ML20209G299
| ML20209G299 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/13/1999 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20209G303 | List: |
| References | |
| NUDOCS 9907190118 | |
| Download: ML20209G299 (13) | |
Text
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UNITED STAT'ES g
j NUCLEAR REGULATOR) COMMISSION 2
WASHINGTON, D.C. 20666 4001 o%
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NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO.50-33G MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 237 License No. DPR-65
- 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 19,1999, 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 requirements have been satisfied.
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ADOCK 05000336 PUR
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. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this iicense amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 237, are hereby incorporated in the license. The licensee shall operate the facilityin accordance with the Technical Specifications.
- 3. The license amendment is effective as of its date of issuance and shall be implemented at the facility within 60 days (including issuance of Technical Requirements Manual for use by licensee personnel), in addition, the licensee shallinclude the relocated information in the Updated Final Safety Analysis Report submitted to the NRC, pursuant to 10 CFR 50.71(e),
as was described in the licensee's application dated March 19,1999, and evaluated in the staff's safety evaluation dated FOR THE NUCLEAR REGULATORY COMMISSION e
J mes W. Clifford, Chief, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to ths Technical Specifications Date of issuance: July 13, 1999 I
ATTACHMENT TCLLICENSE AMENDM6NT NO. 237__.
FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the fol'owing pages of the Apperidix A Technical Specifications with the att lines indicating the areas of change. revised pages. The revised pages ar Remove Insert V
y 3/4 3-30 3/4 3-30 3/4 3-32 3/4 3-32 3/4 3-33 3/4 3-33 3/4 3-34 3/4 3-34 3/4 3-35 3/4 3-35 3/4 3-36 3/4 3-36 3/4 3-37 3/4 3-37 3/4 3-38 3/4 3-38 8 3/4 3-3 8 3/4 3-3 l
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m-lHDil LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIRENENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE.................... 3/4 2-1 3/4.2.2 Deleted 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - Ff......
3/4 2-9 3/4.2.4 AZIMUTHAL POWER TILT
.................. 3/4 2-10 3/4.2.5 Deleted 3/4.2.6 DNB MARGIN....................... 3/4 2-13 i
3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION...........
3/4 3-10 3/4.3.3 MONITORING INSTRUMENTATION 3/4 3-26 Radiation Monitoring 3/4 3-26 Remote Shutdown Instrumentation............. 3/4 3-39 Accident Monitoring...................
3/4 3-46 Radioactive Liquid Effluent Monitoring Instrumentation 3/4 3-50 l
Radioactive Gaseous Effluent Monitoring Instrumentation.
3/4 3-56 1
3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT-LOOPS AND COOLANT CIRCULATION..........
3/4 4-1 Startup and Power Operation...............
3/4 4-1 Hot Standby.......................
3/4 4-la 3/4 4-lb Shutdown Reactor Coolant Pumps - Shutdown 3/4 4-Id i
MILLSTONE - UNIT 2 V
Amendment No. JJ. 75. 77 #7.
0457 pp, Jpf, JJs, JEJ, JEE, J9J237
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. MILLSTONE - UNIT 2 3/4 3-30 Amendment No. JJ, JJ,177, JJJi, JJJ. 237 J
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MILLSTONE - UNIT'2--
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1 MILLSTONE - UNIT 2 3/4 3-34 Amendment No. 237 04so 1
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7,.-e,LSTONE - UNIT 2 NIL 3/4-3-35 Amendment No. 237 7
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MILLSTONE - Unit 2 3/4 3-36.
Amendment No. #J,237
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NIgLSTONE-UNIT 2 3/4 3-37 Amendment No. f). 177, 237 4
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.NILLSTONE.- UNIT 2 3/4 3-38 Amendment No. 237 04sa
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INSTRUNENTATION BASES
~3/4.3.3.2 - DELETED 3/4.3.3.3 - DELETED 3/4 t 3.4 - DELETED 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the facility from locations outside of the centrol room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
9 Mli.LSTONE - UNIT 2 B 3/4 3-3 Amendment No. 7)i. #, 237 0458