ML17311B190
| ML17311B190 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/20/1995 |
| From: | Brian Holian NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17311B191 | List: |
| References | |
| NUDOCS 9509250318 | |
| Download: ML17311B190 (28) | |
Text
r gsait REGS+
0 co r
0 C
O
.r~
cs
~O
+***+
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205550001 September 20, 1995 Hr. William L. Stewart Executive Vice President, Nuclear Arizona Public Service Company Post Office Box 53999
- Phoenix, Arizona 85072-3999
SUBJECT:
ISSUANCE OF AMENDMENTS FOR. THE PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
1 (TAC NO. N91148),
UNIT NO.
2 (TAC NO. N91149),
AND UNIT NO.
3 (TAC NO. N91150)
Dear Nr. Stewart:
The Commission has issued the enclosed Amendment No.100 to Facility Operating License No. NPF-41, Amendment No. 88 to Facility Operating License No. NPF-51, and Amendment No.
71 to Facility Operating License No. NPF-74 for the Palo Verde Nuclear Generating Station, Unit Nos.
1, 2, and 3, respectively.
The amendments consist of changes to the Technical Specifications (TS) in response to your application dated December 7,
- 1994, and supplemented by letter dated August 1, 1995.
These amendments change Note 5 to Table 4.3-1 of TS 3/4.3. 1 to allow verification of the shape-annealing matrix elements used in the core protection calculators.
This provides the option of using generic shape-annealing matrix elements in the core protection calculators.
Presently, cycle-specific shape-annealing elements are determined during startup testing after each core reload. 'se of a generic shape-annealing matrix eliminates several hours of critical path work during startup after a refueling outage.
A copy of the related Safety Evaluation is also enclosed'.
The Notice of issuance will be included in the Commission's next biweekly Federal
~Re ister notice.
Sincerely, Docket Nos.
STN 50-528, STN 50-529 and STN 50-530 Brian E. Holian, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Enclosures:
l.
Amendment No. 100to NPF-41 2.
Amendment No. 88 to NPF-51 3.
Amendment No.
71 to NPF-74 4.
Safety Evaluation cc w/encls:
See next page 950'7250318 950920 PDR'DQCK 05000528 P
4l 4
Mr. William L. Stewart September 20, 1995 cc w/encls:
Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street
- Phoenix, Arizona 85007 T. E. Oubre, Esq.
Southern California Edison Company P. 0.
Box 800
- Rosemead, California 91770 Senior Resident Inspector USNRC P.
O. Box 40
- Buckeye, Arizona 85326 Regional Administrator, Region, IV U. S. Nuclear Regulatory Commission Harris Tower E Pavillion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064
- Chairman, Board of Supervisors ATTN:
Chairman 301 W. Jefferson, 10th Floor
- Phoenix, Arizona 85003
/
Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street
- Phoenix, Arizona 85040 Mr. Curtis Hoskins Executive Vice President and Chief Operating Officer Palo Verde Services 2025 N. 3rd Street, Suite 200
- Phoenix, Arizona 85004 Roy P. Lessey, Jr.,
Esq.
Akin, Gump, Strauss, Hauer and Feld El Paso Electric Company 1333 New Hampshire Avenue, Suite 400 Washington, DC 20036 Ms. Angela K. Krainik, Manager Nuclear Licensing Arizona Public Service Company P.O.
Box 52034
- Phoenix, Arizona 85072-2034
'gpR REgy
~
(4
'~4
~o Cy A.0O CO0
~O
+***+
UNITED STATES NUCLEAR REGULATORY COMMlSSION WASHINGTON, D.C. 2055&0001 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.
100 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 December 7,
- 1994, as supplemented by letter dated August 1,
- 1995, 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-41 is hereby amended to read as follows:
ii
3.
-(2)
Technical S ecifications and Environmental Protect'ion Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 100, and the Envi'ronmental Protection Plan contained in Appendix B, are hereby incorporated into this 1-icense.
APS shall operate the facility in accordance with the Techn'ical 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.
FOR THE NUCLEAR REGULATORY COMMISSION Brian E. Hol ian, Seni or Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
'ttachment:
Changes to the Technical Speci'fications Date of Issuance:
September 20, 1995
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
F00 TO FACILITY OPERATING LICENSE NO.
NPF-41 DOCKET NO.
STN 50-528 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains marginal lines indicating the areas of change.
The corresponding overleaf page is also provided to maintain document completeness.
REMOVE 3/4 3-16 INSERT 3/4 3-16
~
~
TABLE 4.3-$
(Continued)
RERTNOII PROTECTIVE INETRRIIENTRTION IIIRVEIIIIIIICIREIIOIREIIENTI FUNCT IONA UNIT D.
Supplementary Protection System Pressurizer Pressure
- High II.
RPS LOGIC CHANNEL CHANNEL CHECK CALIBRATION CHANNEL FUNCTIONAL
.TEST NODES IN llHICH SURVEILLANCE RE UIRED 1,
2 A.
Matrix Logic B.
Initiatiori Logic I II.
RPS ACTUATION DEVICES A.
Reactor Trip Breakers B.
manual Trip N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
H, R (10) 3A 4*
5*
I, 2, 3*, 4*, 5*
3*
4*
5*
i, ~, 3*, 4*, 5*
Cl m
C)
TABLE NOTATIONS (2)
(3)
(4)
(5)
(6)
With reactor tr'ip breakers in the closed position and the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.
Each STARTUP or when required with the reactor trip breakers closed and the CEA-drive sy. tern capable of rod withdrawal, if not performed in the previous 7 days.
Heat balance on'ly (CHANNEI FUNCTIONAL TEST not included),
above 15% of RATED THERMAL POWER; adjust the linear power level, the CPC delta T
power and CPC nuclear power signa'ls to agree with the calorimetric calculation if absolute difference is greater than 2X.,
During PHYSICS TESTS, these daily calibrations may be suspended provided these calibrations are performed upon reaching each major test power plateau and prior to proceed'ing to the next major test power plateau.
Above 15X of RATED,THERMAL P'OWER, veri fy that the linear power subchannel gains of the excore detectors are consistent with the values used to.establish
.the shape lnnbaling matrix e'llements in the Core Protection Calculators.
Neutron detectors may be excluded from, CHANNEL CALIBRATION; After each 'fuel loading and prior to e'xceeding 70X of RATED THERMAI POWER, the incore detectors shall be usedl to determine or verify the shape anneal'ing matrix elements used in 0he Core Protection Calculators.
This CHANNEL FUNCTIONAL TESl shall include the inject'ion of'imulated process signals into the channel as clpsq to the sensors as practicable to verify OPERABILITY including alarm and/or trip functions.
(7)
(B)
(10)-
Above 70X'f RATED THERMAL POMER, verify:that the total steady-state RCS flow-rate as indicated -by each CPC is.less than or equal to the actual RCS total flow rate determined by ei ther using the reactor coolant pump differential pressure instrumentation or by calorimetric calculations and "if necessary, adjust the CPC addressable constant flow coefficients such that each CPC i'ndicated f'low is less than or equal to the actual'low rate.
Th'e flow measurement uncertainty may be included in the BERRl term in the CPC and is equal to or greater than 4X.
Above 70X of -RATED THEINAL POMER, verify that the total steady-state RCS flow rate ass indicated by each,CPC is less than or equal to the actual RCS total flow >rate determined by either using the reactor coolant pump differential pressure instrwmentation and the ultrasonic flow meter adjusted pump curves or calor'imetric calcu'lations.
The quarterly CHANNEL IFUNCTIONAL TEST ishall, include verification that the correct current va'lues of addrelssdblh c~onstants are installed in~
At least once per 18 months and following maintenance or'djustment of, the reactor trip breakers,
'the CHANNEL FUNGTIONAL TEST sha'll include independent verificatiion of the und'erdoltage and shunt trips.
PALO VERDE UNIT 1 3/4 3-16 Amendment hfo. K
',H,100
~. SiRRECu 0
Cy C
O ch
. r 0
Cy
+n
~O
++*++
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 Amendment No. 88 License No. NPF-51 The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
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 December 7,
- 1994, as supplemented by letter dated August 1,
- 1995, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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:
41 Oi
(2)
Technical S ecifications and Environmental'rotection Pl'an The Technical Specifications contained in Appendix A, as revised through Amendment.No.
88, 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'pecifications 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.
FOR THE NUCLEAR REGULATORY COMMISSION Brian E. Holian, 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:
September 20, 1995
0
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
88 TO FACILITY OPERATING LICENSE NO. NPF-5I DOCKET NO.
STN 50-529 Replace the following page of the Appendix 'A Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains marginal lines indicating the areas of change.
The corresponding overleaf page is also provided to maintain document completeness.
RENDVE 3/4 3-16 INSERT 3/4 3-16
~I I
TABLE 4.3-1 (Continued)
REACTOR PROTECT I VE INSTRUMFNTATION SURVE ILLANCE RQUIREHENTS
(
Xl C7m FUNCTIONAL UNIT D.
Supplementary Protection System Pressurizer Pressure
- High I I.
RPS LOGIC CWANNEL CIIANNFL CHECK CALIBRATION C>rANNEL FUNCTIONAL TEST HODES IN MHICH SURVEILLANCE
.REQUIRED I,
2 A.
Hatrix Logic B.
Initiation Logic
- III, RPS ACTUATION OEVICES A.
Reactor Trip Breakers B.
Hanual Trip N.A.
N.A.
N.AD N.A.
N.A.
H, R(IO) 2 3*
4*
5*
3*
4*
5*
2 3*
4*
5*
1, 2, 3*, 4*, 5*
)
m C7 m
C)
REACTOR PROTECl'IVI= INSI'RUMENTATION SURVEILLANCE RE(UIREMENTS TABLE NOTA'TIONS (2)
(3)
(4)
(5)
(7)
(8)
(10)
With reactor trip breakers in the closed position and the CEA drive system capable of CEA withidrawal, and fuel in the reactor vessel.
Each STARTUP or when required with the lreactor, trip, breakers closed and the CEA drive,system capable of rod withdrawal, if not per'formed in the previous 7 days; Heat balance only (CHANNEL FUNCTIONAL TEST not included),
above 15X of RATED THERtQL POWER; adjust the linear power level, the CPC delta T power and CPC nuclear power,signals to agree with the calorimetric calculation if absolute difference is greater than 2X.
During PHYSICS TESTS, these da'ily calibrations may ibeisuispended provided these calibrations are performed upon reaching each major test power plateau and prior to proceediing to the next ~major test power plateau.
Above 15X of RATED THERMAL POWER, verify that the linear power subchannel ga,ins of the excore detectors iare consistent with the values.used to establish the shape annealing matrix elements in the Core Protection Calculators.
Neutron detectors may be excluded from CHANNEL CALIBRATION.
After each fuel loading and prior to exceeding 70X of RATED THERMAL POWER, the incore detectors shall be used to determine or verify the; shape annealing matr'ix elements used in the Core Protection Calculators.
This CHANNEL FUNCTIONAL TI.=ST shall inc'ludle the injectiion of sim<tlated process signals into the channel as close to the sensors as practicable to vhrify OPERABILITY including alarm and/or trip functions.
Above 70X of RATED THERMAL POWER, verify that the total steady-state RCS flow rate as indicated by each CPC is less than or equal to the actual RCS tdtal flow rate determined by ei'ther using the reactor, coolant pump differential pressure instrumentation or by calorimetric calculations and if necessary, adjust the CPC addressable constant flow coeffic~ients such that each CPC indicated flow is less than or equal to the actual flow rate.
The flow measurement uncertainty may be included
'in the.
BIERF!1 term in th5 CPC and is equal ta or greater than 4X.
Above 70X of RATED THERMAL POWER, verify that the total steady-state RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined-by either -using the reactor coolant pump differential pressure instrumentation and the ultrasonic flow met'er adjusted;pump curves or calorimetric calculations.
The quarterly CHANNEL FUNCTIONAL'EST shall include verification that the correct (current) values, of addressable constants are installed in each OPERABLE CPC.,
At least once per 18 months and following maintenance or adjustment of
~
the reactor trip breakers, the CHANNEL FIJNCTIONAL TES'T shall include independent verif'ication of the undervoltage and shunt trips.
PALO VERDE UNIT.2 3/4 3-16 Amendment No. Ml-,64, 88
pj's BE00
~o O
I 0
qO
++*++
t t
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-530 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
71 License No. NPF-74 The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
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 December 7,
- 1994, as supplemented by letter dated August 1,
- 1995, 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; I
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 Oi
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specificati'ons contained in Appendix A, as revised through Amendment No. 71, 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.
FOR THE NUCLEAR'EGULATORY COMMISSION Brian E.
Hol i an,, Seni or Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office o'f Nuclear Reactor Regulation t
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 20, 1995
0 II
AMENDMENT NO.
ATTACHMENT TO LICENSE AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-74 DOCKET NO.
STN 50-530 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains marginal lines indicating the areas of change.
The corresponding overleaf page is also provided to maintain document completeness.
REMOVE 3/4 3-16
- INSERT, 3/4 3-16
0 Oi
TABLE 4.3-1 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE RE UIREMENTS Crd FUNCT IONA UNI D.
Supplementary Protection System Pressuriter Pressure
- High II.
RPS LOGIC A.
Matrix Logic B.
Initiation Logic I II.
RPS ACTUATION DEVICES CHANNEL CHECK S
N.A.
N.A.
CHANNEL CALI BRATION N.A.
N.A.
CHANNEL NODES IN WHICH FUNCTIONAL SURVEILLANCE
. IE I
~RR II IREE 1,
2 3*
4*
5*
I 2
3*
4*
5*
A.
Reactor Trip Breakers B.
Manual Trip N.A.
N.A.
N;A.
N.A.
M, R(10) 3*
4*
5*
I 2
3*
4*
5*
C7
REACTOR PROTECTIVE INSTRUMENTATION SURV ILLANCE RE UIREMENTS TABLE NOTATIONS (2)
(3)
(4)
(5)
(6)
(7)
(8)
(1o)
With reactor trip breakers in the closed position and the CEA driivei system capable of CEA withdrawal, and fuel'n the reactor vessel.
Each STARTUP or when required with'he reactor trip breakers c'losed and the CEA drive system capable of rod withdrawa'll, if not performed in the previous 7 days.
Heat balance only (CHANNEL FUNCTIONAL TEST not included),
above 15X of RATED THERMAL POWER; adjust the linear empower level, the CPC delta T power and CP'C nuclear power signals to agree with the calorimetric calculation if absolute difference is greater than 2X.
During PHYSICS 1'ESTS, these daily calibrations may be su pended provided these calibrat,ions are performed upon reaching each major test power plateau and prior to proceeding to the next major test power plateau Above 15X of RATED THI=RMAL POWEP., verify that the linear power'ubchannel gains of'he excore detlecitorIs are consistent with the values used to establish the shape annealing matrix 'elements in the Core Protection Calculators.
Neutron detectors may be excluded from CHANNEL CALIBRATION.
After each fuel loading and prior to exceeding 70X of RATED THERMAL POWER, the incore detector.
shall be used to determine or verify the shape annea'ling matrix elements used in thie Core Protection Calculators.
This CHANNEL FUNCTIONAL TEST shall include the injection of simulated i
process signalsi into the channel a's eloise ,to, the sensors as practicable to verify OPERABILITY inctluditig alarm and/or trip
'unctions.
Above 70X of RATED THI=RMAL POWER, verify that the total steady-state RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either using the reactor coolant pump differential pressure instrumentation or by calorimetric calculations and if necessary, adjust the CPC addressable constant flow coefficients such that each CPC inldidated 'flow is less than or equal to the actual flow.rate.
The flotv measurement uncertain'ty may be included in the BERRl term in the CPC and is equal to or greater than 4X.
Above 70X of RATED THERMAL POWER, verify that the tota'1 steady-state RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determi'ned by either using the reactor coolant pump clifferential pressure instrumentation and the ultrasonic flow meter adjusted pump curves or calorimetric calculations.
The quarterly CHANNEL FUNCTIONAL TEST shall include verification thIat the correct (current) values of ad'dress'able constants are installed in each OPERABLE CPC.
At least once per 18 months and following maintenance or adjustment of the reactor trip breakers, the CHANNEL FUNCTIONAL TEST shal'1 include independent verification o'f the'ndervoltage and shunt trips.,
PALO VERDE UNIT 3 3/4 3-16 Amendment No. K~9,71