ML20129F902
| ML20129F902 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/24/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20129F841 | List: |
| References | |
| NUDOCS 9610290233 | |
| Download: ML20129F902 (2) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION if WASHINGTON, D.C. 2056M001 y...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION i
RELATED TO AMENDMENT NO.154 TO FACILITY OPERATING LICENSE NPF-35 AND AMENDMENT NO.146 TO FACILITY OPERATING LICENSE NPF-52 DUKE POWER COMPANY. ET AL.
CATAWBA NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414
1.0 INTRODUCTION
By letter dated August 8,1996, Duke Power Company, et al. (the licensee),
l submitted a request for changes to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS).
Specifically, the licensee proposed to revise Section 6.9.1.9 to reference updated or recently approved methodologies used to calculate cycle-specific limits contained in the Core Operating Limits Report (COLR).
2.0 DISCUSSION AND EVALUATION Generic Letter 88-16 provided guidance on removing cycle-specific parameters that are calculated using NRC-approved methodologies from the Technical Specifications.
Instead, references to named reports, which contain these parameters, are made, and a requirement that the parameters remain within the limits specified in the reports.
The licensee proposed to update the listing for the COLR in TS Section 6.9.1.9 1
as discussed below.
Topical Report BAW-10168P, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants" - Currently, only Revision 1 is referenced. The licensee proposed to add Revisions 2 (approved by letter dated August 22, 1996, R. Jones, NRC, to J. H. Taylor) and 3 (approved by letter dated June 15, 1994, M. Virgilio, NRC, to J. H. Taylor) to the reference. Since these revisions were previously approved for Catawba, their addition to Specification 6.9.1.9 is acceptable.
Topical Report DPC-NE-3002A, "FSAR Chapter 15 System Transient Analysis Methodology" - When the licensee submitted the amendment request, only the original (Revision 0) was referenced.
The licensee proposed to add "through Rev. 2" to this reference.
Revision I was approved by letter dated December 28, 1995, R. E. Martin, NRC, to M. S. Tuckman, DPC; Revision 2 was approved by letter dated April 26, 1996, H. N. Berkow, NRC, to M. S. Tuckman, DPC.
(By Amendment 151, Unit l's reference was updated to Rev. I on August 29,1996.) Since these revisions were previously approved for Catawba, their addition to Specification 6.9.1.9 is acceptable.
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Topical Report DPC-NE-3000P-A, " Thermal-Hydraulic Transient Analysis Methodology" - The licensee proposed to update this reference to Revision 1, which was approved by letter dated December 27, 1995, R. E. Martin, NRC, to M. S. Tuckman, DPC.
(By Amendment 151, Unit l's reference was updated to Revision 1; the net change for Unit 1 is editorial, clarifying the approval date as " December 27, 1995" from " December, 1995".) Since this revision was j
previously approved for Catawba, its addition to Specification 6.9.1.9 is acceptable.
Topical Report DPC-NE-1004A, " Design Methodology Using CASMO-3/ Simulate-i 3P" - Currently, the original (Revision 0) is referenced.
The licensee proposed to replace the original with Revision 1, which was approved by letter i
dated April 26, 1996, R. E. Martin, NRC to M. S. Tuckman, DPC.
Since Revision 1 was previously approved for Catawba, its replacement for Revision 0 is acceptable.
The use of NRC-approved methodologies will ensure that values for cycle-specific parameters are determined consistent with applicable levels of the plant safety analysis.
Therefore, the proposed changes are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no' comments.
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4.0 ENVIRONMENTAL CONSIDERATION
The amendments change recordkeeping, reporting or administrative procedures or requirements. Accordingly', the amendments meet the eligibility criteria for
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categorical exclusion set forth in 10 CFR 51.22(c)(10).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is. reasonable assurance that the health and safety of the i
public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, 4
and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
Peter S. Tam Date: October 24, 1996