ML20092J048
| ML20092J048 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/15/1995 |
| From: | Kalman G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20092J050 | List: |
| References | |
| NPF-06-A-163 NUDOCS 9509210293 | |
| Download: ML20092J048 (9) | |
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UNITED STATES i
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- NUCLEAR REGULATORY COMMISSION B
AsHINGTON, D.C. - "$1
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ENTERGY OPERATIONS. INC.
l DOCKET NO. 50-368 ABirlhtiNUCLEARONE.UNITNO.I ANENDMENT TO FACILITY OPERATING LICENSE Amendment No. 163 1
License No. NPF-6 l
1.
The Nuclear Regulatory Comission (the Commission) has found that:
' A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated October 27, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the 1
Act), and the Comission's rules and regulations set forth in 10 l
CFR Chapter I; B..
The facility'will operate in conformity with the application, the j
provisions of the Act, and the rules an.1 regulations of the Cocnission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conductea without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this license amendment will not be inimical to the j
common defense and security or to the health and safety of the public; and l
c 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.
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9509210293 950915 I
PDR ADOCK 05000368 P
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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. NPF-6 is hereby amended to read as follows:
5 (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 163, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/ff Wm George Kalman, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 15, 1995 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 163 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Revise the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding j
overleaf pages are also provided to maintain document completeness.
I REMOVE PAGES INSERT PAGES V
V 3/4 3-28 3/4 3-28 4
3/4 10-4 3/4 10-4 8 3/4 3-2 8 3/4 3-2 4
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1-
2 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
' SECTION PAGE.
I 1
-~3/4.2-,
.. POWER DISTRIBUTION LIMITS:
3/4.2.1 3 LINEAR HEAT RATE...............................
3/4 2,
- 3/4.2.2i RADIAL PEAKING FACTORS...................'......
.3/4 2-2 3/4.2.3 AEIMUTHAL POWER TILT...........................
3/4-2-3 I
3/4.2;4' DNBR MARGIN....................................
'3/4 2-5
- 3/4.2.5 RCS FLOW RATE..................................
- 3/4 2-7 3/4.2.6 REACTOR. COOLANT COLD LEG TEMPERATURE...........-
3/4 2-8 3/4.2.7-AXIAL SHAPE INDEX..............................
3/4 2-9 3/4.2.8 PRESSURIZER PRESSURE...........................
3/4 2-10' i
3/4. 3 ' INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION.............
3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.............................
3/4 3-10
- 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation...........
3/4 3-24 l
Seismic Instrumentation.......................
3/4 3-30 i
Meteorological Instrumentation.................
3/4 3-33 Remote' Shutdown Instrumentation................
3/4 3-36 Post-Accident Instrumentation'..................
3/4 3-39 Chlorine Detection Systems.....................
3/4 3-42 Fire Detection Instrumentation.................
3/4 3-43 Radioactive Gaseous Effluent Monitoring Instrumentation.............................
3/4 3-45 l
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ARKANSAS - UNIT 2 V
Amendment No. 34,40,-1M,163
INDEX i
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3.3 (continued) 4 Radioactive Liquid Effluent Monitoring Instrumentation.....................................
3/4 3-54 3/4.3.4 TURBINE OVERSPEED PROTECTION.....................
3/4 3-58 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION.........
3/4 4-1 4
3/4.4.2 SAFETY VALVES - SHUTD0WN..............................
3/4 4-3 l '!
3/4.4.3 SAFETY VALVES - 0PERATING.............................
3/4 4-4
,f3/4.4.4 PRES $URIZER...........................................
3/4 4-5 l
!!3/4.4.5 ST EAM GEN ERATO RS......................................
3/ 4 4 - 6 3/4.4.6 l
REACTOR COOLANT SYSTEM LEAKAGE f
L ea ka ge De tection Sys tems.............................
3/4 4-13 Reactor Coolant Sys tem Lea kage........................
3/4 4-14
.j3/4.4.7 CHEMISTRY.............................................
3/4 4-15 ll3/4.4.8 SPECIFIC ACTIVITY.....................................
3/4 4-18 II 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Rea ctor Coola nt Sys tem................................
3/4 4-22 Pressurizer...........................................
3/4 4-25 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 and 3 Components.................
3/4 4-26
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- 3/4.4.11 REACTOR COOLANT SYSTEM VENTS..........................
3/4 4-27 I
' 3/4.5 EMER'iENCY CORE COOLING SYSTEMS (ECCS)
, 3/4.5.1 S A F ETY I NJ E CT I ON TAN KS..............................
3/ 4 5 - 1 11 4
ARKANSAS-UNIT 2 VI Amendment No. 23, #, 63 1
THIS PAGE INTENTIONALLY LEFT BLANK l
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l ARKANSAS - UNIT 2 3/4 3 28 Amendment No. 63. 434. M1,163 i
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e SPECIAL TEST EXCEPTIONS REACTOR COOLANT' LOOPS LTMITINO COMDITION FOR OPERATION 3.10.3 The limitations of Specification. 3.4.1.1 and noted requirements of Table 3.3-1 may be suspended during the performance of startup and PHYSICS TESTS, provided:
a.
The THERMAL POWER does not exceed 5% of RATED THERMAL POWER, and b.
The reactor trip setpoints of the OPERABLE power level channels are set at 5 20% of RATED THERMAL POWER.
APPLICABILITY:
During startup and PHYSICS TESTS.
ACTION:
I With the THERMAL POWER > 5% of RATED THERMAL POWER, immediately trip the reactor.
SURVETLLANCE REOUTREMENTS 4.10.3.1 The THERMAL POWER shall be determined to be 5 5% of RATED THERMAL POWER at least once per hour during startup and PHYSICS TESTS.
4.10.3.2 Each wide range logarithmic and power level neutron flux monitoring channel sha be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours prior to initiating startup or PHYSICS TESTS. P L 1-1 l I ARKANSAS - UNIT 2 3/4 10-3 Amendment No. 149
l 1 4 SPECIAL TEST' EXCEPTIONS i 4 i CENTER CEA MISALIG'WENT 4 l ' LIMITING CONDITION TCR OPERATION i 3.10.4 The requirements of Specifications 3.1.3.1 and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS to determine the isothermal temperature coefficient, moderator temperature coefficient and I i power coefficient provided: a. Only the center CEA (CEA #1) is misaligned, and j b. The limits of Specific'ation 3.2.1 are maintained and determined as specified in Specification 4.10.4.2 below. APPL 1C ARIt ITY: MODES I and 2. i ACTION: With any of the limits of Specification 3.2.1 being exceeded while the requirements of Specifications 3.1.3.1 and 3.1.3.6 are suspended, either: 4 e. Reduce THERMAL POWER sufficiently to satisfy the requirements of j specification 3.2.1. or b. Be in NOT STANDBY within 6 hours. j SURVElLLANCE REOUIREMENTS 4.10.4.1 The THERMAL POWER shall be determined at least once per hour during PHYSICS TESTS in which the requirements of Specifications 3.1.3.1 and/or 3.1.3.6 are suspended and shall be verified to be within the test power plateau. 4.10.4.2 The linear heat rate shall be determined to be within the limits of Specification 3.2.1 by monitoring it continuously with the incore i detection system during PHYSICS TESTS above 5% of RATED THERHAL POWER in 1 which the requirements of Specifications 3.1.3.1 and/or 3.1.3.6 are suspended. I i ARKANSAS - UNIT 2 3/4 10 4 Amendment No.163 i
3/4.3 INSTRUMENTATION BASES 3 /4. 3. 3 MONITORING INSTRUMENTATION i 5 i -3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION .The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded. 4 The PURGE as defined in the definitions section is a release under a purge permit, whereas continuous ventilation is. defined as operation of the purge system after the requirements of the purge permit have been satisfied. When securing the containment purge system to meet the ACTION requirements of this Specification, at least one supply valve and one exhaust valve is to be l closed, and the supply and exhaust f ans secured. 3 /4.3.3. 2 DELETED 3/4.3.3.3 SEISMIC INSTRUMENTATION 4 The OPERABILITY of the seismic instrumentation ensures that i sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix "A" of 10 CFR Part 100. i The instrumentatiop is consistent with the recommendations of Safety Guide
- 12. " Instrumentation for Earthquakes," March, 1971.
3/4.3.3.4 HETEOR0 LOGICAL INSTRUMENTATION i The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release i of radioactive msterials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the i health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs " Feburary 1972. 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of'the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50. ARKANSAS'- UNIT ~2 B 3/4 3 2 Amendment No, a3,440, 440,163 l}}