ML20116J242
| ML20116J242 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/01/1996 |
| From: | Fields M NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20116J247 | List: |
| References | |
| NUDOCS 9608130114 | |
| Download: ML20116J242 (12) | |
Text
_ _ _
gh UNITED STATES
{
,j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 2056M001 49.....,o SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THECITYOFRIVERSIDE.CdLIFORNIA THE CITY OF ANAHEIM. CALIFORNIA DOCKET NO. 50-361 1
SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.130 License No. NPF-10 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern California Edison Company, et al. (SCE or the licensee) dated June 3,1996, as superseded by application dated June 25, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 (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 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.
9608130114 960801 PDR ADOCK 05000361 P
. 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.130, are hereby incorporated in the license. Southern California Edison Company shall operate the i
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 and
]
shall be implemented by August 9,1996.
FOR THE NUCLEAR REGULATORY COMISSION W < ' f f
,.-t $
Mel B. Fields, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 1, 1996
1 ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.130 TO FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 l
Revise the issued but not yet implemented Appendix A Improved Technical Specifications (ITS) by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT ITS 3.3-47 ITS 3.3-47 ITS 5.0-20 ITS 5.0-20 ITS B 3.3-162 ITS 2 3.3-162
PAM Instrumentaticn 3.3.11 1
Table 3.3.11 1 (page 1 ef 1) i Post Accident monitorire Instrumentation ColeITIONS REFERENCED FROM REQUIRED l
FLAICTION REQUIRED CNANNELS ACTION F.1 1.
Excere Neutron Flum 2
G 2.
Reactor Coolant System Net Les Temperature 2 (1 per steen G
[
]
generator) l 4
i' 3.
Reacter Caetant System Cold Les Temperature 2 (1 por steen G
l generater)
I 1
l 4.
Reacter Coolant System Pressure (wide rarge) 2 G
l 5.
Reacter Vesset Water Level 2(d)
N 6.
Contalrument Stay Water Levet (wide range) 2 G
i 7.
Contaltunent Pressure (wide range) 2 G
j 8.
Containment Isolation Valve Positian 2 pei pene g g flow G
path 4
j 9.
Contalrunent Area Radiation (high rarge) 2 N
- 10. Contalrument Hydrogen Monitors 2
G
- 11. Pressurizer Level 2
G
- 12. steam Generator Water Level (wide rarge) 2 per steam generator G
- 13. Condensate storage Tank Level 2
G
- 14. Core Exit Temperature -oundrent 1 2(C)
G
- 15. Core Exit Temperature -Guadrant 2 2(C)
G
- 16. Core Exit Temperature -ouadrant 3 2(C)
G
- 17. Core Exit Temperature-Quadrant 4 2(C)
G
- 18. Auxiliary Feessater Flow 1 per steam generator G
- 19. Containment Pressure (narrow range) 2 G
- 20. Reactor Coolant System Subcooling Norgin Monitor 2
G
- 21. Ps assurizer Safety Valve Position Indication 1 per valve G
- 22. Containment Teeperature 2
G
- 23. Containment Water Level (narrow rarge) 2 G
- 24. NPSI Flow Cold Leg 1 per cold tog G
- 25. NPSI Flow Not Leg 1 per hot tog C
- 26. Steen Line Pressure 2 per steen generator G
- 27. Refueling Water Storage Tank Level 2
G (a) Not rogsf red for isolation velves these associated penetration is f oolated by at toest one closed and de activated automatic valve, closed manuel valve, blind flange, or check valve with flow through the velve secured.
(b) Only one position indication channet is required for penetration flow paths with only one instatted control room indication channel.
(c) A channel consists of two or more core exit thermocowles.
(d) A channel consists of eight sensors in a probe. A channel is OPERABLE if four or more sorwors, one sensor in the @per head and three sensors in the lower head are OPERA 8LE.
SAN ONOFRE--UNIT 2 3.3-47 Amendment No. W,130
\\
~
Prccedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, ad Manuals 5.5.2.12 Ventilation Filter Testing Program (VFTP)
(continued)
The provisions of Technical Specification Surveillance Requirement 3.0.2 and Technical Specification Surveillance Requirement 3.0.3 are applicable to the VFTP test frequencies.
5.5.2.13 Diesel Fuel 011 Testing Program This program implements required testing of both new fuel oil and I
stored fuel oil. The program shall include sampling and testing l
requirements, and acceptance criteria, all in accordance with applicable ASTM standards. The purpose of the program is to l
establish the following:
At least once per 92 days and from new fuel oil prior to a.
addition to the storage tanks by verifying that a sample obtained in accordance with ASTM-D4057-81 has a water and sediment content of less than or equal to 0.05 volume percent, I
an API gravity or an absolute specific gravity within limits, and a kinematic viscosity 9 40 C of greater than or equal to 1.9 but less than or equal to 4.1 when tested in accordance l
with ASTM-0975-81.
b.
At least once every 92 days by obtaining a sample of fuel oil in accordance with ASTM-D4057-81 and verifying that I
particulate contamination is less than long/ liter when checked in accordance with ASTM-D2276-83, Method A.
l l
SAN ONOFRE--UNIT 2 5.0-20 Amendment No. 4N,130 l
PAM Instrumentation
~
B 3.3.11
~
BASES LCO 2, 3.
Reactor Coolant System (RCS) Hot and Cold Lea (continued)
Temperature RCS Hot and Cold Leg Temperatures are Category I variables provided for verification of core cooling and long tern surveillance.
Reactor outlet temperature inputs to the PAMI are provided by two fast response resistance elements and associated transmitters.
l 4.
Reactor Coolant System Pressure (wide rance)
RCS Pressure (wide range) is a Category I variable, provided for verification of core cooling and RCS integrity inng term surveillance.
i 4
{
The pressure transmitters are located inside the containment. Redundant monitoring capability is l
provided by two trains of instrumentation.
4 Operator actions to maintain a controlled cooldown, j
such as adjusting steam generator pressure or level, i
would use this indication.
Furthermore, RCS pressure i
is one factor that may be used in decisions to terminate reactor coolant pump operation.
a 5.
Reactor Vessel Water Level is provided for verification and long ters surveillance of core cooling.
The Reactor Vessel Water Level Monitoring System provides a direct measurement of the collapsed liquid level above the fuel alignment plate. The collapsed i
level represents the amount of liquid mass that is in the reactor vessel above the core.
(continued)
SAN ONOFRE--UNIT 2 8 3.3-162 Amendment No. +B7,130
/
t UNITED STATES g
,g NUCLEAR REGULATORY COMMISSION
't WASHINGTON, D.C. 20066-0001
\\,...../
SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIN. CALIFORNIA DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 3 ANENDNENT TO FACILITY OPERATING LICENSE Amendment No.119 i
License No. NPF-15 J
1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Southern California Edison Company, et al. (SCE or the licensee) dated June 3,1996, as superseded by application dated June 25, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 (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 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.
1 i
2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and 1
paragraph 2.C(2) of Facility Operating License No. NPF-15 is hereby amended to read as follows:
1 (2)
Technical Specifications The Technical Specifications contained in Appendix A and the l
Environmental Protection Plan contained in Appendix B, as revised through Amendment No.119, are hereby incorporated in the license. Southern California Edison Company 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 and shall be implemented by August 9,1996.
FOR THE NUCLEAR REGULATORY COMMISSION j 'f h f,6'h Mel B. Fields, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 1, 1996
4 ATTACHMENT TO LICENSE AMENDMENT 4
AMENDMENT NO.119 TO FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Revise the issued but not yet implemented Appendix A Improved Technical Specifications (ITS) by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
a REMOVE INSERT ITS 3.3-47 ITS 3.3-47 ITS 5.0-20 ITS 5.0-20 4
i l
l i
)
i 1
4 i
0
\\
i a
1 4
PAM Instrumentation 3.3.11 i
Table 3.3.11 1 (page 1 of 1)
Post Accident Monttoring Instrtamentetton l
ColeITIONS REFERENCED FROM REGUIRED FLalCTION REGUIRED CHANNELS ACTION F.1 1.
Excore Neutron Flus 2
G 2.
Reactor Coelant System Not Log Temperature 2 (1 per steen G
l generator)
I 3.
Reactor Coolant System cold Les Temperature 2 (1 per steen G
i ponerator)
]
4.
Reactor Ceolant System Pressure (wide rarge) 2 G
l 5.
neector vessel Water Level 2(d)
N j
6.
Contelrument Sump Water Level (wide range) 2 G
j 7.
Containment Pressure (wide range) 2 G
i 8.
Contalrument Isolation Velve Position 2 per g g flow G
l 9.
Containment Aree Radiation (high range) 2 N
i i
- 10. Containment Hydrogen Monitors 2
G j
- 11. Pressurizer Level 2
G
- 12. steam Generator Water Level (wide range) 2 per steen generator G
j
- 13. Condensate storage Tank Level 2
G
- 14. Core Exit Temperature -Quadrant 1 2(*)
G j
- 15. core Exit Temperature -Quadrant 2 2(CI G
- 16. Core Exit Temperature-Gundrent 3 2(C)
G
- 17. Core Exit Tegerature -Quadrant 4 2(*)
G
- 18. Auxillery Feeddeter Flow 1 per steam generator G
- 19. Containment Pressure (narrow range) 2 G
J j
- 20. Reactor Coolant System $4 cooling Margin Monitor 2
G j
- 21. Pressurizer Safety Valve Position Indication 1 per valve G
- 22. Containment Temperature 2
G
- 23. Contalrument Water Level (narrow range) 2 G
- 24. NPSI Flow cold Les 1 per cold les G
- 25. NPSI Flow Not Leg 1 per hot les G
- 26. Steam Line Pressure 2 per steam generator G
l
- 27. Refuelfrw Water Storage Tank Level 2
G 1
(a) Not regaired for f oolation velves whose associated penetration Is f oolated by at toast one closed and de activated automatic valve, closed manuel volve, blind flange, or check volve with flow through the valve secured.
(b) Only one position indication channet is required for penetration flow paths with only one installed control room indication channel.
(c) A channet consists of two or more core exit thermoco @tes.
(d) A channet consists of eight sensors in a probe. A channel is OPERABLE (f four or more sensors, one sensor in the tgaper head and three sensors in the lower head are OPERA 8LE.
SAN ON0FRE--UNIT 3 3.3-47 Amendment No. M6,119
Proczdures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.12 Ventilation Filter Testing Program (VFTP)
(continued)
The provisions of Technical Specification Surveillance Requirement 3.0.2 and Technical Specification Surveillance Requirement 3.0.3 are applicable to the VFTP test frequencies.
5.5.2.13 Diesel Fuel Oil Testing Program This program implements required testing of both new fuel oil and stored fuel oil. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM standards. The purpose of the program is to establish the following:
At least once per 92 days and from new fuel oil prior to a.
addition to the storage tanks by verifying that a sample obtained in accordance with ASTM-D4057-81 has a water and sediment content of less than or equal to 0.05 volume percent, an API gravity or an absolute specific gravity within limits, and a kinematic viscosity 9 40 C of greater than or equal to 1.9 but less than or equal to 4.1 when tested in accordance l
with ASTM-D975-81.
b.
At least once every 92 days by obtaining a sample of fuel oil in accordance with ASTM-D4057-81 and verifying that l
particulate contamination is less than 10mg/ liter when checked in accordance with ASTM-D2276-83, Method A.
4 l
i a
l SAN ONOFRE--UNIT 3 5.0-20 Amendment No. +M,119
PAM Instrumentation B 3.3.11 BASES LCO 2, 3.
Reactor Coolant System (RCS) Hot and Cold Lea (continued)
Temperature RCS Hot and Cold Leg Temperatures are Category I variables provided for verification of core cooling and long term surveillance.
Reactor outlet temperature inputs to the PAMI are provided by two fast response resistance elements and associated transmitters.
l 4.
Reactor Coolant System Pressure (wide ranae)
RCS Pressure (wide range) is a Category I variable, provided for verification of core cooling and RCS integrity long term surveillance.
The pressure transmitters are located inside the containment. Redundant monitoring capability is provided by two trains of instrumentation.
Operator actions to maintain a controlled cooldown, such as adjusting steam generator pressure or level, would use this indication. Furthermore, RCS pressure is one factor that may be used in decisions to terminate reactor coolant pump cperation.
5.
Reactor Vessel Water Level Reactor Vessel Water Level is provided for verification and long term surveillance of core cooling.
The Reactor Vessel Water Level Monitoring System provides a direct measurement of the collapsed liquid level above the fuel alignment plate. The collapsed level represents the amount of liquid mass that is in the reactor vessel above the core.
l 1
(continued)
SAN ONOFRE--UNIT 3 8 3.3-162 Amendment No. M4,119