ML17311A289
| ML17311A289 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/21/1994 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17311A290 | List: |
| References | |
| NUDOCS 9409280136 | |
| Download: ML17311A289 (32) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION.
wASHlNGTON, D.c. msss-ooo~
9409280i36 '94092i PDR ADOCK 05000528 P
'PDR ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
1 MENDMENT TO FACILITY OPERATING LICENSE Amendment No; Si Li,cense No.
NPF-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
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 California Edison
- Company, Public Service Company of New Mexico, Los Angeles Department of Mater and Power, and Southern California Public Power Authority dated August 5,
- 1993, 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 op'crate 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 wi.thout endangering the health and safety of the public, and (ii) that such activities wi.ll 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-41 is hereby amended to read as follows:
0 4l 0h
1 Mr. William"L. Stewart Arizona Public Service Company Palo Verde CC:
Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street
- Phoenix, Arizona 85007 T.
E. Oubre, Esq.
Southern California Edison Company P. 0.
Box 800
- Rosemead, California 91770 Senior Resident Inspector Palo Verde Nuclear Generating Station 5951 S. Wintersburg Road
- Tonopah, Arizona 85354-7537 Regional Administrator, Region IV U.
S. Nuclear:Regulatory Commission Harris Tower 5 Pavillion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations ABB Combustion Engineering, Nuclear Power 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street
- Phoenix, Arizona 85040 Jack R.
- Newman, Esq.
Newman
- 5. Holtzinger, P.C.
1615 L Street, N.W., Suite 1000 Washington, D.C.
20036 Mr. Curtis Hoskins Executive Vice President and Chief Operating Officer Palo Verde Services 2025 N. 3rd Street, Suite 220
- Phoenix, Arizona 85004 Roy P.
Lessey, Jr.,
Esq.
Akin, Gump, Strauss, Hauer and Feld El Paso Electric Company 1333 New Hampshire Avenue, Suite 400 Washington, DC.
20036 Ms. Angela K. Krainik, Manager Nuclear Licensing Arizona Public Service Company P.
O'.
Box 52034
- Phoenix, Arizona 85072-2034
- Chairman, Maricopa County Board of Supervisors 111 South Third Avenue
- Phoenix, Arizona 85003
ik
3.
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 81, 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.
This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION gj~,Q~ ~
Theodore R. quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
SePtember 21, 1994
4l 4l t;
MENDMENT NO.
ATTACHMENT TO LICENSE AMENDMENT 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.
Remove 3/4 3-58 3/4 3-60 nsert 3/4 3-58 3/4 3-60
lh 4l 4
'I
INSTRUMENTATION OST-ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The post-accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABL'E.
BPPLICABI LITT:
BOOEE I, 2, d 2:
~CT ION:
a ~
With one or more accident monitoring instrumentation channels inoperable, take the action shown in Table 3.3-10.
b.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.3.3.6 Each post-accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.
PALO VERDE - UNIT 1 3/4 3-57
TABLE 3.3-10 INSTRUMENT POST-ACC IOENT HONITOR ING INSTRUMENTATION RE(VIREO NUMBER OF CHANNELS HINIHUH CHANNELS OPERABLE ACTION 1.
Containment Pressure 2.
Reactor Coolant Outlet.Temperature T (Wide Range) 3.
Reactor Coolant Inlet Temperature - T, (Wide Range) 4.
Reactor Coolant System Pressure Mide Range 5.
Pressurizer Water Level 6.
Steam Generator Pressure 7
Steam Generator Mater,l ovol Mido Ranne 8.
Refueling Water Storage Tank Mater Level 9.
Auxiliary Feedwater Flow Rate i0.
Reactor Cooling System,Subcooling Hafgin Monitor 11.
Pr essui izel Safety Valve Posit Ion In¹IcatoI 12.
Containment Mater Level (Narrow Range) 13.
Containment Mater Leve1 (Wide Range) 14.
Core Exit Thermocougles 15.
Reactor Vessel Water Level i6.
Neutron Flux Monitor (Power %ange) 2 2
2 2
2 2jsteam
$ 4 I I4 I d lUr generator 2
2 2
ijvalve 2
2-4/core quadrant 2*
2 1
1/loop 1/loop 1
1 1/steam gernIera I.Or aenerator 1
1 1
i/valve 1-2/core quadrant 1*
1 29,30 29,30 29.30 29,30 29,30 29830 90 1n 44 )VV 29,30 29,30 29,30 29,30 29,30 2-9-,30-29,3Q 31,32 29,30
- A channel is eight sensors in a probe.
A channel is OPERABLE if four or more sensors, two or more in the upper four and two or more in the lower four, are OPERABLE.
C)
TABLE 3.3-10 CTION STATEM NTS ACTION 29 - With the number of OPERABLE Channels one less, than the Required Number of Channels in Table 3.3-10, either restore the Inoperable Channel(s) to, OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 30 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE in Table 3.3-10, either restore the Inoperable Channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 31 - With the number of OPERABLE Channels one less than the Required Number of Channels, either restore the system to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
ACTION, 32 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE in Table 3.3-10, either restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible without shutting down or:
l.
Initiate an alternate method of monitoring the reactor vessel inventory; 2.
Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and 3.
Restore the system to OPERABLE status at the next scheduled refueling.
PALO VERDE - UNIT 1 3/4 3-59 AMENDMENT NO.
27
TABLE 4.3-7 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS INSTRUHENT CHANNEL CHECK CHANNEL CALIBRATION 1.
Containment Pressure Dnsw+ns Pnnl vra4 hll+1n+ Tamnassk'iivn T
IU4rlcs Dermal c
~
il'GQI 4MI 'vvv I Qlll Mlllt It 4 I rlllp4I %l I 4 I r I f Og
$ Il Iu%
~ LuIIyvI 3.
Reactor Coolant Inlet Temperature
-T, (Wide Range)
M 4.
Reactor Coolant System Pressure - Wide Range 5.
Pressurizer Water Level 6.
Steam Generator Pressure 7.
Steam Generator Water Level - Wide Range R
u.
Ketuelsng waTer >rorage ianna waxer Levei 9
Auxiliarv Feedwater Flow Rate 10.
Reactor Coolant System Subcoo]ing Margin Monitor 11.
Pressurizer Safety Valve Position Indicator R
12.
Contairiment Water Level ar ow Range 13.
Containment Water Level (Wide Range) 14.
Reactor Vessel Water-l;evel-16.-
Neutron -Flux Honitor (Power Range)
I
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Cy t7 4~~*4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 h
I'I20NA PUBLIC S RV C
COMPANY T AL.
DOCKET NO.
STN 50-529 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
2 MENDMENT TO FACI ITY OP RATING CENSE Amendment No.
68 License No.
NPF-51 1
~
The Nuclear Regulatory Commission (the Commission) has found that:
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 California Edison
- Company, Public Service Company of New Mexico, Los Angeles Department of Water and
- Power, and Southern California Public Power Authority dated August 5,
- 1993, 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 Part 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 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; 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-51 is hereby amended to read as follows:
0
3.
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.68 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.
This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Theodore R. quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Date of Issuance:
September 21, 1994
4i Cl I
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO 68 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.
Remove 3/4 3-58 3/4 3-60 Insert 3/4 3-58 3/4 3-60
0 Il
)
INSTRUMENT TABLE 3.3-10 POST-ACC IOENT HONITORING INSTRUHENTATION RE(VIREO NUHBER OF CHANNELS HINIHUH CHANNELS OPERABLE ACTION 1.
2.
3.
5.
6.
7.
Steam Generator Mater Level Mide Range 8.
Refueling Water Storage Tank Water Level 9.
Auxiliary Feedwater Flow Rate 10.
Reactor Cooling System Subcooling Hargin Honitor 11.
Pressurizer Safety Valve Position Indicator 12.
Containment Water Level (Narrow Range) 13.
Containment Water Level (Wide Range) 14.
reactor Vesse)
Water Level 16.
Neutron Flux Honitor (Power Range)
Containment Pressure Reactor Coolant Outlet Temperature - T (Wide Range)
Reactor Coolant Inlet Temperature T,~ (Wide Range)
Reactor Coolant system Pressure Wide Range Pressurizer Water Level Steam Generator Pressure 2
2 2
2 2
2/steam generator 2/steam generator 2
2 2
1/val ve 2
2 4/core quadrant 2*
2 1
1/loop 1/loop 1
1 1/steam generator 1/steam generator 1
1 1
1/valve 1
1 2/core quadrant 1*
1 29,30 29,30 29,30 29,30 29,30 29,30 29,30 29,30 29,30 29,30 29,30 29,30 29,30 29,30 31,32 29,30
- A channel is eight sensors in a probe.
A channel is OPERABLE if four or more sensors, two or more in the upper four and two or more in the lower four, are OPERABLE.
C)
il INSTRUMENTATION POST-ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The post-accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
a 0 With one ov more accident monitoring instrumentation channels inoperable, take the action
. hown in Table 3. 3-10.
b.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.3.3.6 Each post-accident monitoring instrumentation channe'1 shall be demonstrated OPERABLE by performance of the CHANNEL CflECK and CHANNEL CALIBRATION operations at the frequencies shown in lTable 4.3-7.
PALO VERDE - UNIT 2 3/4 3-57
ACTION 29-ACTION 30-ACTION 31-ACTION 32-TABLE 3.3-10 (Continued)
ACTION STATEMENTS With the number of OPERABLE Channels one less than the Required Number of Channels in Table 3.3-10, either restore the Inoperable Channel(s) to OPERABLE status within 7 days, or be in HOT SHUTDOWh within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE in Table 3.3-10, either restore the Inoperable Channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
With the number of OPERABLE Channels one less than the Required Number of Channels either restore the system to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the Commission Pursuant to Specification 6.9.2 within 30 days following the event out-lining the action taken, the cause of the inoperability and'he plans and schedule for restoring the system to OPERABLE status.
With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE in Table 3.3-10, either restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible without shutting down or:
l.
Initiate an alternative method of monitoring the reactor vessel inventory:
2.
Prepare and submit a Special Report to the Commission pur-suant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoper-ability and the plans and schedule for restoring the system to OPERABLE status; and 3.
Restore the system to OPERABLE status at the next scheduled refueling.
PALD VERDE " UNIT 2 3/4 3-59
U IC)
TABLE 4.3-7 POST-ACCIDENT HONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS
(
Kl C7m INSTRUHENT CHANNEL CHECK CHANNEL CALIBRATION 1.
Containment Pressure 2
Roactnr Cnnlant
'l Daaha4aaah PAA1ha4.
al ~
A'ddsc laVI VVVI dll'4 4.
Reactor Coo1 ant Outlot. Tomnoraturo - T.
(Wide Ranlle'l faa1 aa4 Taaa ah 4
~ ~ ~
T II.I42 II 4III'dl I'dlllPdl dl \\4l 'd I~o)d (IIIU'd ldll'JJ4/
System Pressure - wide Range M
R R
5.
Pressurizer Water Leve1 6.
Steam Generator Pressure 7.
Dv ~
12.
13.
14a 1r.
4 al ~
16
'team Generator Water Leve1 - Wide Range Rofuolina Wator Stnr~ao T~nk W~tor t ovol huvi 1 4 haaaa ceaada aa4 eah c1 haW Rh4 Reactor Coolant System Subcoo1ing Hargin Honitor Pressurizer Safety Va1ve Position Indicator Containment Water Level (Narrow Range)
Containment Water Leve1 (Wide Range)
Caro Fxit Thormnrnanloc I
DAhP 4 Aah Ilhe t hl l.lh4.AW I haahl IkddlalaVI 4'dealt I
Ildla'dl I 'VV' Neutron F1ux Honitor (Power Kange)
H H
R R
R C)
Ch CO
~
~~gR RE00
~4+
a Wp0 C
1 c
c
~'
o I
v/y
%~*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-530 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
3 AMENDMENT TO FACILITY OPERATING ICENSE Amendment No.
53 License No. NPF-74 The Nuclear Regulatory Commission (the Commission) has found that:
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 California Edison
- Company, Public Service Company of New Mexico, Los Angeles Department of Water and
- Power, and Southern California Public Power Authority dated August 5,
- 1993, 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 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; and I
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:
il Cl
~
3.
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
53, 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.
This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.
FOR THE NUCLEAR'EGULATORY COMMISSION nn/
Attachment:
Changes to the Technical Specifications Theodore R. quay, Director Project Directorate IV-2 Division of Reactor.Projects III/IV Office of Nuclear Reactor Regulation Date of Issuance:
September 21, 1994
II 0
. ~,
V
ATTACHMENT TO LICENSE AMENDMENT MENDMENT NO.
53 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.
Remove 3/4 3-58 3/4 3-60 Insert 3/4 3-58 3/4 3-60
W'
INSTRUMENTATIQN POST-ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3'. 3. 6 The post-accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.
APPLICABILITY:
MODES 1, 2,. and 3.
ACTION:
With one or more accident monitoring instrumentation channels inoperable, take the action shown in Table 3.3-10.
b.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.3.3.6 Each post-accident.monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.
PALO VERDE - UNIT 3 3/4 3-57
INSTRUMENT TABLE 3.3-10 POST-ACC IOENT MONITORING INSTRUMENTATION RE(VIREO NUMBER OF CHANNELS MINIHUH CHANNELS.
OPERABLE ACTION l.
2.
3.
4, 5.
6.
Containment Pressure Reactor Coolant Outlet Temperature T., (Wide Range)
Reactoi'oolant Inlet Temperature - T,d (Wide Range)
Reactor Coolant System Pressure - Wide Range Pressurizer Water Level Steam Generator Pressure 7.
Steam Generator Water Level - Wide Range 15.
Reactor Vessel -Rate(
Level 16 Neutron Flux Mot'ito (Power Range~
8.
Refueling Water Storage Tank Water Level 9.
Auxiliary Feedwater Flow Rate 10.
Reactor Cooling System Subcooling Margin Monitor
-ll.
Pressurizer Safety Valve Position Indicator 12.
Containrment Water l.evel (Nai.row Rangej 13.
Containment Water Lever (Wide Rangej 14.
Core Exif. ThermocoupRs 2
2 2
2 2
2/steam generator 2/steam generator 2
2 2
ljvalve 2
2 4jcore qUddldrlt 24 2
1 1/loop 1/1 oop 1
1/steam generator 1/steam generator 1
1 1
1/valve 1
1 2jcore quadl drlt 29,30 29,30 29,30 29130 29,30 29,30 29,30 29,30 29,30 29,30 29.30 29,30 29$ 30 29,30 31,-3-2 29,30 "A channel is eight sensors in a probe.
A channel is OPERABLE if four or more sensors, two or more ili the Upper foUi and two or moi e in fhe lower four, are OPERABLE.
ACTION 29-ACTION 30 "
ACTION 31-ACTION 32-TABLE 3.3-10 (Continued)
ACTION STATEMENTS With the number of OPERABLE Channels one less than the Required Number of Channels in Table 3.3-10, either restore the Inoperable Channel(s) to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE in Table 3.3-10, either restore the Inoperable Channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or b'e in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
With the number of OPERABLE Channels one less than the Required Number of Channels either restore the system to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the Commission Pursuant to Specification
- 6. 9. 2 within 30 days following the event out-lining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE in Table 3.3-10, either restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible without shutting down or:
l.
Initiate an alternative method of monitoring the reactor vessel inventory:
2.
Prepare and submit a Special Report to the Commission pur-suant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoper-ability and the plans and schedule for restoring the system to OPERABLE status; and 3.
Restore the system to OPERABLE status at the next scheduled refueling.
PALO VERDE - UNIT 3 3/4 3-59
TABLE 4.3-7 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS INSTRUMENT CHANNEL CHECK CHANNEL CALIBRATION 1.
Containment Pressure 2.
Reactor Coolant Outlet Temperature - T (Wide Range)
Ill'4 Reacto<
Cool ant n 4 4 p4 4
cold (Wide Range) 4.
Reactor Coolant System Pressure - Wide Range
~l 2
~ ~
J.
~
1 a.
rressur~zer wa~er Levei H
6.
Steam Generator Pressure 7.
Steam Generator Water Level - Wide Range 8.
Refueling Water Storage Tank Water Level 9;
Auxiliary Feedwater Flow Rate 10, Reactor Coolant Svstem Suhcoolinn Harnin Hnnitnr R
.11.
Pressurizer Safety Valve Position Indicator 19 l'nntsinmont Maine I aual IMie wnu O~nnnl vve ~ v\\a
~ ~ ~ <saws ~ V
~I4V%
~
I
% V\\
~
QI1%AI
~ Vff INII)4/
13.
Containment Water Level (Wide Range) 14.
-Core Exit Thermocouples 15.
Reactor Vessel Water Level 16.
Neutron Flux Monitor (Power Range)
R