ML14183A279
| ML14183A279 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 12/12/1994 |
| From: | Bateman W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A280 | List: |
| References | |
| DPR-23-A-154 NUDOCS 9412150055 | |
| Download: ML14183A279 (6) | |
Text
UNITED STATES 0
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 154 License No. DPR-23
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee), dated October 7, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 3.B. of Facility Operating License No. DPR-23 is hereby amended to read as follows:
9412150055 941212 PDR ADOCK 05000261 P
-2 B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 154, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION illiam H. Ba an, Director Project Directorate II-1 I
Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 12, 1994
ATTACHMENT TO LICENSE AMENDMENT NO. 154 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Pages Insert Pages 6.9-13 6.9-13 6.9-14 6.9-14 6.9-18 6.9-18
6.9.3.3.b The ana cal methods used to determine b core operating limits shall be those previously reviewed and approved by the NRC. The approved revision number shall be identified in the COLR.
.a) XN-75-27(A), latest Revision and Supplements, "Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors." Exxon Nuclear Company. Richland WA 99352.
(Methodology for Specifications 3.1.3.1 - Moderator Temperature Coefficient. 3.10.1.2 - Shutdown Bank Insertion Limits, 3.10.1.3 and 3.10.1.4 - Control Bank Insertion Limits, 3.10.2.1, 3.10.2.2, 3.10.2.2.1, 3.10.2.2.2 - Heat Flux Hot Channel Factor. 3.10.2.1 Nuclear Enthalpy Rise Hot Channel Factor, and 3.10.2.2, 3.10.2.2.1. 3.10.2.2.2, 3.10.2.7. 3.10.2.9, and 3.10.2.11 - Axial Flux Difference) b)
XN-NF-84-73(P). latest Revision and Supplements, "Exxon Nuclear Methodology for Pressurized Water Reactors: Analysis of Chapter 15
.Events," Exxon Nuclear Corporation, Richland WA 99352 (Accepted by the NRC for H. B. Robinson Unit 2 in the Safety Evaluation by the Office of Nuclear Reactor Regulation related to Amendment No.
87 to Facility License No. DPR-23. 7 Nov. 84).
(Methodology for Specifications 3.1.3.1 - Moderator Temperature Coefficient, 3.10.1.2 - Shutdown Bank Insertion Limits. 3.10.1.3 and 3.10.1.4 - Control Bank Insertion Limits, 3.10.2.1, 3.10.2.2, 3.10.2.2.1. 3.10.2.2.2 - Heat Flux Hot Channel Factor. 3.10.2.1 Nuclear Enthalpy Rise Hot Channel Factor, and 3.10.2.2, 3.10.2.2.1, 3.10.2.2.2. 3.10.2.7, 3.10.2.9, and 3.10.2.11 - Axial Flux Difference) c)
XN-NF-82-21(A), latest Revision, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company. Richland WA 99352.
(Methodology for Specification 3.10.2.1 - Nuclear Enthalpy Rise Hot Channel Factor) 6.9-13 Amendment No. T*L,154
d)
XN-NF-8@3(A), latest Revision and Sups ents, "Steamline Break Methodology for PWR's," Exxon Nuclear Corporation, Richland, WA 99352.
(Methodology for Specifications 3.1.3.1 - Moderator Temperature Coefficient, 3.10.1.2 - Shutdown Bank Insertion Limits, 3.10.1.3 and 3.10.1.4 - Control Bank Insertion Limits, 3.10.2.1 - Nuclear Enthalpy Rise Hot Channel Factor.)
e)
XN-75-32(A), Supplements 1, 2, 3, 4, "Computational Procedure for Evaluating Rod Bow," Exxon Nuclear Company, Richland WA 99352.
(Methodology for Specifications 3.10.2.1, 3.10.2.2, 3.10.2.2.1, 3.10.2.2.2 - Heat Flux Hot Channel Factor, 3.10.2.1 - Nuclear Enthalpy Rise Hot Channel Factor) f)
XN-NF-82-49(A), latest Revision and Supplements. "Exxon Nuclear Com any Evaluation Model EXEM PWR Small Break Model," Exxon Nuclear Company, Richland WA 99352.
(Methodology for Specifications 3.10.2.1, 3.10.2.2, 3.10.2.2.1, 3.10.2.2.2 - Heat Flux Hot Channel Factor, 3.10.2.1 - Nuclear Enthalpy Pise Hot Channel Factor, and 3.10.2.2, 3."J.2.2.1, 3.10.2.2.2. 3.10.2.7, 3.10.2.9, and 3.10.2.11 - Axial Flux Difference) g)
EXEM PWR Large Break LOCA Evaluation Model as accepted in Letter, D. M. Crutchfield (NRC) to G. N. Ward (ENC), "Safety Evaluation of Exxon Nuclear Company's Large Break ECCS Evaluation Model EXEM/PWR and Acceptance for Referencing of Related Licensing Topical Reports," July 8, 1986.
EXEM PWR LBLOCA Model includes the following references:
XN-NF-82-20(P). latest Revision and Supplements, "Exxon Nuclear Company Evaluation Model EXEM/PWR ECCS Model Updates," Exxon Nuclear Company. Richland WA 99352.
6.9-14 Amendment No. ML154
q)
AN08-133 (P)(A), "Qualification d& dvanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 Gwd/MTU,"
Advanced Nuclear Fuels Corporation, Richland WA 99352, latest revisions and supplements.
(Methodology for Specifications 3.10.2.1, 3.10.2.2, 3.10.2.2.1, 3.10.2.2.2 - Heat Flux Hot Channel Factor, 3.10.2.1 - Nuclear Enthalpy Rise Hot Channel Factor).
r)
ANF-89-151(A), latest Revision and Supplements, "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, Richland WA 99352.
(Methodology for Specifications 3.1.3.1 - Moderator Temperature Coefficient; 3.10.1.2 - Shutdown Bank Insertion Limits: 3.10.1.3 and 3.10.1.4 - Control Bank Insertion Limits: 3.10.2.1. 3.10.2.2, 3.10.2.2.1 and 3.10.2.2.2 - Heat Flux Hot Channel Factor; 3.10.2.1 - Nuclear Enthalpy Rise Hot Channel Factor, and 3.10.2.2, 3.10.2.2.1, 3.10.2.2.2, 3.10.2.7, 3.10.2.9, and 3.10.2.11 - Axial Flux Difference) s)
EMF-92-081(A), latest Revision and Supplements, "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors." Siemens Power Corporation - Nuclear Division.
Richland, WA 99352 (Methodology for Specifications 3.1.3.1 - Moderator Temperature Coefficient; 3.10.1.2 - Shutdown Bank Insertion Limits: 3.10.1.3 and 3.10.1.4 - Control Bank Insertion Limits; 3.10.2.1. 3.10.2.2, 3.10.2.2.1 and 3.10.2.2.2 - Heat Flux Hot Channel Factor; 3.10.2.1 - Nuclear Enthalpy Rise Hot Channel Factor, and 3.10.2.2, 3.10.2.2.1, 3.10.2.2.2, 3.10.2.7, 3.10.2.9. and 3.10.2.11 - Axial Flux Difference) 6.9.3.3.c The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
6.9.3.3.d The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the Document Control Desk with copies to the Regional Administrator and Resident Inspector.
6.9-18 Amendment No.
,N,154