ML20100J948
| ML20100J948 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/22/1996 |
| 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 | |
| ML20100J950 | List: |
| References | |
| DPR-70-A-180, DPR-75-A-161 NUDOCS 9602290324 | |
| Download: ML20100J948 (14) | |
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k UNITED STATES j
j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20516 4001 tt 4.....s PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NVCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.180 License No. DPR-70 1.
The Nuclear Regulatory Comission (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 28, 1995, 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 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 4
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-70 is hereby amended to read as follows:
9602290324 960222 PDR ADOCK 05000272 P, _
PDR 9y y
4 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.180, 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 and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION G
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Joh'n' F. Stolz, Direct' (Project Directorate'f-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation a
Attachment:
Changes to the Technical Specifications l
Date of Issuance: February 22, 1996 i
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O ATTACHMENT TO LICENSE AMENDMENT NO.180 FACILITY OPERATING LICEN'E NO. DPR-70 l
DOCKET NO. 50-272 3
Revise Appendix A as follows:
Remove Paoes Insert Paaes V
V XII XII 4
3/4 4-17 3/4 4-17 through 3/4 4-19 3/4 4-18 3/4 4-19 B 3/4 4-4 B 3/4 4-4 i
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INDEX
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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i
SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION
...........3/4 4-1 Startup and Power Operation.
i Hot Standby.
.3/4 4-2 Hot Shutdown
.3/4 4-3 Cold Shutdown.
.3/4 4-3b j
3/4.4.2.1 SAFETY VALVES - SHUTDOWN
.3/4 4-4 3/4.4.2.2 SAFETY VALVES - OPERATING
.3/4 4-4a 3/4.4.3 RELIEF VALVES
.3/4 4-5 3/4.4.4 PRESSURIZER
.3/4 4-6 3/4.4.5 STEAM GENERATORS
.3/4 4-7 i
3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection System
.3/4 4-14 l
.3/4 4-15 Pressure Isolation Valves
.3/4 4-16a 3/4.4.7' DELETED 3/4.4.8 SPECIFIC ACTIVITY.
.3/4 4-20 3/4.4.9 PRESSURE / TEMPERATURE LIMITS-Reactor Coolant System
.3/4 4-24 Pressurizer...................
3/4 4-29 Overpressure Ierotection Systems
.3/4 4-30 3/4.4.10 9TRUCTURAL INTEGRITY l
AS!!E Code Class 1, 2, and 3 Components
.3/4 4-32 3/4.4.11 INTENTIONALLY BLANK.
.3/4 4-34 4
3/4.4.12 HEAD VENTS
.3/4 4-35 4
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i SALEM - UNIT 1 V
Amendment No.180 s
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INDEX BASES 1
SECTION M
3
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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 e
1 3/4.3.3 MONITORING-INSTRUMENTATION.
.B 3/4 3-1 j
3/4.3.4 TURBINE OVERSPEED PROTECTION.
.B 3/4 3-4 i
'. 3 /4. 4 -
REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT I
.B 3/4 4-1 1
i CIRCULATION 3/4.4.2
-SAFETY VALVES
.B 3/4 4-la
.B 3/4 4-la 3/4.4.3 RELIEF VALVES 3/4.4.4 PRESSURIZER
.B 3/4 4-2 l
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 ACTIVITY
.B 3/4 4-5
.B 3/4 4-6 3/4.4.9 PRESSURE / TEMPERATURE LIMITS 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 l
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SALEM - UNIT 1 XII Amendment No.180
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i PAGES 3 /4 4-17 THROUGH 3/4 4-19 DELETED I
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' SALEM - UNIT 1:
3/4 4-17 Through 3/4 4-19 Amendment No.180 a
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BASES 2]4.4.6.2 OPERATIONAL LEAKAGE (Continued)
The total steam generator tube leakage limit of 1 GPM for all steam i
generators (but not more than 500 gpd for any steam generator) ensures that' the dosage contribution from the tube leakage will be limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam line break. The 1 GPM limit is consistent with the assumptions used in the analysis of these accidents.
The 500 gpd leakage limit per steam generator ensures that steam generator tube integrity is maintained in the event of a main steam line rupture or under LOCA conditions.
PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.
Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.
l 3/4.4.7 THIS SECTION DELETED i
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SALEM - UNIT 1 B 3/4 4-4 Amendment No.180
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-4 UNITED STATES s
NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20066-0001
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PUBLIC SERVICE ELECTRIC & GAS COMPANY 4
i PHILADELPHIA ELECTRIC COMPANY l
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.161 4
License No. DPR-75 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
4 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 28, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the i
Comission'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 Comission; 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon 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 4
the Comission's regulations and all applicable requirements have been l
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:
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(2) Technical Snecifications and Environmental Protection Plan l
The Technical Specifications contained in Appendices A and B, as revised through Amantaent No.161, are hereby incorporated in the license. The lice te.e shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall i-be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMISSION O
J l
J F. Stolz, Direc r ect Directorate $) 2 Pr Division of Reactor Projects - I/II l
Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical
{
Specifications
}
Date of Issuance: February 22, 1996 j
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3 ATTACHMENT TO LICENSE AMENDMENT N0.161 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Paaes Insert Paaes V
V XII XII 3/4 A-20 3/4 4-20 through 3/4 4-22 3/4 4-21 3/4 4-22 B 3/4 4-5 B 3/4 4-5 4
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e INDEX
. LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAQE
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3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION i'
Startup and Power Operation.......................... 3/4'4-1 Hot Standby.......................................... 3/4'4-2 i
Hot Shutdown........................................ 3/4 4-3
. Cold Shutdown....................................... 3/4 4-4a i
3/4.4.2 SAFETY VALVES - SHUTDOWN............................ 3 /4 4 - 5 3/4.4.3
' SAFETY VALVES - OPERATING............................ 3/4 4-6 i
t 3/4.4.4 PRESSURIZER........................................... 3/4 4-7
.3/4.4.5 RELIEF VALVES........................................ 3/4 4-8 j
3/4.4.6 STEAM GENERATORS..................................... 3/4 4-9 i
3/4.4.7
. REACTOR COOLANT SYSTEM LEAKAGE
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Leakage Detection System............................ 3/4 4-16 1
Operational Leakage.................................. 3/4 4-17 3/4.4.8 DELETED 3/4.4.9 SPECIFIC ACTIVITY.............
............... 3/4 4-23 3/4.4.10 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System............................... 3 /4 4 - 2 7 Pressurizer....
......... 3/4 4-30 i
Overpressure Protection Systems.................... 3/4 4-31 3/4.4.11 STRUCTURAL INTEGRITY ASME Code Class 1, 2, and 3 Components
............. 3/4 4-33 3/4.4.12 HEAD VENTS
.. 3/4 4-34 i
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SALEM - UNIT 2 V
Amendment No.161
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. e INDEX BASES i
SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 PROTECTIVE INSTRUMENTATION............................B 3/4 3-1 1
3/4'.3.2 ENGINEERED SAFETY FEATURES-(ESF)
INSTRUMENTATION........................................B 3/4 3-1 4
3/4.3.3I MONITORING INSTRUMENTATION'............................B 3/4 3-1 3/4.4 REACTOR COOLANT SYSTEM h
1 4
3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT
' CIRCULATION
...........................................B 3/4 4-1 3/4.4.2 1
4
... and SAFETY VALVES
.........................................B 3/4 4-2 i
3/4.4.3
~
3/4.4.4-PRESSURIZER...........................................B 3/4 4-2 3/4.4.5 RELIEF VALVE.
.B 3/4 4-2 j
i 3/4.4.6 STEAM GENERATORS
......................................B 3/4 4-3
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3/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE
........................B 3/4 4-4 9
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.3/4.4.8 DELETED-I 3/4.4.9 SPECIFIC ACTIVITY
.....................................B 3/4 4-6 l
3/4.4.10 PRESSURE / TEMPERATURE LIMITS
...........................B 3/4 4-7 1
3/4.4.11 STRUCTURAL INTEGRITY
..................................B 3/4 4-17 i
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SALEM - UNIT 2 XII Amendment No.161 i
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'e PAGES 3/4 4-20 THROUGH 3/4 4-22 DELETED SALEM - UNIT **
3/4 4-20 through 3/4 4 22 Amendment No,161
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i PEACTOR COOLANT SYSTEM
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BASES j
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3/4.4.7.2 OPERATIONAL LEAKAGE ~(Continued)
I The total steam generator tube leakage limit of 1 GPM for all steam generators (but not more than 500 gpd for any steam generator) ensures that I
the dosage contribution from the tube leakage will be limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam line break. The 1 GPM limit is consistent with the assumptions used in the analysis of these accidents.
The 500 gpd leakage l
limit per steam generator ensures that steam generator tube integrity is j
maintained in the event of.a main steam line rupture or under LOCA conditions.
1 PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.
l Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to i
be promptly placed in COLD SHUTDCWN.
i
'3/4.4.8 I
THIS SECTION DELETED
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i SALEM - UNIT 2 B 3/4 4-5 Amendment No.161