ML17312B014
| ML17312B014 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/23/1996 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17312B015 | List: |
| References | |
| NUDOCS 9610300251 | |
| Download: ML17312B014 (36) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHlkGTOk, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY T AL.
CK T NO.
TN 0-A 0 VERD NUCL AR GENERATING STAT ON UNIT NO.
1 AHENDHENT TO FACILITY OPERATING LICENSE Amendment No. 109 License 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 Hexico, Los Angeles Department of Water and
- Power, and Southern California Public Power Authority dated June 17,
- 1996, 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; 2.
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 Sl of the Commission's regulations and all applicable requirements have been satisfied.
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:
9610300251 96i023 PDR ADOCK 05000528 P
3.
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 109, 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 its date of issuance to be implemented within 45 days of the date of issuance.
I FOR THE NUCLEAR REGULATORY COMMISSION J
es M. Cliff d, Senior 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:
October 23, 1996
0
ATTACHMENT TO C
109 TO FACILITY OP RATING IC NSE 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, marginal lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Q,')~RT 1-3 3/4 2-10 B 3/4 2-4 1-3 3/4 2-10 B 3/4 2-4
DEFINITIONS CORE OPERAT NG IMITS R PORT 1.9a The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits for the current operating reload cycle.
These cycle-specific core operating l'imits shall be determined for each reload cycle in accordance with Technical Specification 6.9. 1.
Plant operation within these operating limits is addressed in individual specifications.
UVA
-31 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/
gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in ICRP-30, Supplement to Part I, page 192-212, Table titled, "Coasaitted Dose Equalivent in Target Organs or Tissues per Intake of Unit.Activity."
E AVERAGE DISINTEGRATION ENERGY
- 1. 11 E shall 'be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for
- isotopes, other than iodines, with half-lives greater than 15 minutes.,
making up at least 95X of the total noniodine activity in the coolant.
ENGINEERED SAFETY FEATURES
RESPONSE
TIME
- 1. 12 The ENGINEERED SAFETY FEATURES
RESPONSE
TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays where applicable.
FRE UENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1. 1.
GASEOUS RADWASTE SYSTEM
- 1. 14 A GASEOUS RADWASTE SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
1.15 IDENTIFIED LEAKAGE shall be:
a.
Leakage into closed
- systems, other than reactor coolant pump controlled bleed-off flow, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or c.
Reactor Coolant System leakage through a steam generator to the
,secondary system.
PALO VERDE UNIT 1
1-3 Amendment No. 69, 109
E F INITI ON S 1.16 K., is the k effective calculated by qonpidering the actual CEA,con-,
figuration and assuming that the fully or partially 'inserted full-length'E'A of the highest. worth is fully withdrawn.,
H R
1.17 HEHBER(S)
OF THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant.
This t:ategory does not include employees of the licensee, its contractors, or vendors. 'lso excluded from this c'at4go'ry
're persons who enter the site to service equipment or to make delivepie's.,'his category does inc'Iude persons who use portions of the site for. recrea-tional, occupational, or other purposes not assoc';ia'ted with the plant.
FF T
hLIKGJIHL HILIOEH1 1.18 The OFFSITE DOSE, CALCULATION HANUAL (ODCH) shall contain the methodology and parameters used in tlute calculation of offsite doses resulting from radioactive gaseous and 'liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints,'.ahd in 'the conduct qf )he, Environmental Radiological Honitoring Progr'am,'.
'The ODCH shall also contain
,'1) the Radioactive Effluent Controls and Radiol,ogica'1 Environmental,Honitoring, Programs required by Section 6.8.4, and,'(2) desCription.
of the info~~altiqn, that should be included in the Annual Radiological Environmental Gpedatin<
and Annual Radioactive Effluent Release Repqrty rjequired by Specificatio>'~s,'6.$.1,'.7 and 6.9.1.8.
L.'lllUII 1.19 A system, subsystem, train, component, or device shall'e OPERABLE or have OPERABILITY when it is capable of per'forming its specified function(s),
and when all necessary attendlant instrumentation, controls, electrical
- power, cooling or seal water; lubrication. or other auxiliary -equ'ipment that are, required for the system, subsystem, tra'in,'bmp'onent, or device to perform its function(s) are also capable of performing their related support fu~ctlio~(s);,
~~~aMA U~ll=-EEl
,1.20 An 'OPERATIONAL NODE (i.e.
NODE) shall correspond to any one ipcltusfve, combination of core reactivity conditiqn,ipolwer, lqvel, and cold leg reactor coolant temperature specified in Table i1.).,
PALO VERDE -. UNIT 1 1-4 AHENDHENT NO.m9.a.~
80
POWER DISTRIBUTION LIMITS':.";
3/4.2.7 AXIAL SHAPE INDEX LIMITING CONDITION FOR OPERATION 3.2.7 The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the limits specified in the CORE OPERATING 'LIMITS REPORT:
APPLICABILITY:
MODE 1 above 20K of RATED THERMAL POWER".
ACTION:
With the core average AXIAL SHAPE INDEX outside the limits specified in the CORE OPERATING LIMITS REPORT, restore the core average ASI to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 20K of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.2.7 The core average AXIAL SHAPE INDEX shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> using the COLSS or any OPERABLE Core Protection Calculator channel.
See Special Test Exception 3.10.2.
PALO VERDE - UNIT 1 3/4 2-9 AMENDMENT NO. 69
POW R
ISTR BUTION~IM:ITS 3 4.2.
PRESSURIZER PRESSURE 3.2.8 The pressurizer pressure sha'll be maintained'etween 2130 psia and 2295 psia.
EE>>
E, d
~CT ON:
With the pressuri'zer pressure outside its aboVe limlit<, 're<tore the pretsUre'o within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in't', least HOT STANIDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
4.2.8 The pressurizer press,ure shall be de'termined to be within its lirhit't least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
PALO VERDE UNIT 1 3/4 2-10 Amendment No. 5M9, 109
POW R DISTRIBUTION LIMITS BASES 3 4.2.5 RCS FLOW RATE This specification is pr'ovided to ensure that the actual RCS total flow rate is maintained at or above the minimum value used in the safety analyses.
The minimum value used in the safety analyses is 95K of the design flow rate (164.0 x 10 ibm/hr) or 155.8 x 10 ibm/hr.
The actual RCS flow rate is determined by direct measurement and an uncertainty associated with that measurement is considered when comparing actual RCS flow rate to the minimum required value of 155.8 x 10 ibm/hr.
4.
.6 R ACTOR COOLANT COLD LEG TEMPERATURE This speci,fication is provided to ensure that the actual value of reactor coolant cold leg temperature is maintained within the range of values used in the safety analyses.
3 4.2.7 AXIAL SHAPE INDEX This specification is provided to ensure that the actual value of the core average AXIAL SHAPE INDEX is maintained within the range of values used in the safety analyses.
3 4.2.8 PRESSURIZER PRESSURE This specification is provided to ensure that the actual pressurizer pressure is maintained within the range of values safety analyses.
The values for the pressurizer pressure LCO values and include consideration of instrument uncertainties.
value of used in the are indicated PALO VERDE UNIT 1
B 3/4 2-4
'Amendment No. 84, 109
41
~I
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0 Cy nO cA p
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+w*w+
UNITED STATES NUCLEAR'REGULATORY COMMISSION WASHtNGTON, D.C. 2055&4001~
ARI ONA PUBLIC S RV C
OMPANY T A.
DOCKET NO.
STN 50-5 9
PA 0 V R
NUCLEAR GENERAT NG STATION UNIT NO.
2 AM N ENT TO FACILITY OP RAT NG CENSE Amendment No. 101 License.No.
NPF-51 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 June 17,
- 1996, 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:
4l
3.
(2)
Technic l ecifications-'and nviro mental Protection" Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 101, 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, except where otherwise stated in specific license conditions.
This license amendment is effective as of its date of issuance to be implemented within 45 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION J
es M. Cliff d, Senior 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:
October 23, 1996
ATTACHMENT TO IC NSE AH NDMENT AMENDHENT NO.
10i TO FACIL TY OPERATING LICENSE NO. NPF-51 DOCKET NO.
STN 50-5 9
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.
The corresponding overleaf pages are also provided to maintain document completeness.
Q$~RT 1 3/4 2-10 B 3/4 2-4 1-3 3/4 2-10 B 3/4 2-4
41
'C 0
DEFINITIONS CORE OPERATING LIMITS REPORT 1.9a The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits for the current operating reload cycle.
These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Technical Specification 6.9. 1.
Plant operation within these operating limits is addressed in individual specifications.
DOSE E UIVA NT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/
gram) which al'one would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-.135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in ICRP-30, Supplement to Part 1,
page 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."
E - AVERAGE DISINTEGRATION ENERGY
- 1. 11 E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for
- isotopes, other than, iodines, with half-lives greater than 15 minutes, making up at least 95X of the total noniodine activity in the coolant.
ENGINEERED SAFETY F ATURES
RESPONSE
TIME
- 1. 12 The ENGINEERED SAFETY FEATURES
RESPONSE
TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays where applicable.
FRE UENCY NOTATION
- 1. 13 The FRE(UENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table l.l.
GASEOUS RADWASTE SYSTEM
- 1. 14 A GASEOUS RADWASTE SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
IDENTIFIED LEAKAGE 1.15 IDENTIFIED LEAKAGE shall be:
a.
Leakage into closed
- systems, other than reactor coolant pump controlled bleed-off flow, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or c.
Reactor Coolant System leakage through a steam generator to the secondary system.
PALO VERDE UNIT 2 1-3 Amendment No. 5S, iOi
EF INITIONS
~i 1.16 K., fs the k effective calculated by consfderfr~g the actual CEA aon~
ffguratkon and assuming that the fully or partially inserted full-length CEA of the highest inserted worth is fully withdrawn.
1.17 MEMBER(S) OF Tl'IE IPUBLIC shall include all pe'rsOns who are not occupa-tionally associated with the plant.
Thisl category does not fnclude employees of the licensee its contrictors, or vendors.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This category does 'include persons idaho u. e por'tfons of the site for recreationa'I, occupational, or other purposes not associated with the, plant.
JJII!!IUllLSD!S!M!!!51 1.18 The OFFSITE DOSE CALCUIATION MANUALl(OQCM).Shall,'contain the methodOlagy and parameters used fin the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monftorfngi Alarm/Trip Setpofots, and, in the conduct of 'the Environmental Radiological Monitoring Program.
The ODCM shall also contain
(]) the Radioactive Effluent Controls and Radiologlical Environmental, Monitoring Programs required by Section 6.8.~I, and (2) descriptions of'the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.7 and 6.9.1.8.
OP RABL - OP RAB]~TY
- 1. 19 A system, subsystem train, component, or device shall be OPERABI.E or have OPERABILITY when it ~is capable of pe)Worming its specified function(s)>
and when all necessary attendant
',Instrumentation, contr'ols, electrical power',',
cooling or seal water, lubrication or other auxiliary equipment that are required For the system, subsystem, train component, or device to perform its, function(s) are also capable of performfnt) their related support functlfonl(s).
i
! ~!!!
1.20 An OPERATIONAL MODE (f.e.
NODE) shall correspond to any one inclusive combination of core reactivity condition,,power, level, and cold leg reactor coolant temperature specified i,n Table 1.1.,
PALO VERDE - UNIT 2
'MENDMENT NO. iH-, Wl-67
p
- 4 POWER DISTRIBUTION LIMITS 3/4.2.7 AXIAL SHAPE INDEX LIMITING CONDITION FOR OPERAT'ION-3.2.7 The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the limits specified in the CORE OPERATING LIMITS REPORT.
APPLICABILITY:
HODE 1 above 20K of RATED THERMAL POWER".
ACTION:
With the core average AXIAL SHAPE INDEX outside the limits specified in the CORE OPERATING LIMITS REPORT,.restore the core average ASI to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 20K of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE RE UIREHENTS 4.2.7 The core average AXIAL SHAPE INDEX shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> using the COLSS or any OPERABLE Core Protection Calculator channel.
See Special Test Exception 3. 10.2.
PALO VERDE " 'UNIT 2 3/4 2-9
.AMENOMENT NO. N, 55
POWER DISTRIBUTION I IMIT!i
.8 PRESSURIZER PRESSURE LIMITING CONDITION liOR OPERATION 3.2.8 The pressurizer pressure shall be maintained between 2130, psia and 2295 psia.
'l d
~T~ON:
With the pressurizer pre.'sure outside its abo've'limits,'estore the pressure to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in a't lea'st
'HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
4.2.8 The pressurizer pressure shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- See Special Test Exception 3.,10.5 PALO VERDE - UNIl' 3/4 2-1O Amendment No.3~4, i 01l
POWER DISTRI UTION LIMITS'ASES 3 4.2.5 RCS F
OW RATE This specification is provided to ensure that the actual RCS total flow rate is maintained at or above the minimum value used in the safety analyses.
The minimum value used in the safety analyses is 95X of the design flow rate (164.0 x 10 ibm/hr) or 155.8 x 10 ibm/hr.
The actual RCS flow rate is determined by direct measurement and an uncertainty associated with that measurement is considered when comparing actual RCS flow. rate to the minimum required value of 155.8 x 10 ibm/hr.
3 4.2.6 R ACT R COOLANT COLD LEG T MP RATUR This specification is provided to ensure that the actual value of reactor coolant cold leg temperature is maintained within the range of values used in the safety analyses.
3 4.2.7 AXIAL SHAPE INDEX This specification is provided to ensure that the actual, value of the core average AXIAL SHAPE INDEX is maintained within the range of values used in the safety analyses.
3 4.2.8 PRES URIZER PRESSURE This specification is provided to ensure that the actual value of pressurizer pressure is maintained within the range of values used in the safety analyses.
The values for the pressurizer pressure LCO are indicated values and include consideration of instrument uncertainties.
PALO VERDE UNIT 2 B 3/4 2-4 Amendment No. 49,101
%I n nfcu cW
~o Cy OO Q r
~O
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 R
NAPUB ICSRVC PN TA.
CK T NO 0-PALO V RDE NUCLEAR GENERATING STATION UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 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 Hexico, Los Angeles Department of Water and
- Power, and Southern California Public Power Authority dated June 17,
- 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the. Act) and the Comnission'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 ConmIission; C.
D.
E.
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; 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 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:
3.
(2)
Te hnic 1
ecifications and nvironmental Protecti n 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 facil'ity in accordance.with the Technical Specifications and the Environmental Protection
- Plan, except where otherwise stated in specific l.icense conditions.
This license amendment is effective as of its date of issuance to be implemented within 45 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COHHISSION N.
J es W. Cliffo
, Senior Project Hanager Project Directorate IV-'
Division of Reactor Projects III/IV'ffice of Nuclear Reactor.Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 23, 1996
4>
ATTACHMENT TO LIC NS NT AMENDMENT NO.
81 TO FACI ITY OP RATING ICENS NO. NPF-74 CK T NO.
S 50-0 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.
The corresponding overleaf pages are also provided to maintain document completeness.
R MOVE 1-3
.3/4 2-10 B 3/4 2-4'S~RT 1-3 3/4 2-10 B 3/4 2-4
0 4l I
'EFINITIONS OR P RATING LIMITS REPORT 1.9a The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits for the current operating reload cycle.
These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Technical Specification 6.9. 1.
Plant operation within these operating limits is addressed in individual specifications.
DOS UIVALENT I-131 1.10 DOSE E(UIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) which alone would produce the same thyroid dose, as the quantity and isotopi'c mixture of I-131, I-132, I-133, I-134 and I-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in ICRP-30, Supplement to Part 1,
page 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."
- AVERAGE DISINTEGRATION ENERGY
- l. 11 E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for
- isotopes, other than iodines, with half-lives greater than 15 minutes, making up at least 95X of the total noniodine activity in the coolant.
NG NEERED SAFETY FEATURES
RESPONSE
TIME
- 1. 12 The ENGINEERED SAFETY FEATURES
RESPONSE
TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays where applicable.
R U NCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table l.l.
GAS OUS RADWASTE SYSTEM
- 1. 14 A GASEOUS RADWASTE SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total.radioactivity prior to release to the environment.
E TI D
EAKAGE 1.15 IDENTIFIED LEAKAGE shall be:
a.
Leakage into closed
- systems, other than reactor coolant pump controlled bleed-off flow, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or c.
Reactor Coolant System leakage through a steam generator to the secondary system.
PALO VERDE UNIT 3 1-3 Amendment No. 48,81
EF INITIONS
- 1. 16 K., is the k effective ca1lcu'lated by consider'ing the actual CEA con,-
figuration and assuming that the fully or partially inserted full-length CEA; of the highest.inserted worth is fully withdrawn.
~
H MIJLLK
- 1. 17 MEMBER(S)
OF THE PUBLIC shall include all persons, who are not occupa-tionally associated with the plant.
This, category does not include employees of the licensee, its contractors, or vendors.
Also excluded from this, category are persons who enter the site to, service equipment or to make deliveries.
This category does include persons who use portions of the site for recreational, occupaitional, or other purposes not associated with the plant.
MI N.1DK51
- 1. 18 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodblogy and parameters used in the calculation of offsite,doses, resu'lting from radioactive gaseous and liquid effluents,:in:the calculation of gaseous and liquid effluent monitoriing Alarm/Trip Setpoints,,
and, in the conduct of'the Environmental Raidiological Monitoring Program.
The ODCM sha'll also contain (1) the Radioactive Eff1luent Controls and Radiologcal,Environmental Monitoring Programs required by Section 6.,8.¹,,and (2) descriptions of'th'e information that should be included in.the Annual Radiological Environmental Operating and Annual Radioactive Effluent Re'lease Reports required by Specifications 6.9.1.7 and 6.9. 1.8.
"lEIU-
- 1. 19 A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s)l, and.when all necessary attendant instrumentation, controls, electrical'ower,
'ooling or seal wa'ter, ',lubricationi or other <<uxiliary equipment that are
'equired for the s,y'stem, subsystem,
- train, component, or device to perform its function(s) are al,so caj)able of performing. their related support functlionl(s).
'TN JSIK 1.20 An OPERAT][ONAL MODE (i.,e.
NODE) shall Correspond to any one inclusive combination of core reactivity condition, power, level,,and cold leg reactor coolant temperature specified in Tab'le 1.2.
PALO VERDE - UNIT 3 1-4'MENDMENT NO. &M, l52
POWER DISTRIBUTION LIMITS 3/4.2.7 AXIAL SHAPE INDEX'IMITING CONDITION FOR OPERATION 3.2.7 The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the limits specified in the CORE OPERATING LIMITS REPORT.
APPLICABILITY:
MODE 1 above 20K of RATED THERMAL POWER".
ACTION:
With the core average AXIAL SHAPE INDEX outside the limits specified in the CORE OPERATING LIMITS REPORT, restore the core average ASI to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 20K of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.2.7 The core average AXIAL SHAPE INDEX shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> using the COLSS or any OPERABLE Core Protection Calculator channel.
See Special Test Exception 3. 10.2.
PALO VERDE - UNIT 3 3/4 2-9 ANENDNENT ND.N,42
LIMITING CONDITION IFOR OPERATION 3.2.8 The pressurizer pressure shaill be maintained between 2130 psia and 2295 psia.
d>>l I IT: I II I: dl, ACTION:
With the pressurizer pressure outside its above'limits, restore the pressure to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in ait lea~st HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
4.2.8 The pressurizer pressure shaill be determined to be within its liimit ait least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
PALO VERDE UNIT 3 3/4 2-10 Amendment No., &MID,81
BASES 3 4.2.5 RCS FLOW RATE This specification is provided to ensure that the'actual RCS total flow rate is maintained at or above the minimum value used in the safety analyses.
The minimum value used in the safety analysis is 95X of'he design flow rate (164.0 x 10 ibm/hr) or 155.8 x 10 ibm/hr.
The actual RCS flow rate is determined by direct measurement and an uncertainty associated with that measurement is considered when comparing actual RCS flow rate to the minimum required value of 155.8 x 10 ibm/hr.
4.2.6 R ACTOR COOLANT COLD LEG TEMPERATURE This specification is provided to ensure that the actual value of reactor coolant cold leg temperature is maintained within the range of values used in the safety analyses.
3 4.2.7 AXIAL SHAPE INDEX This specification is provided to ensure that the actual value of the core average AXIAL SHAPE INDEX is maintained within the range of values used in the safety analyses.
3 4.2.8 PRESSURIZER PRESSUR This specification is provided to ensure that the actual value of pressurizer pressure is maintained within the range of values used in the safety analyses.
The values for the pressurizer pressure LCO are indicated values and include consideration of instrument uncertainties.
PALO VERDE UNIT 3 B 3/4 2-4 Amendment No. 48, 81
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