ML20217P726
| ML20217P726 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 04/08/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217P724 | List: |
| References | |
| NUDOCS 9804100167 | |
| Download: ML20217P726 (3) | |
Text
'
f U:
p
'l UNITED STATES g
NUCLEAR REGULATORY COMMISSION o*
WASHINGTON, D.C. acceMe01 l
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RFI ATED TO AMENDMENT NO.178 TO FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT NO.160TO FACILITY OPERATING LICENSE NPF-17 l
DUKE ENERGY CORPORATION MCGUIRE NUCI FAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370
1.0 INTRODUCTION
By letter dated December 17,1997 Duke Energy Corporation (the licensee) submitted a request for changes to the McGuire Nuclear Station, Units 1 and 2, Technical Specifications (TS). The requested changes would revise TS Section 6.9.1.9 to reference updated or recently i
approved topical reports, which contain methodologies used to calculate cycle-specific limits contained in the Core Operating Limits Report (COLR). These topical reports have all been previously approved by the staff under licensing actions separate from the current amendment i
request.
2.0 EVALUATION Generic Letter 88-16 provided guidance on removing cycle-specific parameters that are calculated using NRC-approved methodologies from the TS. The parameters are to be replaced in the TS with a reference to the approved report. By letter dated December 17,1997, the licensee proposed changes that reflect the current versions of these reports.
The licensee has proposed to update the listing for the COLR in TS Section 6.9.1.9, as follows:
Topical Report BAW-10168P-A, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants"- The licensee proposed to add Revision 2 (approved by letter dated August 22,1996, R. Jones, NRC, to J. H. Taylor) and Revision 3 (approved by letter dated June 15,1994, M. Virgilio, NRC, to J. H. Taylor) to the reference. The licensee's amendment request inadvertently omitted the "-A' designation at the end of the topical report number. The staffs correction of this typographical error in the TS page is purely editorial, and does not change the staffs original proposed no significant hazards determination. Since these revisions were previously ' approved for the McGuire Nuclear Station, Units 1 and 2, their addition to Specification 6.9.1.9 is acceptable.
Topical Report DPC-NE-3002A, "FSAR Chapter 15 System Transient Analysis Methodology"-
The licensee proposed to add "Through Rev. 2" to this reference. Revision 2 was approved by 9804100167 980408 i
PDR ADOCK 05000369 i
P PM
. letter dated April 26,1996, H. N. Berkow, NRC, to M. S. Tuckman, formally Duke Power Company (DPC). The licensee's amendment request inadvertently omitted the 'A' designation at the end of the topicel report number. The staffs correction of this typographical error in the TS page is purely editorial, and does not change the staffs original proposed no significant hazards determination. Since these revisions were previously approved for as McGuire Nuclear Station, Units 1 and 2, their addition to Specdication 6.9.1.9 is acceptable.
Topical Report DPC-NE-3000P-A, Rev.1, " Thermal-Hydraulic Transient Analysis ":"-T-:'c-gy"
- The proposed change is considered editorial. It clarifies the approval date as " December 27, 1995," from " December 1995." The licensee's submittal inadvertently omitted the "-A"
,, designation at the. end of the topical report number. The staffs correction of this typographical error in the TS page is purely editorial, and does not change the staffs original proposed no significant hazards determination. Since this revision was previously approved for the McGuire Nuclear Station, Units 1 and 2, its addition to Specification 6.9.1.9 is acceptable.
Topical Report DPC-NE-iOO4A, Rev.1 " Nuclear Design Methodology Using CASMO-3/
SIMUt. ATE-3P"- The licensee proposed to replace the original with Revision 1, which was approved by letter dated April 26,1996, R. E. Martin, NRC, to M. S. Tuckman, DPC. Since Revision 1 was previously approved for the McGuire Nuclear Station, Units 1 and 2, its replacement is acceptable.
Topical Report DPC-NE-2004P-A, Rev.1, " Duke Power Company McGuire and Catawba
- Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01"- Revision 1 was approved by letter, P. S. Tam, NRC, to M. S. Tuckman, DPC, dated February 20,1997 (filed under TACs M97139 and M97140) Since Revision 1 ws; previously approved for the McGuire Nuclear Station, Units 1 and 2, its replacement is acceptable, Topical Report DPC-NE-2005P-A, Rev.1, " Thermal Hydraulic Statistical Core Design Methodology"- Revision 1 was approved by letter, H. N. Berkow, NRC, to M. S. Tuckman, DPC, dated November 7,1996. Since Revision 1 was previously approved for the McGuire Nuclear Station, Units 1 and 2, its replacement is acceptable. Also, the designation "NE " was added to the topical report number, which is consistent with other DPC topical report numbering.
. Topical Report DPC-NE-2008P-A, " Fuel Mechanical Reload Analysis Methodology Using TACO 3," April 3,1995 - Currently, Babcock and Wilcox (B&W) Topical Report BAW-10162P-A is referenced. By letter, H. N. Berkow, NRC, to M. S. Tuckman, DPC, dated April 3,1995, the staff approved transfer of the fuel performance code TACO 3 from B&W to DPC for reload licensing applications. The licensee's request for amendment inadvertently omitted the *P-A" designation at the end of the topical report number. The staffs correction of this typographical error in the amended TS page is purely editorial, and does not change the staffs original proposed no significant hazard determinatum. The proposed replacement of BAW-10162P-A with DPC-NE-2008P-A reflects the staffs previous approval, and is acceptable.
Topical Report BAW-10183P-A, " Fuel Rod Gas Pressure Criterion," B&W Fuel Company, July 1995 - The licensee proposed to reference the approved version, dated July 1995. The licensee's request for amendment inadvertenty omitted the "A " designation at the end of the
F
. topical report number. The staff's correction of this typographical error in the amended TS page is purely editorial, and does not change the staff's original proposed no significant hazards determination. This change, as corrected, reflects the approved status of the topical report and is acceptable.
The use of NRC-approved methodologies will ensure that values for cycle-specific parameters are determined consistent with applicabis levels of the plant safety analysis. Therefore, the proposed changes are acceptable.
3.0 SIATE CONSULTATION In accordance with the Commission's regulations, the North Carolina State official was notifed.
of the proposed issuance of the amendments. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for 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 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
i Principal Contributor: Frank Rinaldi Date:
April 8, 1998
.