ML20212B718
| ML20212B718 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/14/1999 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212B721 | List: |
| References | |
| NUDOCS 9909200223 | |
| Download: ML20212B718 (11) | |
Text
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k UNITEDGTATES y r-B NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 2055f>441
%,.....f PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY l
ATLANTIC CITY ELECTRIC COMPANY l
DOCKET NO. 50-272 1
l SALEM NUCLEAR GENERATING STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 224 License No. DPR-70 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric & Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the ligensees) dated July 2,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the l
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; I
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 set forth in 10 CFR Chapter I; 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.
l 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-70 is hereby amended to read as follows:
l 9909200223 990914 PDR ADOCK 05000272 P
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through l
Amendment No. 224, are hereby incorporated in the license. The licensee shall l
operate the facility in accordance with the Technical Specifications.
1 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days. In addition, the licensee shall include the relocated information in the Updated Final Safety Analysis Report submitted to the NRC, pursuant to 10 CFR 50.71(e),
l as was described in the licensee's application dated July 2,1999, and evaluated in the staff's safety evaluation dated September 14, 1999.
4 FOR THE NUCLEAR REGULATORY COMMISSION h
i J mes W. Clifford, Chief, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: September 14, 1999
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l ATTACHMENT TO LICENSE AMENDMENT NO. 224 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
1 Remove Paaes Irisert Paaes IV ly Xil XII 3/4 3-70 3/4 3-71 t
8 3/4 3-4 B 3/4 3-4 B 3/4 3-5 l
"/
0 INDEX LIMITING CONDITIONS FOR' OPERATION AND SURVEILLANCE REQUIREMENTS FEE.Tl2N.
PAGE I'
3/4.2 POWER' DISTRIBUTION LIMITS 3/4.2.1-AXIAL FLUX DIFFERENCE 3/4 2-1 3/4.2.2 HEAT--FLUX HOT CHANNEL FACTOR 3/4 2-5
'3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO 3/4 2-11 l
3/4.2.5 DNB PARAMETERS 3/4 2-13 l
l 3/4.3 INSTPUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM
.INSTRUMENTASION 3/4 3-14 l
l
.3/4.3.3 MONITORING INSTRUMENTATION-L
. Radiation Monitoring Instrumentation 3/4 3-35 l
Movable Incore Detectors 3/4 3-39 Remote Shutdown Instrumentation 3/4 3-46 Accident Monitoring Instrumentation 3/4 3-53 Radioactive Liquid Effluent Monitoring Instrumentation 3/4 3-58 Radioactive Gaseous Effluent Monitoring I
. Instrumentation 3/4 3-64 3/4.3.4 DELETED l
l l
l l
i i
SALEM - UNIT 1-IV Amendment No, f67, 224
F l
INDEX BASES SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 PROTECTIVE. INSTRUMENTATION
. B 3/4 3-1 3/4.3.2 ENGINEERED ' SAFETY FEATURES (ESP)
INSTRUMENTATION
. B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION.........
. B 3/4 3-1 l
3/4.3.4 DELETED 3/4.4 PEACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION.
B 3/4 4-1 3/4.4.2 SAFETY. VALVES
. B 3/4 4-la 3/4.4.0 RELIEF VALVES B 3/4 4-la 3/4.4.4 PRESSURIZER.
B 3/4 4-2 3/4.4.5 STEAM GENERATORS B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE B 3/4 4-3 3/4.4.7 DELETED 3/4/4.8 SPECIFIC ACTIVI1Y.
B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS B 3/4 4-6 3/4.4.10' STRUCTURAL INTEGRITY B 3/4 4-17 3/4.4.11 BLANK.
B 3/4 4-17 3/4.4 12 REACTOR VESSEL HEAD VENTS B 3/4 4-17 1
1 1
SALEM - UNIT 1 XII Amendment No. 78@,224
r -~
INSTPUMENTATION BASES l
3/4.3.4 DELETED 1
4 4
SALEM - UNIT 1 B 3/4 3-4 Amendment No. 224
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UNITED STATE 3
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j NUCLEAR REGULATORY COMMISSION
't WASHINGTON, D.c. 20555 4001
,o PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 205 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric & Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated July 2,1999, 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; 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 set forth in 10 CFR Chapter I; 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-75 is hereby amerided +o mad as f:' Jews:
'/
1
. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
205, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days. In addition, the licensee shall include 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 Jul staff's safety evaluation dated September 14, 1999. y 2,1999, and evaluated in the l
FOR THE NUCLEAR REGULATORY COMMISSION James W. Clifford, Chief, Section 2 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technica!
l Specifications l
Date of issuance: September 14, 1999 l
l l
l l
ATTACHMENT TO LICENSE AMENDMENT NO 205 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages as indicated. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Paaes Insert Paaes IV IV 3/4 3-65 3/4 3-66 B 3/4 3-4 B 3/4 3-4 8 3/4 3-4a
e INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION
- fAGT, 3/4.2 POWER DISTRIBUTION LIMITS 1
3/4.2.1 AXIAL FLUX DIFFERENCE
.................... 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR
.. 3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR.................. 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO.......
............... 3/4 2-13 3/4.2.5 DNB PARAMETERS
. 3/4 2-16 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION
... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION
. 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation................. 3/4 3-38 Movable Incore Detectors............................ 3/4 3-42 Remote Shutdown Instrumentation..................... 3/4 3-43 Accident Monitoring Instrumentation................. 3/4 3-50 Radioactive Liquid Effluent Monitoring Instrumentation...................................... 3/4 3-53 Radioactive Gaseous Effluent Monitoring Instrumentation..................................... 3/4 3-59 3/4.3.4 DELETED i
-f 5
SALEM - UNIT 2-IV Amendment No. fg7, 205 I
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i INSTRUMENTATION BASES CDOSS REFERENCE - TABLES 3.3-13 and 4.3-13 T/S Table Instrument Description Acceptable RMS Item No.
Channels la Waste Gas Holdup System Noble Gas Activity 2R41A, B and Din ia 2a Containment Purge and Pressure - Vacuum 2R12A or 2R41A, Relief Noble Gas Activity B and Din (2) 3a Plant Vent Header System Noble Gas Activity 2R16 or 2R41A, B and DID"'
(1)
The channels listed are required to be operable to meet a single operable channel for the Technical Specification's " Minimum Channels Operable" requirement.
(2) 2R41D is the setpoint channel. 2R41A and 2R41B are the measurement channels.
l 3/4.3.4 DELETED j
l Salem Unit 2 B 3/4 3-4 Amendment No. 175,205