ML20199E869
| ML20199E869 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/13/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199E868 | List: |
| References | |
| NUDOCS 9711240017 | |
| Download: ML20199E869 (3) | |
Text
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i UNITFD STATES g
j NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 3068H001 o
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMEMDMENT NO. 154 TO FACILITY OPERATING LICENSE NPF-52 D_ UKE ENERGY CORPORATION. ET AL.
CATAWBA NUCLEAR STATION. UNIT 2 DOCKET NO 50-414 1.0 INTRODUCTIO_N By letter riated May 27,1997, Duke Energy Corporation (licensee, formerly Duke Powt.r Company) proposed a change to the Technical Specifications (TS) for the Catawba NucMar Station, Unit 2. The proposed changes would revise TS section 4.4.5, Steam L.nerator Surveillance Requirements, to delete references to repair criteria (P and attemate tube plugging) and epair methods (sleeving) that are not applicable to the Catawba Unit 2 steam generators. Also, unused paragraph rumbers will be removed and one typographical error will be corrected.
Prior to 1996, Catawba Unit 1 and Unit 2 had a combined TS document. Several TS amendments described below were approved by the staff that permitted the use of steam generator tube sleeves and interim steam generator tube plugging criteria for the tube support plate elevations for Unit 1. These repair methods were contained in the combined TS document. By letter dated July 18,1994, the licensee proposed to split the Catawbc Technical Specification document into separate documents for Unit 1 and Unit 2. As a resen, the staff issued Amendments 148 for Unit 1 and 142 for Unit 2 on June 12,1996, splitCng the joined TS document into two separate documents. Both the staff and the licensee did 1ot recognize then that the steam generator tube repair methods were applicable to Unit 1 only and were not applicable to the Unit 2 steam generators, which are different from the design of Unit 1.
2.0 EVALUAT10B The following were previous amendments to the TS that were involved with steam generator tube repair and sleeving.
By application dated December 19,1990, the licensee proposed a revision to the Catawba TS l
to allow the option of using the B&W (Babcock & Wilcox) Kinetic Sleeving Process for 3/4-inch OD Tube Repair as described in Topical Report BAW-2045(P)-A. This proposed amendment was approved as Amendment 84 for Unit 1 and Amendment 78 for Unit 2 on March 4,1991.
On May 19,1992, the licensee submitted a proposed amendment to the Catawba TS. This proposed revision would allow the use of B&W Kinetic Sleeving Process, as described in 9711240017 971113 PDR ADOCK O 4y4 i
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L o # p Topical Report BAW 2045P, Rev.1 ' Recirculating Steam Generator Kinetic Sleeve Quahfications for 3/4 inch OD Tubes,' to repair steam generator tubes. As a result, the staff issued Amendment 99 for Unit 1 and Amendment 93 for Unit 2 on August 14,1992.-
By application dated August 24,1992, the !!censee proposed a revisio' to the Catawba TS to allow the implementation of interim steam generator tube plugging criteria for the tube support plate elevations for Unit 1, Cycle 7. The application was approved as Amendment 102 for Unit 1 and 96 for Unit 2 on Sept $mber 25,- 1992, to permit the use of the interim plugging criteria for Unit 1. The licensee later submitted an application dated Octobe' 5,1993, which requested changes to the TS that would allow the continuance of voltage-b.aed steam generator tube plugging criteria for defects located at the tube support elevations. The application also proposed administrative changes to preserve the current combined TS -
applicable to Unit 2. ' As a result, the staff lasued Amendment 111 for Unit 1, and 1
Amendment 105 for Unit 2, on December 16,1993.
The proposed clianges to the Catawba Un". 2 TS delete repair criteria (F* and Attomate Tube Plugging) and repair methods (sleeving) that are not applicable to the Catawba Unit 2 steam
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generators. These criteria have not been used and are not applicable to the Westinghouse Model Dd steam generators in use at Catawba Unit 2. The repair methods were applicable to Catawba Unit 1, Westinghouse D3 steam generators, which were in use prior to their replacement in 1996 with B&W-designed steam generators. By Amendment No.151 to Unit 1, the staff approved use of the new steam generators and deleted similar repair criteria and repair methods from the Unit 1 TS.
l The licensee proposes to revise Catawba Unit 2 TS Section 3/4.4.5 as follows:
Section 4.4.5.2, Steam Generator Tube Sample Selection and Inspection - Delete unused paragraph number "c" and "e" and renumber "d* to 'c." This change is editorial and is acceptable, j
. Section 4.4.5.4, Acceptance Criteria - All references to sleeves, repair process, F* distance, attomate tube plugging criteria, tube roll expansion, and an unused paragraph number will be deleted. " Repair" limit will be replaced with " plugging' limit. These changes delete references to a repair method that is not applicable to Unit 2..
Section 4.4.5.5, Reports - In paragraphs a and b.3, replace tubes ' repaired
- with tubes
'plegged." These changes are consistent with the removal of the inapplicable repair method and are, thus, acceptable. Also, the deletion of unused paragraph numbers d and e is an y
editorial change and is acceptable.
l Table 4.4-2, Steam Generator Tube Inspection - Correction of a typographical error, ' deflective" to " defective.'
l E
.3-h Bases Section 3/4.4.5, STEAM ' GENERATORS - The second paragraph referring to the sleeving process will be deleted. Also, references to repairing and alternate tube plugging -
criteria will be deleted, replaced with references to plugging criteria. These changes delete references to a repair method that is not applicable to Unit 2.
These proposed changes will make the Unit 2 stssm generator surveillance requirements consistent with the Standard Technical Specifications, NUREG-0452, Rev. 4. The staff finds the proposed changes acceptable.
3.0 STATE CONSULTATIOff in accordance with the Commission's regulations, the South Carolina State official wPs notifMKi -
of the proposed issuance of the amendments. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes requirements with respect to installation or use of a facility component located within the restricted area, and makes changea, to surveillance requirements.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the typaa, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (62 FR 33122 dated June 18,1997). Accordingly. the amendment meets the eligibility enteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
. The staff has concluded, based on the considerations discusseo above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Andrea T. Keim p
Date: November 13, 1997
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