ML17304A878
| ML17304A878 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/28/1988 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17304A879 | List: |
| References | |
| NUDOCS 8901190136 | |
| Download: ML17304A878 (9) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 41 License No.
NPF-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
The application for amendment, dated July 25, 1988 by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric
- Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Mater and Power, and Southern California Public Power Authority (licensees),
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; The facility will operate in conformity with the application, the provisions of Act, and the regulations of the Commission; 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; 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; 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 Facility Operating License No.
NPF-41 is hereby amended to read as follows:
890ii90i36 8812287 PDR
- DOCK 05000528 P
Pbg
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 41, 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.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION EQclosure:
Changes to the Technical Specifications eorge M
- Knighton, ector Project Directorate Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation Date of Issuance:
December 28, 1988
ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO. 41 TO FACILITY OPERATING LICENSE NO. NPF-41 DOCKET NO.
STN 50-528 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains a vertical line indicating the areas of change.
Also to be. replaced is the following overleaf page to the amended page.
Amendment Pa es 3/4 3-30 Overleaf Pa es 3/4 3-29
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TABLE 3.3-5 (Continued)
ENGINEEREO SAFETY FEATURES
RESPONSE
TIMES INITIATING SIGNAL AND FUNCTION 2.
Pressur izer Pressur e - Low a.
Safety Injection (HPSI) b.
Safety Injection (LPSI) c.
Containment Isolation 1.
CIAS actuated mini-purge valves 2.
Othe~
CIAS actuated valves 3.
Containment Pressure - High a.
Safety Injection (HPSI) b.
Safety Injection (LPSI) c.
Containment Isolation 1.
CIAS actuated mini-purge valves 2.
Other CIAS actuated valves d.
Main Steam Isolation 1.
MSIS actuated MFIV'st e.
Containment Spray Pump 4.
Containment Pressure
- High-High a.
Steam Generator Pressure - Low a.
Main Steam Isolation 1.
MSIS actuated MFIY's8 6.
Refueling Mater Tank - Low a.
Containment Sump Recirculation 7.
Steam Generator Level - Low a.
Auxiliary Feedwatet (Motor Drive) b.
Auxiliary Feedwater (Turbine Drive)
RESPONSE
TIME IN SECONOS 3QA/30**
< '30*/30*<
< 10.6~/10.6*~
313'/313BA 3Q*/3Q0*
(
30iB,'/303tiB,'
lp. 6"/10. 6""
( 31'/3133l3B
( 5 63'/5
< 1O.6~/10.6*~
33'/233tiB' 33%/233iEA 5 6A'/5 10.6"/10.6"
< 45k/45k*
46*/23*iB
( 30%/3PA*
PALO VERDE - UNIT 1 3/4 3-29 AMENDMENT NO. >~
NR 2 1~88
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES
RESPONSE
TIMES INITIATINGSIGNAL AND FUNCTION
RESPONSE
TIME IN SECONDS 8.
Steam Generator Level - High a.
Hain Steam Isolation 1.
HSIS actuated HSIV's
< 5 6*/5 6<<<<
2.
HSIS actuated HFIV's¹
< 10.6*/10.6""
9.
Steam Generator hP-High-Coincident Mith Steam Generator Level Low a.
Auxiliary Feedwater Isolation 16<</16'<<<<
from the Ruptured Steam Generator 10.
Control Room Essential Filtration Actuation 11.
4.16 kV Emergency Bus Undervoltage (Degraded Voltage)
Loss of Power 90K system voltage
< 180*/180**¹¹
< 35.0
.12.
4.16 kV Emergency Bus Undervoltage (loss of Voltage)
Loss of Power
< 2.4 TABLE NOTATIONS "Diesel generator starting and sequence loading delays included.
Response
time limit includes movement of valves and attainment of pump or blower discharge pressure.
""Diesel generator starting delays not included.
Offsite power available.
Response
time limit includes movement of valves and attainment of pump or blower discharge pressure.
¹HFIV valves tested at simulated operating conditions; valves tested at
. static flow conditions to < 8.6"/8.6"* seconds.
¹¹Radiation detectors are exempt from response time testing.
The response time of the radiation signal portion of the channel shall be measured from the detector output or from the input of first electronic component in channel to closure of dampers M-HJA-M01, M-HJA-M52, H-HJB-H01 and M-HJB-H55.
PALO VERDE - UNIT 1 3/4 3-30 AMENDMENT NO.
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