports. This amendment request which incorporates an editorial change, removes specific vendor Technical Report references, and states the reports in generic terms. This amendment requests allows ,
Comed to use advanced NRC approved sleeving processes, and also precludes unnecessarily burdening the Nuclear Regulatory Commission (NRC) with additional amendment requests as new methodologies are perfected for steam generator sleeving processes.
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Mr. Russell July 6,1994 The amendment request is subdivided as follows:
Attachment A: Description and Safety Analysis of Proposed Changes Attachment B: Proposed Revision to the Technical Specifications Attachment C: Evaluation of Significant Hazards Considerations Attachment D: Environmental Assessment The proposed changes have been reviewed and approved by the On-site and Off-site Review Committees in accordance with Comed procedures. Comed has reviewed this proposed amendment in accordance with 10 CFR 50.92(c) and has determined that no significant hazards consideration exists.
Comed is notifying the State of Illinois of our application for these amendments by transmitting a copy of this letter and the associated attachments to the designated State Official.
Comed requests that this proposed amendment, which is editorial in nature be given an expeditious review and approval prior to September 9,1994. Approval of this amendment package would allow Byron to use advanced, NRC approved sleeving processes during the upcoming UnP.1 fall refueling outage.
To the best of my knowledge and belief, the statements contained in this document are true and correct. In some respects these statements are not based on my personal knowledge, but on information furnished by other CECO employees, contractor employees, and/or consultants. Such information has been reviewed in accordance with company practice, and I believe it to be reliable.
Please address any further comments or questions regarding this matter to this office.
Sincerel
(/ l , ,y, W / j _d Denise M. Saccom'an o
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Nuclear Licensing Administrator Attachments cc: R. Assa, Braidwood Project Manager - NRR .
G. Dick, Byron Project Manager - NRR ![,,, OFFICIAL SEAL,-,,,,,,....,,,,,,,,,,,,,!
l H. Peterson, Senior Resident inspector - Byron 3 MAR ( JO YACK h S. G. Dupont, Senior Resident inspector - Braidwood 4 retany punuc statt or attisoiss B. Clayton, Branch Chief - Region til f.uv c uwssmms:nirseyj Office of Nuclear Facility Safety - IDNS 6 ~b : . 94 'fc/
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ATTACHMENT A DESCRIPTION AND SAFETY ANALYSIS OF PROPOSED CHANGES TO APPENDlX A TECHNICAL SPECIFICATIONS OF FACILITY OPERATING LICENSES NPF-37, NPF-66, NPF-72, AND NPF-77 i
- 1. Description of the Proposed Change Commonwealth Edison Company (Comed) requests to amend Technical Specifications (TS) 3.4.5 " Steam Generators" and the associated bases by removing specific vendor Technical Report references. As the current Westinghouse and Babcock & Wilcox (B&W) sleeving processes are upgraded, new Technical Reports will be issued. Under the current Technical Specification, if the new methodology is found acceptable by the NRC Technical Review Staff, Comed would be required to submit another amendment package, requesting authorization to use the improved process. Removing specific references to Technical Report revisions and identifying the reports in generic terms will allow Comed the option to use advanced processes after NRC approval, subject to any limitations and restrictions noted by the NRC staff.
This change will also preclude unnecessarily burdening the NRC with additional amendment requests as new methodologies are perfected for steam generator (SG) sleeving processes.
Additionally, this amendment request contains an editorial change when referencing Babcock & Wilcox Nuclear Service Company. This change refers to the vendor as Babcock & Wilcox Nuclear Technologies (BWNT).
Copies of the Technical Specification and bases page with the changes indicated are included in Attachment B of this submittal.
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- 2. Description of Current Requirements:
The current requirements identified in Technical Specifications Section 3/4.4.5 " Steam Generators" allows the use of the sleeving processes approved in Westinghouse report WCAP-13698 Rev.1 and B&W Topical Report BAW 2045PA Rev.1. The tube repair processes described in the specified vendor Technical Reports are referenced in the Surveillance Requirements, " Acceptance Criteria" and associated bases for the Byron and Braidwood Steam Generators in Technical Specification amendments 58 and 50, respectively.
- 3. Bases for the Current requirements:
The approved sleeving processes for Byron and Braidwood are described in Westinghouse report WCAP-13698 Rev.1 and B&W Topical Report BAW-2045PA Rev.1. The methodologies discussed in these Technical Reports and the additional actions specified in the Byron and Braidwood Technical Specification amendments 58 and 46, respectively, are the alternate tube repair methods authorized for Byron and Braidwood. The Technical Reports describe the Westinghouse laser weld and the B&W kinetic welded sleeving methods currently approved by the Staff. Based on the techniques described in the Technical Reports Byron and Braidwood were authorized to use these sleeving processes.
- 4. Description of the Need for Amending the Technical Specifications:
Byron and Braidwood are requesting a generic wording change when referring to the vendor Technical Reports in the TS 3/4.4.5.4 ' Acceptance Criteria" and the associated bases. Changing the acceptance criteria to reference the current NRC approved Westinghouse and BWNT Technical Reports will reduce the burden and expense for Byron and Braidwood by eliminating the need for additional amendment requests, in referencing the current NRC approved Technical Report, the burden on the NRC Technical Review staff for review of additional amendment requests can also be minimized. As new methodologies are developed for the Westinghouse and BWNT sleeving processes, Comed will have the option to use the advanced process after NRC approval, subject to any limitations and restrictions noted by the NRC staff.
Another editorial change is requested to refer to Babcock & Wilcox Nuclear Service Company as Babcock & Wilcox Nuclear Technologies.
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! 5. Description of the Proposed Amendment:
Specification 4.4.5.4. Steam Generator Acceotance Criteria Current Specification:
- a. 10) a) " Laser welded sleeving as described by Westinghouse Report WCAP-13698, Rev.1, or" Replace with:
" Laser welded sleeving as described in a Westinghouse Technical Report currently approved by the NRC, subject to the limitations and restrictions as noted by the NRC staff, or" Current Specification:
a.10) b) " Kinetic welded sleeving as described by Babcock & Wilcox Topical Report B AW 2045PA, Rev.1."
Replace with:
" Kinetic welded sleeving as described in a Babcock & Wilcox Nuclear Technologies Technical Report currently approved by the NRC, subject to the limitations and restrictions as noted by the NRC staff."
Bases for 3/4.4.5, S. team Generators in the bases section, an editorial change is required to eliminate the reference to a specific Technical Report approved by the NRC. This change will delete the Westinghouse WCAP-13698 Rev.1 and the B&W Topical Report BAW-2045PA Rev.1 references in the second and third paragraphs. The references will be replaced with the generic words used in Insert "C". This change will assist Byron and Braidwood in minimizing the duplication effort and expense of submitting additional amendment requests.
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- 6. Bases of the Proposed Amendment:
The Steam Gr.cerator sleeving processes approved by the NRC for Byron and Braidwood stations currently specify a distinct vendor Topical Report. As advances in -
sleeving processes are made, Byron and Braidwood would be required to submit additional TS changes in order to use these new techniques. Changing the TS
" Acceptance Criteria" to reference the current NRC approved Westinghouse and DWNT Technical Reports can reduce this burden and expense for Byron and Braidwood. Also the burden on the NRC staff can be reduced by eliminating additional Omendment requests requiring review as new methodologies are developed for the sleeving processes.
- 7. Impact of the Proposed Change:
The original amendment requested approval of Steam Generator sleeves installed using the Westinghouse process (laser welded joints) or the B&W process of kinetically welded joints. The current requirements identif!ed in Technical Specifications section 3/4.4.5 " Steam Generators" allow the use of the sleeving processes approved in Westinghouse report WCAP-13698 Rev.1 and B&W Topical Report BAW-2045PA Rev.1. Referencing the current NRC approved Westinghouse or BWNT Steeving Technicai Geports subject to the limitations and restrictions as noted by the NRC, has no effect upon design transients and accident analyses.
e The implementation of the proposed tube repair method does not introduce significant or adverse c' 'ges to the plant design basis. Use of laser welded or kinetically welded sleeving processes approved by the NRC will continue to maintain the overall tube bundle structural integrity at a level consistent with that of the originally supplied tubing during all plant conditions.
Based on the above, the proposed amendment request has no significant negative impact on any system or operating mode.
- 8. Schedule Requiroments:
Byron and Braidwood have been authorized to use the sleeving processes from Westinghouse and BWNS in Technical Specification amendments 58 and 46, respectively. Comed requests this supplemental amendment be given an expeditious review and approval prior to September 9,1994. This woulo allow the use of any advanced technological improvements in the sleeving processes during the upcoming Byron Unit 1 refueling outage.
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