ML17311A392
| ML17311A392 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/03/1994 |
| From: | Brian Holian Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17311A393 | List: |
| References | |
| NUDOCS 9411140014 | |
| Download: ML17311A392 (30) | |
Text
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UNITED STATES NUCL'EAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 9oxi<4oox4 eoxzo3 V PDR ADOCK 05000528 P
PDR ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 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'f New Mexico, Los Angeles Department of Water and
- Power, and Southern California Public.Power Authority dated January 4,
- 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.
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 publ'ic, 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-41 is hereby amended to read as follows:
,I l'
3.
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 86, 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 Date of Issuance:
November 3,
1994 Brian E. Holian, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Cl
AMENDMENT 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 2-3, B 3/4 2-2 Insert 3/4 2-3 B 3/4 2-2'
Il
POWER DISTRIBUTION LIMITS 3/4.2.3 AZIMUTHAL POWER TILT - Tq LIMITING CONDITION FOR OPERATION 3.2.3 The AZIMUTHAL POWER TILT (T ) shall be less than or equal to the following limits:
a.
The AZIMUTHAL POWER TILT Allowance used in the Core Protection Calculators (CPCs),
and b.l.
The limit specified in the CORE OPERATING LIMITS REPORT with COLSS in service, or b.2.
T
< 0.03 with COLSS out of service.
APPLICABILITY:
MODE I above 20X of RATED THERMAL POWER*.
~CTI ON:
a ~
b.
With the measured AZIMUTHAL POWER TILT determined to exceed the AZIMUTHAL POWER TILT Allowance used in the CPCs, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either correct the power tilt or adjust the AZIMUTHAL POWER TILT Allowance used in the CPCs to greater than or equal to the measured value.
With the measured AZIMUTHAL POWER TILT determined to exceed the limit specified in the CORE OPERATING LIMITS REPORT with COLSS in service or 0.03 with COLSS out of service:
Due to misalignment of either a part-length or full-length CEA, within 30 minutes verify that the Core Operating Limit Supervisory System (COLSS)
(when COLSS is being used to monitor the core power distribution per Specifications 4.2.1 and 4.2.4) is detecting the CEA misalignment.
2.
3.
Verify that the AZIMUTHAL POWER TILT is 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 /> after exceeding the limit or reduce THERMAL POWER to less than 50X of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and verify that the Variable Overpower Trip Setpoint has been reduced as appropriate within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50X of RATED THERMAL POWER may proceed provided that the AZIMUTHAL POWER TILT is verified within its limit at least once per hour for 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> s or until verified acceptable at 95X or greater RATED THERMAL POWER.
- See Special Test Exception 3.10.2.
PALO VERDE UNIT I 3/4 2-3 AMENDMENT NO. 38, ~,
86
0 POMER DISTRIBUTION LIMIlS 5 NVEIL~ GF EEIEIIEEE EEVE
,4.2.3.1 The provisions of Spec'ification 4.04 ar4 n'ot'applicable.
4.2.3.2
- The AZIMUTHAL POWER TILT shall be determined to be within its "limits above 20K of RATED THIEiWL POWEii by:
aO Continuously Ntonito'ring-the tiltwith COLS'S whe'n the COLSS is in service.
b.
Calculating the tilt at 'least once'pe'r 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the COLSS is out of service.
c.
Verifying at least onc:e per 31 day~i, that 'the.
COLSS Azimuthal'ilt Alarm is actuated at an AZIMUTHALPOWER TILT less than or equal to the AZIMUTHAL POb/ER TILT 'Allowance used
-.in the CPCs.
d.
Using the incore detectors at least once per 31 EFPD to indepe6dehtliy
'onfirm the validity of the COLSS calculated
'AZIMUTHAL POWER TILT,.
PALO VERDE - UNIT 1 3/4 2-4 AMENDMENT NO 38
3/4. 2 POWER DISTRIBUTION LIMITS BASES 3/4.2.1 LINEAR HEAT RATE The limitation on linear heat rate ensures that,in the event of a
- LOCA, the peak temperature of the fuel cladding will not exceed 2200'F.
Either of the two core power distribution.monitoring systems, the Core Operating Limit Supexvisory System (COLSS) and the Local Power Density channels in the Core Protection Calculators (CPCs), provide adequate monitoring of the core power distribution and are capable of verifying that the linear heat rate does not exceed its limits.
The COLSS performs this function by continuously monitoring the core power distribution and calculating a core power operating limit corresponding to the allowable peak linear heat rate.
Reactor operation at or below this calculated power level assures that the limits specified in the CORE OPERATING LIMITS REPORT are not exceeded.
The COLSS calculated core power and the COLSS calculated core power operating limits based on linear heat rate are continuously monitored and displayed to the operator.
A COLSS alarm is annunciated in the event that the core power exceeds the core power operating limit.
This provides adequate margin to the linear heat rate operating limit for normal steady-state opera-tion.
Normal reactor power transients or equipment failures which do not require a reactor trip may result in this core power operating limit being exceeded.
In the event this occurs, COLSS alarms will be annunciated.
If the event which causes the COLSS limit to be exceeded results in conditions which approach the core safety limits, a reactor trip will be initiated by the Reactor Protective Instrumentation.
The COLSS calculation of the linear heat rate includes appropriate penalty factors which provide, with a 95/95 probability/
confidence level, that the maximum linear heat rate calculated by COLSS is conservative with respect to the actual maximum linear heat rate existing in the core.
These penalty factors are determined from the uncertainties associated with planar radial peaking measur,ement, engineering heat flux uncertainty, axial densification, software algorithm modelling, computer processing, rod bow, and core power measurement.
Parameters required to maintain the operating limit power level based on linear heat rate, margin to DNB, and total core power are also monitored by the CPCs.
Therefore, in the event that the 'COLSS is not being used, operation within the linear heat rate limit can be maintained by utilizing any operable CPC channel.
The above listed uncertainty and penalty factors plus those asso-ciated with the CPC startup test acceptance criteria are also included in the CPCs.
PALO VERDE - UNIT 1 B 3/4 2-.1 AMENDMENT NO. N, 69
POWER DISTRIBUTION LIM l
BASES 3 4.2.2 PLANAR RADIAL PEAKING FACTOILS Limiting the value. of the PLANAR RADIAL-PEAKING FACTORS (F') used in the COLSS and CPCs to value.; equal to or greater than the measured PLANAR RADIAL PEAKING FACTORS (F) provides assurance that the, limits calculated by CALSS and the CPCs remaiii~ valid.
Data from the incore idetectors are used for determining the measured PLANAR RADIAL PEAKI'NG'FACTORS'.
'A minimum core power at 20X of RATED THI=RMAL POWER i,s assumed in determining the PLANAR RADIAL PEAKING FACTORS.
I'he 20X,RA1'ED THERIACAL POWER Chrleshold i's due to the neutron flux detector system being inaccurate below '20X cOre power.
Core noise leiel't low power is too large to obtain usable detector reading..
The periodic surveillance requirements for determining the.measured'PL'ANAR RADIAL PEAKING
'ACTORS provides assurance that thie.PLANAR RADIAL'EAKING FACTORS used ih COLSS and the CPCs remaiin 'valid thiroughout the fuhl 'cycle.
Determining the measured PLANAR RADIAL PEAKING FACTORS after each fuel load'ing prior to
'xceeding 70X of RATED THEIRMAL POWER provides additional as. urance that phd core was properly loaded.
3/4
~ 2 e 3 AZIMUTHAL POWER TILT Tq The limitations on thee AZIMUTHAI POWER 'TII.'.T hre provided to ensure that design safety margins are maintained,.
An AZIMUTHAL'POWER TILT greater thar'he limit specified in the CORE OPERATING LIMITS REP'ORI with COLSS in service or 0.03 with COLSS out of,service is not expected'nd if 'it'should occur, operation is restricted to only.those. conditions required to identify thie chausse of the tilt.
The tilt is norma'lly calculateid Liy COLSSA'inimum core PoMer of 20% of RATED THERMAL POWER is assumed by the Cl'Cs in its input. to COLSS 'for calculation of AZIMUTHAL POWER TILT.
The 20%
RATI=D THERMAL POWER thresh&id i0 due to the neutron flux detector system bein) inaccurate below 20% core ipower.
Core noise level at low power is too large tio obtain usable detector readings.
The surveillance requirements specif'ied when'OLSS is out of service pro0ide hn acceptable means of detecting the presence of a, steady-state tilt. It is necessary to explicitly account for power asymwletries because the radial peiak~
ing factors used in the core power distribution calculations aire based on a'
,untilted power distri,but,ion.
The AZIMUTHAL POWER TILT is equal to (Pi<<<</P,.,)-1.0 where:
AZIMUTHAL POWER 'TILT 'is measured by assuming that the ratio of the power at any core location in the pre. ence of a tilt to the untilted power at the location is of.the form:
Pf ]~/ P
~ ) ~
I + Tq g c0 s
( 8 8 )
where:
T is the peak fractiona'I tilt amplitude. at the core periphery g is the radial normalizing factor' is the azimuthal core location 8, is the azimuthial core location of maximum til',t PALO VERDE UNIT I B 3/4 2-2 AMENDMENT.NO. 88,+i9-,
86
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001,,,.
ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-529 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE 2.
Amendment No.
74 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 Hexico, Los Angeles Department of Mater and
- Power, and Southern California Public Power Authority dated January 4,
- 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'ot 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 applicabTe 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-51 is hereby amended to read as follows:
0 t'
3.
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 74, 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 Date of Issuance:
November 3, 1994 Brian E.
Hol i an, Seni or Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
i~
4l
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
74 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 2-3 B 3/4 2-2 Insert 3/4 2-3 B 3/4 2-2
I
0 POWER DISTRIBUTION LIMITS 3/4 ~ 2 e 3 AZIMUTHAL POWER TILT Tq LIMITING CONDITION FOR OPERATION 3.2.3 The AZIMUTHAL POWER TILT (T ) shall be less than or equal to the following limits:
'a ~
b.l.
b.2.
APPLICABILITY:
ACTION:
a ~
b.
The AZIMUTHAL POWER TILT Allowance used in the Core Protection Calculators (CPCs),
and The limit specified in the CORE OPERATING LIMITS REPORT with COLSS in service, or T
~ 0.03 with COLSS out of service.
MODE I above 20X of RATED THERMAL POWER*.
With the measured AZIMUTHAL POWER TILT determined to exceed the AZIMUTHAL POWER TILT Allowance used in the CPCs within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> s either correct the power tilt or adjust the AZIMUTHAL POWER TILT Allowance used in the CPCs to greater than or equal to the measured value.
With the measured AZIMUTHAL POWER TILT determined to exceed the limit specified in the CORE OPERATING LIMITS REPORT with COLSS in service or 0.03 with COLSS out of service:
Due to misalignment.of either a part-length or full-length CEA, within 30 minutes verify that the Core. Operating Limit Supervisory System (COLSS)
(when COLSS is being used to monitor the core power distribution per Specifications 4.2.1 and 4.2.4) is detecting the CEA misalignment.
.2.
3.
Verify that the AZIMUTHAL POWER TILT is 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 /> after exceeding the limit or reduce THERMAL POWER to less than 50X of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and verify that the Variable Overpower Trip Setpoint has been reduced as appropriate within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50X of RATED THERMAL POWER may proceed provided that the AZIMUTHAL POWER TILT is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable at 95X or greater RATED THERMAL POWER.
- See Special Test Exception 3.10.2.
PALO VERDE UNIT 2 3/4 2-3 AMENDMENT NO. 8S,~
74
POWER DISTRIBUTION,'LIMITS SURVEILLANCE RE UIRIEMENTS.
4.2.3.1 The provisions of Specificat'ion 4.0.4 hre net applicable.
4.2.3.2 The AZIMUTHALPOWER TIL'T shall, be determi~ned to be within its limits above 2'f RATED THERMAL POWER by:
aO b.
c Continuou. ly. monitoring.the tiltwith COLSS when the COLSS is in service.
Calculating the tilt at.lea. t once Pe& 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the COLSS 'is
'ut of service.
Verifying at leas't once per 31 days',-'hat the COLSS Azimuthal T'ilt',
Alarm is actuated at, an AZIMUTHAL PQMER TILT less than or equal'0, the AZIMUTHAL'POKIERTIII.T Allowance used in the CPC..
Using the incore detectors at least once,pdr 31 EFPD to independently confirm the validity of the COLSS calculated AZIMUTHAL POWER TIILT.'ALO VERDE - UNIT 2 3/4 2-4 AMENDMENT NO. 25
BASES 3/4. 2. 1 LINEAR HEAT RATE The limitation on linear heat rate ensures that in the event of a LOCA, the peak temperature of the fuel cladding will not exceed 2200 F.
Either of the two core power distribution monitoring systems, the Core Operating Limit Supervisory System (COLSS) and the Local Power Density channels in the Core Protection Calculators (CPCs), provide adequate monitoring of the core power distribution and are capable of,verifying that the linear heat rate does not exceed its limits.
The COLSS performs this function by continuously monitoring the core power distribution and calculating a core power operating limit corresponding to the allowable peak linear heat rate.
Reactor operation at or below this calculated power level assures that the limits specified in the CORE OPERATING LIMITS REPORT are not exceeded.
The COLSS calculated core power and the COLSS calculated core power operating limits based on linear heat rate are continuously monitored and displayed to the operator.
A COLSS alarm is annunciated in the event that the core power exceeds the core power operating limit.
This provides adequate margin to the linear heat rate operating limit for normal steady-state opera-tion.
Normal reactor power transients or equipment failures which do not require a reactor trip may result in this core power operating limit being exceeded.
In the event this occurs, COLSS alarms will be annunciated.
If the event which causes the COLSS limit to be exceeded results in conditions which approach the core safety limits, a reactor trip will be initiated by the.Reactor Protective Instrumentation.
The COLSS calculation of the linear heat rate includes appropriate penalty factors which provide,, with a '95/95 probability/
confidence level, that the maximum linear heat rate calculated by COLSS is conservative with respect to the actual maximum linear heat rate existing 'in the core.
These penalty factors are determined from the uncertainties associated with planar radial peaking measurement, engineering heat flux uncertainty, axial densification, software algorithm modelling, computer processing, rod bow, and core power measurement.
Parameters required to maintain the operating limit power level based on linear heat rate, margin to DNB, and total core power are also monitored by the CPCs.
Therefore, in the event that the COLSS is, not being used, operation within the linear heat rate limit can be maintained by utilizing any operable CPC channel.
The above listed uncertainty and penalty factors plus those asso-ciated with the CPC startup test acceptance criteria are also included in the CPCs.
PALO VERDE " UNIT 2 B 3/4 2-1 AMENDMENT NO.
IH~ 55
POWER DISTRIBUTION LIMI S BASES 3 4.2.2 PLANAR RADIAL PEA'KIhIG IFACTOILS II Limiting the value. of the PLANAR RADIAL PEAKING FACTORS (F ') used 'in'th'e COLSS and CPCs to values equal
'to or greater than the measured PLANAR RADIAL PEAKING FACTORS (F') provides assurance that the, limits calculated by CULSC and the CPCs remain valid.
Data from the incore detectors are used for
'etermining the measured PLAhlAR RADIAL PEAKING 'FACTORS.'
minimum core power at 20X of RATED THERNAL POWER i.s assumed in Hele~ining the PLANAR RADIAL PEAKING FACTORS.
Ihe 20X IRATED THERNL POWER khrkshold i's due to the neutron flux detector system being inaccurate below 20X core power.
Core noise 'level at 'low power is too large to obtain usable detector readings.
The periodic surveillance requirements for determining the aieaIsured'PL'ANAR RADIAL PEAKING
'ACTORS provides
- a. surance that the PLANAR RADIAL'EAKiNG'ACTORSused in COLSS and the CPCs remaiin valid throughout the fudl cycle.
Determining 'the measured PLANAR RADIAL PEAIKING I;ACTORS after each fuel loading prior to exceeding 70X of RATED THEIRNAL POW'ER provide,s additional assurance that the core was properly 'lloaded.
3/4 ~ 2 e 3 AZINUTHAL POWER TILT Tq The limitations on the,AZINUTHAL POWER TIL'T Are'rov'ided to ensure that design safety margins are maintained.,
An AZIMUTHAL 'POWER TILT greater than'he limit specified in the CORE OPERATING LINITS REPORII with COLSS in service or 0.03 with COLSS out of service is not expected'an'd if it should occur,,
operation is restricted to only those conditions required to identify the cau. e of the tilt.
The tilt is normally calculate~i by COLSS
,A minimum core power of 20% of RATED THERNAL POWER, is assumed by the CPCs in its input to COLSS for calculation of AZIMUTHAL POWER 'lILT.
The 20%
RATED THERNAL POWER threshold is due to the neutron flux de'tector system being inakcuIate below 20X core power.,
Core noise level at low power is too large to obtain usable detector readings.,
The surveillance requirements specifi'ed when'COLSS is out of service provide an acceptable means of detect'ing the presence of a steady-state tilt. It i.
necessary to explicitly account for power as~rmmetries because the radial peaking factors -used in the core power distribution calcu'lations are based on an untilted power distribution.
The AZIMUTHAL POWER TILT is equal to (P,,-<</P-<<)-1.0 where:
AZIMUTHAL POWER TILT is measured by assuming that the ratio of the power at any core location in the presence of a tilt to the untilted power at the location is of the form:
~i<<=1+
qg where:
Tq is the peak fractional tilt amplitude at the core periphery is the radial normalizing factor 8 is the azimuthal core 'location 8, is the azimuthal core location of maximum tilt PALO VERDE UNIT 2!
B 3/4 2-2 AMENDMENT NO. RS,R&
74
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UNITED STATES NUCLEAR REGULATORYCOMMISSlON WASHINGTON, D.C. 2055&4001 ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-530 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.5B 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'uthority dated January 4,
- 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.
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:
II
3.
(2)'echnical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through. Amendment No.
5B, 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 Date of Issuance:
November 3, 1994 Brian E.
Hol ian, Seni or Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
l'
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
58 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 3/4.2-3 B 3/4'-2 Insert 3/4 2-3' 3/4 2-.2
It
~!
POWER DISTRIBUTION LIMITS 3/4 o 2 e 3 AZIMUTHAL POWER TILT Tq LIMITING CONDITION FOR OPERATION 3.2.3 The AZIMUTHAL POWER TILT (T ) shall be less than or equal to the following limits:
a.
The AZIMUTHAL POWER TILT Allowance used in the Core Protection Calculators (CPCs),
and
- b. l. The limit specified in the CORE OPERATING LIMITS REPORT with COLSS in
- service, or b.2.
T
< 0.03 with COLSS out of service.
APPLICABILITY:
MODE I above 20X of RATED THERMAL POWER*.
ACTION:
a.
b.
With the measured AZIMUTHAL POWER TILT determined to exceed the AZIMUTHAL POWER TILT Allowance used in the CPCs within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either correct the power tilt or adjust the AZIMUTHAL POWER TILT Allowance used in the CPCs to greater than or equal to the measured value.,
With the measured AZIMUTHAL POWER TILT determined to exceed the limit specified in the CORE OPERATING LIMITS REPORT with COLSS in service or 0.03 with COLSS out of service:
1.
Due to misalignment of either a part-length or full-length CEA, within 30 minutes verify that the Core Operating Limit Supervisory System (COLSS)
(when COLSS is being used to monitor the core power distribution per Specifications 4.2.1 and 4.2.4) is detecting the CEA misalignment.
2.
Verify that the AZIMUTHAL POWER TILT is 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 /> after exceeding the limit or reduce THERMAL POWER to less than 50X of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and verify that the Variable Overpower Trip Setpoint has been reduced as appropriate within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
3.
Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50X of RATED THERMAL 'POWER may proceed provided that the AZIMUTHAL POWER TILT is veri'fied within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable at 95X or greater RATED THERMAL POWER.
- See Special Test Exception 3.10.2.
PALO VERDE UNIT 3 3/4 2-3 AMENDMENT NO. 44,~ 58
It POWER DISTRIBUTION L'IHITS SURVEILLANCE RE UIREHENTS 4.2.3.1 The provisions of Specification 4.9.4 a>>e not applicable.
4.2;3;2 The AZIHUTHAL POWER TILT shall be determined to be within its limits above 20X of RATED THERHAII POWER by:
ao, Continuous'ly monitoring'the 'tilt with,COLSS',.when the COLSS is in
.ser vice.
b.
Calculating the tilt at least once per 12. hours when the CGLSS is out, of ser'ivice.
c.
Verifying at least once per 31 days, that the COLSS Azimuthal Ti'lt'larm is actuated at an AZIHUTHAL POWER TILT loess than -or equal.to the AZIHUTNAL POWER TILT Allowance used in the CPCs,.
d.
Using the incore detectors a't least once Pe>> 31'EFPD'-to independently'onfirm the validity of the COLSS calculated AZIMUTHAL POWER TILT.
PALD VERDE - VNIT 3 3/4 2-4 AHENDHENT N0.14
3/4. 2 REER DISTRIBUTION LIMITS BASES 3/4.2.1 LINEAR HEAT RATE The limitation on linear heat rate ensures that in the event of a. LOCA, the peak temperature of the fuel cladding will not exceed 2200'F.
Either, of. the two core power distribution monitoring systems, the Core Operating Limit Supervisory System (COLSS) and the Local Power Density channels in the Core Protection Calculators (CPCs), provide adequate monitoring of the core power distribution and are capable of verifying that the linear heat rate does not exceed its limits.
The COLSS performs this function by continuously monitoring the core power distribution and calculating a core power operating limit corresponding to the allowable peak linear heat rate.
Reactor operation at or below this calculated power level assures that the limits specified in the CORE OPERATING LIMITS REPORT are not exceeded.
The COLSS calculated core power and the COLSS calculated core power operating limits based on linear heat rate are continuously monitored and displayed to the operator.
A COLSS alarm is annunciated in the event that the core power exceeds the core power operating limit.
This provides adequate margin to the linear heat rate operating limit for normal steady-state opera-tion.
Normal reactor power transients or equipment failures which do not require a reactor trip may result in this core power operating limit being exceeded.
In the event this occurs, COLSS alarms will be annunciated.
If the event which causes the COLSS limit to be exceeded results in conditions which approach the core safety limits, a reactor trip will be initiated by the Reactor Protective Instrumentation.
The COLSS calculation of the linear heat, rate includes appropriate penalty factors which provide, with a 95/95 probability/
confidence level, that the maximum linear heat rate calculated by COLSS is conservative with respect to the actual maximum linear heat rate existing in the core.
These penalty factors are determined from the uncertainties associated with planar radial peaking measurement, engineering heat flux uncertainty, axial densification, software algorithm modelling, computer processing, rod bow, and core power measurement.
Parameters required to maintain the operating limit power level based, on linear heat rate, margin to ONB, and total core power are also monitored by the CPCs.
Therefore, in the event that the COLSS is not being used, operation within the linear heat rate limit can be maintained by utilizing any operable CPC channel.
The above listed uncertainty and penalty factors plus those associated with the CPC startup test acceptance criteria are also included in the CPCs.
PALO VERGE - UNIT 3 B 3/4 2"1 AMENOMENT NO. IS, 42
0 POWER DISTRIBUTION LIMITS BASES 3 4.2.2 PLANAR RADIAI PEAlt ING FACTORS i.imiting the values of the PLANAR RADIAL PEAKING FACTORS (F') used
'in the COLSS and CPCs to values equal to or greater than the measured PLANAR RADIAL PEAKING FACTORS (F",) provides assurance that the limits calculated by COLSS and the CPCs remain valid.
Data from the incore detectors are used for determining the measured Pl ANAR RADIAL PEAKING 'FACTORS.
A minimum core power at 20X of RATED THERMAL POWER is assumed in clethrrhining the PLANAR RADIAl.
PEAKING FACTORS.
The 20X RATED THERMAL POWER threshold is-due to the neutron flux detector system being inaccurate below 20X core power.
Core noise level at low power is too large to obtain usable detector readings.
The periodic surveillance requirements for determining the measured
'PLANAR RADIAL PEAKING FACTORS provides assurance that the PLANAR RADIAL'PEAKING FACTORS used in COLSS and the CPCs remain valid throughout the 'fuel Icycle.
Determining the measured PLANAR RADIAI PEAKING FACTORS after each fuel loading prior to exceeding 70X of RATED THERMAL POWER provides additiI>nal assurance that the core was properly loaded.
3 /4 ~ 2 o 3 AZIMUTHAL POWER TILT Tq The limitations on the AZIMUTHAL POWER TILT are provided to ensure that design safety margins are maintained.
An AZIMUtTHAL POWER TILT greater than the limit specified in the CORE OPERATING LIMITS REPORT w.ith COLSS in sex'vice
'r 0.03 with COLSS out of service is not expected and if it should occur,~ oper-ation is restricted to only those conditions required to ;ident',ify the cause~
of'he tilt.
The tilt is normally calculated by COLSS.
A m',inimum core power bf 20X of RATED THERMAL POWER is assumed by the CPCs in its 'input to COLSS for calculation of AZIMUTHAL POWER TILT.
'The 20NI RIITEtD tHERMAL POWER thresholdi is due to the neutron flux detector system being inaccui;ate below 20X core power.
Core noise level at low power is too large tci obtain usable detector readings.
The surveillance requ'irements specified when COLSS is out'of service prokidh aln acceptable means of detecting the presence of a steady-state tilt. It is, necessary to explicitly account for power asymmetries because the radial peaking factors used
'in the core power distrkbutidn kalculations are based on
'n untilted power distribution.
Th AZIMUTHAL POWER TILT i q
1 to (P,',-I P'<<',)-1.0 where:
AZIMUTHAL POWER II'ILT is measured by ass6mihg 'that the ratio of the power at any'core location in the presence of a til~t to ~the untilted power at, tahe location is of the form:
P g /P i gt I + T 9 cos (e e) where:
T is the peak fractional tilt ampl)tude at the 'core periphery g is the radial normalizing factor is the azimuthal core location 8, is the azimuthal core location of maximum tilt PALO VERDE 'UNIT 3 B, 3/4 2-2 AMENDMENT NO. 44, W4 58