ML17311A925
| ML17311A925 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/25/1995 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17311A926 | List: |
| References | |
| NUDOCS 9506020358 | |
| Download: ML17311A925 (30) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 PUB IC S RVIC COMPANY ET DOCK T 0.
STN '50-528 0
D UC R
G NERA G
S AT ON U
0 D
T 0 FACI IT OP RA ING CENS Amendment No.
91 License No. NPF-41 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 November 2,
- 1994, complies with the standard's 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 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:
9506020358 950525 PDR ADOCK 05000528 P
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(2) T i
ec'ions and Environment Protection P
The Technical Specifications contained: in 'Appendix A', as revised through Amendment No.
9i, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.
APS shal,l 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 to be implemented 45 days from the date of issuance.
.FOR THE NUCLEAR REGULATORY COMMISSION harles R. Thomas, Project Hanager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
i ~
'l 0
T HME TO C
S AH 91 0
FAC TY 0 ERATING 'LIC NS NO.
NPF-'41 OC NO.S
-58; 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.
The corresponding overleaf pages are also provided to maintain document, completeness.
~R~OV 5-'4 B 3/4 3-4 INSERT 5-4 B '3/4 3-4
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Oltsite Dose Calculation hLanuat Palo Verde Nuclear Generating Station O
W I
M Fuel Building Fuel Building Exhaust Main Steam Support Containmenl Structure
~
Jar Condensor Vacuum and Plant Vent Exhaust Operations Support Building lli%imt Ilt CONI n.
124 0 CONi sr r.
Spray Pond Auxiliary Building Radwaste Building Control Diesel Gen Building Building i
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Elevation of Exhaust Point Above'Grade Plant Vent and Condensor Vacuum 145'uel Building 109'-9" Palo Verde Nuclear Generating Station GASEOUS EFFLUENT RELEASE POINTS Fig, 5.1-3
II
INSTRUMENTATION BASES
Response
time may be demonstrated by any series of sequential, overlapping, or total channel test measurements provided that such tests demonstrate the total channel response time as defined.
Sensor response time verification may be demonstrated by either (1) in place, onsite, or offsite test measurements or (2) utilizing replacement sensors with certified response times.
3/4. 3. 3 MONITORING INSTRUMENTATION 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.
3/4.3.3.2 INCORE DETECTORS The OPERABILITY of the incore detectors with the specified minimum comple-ment of, equipment ensures that the measurements obtained
.from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
3/4. 3. 3. 3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of,a seismic event and evaluate the response of those features important to safety.
This capabil-ity 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.
The instrumentation is consistent with the recommendations of Regulatory Guide 1. 12, "Instrumentation for Earth-
~
quakes," April 1974 as identified in the PVNGS FSAR.
The seismic instrumenta-tion for the site is located in Table 3.3-7.
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that suffi-cient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability.is required: to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs,"
February 1972.
Wind speeds less than 0.6 MPH cannot be measured by the meteorological instrumentation.
3/4. 3. 3. 5 REMOTE SHUTDOWN SYSTEM The OPERABILITY of the. remote shutdown system ensures that sufficient capability is available to permit safe shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.
This capability is requir ed in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR Part 50.
PALO VERDE - UNIT 1 8 3/4 3-3 AMENDMENT KO. 27
NS U
O BASES U
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d)
The parameters selected to be monitored ensure that'1) the condition'f'he reactor is known, (2) condition.
in the'CS are
- known, (3) the steam generators are available For residual heat i'eaiovhl,'4) a source of water is available for makeup to the
- RCS, and (5) the charging system is available
'to'akeup water to the IRCS.
The OPERABILITY of'he remote hutdown sQst6m 'insures that a fire s'vil'1 not preclude achieving saiFe shutdown.
The remote shutdown system instrumentation, control and power circuits and disconnect switches necessary to eliminate effects of the fire and allow operation of instrumentation,',
control and power circuits required to achidve and maintain a safe shutdown condition are independent of areas where a fire ~'.ould damage systems noi'~a'lip'i used to shutdown the reactor.
This capability'0 c'onsistent with Gener'sl
'esign Criterion 3 and Appendix R to 19 CFR 50.
The alternate disconnect methods or po>ver or control circuits ensui"e 'that sufficient capability is available to permit shutdoWn and maintenance of cold, shutdown of the faci'lity by rellying on additional o'perator actions at local control stations rather than at the RSP.
3~4...
T-M ENT 1 NIT Rill IN'YAjfgl The OPERABILITY of the post-accident, mi)nitoring instrumentation ensures that sufficient information is available on selected
)plaint parameters to monitor and assess these variables fol'lowing an accident.
This capability is consistent with the recommendations of Regulat'ory GUide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," Deceimber 'l975 and NUREG 0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Tenn Recommendations.~
The containment high range area, monitors (RU-148
- 8. RU-149) and the main steamline radiation monitors (RU-139i A5B and RU-140'KB) are in Table 3.,3-6.
The high range effluent monitors andi samplers (RU-144 and RU-146) are in the ODCM.
The containment hydrogen monitors arch in Specification 3/4.6.5. 1.,
The Post Accident Sampling System (RCS coolant) is in Table 3.3-6,.
The Subcooled
.Margin Moinitor (SMM), the Heat Junction Thermocouple (HJTC),
and the Core Exit Thermocouples (CET) 'corhpr'use the Inadequate Core
'Cooling (ICC) instrumentation required by Item II.F'.2 NUREG-0737, the Post TMI-2 Action Plan.
The function of the-ICC instrument, ation is to enhance the ability of the plant operator to diagnose the approach to existance of, and recovery from ICC.
Additionally, they aid in tracking reactor coo'llant inventory.
These instruments aire included in the Technical Specifications at the request of NRC Generic Letter 83-37.
These are not required by the accident analysis, nor to bringI the plant to Cold Shutdown.
PALO VERDE UNIT 1 B 3/4 3-4 Amendment No. 91
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 R
ON UBL C S RVIC CO PANY T
DOCKET NO.
STN 50-529 PA 0 VERD NUCLEAR GEN RATING STATION UNIT NO.
2 ENDHENT TO ACILITY OPERATING LICENSE Amendment No.
79 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 November 2,
- 1994, 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 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:
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(2)
S e fic on a
v ronme t rotection Pl The Technical Specifications contained i'n Appendix A, as revised through Amendment No.
79, 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 to be implemented 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION harles R. Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of 'Nucl'ear Reactor Regulation;
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 25, 1995
0 P
TACHMEN 0
CENS AM NDM NT 79 TO FA TY OP ING CENS NO.
NPF-5 OCK T 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.
The corresponding overleaf pages are'lso provided to maintain document completeness.
~RM~O 5-4 B 3/4 3-4 SERT 5-4',
B 3/4 3-4
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Ottsite Dose Carcuralen Manual Palo Verde Nuclear Generating Station Fuel Building Fuel Building Exhaust Containment Main Stear'n Condensor Vacuum and Support Plant Vent Exhaust Structure AS Operations Support Building r
x
= xCHHOI5
~ x t(x<t tx CON I T
- err, CONI Spray Pond Auxiliary Building Radwaste Building Control Building Diesel Gen Building EXHAUST POINTS KEY PLAN Point t45'09'-9" Elevation of Exhaust Above Grade Plant Vent and Condensor Vacuum Fuel Building Palo Verde Nuclear Generating Station GASEOUS EFFLUENT RELEASE POINTS Fig. 5.1-3
e 1
INSTRUMENTATION BASEST 3/4.3. 3 MONITORING INSTRUMENTATION 3/4.3. 3. 1 RADIATION HONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that:
(1) the radiation levels are continually measured in the areas served by the individual channe)s and (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
3/4.3.3.2
'INCORE DETECTORS The OPERABILITY of the incore detectors with the specified minimum comple-ment of equipment ensures that the measurements obtained from use of this'ystem accurately represent
.the spatial neutron flux distribution of the reactor core.
3/4. 3.3. 3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.
This capabil-ity 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.
The instrumentation is consistent with the recommendations of Regulatory Guide 1.12, "Instrumentation for Earth-quakes,". April 1974 as identified in the PVNGS FSAR.
The seismic instrumenta-tion for the site is listed in. Table 3. 3-7.
3/4. 3.3. 4 METEOROLOGICAL INSTRUHENTATION
. The OPERABILITY of the meteorological instrumentation ensures that suffi-cient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health. and safety of the
~ublic and is consistent with the recommendations of Regulatory Guide 1.23
'Onsite Meteorological Programs,"
February 1972.
Mind speeds less than 0.6 HPH cannot be measured by the meteorological instrumentation.
3/4.3.3.5 REMOTE SHUTDOWN SYSTEM The OPERABILITY'f the remote shutdown system ensures that sufficient capability is available to permit safe 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 Criterion 19 of 10 CFR Part 50.
PALO VERDE - UNIT 2 B 3/4 3-3 AMENDMENT NO.
19
INSTRUH T
BASES
~EMOT I U N
XSJRI lC:
The parameters selected to be monitored ensure that; (1) the condition of the reactor is known, (2) conditions in the RCS are
- known, (3) the steam generators are available for residual heat removal (4) a source of wat'er'is'vailable for makeup to the
The OPERABILITY of the remote shutdown system insures that a fire will not preclude achiieving safe shutdown.
The remote shutdown system
-instrumentation, control and power circuits and discoinnect switches neces~;ary to eliminate effeicts, oF the fire and allow-operation iof instrumt.ntation, control and power circuits required.to achieve and maintain a safe shutdown condition are independent of areas where a fire could damage systems normally
'sed to shutdown the reactor.
This capability is consisteIit with Generali Design Criterion 3 and Appendix R tio 10 CFR 50.
The alternative dlisconnect methods or power or contrail circuits ensure'that
'ufficient capability is available to permit
. hutdown and maintenance of cold shutdown of the facility by relying on additional operator actions at local control stations rather than at the RSP.
The OPERABILITY of the post-accident.
monjitoriaIg instrumentation ensue'es that sufficient information is avai'lable on selected plant parameters to monitor and assess these varialbles Following an accident.
This capabil'it> ill consistent with the recommendations of'eguilatory Guide 1.97, "Instrumentation for Light-Mater-Cooled Nuclear Plants to Asisess Plant Conditions During'riid
'ollowing an Accident," December 1975 and NURFG 0578,'"TNI-2 Lessons Learned'ask Force Status Report and Slhort-Term Recoazllenlations."
The containment hIlgh rangie airea monitors (RU-1i48 5 RU-149) and the mrIin steamline radiation monitors (IRU-13!3 ASB and RU-140 AItB)'re in Table 3'.3 6.'he high range effluent monitors and samplers (Rjtl-144 and RU-146) are iin the ODCM.
The containment hydrogen monitors ar'e in Spdcification 3/4.6.4. 1.
The Post Accident Sampling System (RCS coolant) is iin 1'ab'le 3.3-6.
The Subcooled Margin Monitor (SHM), the Heat Junction Thermocouple (HJTC),
and the Core E)(it Thermocouples (CET) comprise t'e Inadequate Ciore Cooling (ICC) instrumentation required by Iterh II.F.2 NUREG-0737, the Piost THI-2 Act'ion Plan,.
The function of the ICC instrumentation is to enhance thb ability of the plant operator to diagnose the apjproach to existance of, and recovery from ICC,.
Additionally, they aid in tracking reactor roolant inventory.
These instruments arei included in thie Technica'll Specificatiions at the request of 'NRC Generic Letter 83-37.
These are not required by the'ccident analysis nor to bring the plant to Colid Shutdown PALO VERDE UNIT 2 B 3/4 3-4i Amendment Nio. 49, 79
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.'5';,UNITED.
STATES'UCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 RIZONA"'PUBLIC SERVICE COMPANY ET AL.
DOCK T NO STN 50-530 P
0 ERDE NUCLEAR GENERATING'TATIO U
T NO.
3 MENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. NPF-74 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'aso Electric
- Company, Southern California Edison
- Company, Public Service Company of New Mexico, Los Angeles Department of Water'nd
- Power, and Southern California Public Power Authority dated November 2,
- 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commiss'ion's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the, application, the pr'ovisions of the Act,:and the rules and'egulations of the Commissi'on; 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-74. is hereby amended. to read as follows:
0 II f
(2) e i
ons a d v r me t 1
P otection P
n The Technical Specifications contained in Appendix A, as revised through Amendment No.
62, 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 to be implemented 45, days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION harles R. Thomas, Project Manager
- Project Directorate IV-2.
Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of, Issuance:
May 25, 1995
0
,A tJ
~
~
62 TT C
AMNMN FAC TY OP RATING L C
NSE NO. 'NPF-7 OCK NO; ST 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.
The corresponding overleaf pages are, also provided to maintain document completeness.
, INSERT 5-4 8 3/4 3-3
'B 3/4 3-4 5-4' 3/4. 3-3 B 3/4 3-4
0 il I
d tO I
M Oftsile Dose Catcuialen Manual Fuel Building Exhaust Fuel Building Main Steam Support Containment Structure Condcnsor Vacuum and Plant Vent Exhaust Palo Verde Nuclear Generating Station Operations Support Building iIgiIL'-
r llf CONI CONT I-.IW S-Spray Pond Auxiliary Building Radwaste Building Control Building Diesel Gen Building ru CL c+
EXHAUST POINTS KEY PLAN Elevation of Exhaust Point Above Grade Plant Vent and Condensor Vacuum 145'uel Building 109'-9" Palo Verde Nuclear Generating Station GASEOUS EFFLUENT RELEASE POINTS Fig. 5.1-3
NSTR SASES M T OR STR TION (Continued) materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs,"
February 1972.
Wind speeds less than 0.6 MPH cannot be measured by the meteorological instrumentation.
3 4.3.3 0
SH 0
YSTE The OPERABILITY of the remote shutdown system ensures that sufficient capability is available to permit safe 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 Criterion 19 of 10 CFR Part 50.
The parameters selected to be monitored ensure that (1) the condition of the reactor is known, (2) conditions in the RCS are
- known, (3) the steam generators are available for residual heat removal, (4) a source of water is available for makeup to the
The OPERABILITY of,the remote shutdown system insures that a fire will not preclude achieving safe shutdown.
The remote shutdown system instrumentation, control and power circuits and disconnect switches necessary to. eliminate effects of the fire and allow operation of instrumentation, control and power circuits required to achieve and maintain a safe shutdown condition are independent of areas where a fire 'could damage systems normally used to shutdown the reactor.
This capability is consistent with General Design Criterion 3 and Appendix 'R to 10 CFR 50.
The alternate disconnect methods or power or control. circuits ensure that sufficient capability is available to permit shutdown and maintenance of cold shutdown of the facility by relying on additional operator actions at local control stations rather than at the RSP.
TORING INSTRUMENTATION The containment high range area monitors (RU-148
& RU-149) and-the main steamline radiation monitors (RU-139 A&B and RU-140 A&B) are in Table 3.3-6.
The high range effluent monitors and samplers (RU-144 and RU-146) are in the 3 4.3 3
0 I
'he OPERABILITY af"%he post-accident monitoring instrumentation ensures that sufficient conformation is available on selected plant parameters to monitor and assess these variables following an accident.
This capabili,ty is consistent with the recommendations of Regulatory Guide 1'.97, "Instrumentation for Light-Mater-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG 0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."
PALO VERDE UNIT 3 B 3/4 3-3 Amendment No. 48,62
T 0 BASES POST-CC D
T MO O'OIR~IG QSTRU~MNTATION,(Cbntlinked)
ODCH.
The containment hydrogen monitors arh in Specification 3/4.6.4.1 The Post Accident Sampling System (RCS coolant) id ih Table 3.3-6.
The Subcooled Marg;in Monitor (SMM), the Heat Junction Thermocouple
'(HJTC),
and the Core Exit Thermocouples (CET) coritprise the Inadequate Core Cooling (ICC) instrumentation required by Itemi II.F.2 NUREG-0737, the Pdst TMI-2 Action Plan.
The function of the ICC instrumentation is to enhance the ability of the plant operator to diagnose the 'apl)roach to existance of, and recovery from ICC.
Additiona11ly, they aid in tracking reactor coolant inventory.
These instruments are included jin ith0 Technical Specifications at the request of NRC Generic Letter 83-37.
These are not required by the accident analysis, nor to bring the plant, to Cold Shutdown.
In the event more than four sensors in a Reactor Vessel Level channel are inoperable, repairs may only,be possible during'he next refueling outage.
This is because the sensors are accessible. 6nly Aft'er the missile shield and reactor vessel head are removed.
It is not felasibl'e to repair a channel except during a refueling outage when the missile shield and reactor ve. sel head are removed to refuel the core.
If both ch0nn'els a'e 'inoperable, the channels shall be restored to OPERABLE statlls 'in'the nearest refueling outage.
If only one channel is inoperable, it is intended that tlhis channel be restored to OPERABLE status in a refueling outage as soon as reasonably possible.
3 4.3.3.
LOOS -PARi~D~ET~C~ON INSTRUMENTATION The OPERABILITY of the loose-pairt detection instrument, ation ensures that sufficient capability is available to detect loose imetal'lic parts in the primary system and avoid or mitigate damage to primary system component..
The allowable out-of.-service times an'd surveillanc'e requirements are consistent with the recommendations of Regulatory Guide 1. 133,'Loose-'Part Detection Program for the Primary System of Light-Water-Cooled Reactors,"
May 1981.
~4..
EXL B,
A t NIT'I'I'IN"R NISI'Tf The explosive gas in!trumentation is provided for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the GASEOUS RADWASTE SYSTEH.
The OPERABILITY ar>d use of thi,s instrumentation is consistent with the requirements of General'De'sign Cri,teria 6O, 63,,
and 64 of Appendix A to 10 CFR Part 50.
PALO VERDE UNIT 3
.B 3/4 3-4 Amendment No. 4~4,62