ML20154N269
| ML20154N269 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/19/1998 |
| From: | Fields M NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20154N273 | List: |
| References | |
| NUDOCS 9810210235 | |
| Download: ML20154N269 (8) | |
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. =8 aaai 49 * * * * *,o ARIZONA PUBLIC SERVICE COMPANV. ET AL.
DOCKET NO. STN 50-530 PALO VERDE NUCLEAR GENEW]NG STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.119 License No. NPF-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
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1 A.
The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural improvement and Power District, El Paso Electric Company, Southern Califomia Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southem Califomia Public Power Authority dated October 6,1998, 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 (i) that the activities authorized by this amendment can be conducted wkhout 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.
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-74 is hereby amended to read as follows:
9810210235 981019 PDR ADOCK 05000530 P
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1 (2)
Technical Soecifications and Environmental Protection Plan 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 into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION fff l
Mel B. Fields, Project Manager Project Directorate IV-2 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 19, 1998 i
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.119 TO FACILITY OPERATING LICENSE NO. NPF-74 DOCKET NO. STN 50-530 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 1.1-5 1.1-5 3.3.1-6 3.3.1-6 3.3.1-8 3.3.1-8 3.3.1-10 3.3.1-10 3.3.2-5 3.3.2-5 i
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Definitions 1.1 1.1 Definitions LEAKAGE (continued) c.
Pressure Boundary LEAKAGE LEAKAGE (except SG LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.
MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, cold leg reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.
NEUTRON RATED The indicated neutron flux at RTP.
THERMAL POWER (NRTP)
(for Unit 3 only)
OPERABLE-OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function (s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power. cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train.
component, or device to perform its specified safety function (s) are also capable of performing their related support function (s).
PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.
These tests are:
i a.
Described in Chapter 14 Initial Test Program of the UFSAR:
b.
Authorized under the provisions of 10 CFR 50.59: or c.
Otherwise approved by the Nuclear Regulatory Commission.
(continued)
PALO VERDE UNITS 1 AND 2 1.1-5 AMENDMENT NO. 117 PALO VERDE UNIT 3 AMENDMENT NO. 4 U,119
i RPS Instrumentation-Operating 3.3.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.6
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER = 15% RTP.
Verify linear power-subchannel gains of the 31 days excore detectors are consistent with the values used to establish the shape annealing matrix elements in the CPCs.
NOTES-------------------
l 1.
The CPC CHANNEL FUNCTIONAL TEST shall include verification that the correct values of addressable constants are installed in each OPERABLE CPC.
2.
Not required to be performed for logarithmic power level channels until 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after reducing THERMAL POWER */ logarithmic power
- below I
Perform CHANNEL FUNCTIONAL' TEST on each 92 days channel.
NOTE--------------------
Neutron detectors are excluded from the CHANNEL CALIBRATION.
Perform CHANNEL CALIBRATION of the power 92 days range neutron flux channels.
(continued)
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- THERMAL POWER for Units 1 and 2.. logarithmic power for Unit 3.
l PALO VERDE UNITS 1 AND 2 3.3.1-6 AMENDMENT NO. 117 PALO VERDE' UNIT 3 AMENDMENT NO.147.119
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RPS Instrumentation-Operating 3.3.1 Table 3.3.1-1 (page 1 of 3)
.[
Reactor Protective system Instrumentation APPLICABLE MODES OR OTHER SPECIFIED SURVEILLANCE FUNCTION CONDITIONS REQUIREMENIS alt.0WABLE VALUE 1.
Verlable Over Power 1,2 SR 3.3.1.1 Celling 5 111.0% RTP SR 3.3.1.4 Band s 9.9% RTP SR 3.3.1.6 Incr. Rate 5 11.0%/ min RTP SR 3.3.1.7 Decr. Rate > 5%/sec RTP SR 3.3.1.8 SR 3.3.1.9 SR 3.3.1.13 3-l 2.
Logarithmic Power Level - High(a) 2 SR 3.3.1.1 s 0.011% (NRTP for Unit 3) l
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SR 3.3.1.7 SR 3.3.1.9 j
Pressurizer Pressure - High 1,2 SR 3.3.1.1 s 2388 psia SR 3.3.1.7 SR 3.3.1.9 SR 3.3.1.13 r
4 Pressurizer Pressure-Low 1,2 SR 3.3.1.1
= 1821 psia SR 3.3.1.7 hR 3.3.1.9 SR 3.3.1.12 SR 3.3.1.13 5.
Containment Pressure-High 1,2.
SR 3.3.1.1 s 3.2 psig SR 3.3.1.7 SR 3.3.1.9 SR 3.3.1.13 6.
Steam Generator #1 Pressure-Low 1,2 SR 3.3.1.1 a 890 psis SR 3.3.1.7 SR O.1.9 SR S 1.13 7.
Steam Generator #2 Pressure-Low 1,2 SR 3.3.1.1
= 890 pela SR 3.3.1.7 SR 3.3.1.9 SR 3.3.1.13 (continued)
(a) Trip may be bypassed when THERMAL POWER */logerithmic power
- is > 1E 4% RTP (NRTP for Unit 3). Bypass shall be automatically removed when THERMAL POWER */ logarithmic power' is 51E 4% RTP (NRTP for Unit 3).
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THERMAL POWER for Unita 1 and 2, togerithmic power for Unit 3.
PALO VERDE UNITS 1 AND 2 3.3.1-8 AMENDMENT NO. 117
. PALO VERDE UNIT 3 AMENDMENT NO. 444,119
RPS Instrumentation-Operating 3.3.1 l
Table 3.3.1 1 (page 3 of 3) l Reactor Protective System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED SURVEILLANCE FUNCTION CONDITIONS REQUIREMENTS ALLOWABLE VALUE
- 14. Local Power Density-l!(gh(b)'
1,2 SR 3.3.1.1 5 21.0 kW/ft SR 3.3.1.2 SR 3.3.1.3 SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.7 SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.11 SR 3.3.1.12 SR 3.3.1.13 15..DepartureFromNulgateBolling 1,2 SR 3.3.1.1
= 1.30 i
Ratlo (DNBR)- Low SR 3.3.1.2 SR 3.3.1.3 d
SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.7 SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.11 J
(b) Trip may be bypassed when THERMAL POWER */ logarithmic power
- shall be automstically removed when THERMAL POWER */ logarithmic power
- is a 1E 4X RTP (NRTP for Unit 3).
- THERMAL POWER for Units 1 and 2, logarithmic power for Unit 3.
PALO VERDE UNITS 1 AND 2 3.3.1-10 AMENDMENT NO.-117 PALO. VERDE UNIT 3 AMENDMENT NO. 4 #,119
RPS Instrumentation-Shutdown 3.3.2 Table 3.3.2 1 Reactor Protective System Instrumentation Shutdown APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS SURVEILLANCE FUNCTION REQUIREMENTS ALLOWA8LE VALVE 1.
Logarithmic Power Level-High(d) 3(a), 4(a), $(a)
SR 3.3.2.1 s 0.011% gip (for l c)
SR 3.3.2.2 (NRTP SR 3.3.2.?,
Unit 3) l SR 3.3.2.4 SR 3.3.2.5
- 2. - Steam Generator #1 Pressure Low (b) 3(a)
SR 3.3.2.1 a PoO psis SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.5 3.
Steam Generator #2 Pressure-Low (b) 3(a)
SR 3.3.2.1 a 890 psis SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.5 (a)
With any Reactor Trip Circuit Breakers (RTCBs) closed and any control element assembly capable of being withdrawn.
~(b)
The setpoint may be decreased as steam pressure is reduced, provided the margin between steam pressure and the setpoint is maintained s 200 psig. The setpoint shall be automatically increased to the normal setpoint as steam pressure is increased.
(c)
The setpoint must be reduced to s 1E-4% RTP (NRTP for Unit 3) when itse than 4 RCPs are running.
(d)
Trip may be bypassed when THERMAL POWER */ logarithmic power
- is > 1E-4% RTP (NRTP for Unit 3). Bypass shall be automatically removed when THERMAL POWE.t*/ logarithmic power
- is s 1E 4% RTP (NRTP for Unit 3).
- THERMAL POWER for Unis 1 and 2, logarithmic power for Unit 3.
~PALO VERDE UNITS 1 AND 2 3.3.2-5 AMENDMENT NO. 117 PALO VERDE UNIT 3 AMENDMENT NO. 4 W,119