ML17300B242
| ML17300B242 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/22/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17300B243 | List: |
| References | |
| NUDOCS 9001100151 | |
| Download: ML17300B242 (23) | |
Text
g:fE'AKgb (4
po
+iI*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC. SERVICE COMPANY -ET AL.
DOCKET-NOS..STN.50-528 PALO VERDE.NUCLEAR.GENERATING. STATION -UNIT.NO.. 1 AMENDMENT-TO FACILITY.OPERATING. LICENSE Amendment No. 45 License No.
NPF-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated October 10, 1989 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 Water 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; B.
The facility will operate in conformity with the application, the provisions of the 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; 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:
=-- --- ~g 8g1222 gppf1QQ151 Q5ppp528
r P,
t, j
~
z
~
~ e h
(2)
Techni ca 1.S ecifications-and. Environmental. Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 45, 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.
The changes in the Technical Specifications are to become effective within 45 days'of issuance of the amendment.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time.
The period of time during changeover shall be minimized.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Georg
. Knigh, Director Project Directorate V
Division of Reactor Projects III, IV, V and Special Projects Date of Issuance:
December 22, 1989
ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.
45 TO FACILITY OPERATING LICENSE NO. NPF-41 DOCKET NO.
STN 50-528 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Amendment Pa e
3/4 3-29 3/4 3-30
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES
RESPONSE
TIMES INITIATING SIGNAL AND FUNCTION
RESPONSE
TIME IN SECONDS 8.
Steam Generator Level - High a.
Main Steam Isolation 1.
MSIS actuated MSIV's 5 6*/5 6%A 2.
MSIS actuated MFIV's¹ yO 6*/IO 6A*
9.
Steam Generator hP-High-Coincident With Steam Generator Level Low a.
Auxiliary Feedwater Isolation from the Ruptured Steam Generator 10.
Control Room Essential Filtration Actuation ll.
- 4. 16 kV Emergency Bus Undervoltage (Degraded Voltage)
Loss of Power 90X system voltage
]6A/]6*A
< 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.
¹MFIV 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-MOl, M-HJA-M52, M-HJB-MOl and M-HJB-M55.
¹¹¹The provisions of Specification 4.0.4 are not applicable for the turbine-driven Auxiliary Feedwater pump ENGINEERED SAFETY FEATURES
RESPONSE
TIME for entry into Mode 3.
PALO VERDE - UNIT 1 3/4 3-30 AMENDMENT NO.
45
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES
RESPONSE
TIMES INITIATING SIGNAL AND FUNCTION 2.
Pressurizer Pressure Low a.
Safety Injection (HPSI) b.
Safety Injection (LPSI) c.
Containment Isolation l.
CIAS actuated mini-purge valves 2.
Other 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's¹ e.
Containment Spray Pump 4.
Containment Pressure
- High-High a.
Steam Generator Pressure
- Low a.
Main Steam Isolation 1.
MSIS actuated MFIV's¹ 6.
Refueling Water Tank - Low a.
Containment Sump Recirculation 7.
Steam Generator Level -
Low a.
Auxiliary Feedwater (Motor Drive) b.
Auxiliary Feedwater (Turbine Drive)¹¹¹
RESPONSE
TIME IN SECONDS 30*/30*%
< 30m/30~x
< 10.6*/10.6""
31%/31%A 30%/30%%
30%/30*8
< 10.6~/10.6~~
31K'/31K'*
5 6A'/5 6*%
< 10.6*/10.6*~
33)h/23**
33k/23*)k
< 10.6"/10. 6*"
45k/45*)k 46k/23*%'0'I/30'A*
PALO VERDE - UNIT 1 3/4 3-29 AMENDMENT NO.
45
~P RED(
+~
'o Cy A.0 0
Cy 4O
~O
++*++
UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA.PUBLIC SERVICE-COMPANY
DOCKET-NOS.-STN.50 529 PALO. VERDE.blUCLEAR.GENERATING.STATION -UNIT,.NO 2
AMENDMENT-TO-FACILITY.-OPERATING-LICENSE Amendment No. 31 License No.
NPF-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated October 10, 1989 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 Water 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; 6.
The facility will operate in conformity with the application, the provisions of the Act, pnd 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 wi 11 be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment wil'I 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-51 is hereby amended to read as follows:
~
~
~
~
t2) T~l "I
1-S Ifl I
d.F The Technical Specifications contained in Appendix A, as revised through Amendment No. 3l; and the Environmental Protection Plan contained in Appendix 8, 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.
The changes in the Technical Specifications are to become effective within 45 days of issuance of the amendment.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time.
The period of time during changeover shall be minimized.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications George
. Knighto Director Project Directorate V
Division of Reactor Projects III, IV, V and Special Projects Date of Issuance:
December 22, 1989
ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.
31 TO FACILITY OPERATING LICENSE NO. NPF-51 DOCKET NO.
STN 50-529 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Amendment Pa e
3/4 3-29 3/4 3-30
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES
RESPONSE
TIMES INITIATING SIGNAL AND FUNCTION 2.
Pressurizer Pressure Low a.
Safety Injection (HPSI) b.
Safety Injection (LPSI) c.
Containment Isolation 1.
CIAS actuated mini-purge valves 2.
Other 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's¹ e.
Containment Spray Pump 4.
Containment Pressure
- High-High a.
Steam Generator Pressure
- Low a.
Main Steam Isolation 1.
MSIS actuated MFIV's¹ 6.
Refueling Water Tank - Low a.
Containment Sump Recirculation 7.
Steam Generator Level -
Low a,
Auxiliary Feedwater (Motor Drive) b.
Auxiliary Feedwater (Turbine Drive)¹¹¹
RESPONSE
TIME IN SECONDS 3QA/3QA'A' 3Q)h/3Q**
< 10.6"/10.6"~
3] A/31%A' 3Qa/3Qa~
(
3QA/3QkA'O 6A/1Q 6%A 31K/3] A)k
( 5 6)k/5 6AA' 1O.6</1Q.6**
( 339(/23k'A 33k/23K'A
( 5 6'4/5 6)k'k
< 10. 6"/10. 6""
( 45k/45%A 46K/23k)k
( 3QA/3QA*
PALO VERDE " UNIT 2 3/4 3"29 AMENDMENT NO.
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES
RESPONSE
TIMES INITIATING SIGNAL AND FUNCTION
RESPONSE
TIME IN SECONDS 8.
Steam Generator Level - High a.
Main Steam Isolation 1.
< 5 6~/5 6~*
2.
MSIS actuated MFIV's¹ 10 6A/10 6k*
9.
Steam Generator hP-High-Coincident Mith Steam Generator Level Low a.
Auxiliary Feedwater Isolation from the Ruptured Steam Generator 10.
Control Room Essential Filtration Actuation 11.
- 4. 16 kV Emergency Bus Undervoltage (Degraded Voltage)
Loss of Power 90X system voltage 16k/16'AJc
< 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.
¹MFIV 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, M-HJB-M01 and M-HJB-M55.
¹¹¹The provisions of Specification 4.0.4 are not applicable for the turbine-driven Auxiliary Feedwater pump ENGINEERED SAFETY FEATURES
RESPONSE
TIME for entry into Mode 3.
PALO VERDE - UNIT 2 3/4 3"30 AMENDMENT NO.
31
~O,R REOIj Ci+
+4 PO
~
Op
- 0O
~
~
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA-PUBLIC SERVICE COMPANY ET. AL.
DOCKET-NOS.-STN.50-530 PALO VERDE. NUCLEAR. GENERATING. STATION UNIT.NO. 3 AMENDMENT TO. FACILITY-OPERATING -LICENSE Amendment No. 20 License No. NPF-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated October 10, 1989 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, Pub lic Service Company of New Mexico, Los Angeles Department of Water 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
TheIe is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the hea'Ith 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-74 is hereby amended to read as follows:
1
~
J I
~ 1
)
I K t'
~
(2)
Technical S ecifications-and Environmental.Protection,-Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 2g 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.
The changes in the Technical Specifications are to become effective within 45 days of issuance of the amendment.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time.
The period of time during changeover shall be minimized.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications George Knighton irector Project Directorate V
Division of Reactor Projects III, IV, V and Special Projects Date of Issuance:
December 22, 1989
ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.
2O 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 vertical lines indicating the areas of change.
Amendment Pa e
3/4 3-29 3/4 3-30
TABLE 3. 3-5 (Continued)
ENGINEERED SAFETY FEATURES
RESPONSE
TIMES INITIATING SIGNAL AND FUNCTION
RESPONSE
TIME IN SECONDS 8.
Steam Generator Level - High a.
Main Steam Isolation 1.
< 5 6*/5 6~~
2.
MSIS actuated MFIV's¹ yP 6A/IO 9.
Steam Generator bP-High-Coincident Mith Steam Generator Level Low a.
Auxiliary Feedwater Isolation from the Ruptured Steam Generator 10.
Control Room Essential Filtration Actuation ll.
4.'16 kV Emergency Bus Undervoltage (Degraded Voltage)
Loss of Power 90% system voltage y6A/I6**
< 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.
¹MFIV 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-MOl, M-HJA-M52, M-HJB-M01 and M-HJB-M55
¹¹¹The provisions of Specification 4. 0. 4 are not applicable for the turbine-driven Auxiliary Feedwater pump ENGINEERED SAFETY FEATURES
RESPONSE
TIME for entry into Mode 3.
PALO VERDE - UNIT 3 3/4 3-30 AMENDMENT NO.
TABLE 3. 3-5 (Continued)
ENGINEERED SAFETY FEATURES
RESPONSE
TIMES INITIATING SIGNAL AND FUNCTION 2.
Pressurizer Pressure Low a.
Safety Injection (HPSI) b.
Safety Injection (LPSI) c.
Containment Isolation 1.
CIAS actuated mini-purge valves 2.
Other 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's¹ e.
Containment Spray Pump 4.
Containment Pressure
- High-High a.
Steam Generator Pressure Low a.
Main Steam Isolation 1.
MSIS actuated MFIV's¹ 6.
Refueling Water Tank - Low a.
Containment Sump Recirculation 7.
Steam Generator Level -
Low a.
Auxiliary Feedwater (Motor Drive) b.
Auxiliary Feedwater (Turbine Drive)¹¹¹
RESPONSE
TIME IN SECONDS
( 30K/30*)k
( 3Q*/3Q**
< 10.6</10.6~*
( 31*/3]**
( 30k/30*4' 30*/30K*
< 10.6~/10.6"*
31*/31**
< 5 6a/5 6**
< 10.6"/10.6*"
( 33*/23K'k 338/23**
5 6~/5 6~*
< 10.6"/10.6**
45k/45K'*
46~/23**
( 30*/30%*
PALO VERDE - UNIT 3 3/4 3-29 AMENDMENT NO.
20