ML20046C803
| ML20046C803 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/26/1993 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO) |
| Shared Package | |
| ML20046C804 | List: |
| References | |
| NPF-49-A-081 NUDOCS 9308120196 | |
| Download: ML20046C803 (6) | |
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UNITED STATES 1 (; ~,/!
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-4001 NORTHEAST NUCLEAR ENERGY COMPANY. ET AL, DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT N0. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 License No. NPF-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated March 15, 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; 8.
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 reqcirements have been satisfied.
9308120196 930726 PDR ADOCK 05000423 P
r 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. NPF-49 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 81
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/
/ohn F. Stolz, Direc or
' Project Directorate I-4 Di1Tision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 26,1993
ATTACHMENT TO LICENSE AMENDMENT NO. 81 FACILITY OPERATING LICENSE NO NPF-42 DOCKET NO. 50-423 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert I
5-5 5-5 6-20 6-20 6-20A t
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9 DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies.
Each fuel assembly shall consist of 264 zircaloy-4 or ZIRLO clad fuel rods with an initial composition of natural uranium dioxide or a maximum nominal enrichment of 5.0 weight percent U-235 as fuel material.
Limited substitutions of zircaloy-4, ZIRL0 or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used.
Fuel assembly configurations shall be limited to those fuel designs that. have been analyzed with applicable NRC staff-approved codes and methods, and shown by test or cycle-. specific reload analyses to comply with all fuel safety design bases.
Each fuel rod shall have a nominal active fuel length of 144 inches.
A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.
CONTROL R00 ASSEMBLIES 5.3.2 The core shall contain 61 full-length control rod assemblies.
The I
full-length control rod assemblies shall contain a nominal 142 inches of absorber material.
The nominal values of absorber material shall be 95.3%
j hafnium and 4.5% natural zirconium or 80% silver,15% indium, and 5% cadmium.
All control rods shall be clad with stainless steel.
5.4 REACTOR COOLANT SYSTEM i
DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
a.
In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2500 psia, and c.
For a temperature of 650*F, except for the pressurizer which is 680*F.
VOLUME l
5.4.2 The total water and steam volume of the Reactor Coolant System is 12,240 cubic feet at a nominal T f 587'F.
avg 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-3.
MILLSTONE - UNIT 3 5-5 Amendment No. 42, 77,81 oils
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Cont.)
~
2.
Shutdown Rod Insertion Limit for Specification 3/4.1.3.5, 3.
Control Rod Insertion Limits for Specification 3/4.1.3.6, ND 4.
Axial Flux Difference Limits, target band, and APL for Specifica-tions 3/4.2.1.1 and 3/4.2.1.2, ND 5.
Heat Flux Hot Channel Factor, K(z), W(z), APL
, and W(z)BL fr Specifications 3/4.2.2.1 and 3/4.2.2.2.
6.
Nuclear Enthalpy Rise Hot Channel Factor, Power Factor Multiplier for Specification 3/4.2.3.
6.9.1.6.b The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:
1.
WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"
July 1985 (H Proprietary). (Methodology for Specifications 3.1.1.3--
Moderator Temperature Coefficient, 3.1.3.5--Shutdown Bank Insertion Limit, 3.1.3.6--Control Bank Insertion Limits, 3.2.1--Axial Flux Difference, 3.2.2--Heat Flux Hot Channel Factor, 3.2.3--Nuclear Enthalpy Rise Hot Channel Factor.)
2.
WCAP-8385, " Power Distribution Control and Load Following Procedures - Topical Report," September 1981 (W Proprietary).
3.
T. M. Anderson to K. Kniel (Chief of Core Performance Branch, NRC),
January 31, 1980--
Attachment:
Operation and Safety-Analysis Aspects of an Improved Load Follow Package.
4.
NUREG-800, Standard Review Plan, U.S. Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981 Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC),
Revision 2, July 1981.
5.
WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION," June 1983 (H Proprietary).
(Methodology for Specifications 3.2.1--Axial Flux Difference
[ Relaxed Axial Offset Control) and 3.2.2--Heat Flux Hot Chan'nel Factor [W(z) surveillance requirements for F Methodology].)
g 6.
WCAP-9561-P-A, ADD. 3, Rev. 1, "BART A-1:
A COMPUTER CODE FOR THE BEST ESTIMATE ANALYSIS OE REFLOOD TRANSIENTS--SPECIAL REPORT:
THIMBLE MODELING H ECCS EVALUATION MODEL," July 1986 (H Proprie-tary).
(Methodology for Specification 3.2.2--Heat Flux Hot Channel Factor.)
7.
WCAP-10266-P-A, Rev. 2, "THE 1981 VERSION OF WESTINGHOUSE EVALVATION MODEL USING BASH CODE," March 1987 (W Proprietary).
(Methodology for Specification 3.2.2--Heat Flux Hot Channel Factor.)
MILLSTONE - UWIT 3 6-20 Amendment No. 7f, 77, ES, 59,81 0117
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Cont.)
8.
WCAP-11946, " Safety Evaluation Supporting a More Negative E0L Moderator Temperature Coefficient Technical Specification for the Millstone Nuclear Power Station Unit 3," September 1988 (M Proprie-tary).
9.
WCAP-10054-P-A, " WESTINGHOUSE SMALL BREAK ECCS EVALUATION H0 DEL USING THE NOTRUMP CODE," August 1985 (H Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
10.
WCAP-10079-P-A, "NOTRUMP - A N0DAL TRANSIENT SMALL BREAK AND GENERAL NETWORK CODE," August 1985 (H Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
11.
WCAP-12610, " VANTAGE + Fuel Assembly Report," June 1990 (W Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
l MILLSTONE - UNIT 3 6-20a Amendment No. 81 0117