ML20212M253
| ML20212M253 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/01/1999 |
| From: | Anthony Mendiola NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212M258 | List: |
| References | |
| NUDOCS 9910120289 | |
| Download: ML20212M253 (16) | |
Text
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UNITED STATES g-E NUCLEAR REGULATORY COMMISSION if WASHINGTON, D.C. 2055W1
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i COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LASALLE COUNTY STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 134 License No. NPF-11 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated May 19,1999, 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 app!.ation, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance (i) that the activities authcrized 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 ferth in 10 CFR Chapter I; D.
The issuance of this amendrnent 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 enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-11 is hereby amended to read as follows:
j 9910120289 991001 PDR ADOCK 05000373 i
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Technical Specifications and Environrnental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 134, and the Environmental Protection Plan contained in
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Appendix B, are hereby incorporated in the license. The licensee 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 within 30 days. Implementation of this amendment shallinclude the
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relocation of certain technical specification requirements to the appropriate licensee-controlled documents as described in the Licensee's application dated May 19,1999 and its supplements dated September 10,1999, and evaluated in the staff's Safety Evaluation Report attached to this amendment.
FOR THE NUCLEAR REGULATORY COMMISSION
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, Anthony J. Mendiola, Chief, Section 2 Project Directorate lil Division of Licensing Project Management Office of Nuclear Reactor Regulation At'.achment:
Changes to the Technical Specifications Date of issuance:
October 1,1999
ATTACHMENT TO LICENSE AMENDMENT NO.134 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 Replace the following pages of the Appendix "A" Technical Specifications with the enc'osed pages. The revised pages are identified by amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT VI VI XIll Xill XXil XXII 3/4 4-10 3/4 4-10 3/4 4-11 3/4 4-12 B 3/4 4-2 B 3/4 4-2 B 3/4 4-2a l
i
a INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM
-Recirculation Loops....
3/4 4-1 Jet Pumps....................................
3/4 4-2 Recirculation Loop Flow................
3/4 4-3 Idle Recirculation Loop Startup......
3/4 4-4 Thermal Hyudraulic Stability.............
3/4 4-4a 3/4 4.2 SAFETY / RELIEF VALVES........
3/4 4-5 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.....
3/4 4-6 Operational Leakage............
3/4 4-7 3/4.4.4 DELETED.
3/4 4-10 3/4.4.5 SPECIFIC ACTIVITY......
3/4 4-13 3/4.4.6 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System.....
3/4 4-16 Reactor Steam Dome....
3/4 4-20 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES.........
3/4 4-21 3/4.4.8 STRUCTURAL INTEGRITY.................
3/4 4-22 3/4.4.9 RESIDUAL HEAT REMOVAL Hot Shutdown........
3/4 4-23 Cold Shutdown..........
3/4 4-24 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ECCS-OPERATING......
3/4 5-1 3/4.5.2 ECCS-SHUTDOWN.........................
3/4 5-6 3/4.5.3 SUPPRESSION CHAMBER.........................
3/4 5-8 LA SALLE - UNIT 1 VI Amendment No. 134
~
1 INDEX BASES SECTION PAGE INSTRUMENTATION (Continued)
MONITORING INSTRUMEETATION (Continued)
Meteorological Monitoring Instrumentation.
B 3/4 3-4a Remote Shutdown Monitoring Instrumentation.
B 3/4 3-4a Accident Monitoring Instrumentation....
B 3/4 3-5 Source Range Monitors.
B 3/4 3-5 Deleted.
B 3/4 3-5 Explosive Gas Monitoring Instrumentation.
B 3/4 3-6 Loose-Part Detection System....
B 3/4 3-6
.3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION......
B 3/4 3-6 3/4.4 REACTOR COOLANT S'.' STEM 3/4.4.1 RECIRCULATION SYSTEM....
B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES.....
B 3/4 4-2 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.
B 3/4 4-2 Operational Leakage..........
B 3/4 4-2 3/4.4.4 DELETED....
B 3/4 4-2 3/4.4 5 SPECIFIC ACTIVITY............
B 3/4 4-3 3/4.4.6 PRESSURE / TEMPERATURE L1MlTS.......
B 3/4 4-4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES...........
B 3/4 4-5 3/4.4.8 STRUCTURAL INTEGRITY......
B 3/4 4-5 3/4.4.9 RESIDUAL HEAT REMOVAL.....
B 3/4 4-5 i
LA SALLE - UNIT 1 XIII Amendment No.134 j
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INDEX LIST OF TABLES (Continued)
TABLE PAGE 4.3.7.3-1 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS........
3/4 3-65
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3.3.7.4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION.
3/4 3-67 1
4.3.7.4-1 REliOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................
3/4 3-68 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION.................
3/4 3-70 4.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION j
SURVEILLANCE REQUIREMENTS........
3/4 3-71 j
i 3.3.7.11-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION................
3/4 3-63 4.3'.7.11-1 EXPLOSIVE GAS MONITORING INSTRUMENTAT ON SURVEILLANCE REQUIREMENTS.........
3/4 3-84 3.3.8-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION...............................
3/4 3-87 3.3.8-2 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SETPOINTS.....................
3/4 3-88 4.3.8.1-1 FEEDWATER/ PAIN TURBINE TRIP SYSTEM ACTUATION INSTRL' MENTATION SURVEILLANCE REQUIREMENTS......
3/4 3-89 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES..............................
3/4 4-9 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM...................
3/4 4-15 4.4.6.1.3-1 REACTOR VESSEL MATEFIAL SURVEILLANCE PROGRAM WITHDR71AL SCHEDULE........................
3/4 4-19 LA SALLE - UNIT 1 XXII Amendment No. 134
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3/4.4.4 INTENTIONALLY LEFT BLANK.
PAGES 3/4 4-11 AND 3/4 4-12 ARE DELETED l
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.' LA SALLE - UNIT 1-3/4 4<10
- NEXT PAGE IS 3/4 4-13 Amendment No. 134 g
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REACTOR COOLANT SYSTEM BASES 3/4.4.2 SAFETY / RELIEF VALVES The safety valve function cf the safety / relief valves operate to prevent the reactor coolant system from being pressurized above the Safety Limit of 1325 psig in accordance with the ASME Code. Analysis has shown that with the safety function of one of the thirteen safety / relief valves inoperable the reactor pressure is limited to within ASME Ill allowable values for the worst case I
upset transient. Therefore, operation with any 12 SRVs capable of opening is allowable,
)
although allinstalled SRVs must be closed and have position indication to ensure that integrity of the primary coolant boundary is known to exist at all times.
j l
Demonstration of the safety / relief valve lift settings will occur only during shutdown and will be performed in accordance with the provisions of Specification 4.0.5.
3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.3.1 LEAKAGE DETECTION SYSTEMS j
The RCS leakage detection s'ystems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure boundary. These detection systems are consistent with the recornmendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.
3/4 4.3.2 OPERAT!ONAL LEAKAGE The allowable leakage rates from the reactor coolant system have been based on the predicted and experimentally observed behavior of cracks in pipes. The normally expected background leakage due to equipment design and the detection capability of the instrumentation for determining system leakage was also considered. The evidence obtained from experiments suggests that for leakage somewhat greater than that specified for unidentified leakage the probability is small that the imperfection or crack associated with such leakage would grow rapidly. However, in all cases, if the leakage rates exceed the values specified or the leakage is located and known to be PRESSURE BOUNDARY LEAKAGE, the reactor will be shutdown to allow further investigation and corrective action.
The Surveillance Requirements for RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA. Leakage from the RCS pressure isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.
3/4.4.4 DELETED LA SALLE - UNIT 1 B 3/4 4-2 Amendment No. 134
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q UNITED STATES j
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20555 4 01 3
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LASALLE COUNTY STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 119 License No. NPF-18 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Comme.1 wealth Edison Company l
(the licensee), dated May 19,1999, 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 l
Act, and the 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 enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follows:
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1 (2)
Technical Soecifications. FLEnvironmental Protection Plan I
The Technical Specifications contained in Appendix A, as revised through Amendment No. 119
, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee 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 within 30 days from the date of issuance. Implementation of this amendment shallinclude the relocation of certain technical specification requirements to the appropriate licensee-controlled documents as described in the Licensee's application dated May 19,1999 and its supplements dated September 10,1999, and evaluated in the staff's Safety Evaluation Report attached to this amendment.
FOR THE NUCLEAR REGUI.ATORY COMMISSION
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e
, Anthony J. Mer.diola, Chief, Section 2
~ Project Directorate lli Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 1,1999-
n l
f ATTACHMENT TO LICENSE AMENDMENT NO.119 l
FACILITY OPERATING LICENSE NO. NPF-18 l
DOCKET NO. 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pcges are identified by amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT VI VI i
Xill XIll XXII XXil l
3/4 4-11 3/4 4-11 1
3/4 4-12 4
-3/4 4-13 B 3/4 4-2 B 3/4 4-2 i
i i
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i s
I E
l.
INDEX.
I-LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops........................... <
3/44-1 Jet Pumps 3/4 4-3 Recirculation Loop Flow.....................
3/44-4 Idle Recirculation Loop Startup...
3/4 4-5 Thermal Hydraulic Stability.....
3/4 4-Sa 3/4.4.2 SAFETY / RELIEF VALVES..........................
3/4 4-6
.3/4 4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems..
3/4 4-7 Operational Leakage....
3/44-8 3/4.4.4 DELETED...
3/4 4-11 3/4.4.5 SPECIFIC ACTIVITY........
3/4 4-14 3/4.4.6 PRESSURE / TEMPERATURE LIMITS Reacter Coolant System...
3/4 4-17
]
Reactor Steam Dome...
3/4 4-21 3/4.4.7 MAIN STEAM LINE ISCLATION VALVES..
3/4 4-22 3/4.4.8 STRUCTURAL INTEGRITY..
3/4 4-23 3/4.4.9 RESIDUAL HEAT REMOVAL Hot Shutdown.............
3/4 4-24 Cold Shutdown...........................
3/4/4-25 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 : ECCS-OPERATING,.
3/4 5-1 3/4.5.2 ECCS-SHUTDOWN.,....
3/4 5-6 3/4.5.3 SUPPRESSION CHAMBER..........
3/4 5-8 i
LA SALLE - UNIT 2 VI Amendment No. 119 i
r ef-s 7
INDEX L
BASES P
P SECTION.
PAGE-INSTRUMENTATION (Continued)
L MONITORING INSTRUMENTATION (Continued)
L Meteorological Monitoring Instrumentation............... B 3/4 3-4a
-Remote Shutdown Monitoring Instrumentation........
B 3/4 3-4a i
Accident Monitoring Instrumentation..............,.
. B 3/4 3-5 Source Range Monitors.............................
B 3/4 3-5 Deleted........................................ B 3/4 3-5 L
' Explosive Gas Monitoring Instrumentation...........
. B 3/4 3-6 Loose-Part Detection System........................... B 3/4 3-6 B 3/4 3-6 O
3/4.4 REACTOR COOLANT SYSTEM
!~
3/4.4.1 ~ RECIRCULATION SYSTEM........
... B 3/4 4-1 3/4.4.2 : SAFETY / RELIEF VALVES.................
B 3/4 4-1a 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems...........
...... B 3/4 4-2 j
Operational teakage............................. B 3/4 4-2 L
3/4.4.4 D E LETE D.............................
8 3/4 4-2 l~
J 3/4.4.5 SPECIFIC ACTIVITY............................ B 3/4 4-3 3/4.4.6 l FRESSURE/ TEMPERATURE LIMITS................ B 3/4 4-4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES.............. B 3/4 4-5 3/4.4.8 STRUCTURAL INTEGRITY,.......
..... B 3/4 4-5 3/4.4.9 RESIDUAL HEAT REMOVAL B 3/4 4-5 LA SALLE - UNIT 2 Xill Amendment No.119
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INDEX LIST OF TABLES (Continued)
TABLE PAGE 3.3.7.4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION
. 3/4 3-67
)
i 4.3.7.4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.
3/4 3-68 l
3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION.
3/4 3-70 l
4.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION l
SURVEILLANCE REQUIREMENTS 3/4 3-71 4
3.3.7.11-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION.
3/4 3-83 4.3.7.11-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANrE REQUIREMENTS 3/4 3-84 3.3.8-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION.
3/4 3-87 3.3.8-2 FEEDWATER/MA!N TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SETPOINTS 3/4 3-88 4.3.8.1 -1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-89 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES.
3/4 4-10 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM 3/4 4-16 4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVElLLANCE PROGRAM WITHDRAWAL SCHEDULE.
3/4 4-20 LA SALLE - UNIT 2 XXII Amendment No. 119 i
m-c).
E I
3/4.4.4 INTENTIONALLY LEFT BLANK PAGES 3/4 4-12 AND 3/4 4-13 ARE DELETED I
J LA SALL. UNIT 2-3/4 4-11 NEXT PAGE IS 3/4 4-14 Amendment No.119 L
REACTOR COOLANT SYSTEM BASES 3/4,4.3 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.3.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure boundary. These detection systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.
3/4.4.3.2 OPERATIONAL LEAKAGE The allowable leakage rates from the reactor coolant system have been based on the predicted and experimentally observed behavior of cracks in pipes. The normally expected background leakage due to equipment design and the detection capability of the instrumentation for determining system leakage was also considered. The evidence obtained from experiments suggests that forleakage somewhat greater than that specified for unidentified leakage the probability is small that the imperfection or crack associated with such leakage would grow rapidly. However, in all cases, if the leakage rates exceed the values specified or the leakage is located and known to be PRESSURE BOUNDARY LEAKAGE, the reactor will be shutdown to allow further investigation and corrective action.
The Surveillance Requirements for RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of gross valve tailure and consequent intersystem LOCA. Leakage from the RCS pressure isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.
3/4.4.4 DELETED LA SALLE - UNIT 2 B 3/4 4-2 Amendment No.119