ML20084E677
| ML20084E677 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/22/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Philadelphia Electric Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20084E680 | List: |
| References | |
| DPR-70-A-167, DPR-75-A-149 NUDOCS 9506010494 | |
| Download: ML20084E677 (10) | |
Text
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k UNITED STATES j,
,j NUCLEAR REGULATORY COMMISSION
~r WASHINGTON. O.C. 20665 0001
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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY 4
ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.167 License No. DPR-70 1.
The Nuclear Regulatory Commission (the Comission 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 September 29, 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; 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 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 Specifica-tions 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:
9506010494 950522 PDR ADOCK 05000272 P
. (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 167, 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 its date of issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
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n F. Stolz, Direct P oject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: flay 22,1995
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ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Paaes Insert Paaes IV IV J
3/4 3-40 through 3/4 3-45 3/4 3-40 through 3/4 3-45 8 3/4 3-2 B 3/4 3-2 i
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAgg 3/4.2 POWER DISTRIBtfrION 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
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3/4.2.3 NUCLEAR ENTHALPY HOT CdANNEL FACTOR 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO 3/4 2-11 3/4.2.5 DNB PARAMETERS 3/4 2-13 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 3-35 Movable Incore Detectors 3/4 3-39 Remote Shutdown Instrumentation 3/4 3-4(
Accident Monitoring Instrumentation 3/4 3-53 Radioactive Liquid Effluent Monitoring Instrumentation 3/4 3-58 Radioactive Gaseous Effluent Monitoring Instrumentation 3/4 3-64 3/4.3.4 TURBINE OVERSPEED PROTECTION 3/4 3-70 i
t SALEM - UNIT 1 IV Amendment No.167 l
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PAGES 3/4 3-40 THROUGH 3/4 3-45 ARE DELETED i
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SALEM - UNIT 1 3/4 3-40 through 3/4 3-45 Amendment No.I N I
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INSTRUMENTATION BASES 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION (Continued)
CROSS REFERENCE - TABLES 3.3-6 AND 4.3-3 Func Rad Mon Rad Mon Uglig Number Punction Area Moniters l
1a-1R5/1R9 Fuel Storage Area lb 1R44 Containment Area Process Monitors 2a1 1R12A Containment Purge & Pressure / Vacuum Relief Gaseous Activity 1R41C Plant Vent Noble Gas Monitor may substitute for 1R12A when the Purge & Pressure / Vacuum Relief Valves are open.
2a2 1R11A Containment Purge & Pressure / Vacuum Relief Air Particulate Activity 2b1 1R45B Medium Range Auxiliary Building Exhaust System (Plant Vent)
Noble Gas Effluent 2b2 1R45C High Range Auxiliary Building Exhaust System (Plant Vent)
Noble Gas Effluent 2b3 1R46 Main Steamline Discharge (Safety Valves and Atmospheric Dump Valves) Noble Gas Effluent 2b4 1R15 Condenser Exhaust System Noble Gas Effluent 3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core. The OPERABILITY of this system is demonetrated by irradiating each detector used and normalizing its respective output.
3/4.3.3.3 THIS SECTION DELETED 3/4.3.3.4 THIS SECTION DELETED SALEM - UNIT 1 L 3/4 3-2 Amendment No.167
a uauqk UNITED STATES y o-NUCLEAR REGULATORY COMMISSION If WASHINGTON, D.C. 20066-0001
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,e" PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 I
SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.149 i
License No. DPR-75 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
J A.
The application for amendment filed by the Public Service Electric &
1 Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated September 29, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
. (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.149, 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 its date of issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
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f o 'F. Stolz, D ctor oject Directora e I-2 3
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 22, 1995 l
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ATTACHMENT-T0 LICENSE AMENOMENT NO.I49 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Paggi Insert Paae i
B 3/4 3-2 B 3/4 3-2 1
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l INSTRUMENTATION BASES 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION (Continued)
CROSS REFERENCE - TABLES 3.3-6 and 4.3-3 Func Rad i4on Rad Mon Uglit Number Function Area Monitors la 2R5/2R9 Fuel Storage Area I
ib 2R44 Containment Area Process Monitors 2a1 2R12A Containment Purge & Pressure / Vacuum Relief Gaseous Activity 2R41C Plant Vent Noble Gas Monitor may substitute for 2R12A when the Purge & Pressure Vacuum Relief Valves are open.
2a2 2R11A Containment Purge & Pressure / Vacuum Relief Air Particulate Activity 2b1 2R45B Medium Range Auxiliary Building Exhaust System (Plant Vent)
Noble Gas Effluent 2b2 2R45C High Range Auxiliary Building Exhaust System (Plant Vent)
Noble Gas Effluent 2b3 2R46 Main Steamline Discharge (Safety Valves and Atmospheric Dump Valves) Noble Gas Effluent 2b4 2R15 Condenser Exhaust System Noble Gas Effluent 3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core. The OPERABILITY of this system is demonstrated by irradiating each detector used and normalizing its respective output.
d For the purpose of measuring F (Z) or P a full incore flux map is used.
Quarter-core flux maps, asdef$nedinWdkP-8648, June 1976, may be used in recalibration of the excore neutron flux detection system, and full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.
3/4.3.3.3 THIS SECTION DELETED 3/4.3.3.4 THIS SECTION DELETED SALEM UNIT 2 B 3/4 3-2 Amendment Ne.149
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'p-4 UNITED STATES NUCLEAR REGULATORY COMMISSION I
E WASHINGTON, D.C. c61
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 167 AND149 TO FACILITY OPERATIRQ LICENSE NOS. DPR-70 AND DPR-75 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY SALEM NUCLEAR GENERATING STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311
1.0 INTRODUCTION
By letter dated September 29, 1994, the Public Service Electric & Gas Company (the licensee) submitted a request for changes to the Salem Nuclear Generating Station, Unit Nos. I and 2, Technical Specifications (TS). The requested changes would remove the sections that are entitled " Seismic Instrumentation" and " Meteorological Instrumentation" and relocate the information and testing requirements to the Salem Updated Final Safety Analysis Report (UFSAR).
2.0 lElGROUND Section 182a of the Atomic Energy Act (the "Act") requires applicants for nuclear power plant operating licenses to include TS as part of the license.
The Commission's regulatory requirements related to the content of TS are set i
forth in 10 CFR 50.36. That regulation requires that the TS include items in i
five specific categories, including (1) safety limits, limiting safety system settings and limiting control settings; (2) limiting conditions for operation; i
(3) surveillance requirements; (4) design features; and (5) administrative controls. However, the regulation does not specify what matters are to be included in a plant's TS.
The Commission has provided guidance for the contents of TS in its " Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors" (" Final Policy Statement"), 58 FR 39132 (July 22,1993), in which the Commission indicated that compliance with the Final Policy Statement
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satisfies Section 182a of the Act.
In particular, the Commission indicated 1
that certain items could be relocated from the TS to licensee-controlled documents, consistent with the standard enunciated in Portland General Electric Co. (Trojan Nuclear Plant), ALAB-531, 9 NRC 263, 273 (1979).
In that case, the Atomic Safety and Licensing Appeal Board indicated that " technical specifications are to be reserved for those matters as to which the imposition
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