ML20058H002
| ML20058H002 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/03/1993 |
| From: | Blough A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058H005 | List: |
| References | |
| NUDOCS 9312100228 | |
| Download: ML20058H002 (7) | |
Text
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'o UNITED STATES
[, gr [,,p, NUCLEAR REGULATORY COMMISS'.ON rj WASHINGTON, D. C. 20555 kV p#
NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 109 License No. DPR-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated July 29, 1993, 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 2.C.(2) of Facility Operating License No. DPR-42 is hereby amended to read as follows:
9312100228 931203 DR ADOCK 05000282 PDR
i Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.109, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A. Randolph Blough, Acting Director Project Directorate III-I Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: Decater 3,1993 i
l t
5 ATTACHMENT TO LICENSE AMENDMENT NO.109 FACILITY OPERATING LICENSE NO. DPR-42 DOCKET NO. 50-282
{
t Revise Appendix A Technical Specifications by removing the pages identified i
below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVf INSERT
{
TS 6.7-5 TS 6.7-5 l
i I
i
TS.6.7-5 XN-NF-77-57 (A), XN-NF-77-57, Supplement 1 (A), " Exxon Nuclear Power Distribution Control for Pressurized Water Reactors Phase II", May, 1981 WCAP-13677, "10 CFR 50.46 Evaluation Model Report: E-COBRA / TRAC 2-Loop Upper Plenum Injection Model Update to Support ZIRIA Cladding Options", April 1993 (approved by NRC SE dated November 26, 1993).
NSPNAD-93003-A, " Transient Power Distribution Methodology",
(latest approved version)
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
- d. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be supplied upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
L. REPORTABLE EVENTS The following actions shall be taken for REPORTABLE EVENTS:
- a. The Commission shall be notified by a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and
- b. Each REPORTABLE EVENT shall be reviewed by the Operations Committee and the results of this review shall be submitted to the Safety Audit Committee and the Vice President Nuclear Generation.
Prairie Island Unit 1 Amendment No. 52, $3,109 Prairie Island Unit 2 Amendment No. EE, EE,102
.f' " *%'o, UNITED STATES C
8 NUCLEAR REGULATORY COMMISSION o
a.
ey WASHINGTON, D. C. 20555
\\...../
i NORTHERN STATES POWER COMPANY DOCKET NO. 50-306
\\
PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. DPR-60 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated July 29, 1993, 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 (1) 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 2.C.(2) of Facility Operating License No. DPR-60 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.102, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A. Randolph Blough, Acf5.. A[
i hg ".r<etor Project Directorate 111-1 Division of Reactor Projects - III/IV/V Office of Nuclect Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: [bcerter 3,1993 J
li
?
ATTACHMENT TO LICENSE AMENDMENT NO. in?
FACILITY OPERATING LICENSE NO. DPR DOCKET NO. 50-306 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
j REMOVE INSERT l
TS 6.7-5 TS 6.7-5 l
l f
i
.1
\\
l I
g_m 3
TS.6.7-5 j
XN-NF-77-57 (A). IN-NF-77-57, Supplement 1 (A), " Exxon Nuclear Power Distribution Control for Pressurized Vater Reactors Phase II", May, 1981 i
VCAP-13677, "10 CFR 50.46 Evaluation Model Report: E-COBRA / TRAC 2-Loop Upper Plenum Injection Model Update to Support ZIRIA Cladding Options", April 1993 (approved by NRC SE dated November 26 1993)
NSPNAD-93003-A, " Transient Power Distribution Methodology",
(latest approved version)
- c. The core operating limits shall be determined such that all i
applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic ILuits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
- d. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be supplied upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
B. REPORTABLE EVENTS The following actions shall be taken for REPORTABLE EVENTS:
- a. The Commission shall be notified by a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and
- b. Each REPORTABLE EVENT shall be reviewed by the Operations Committee and the results of this review shall be submitted to the Safety Audit Committee and the Vice President Nuclear Generation.
i 1
1 l
Prairie Island Unit 1 Amendment No. $2, $),109 Prairie Island Unit 2 Amendment No. EE, EE,102 I