ML20236U461
| ML20236U461 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/17/1987 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236U462 | List: |
| References | |
| TAC-66001, TAC-66002, NUDOCS 8712030069 | |
| Download: ML20236U461 (16) | |
Text
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- ps necoq[o UNITED STATES g
NUCLEAR REGULATORY COMMISSION
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- E WASHINGTON, D. C. 20555
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SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET N0. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Araendment No. 62 License No. NPF-10 1.
The Nuclear Regulatory Comission (the Commission) has found that:
4 A.
The applications for amendment to the license for San Onofre Nuclear Generating Station Unit 2 (the facility) filed by the Southern California Edison Company (SCE) on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and The City of Anaheim, California (licensees) dated August 5, 1987, and September 18, 1987 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applications, as amended, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(1) 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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' 2.
Accordingly, the license.is amended by changes to the Technical Specifications as indicated in the attachment to this amendme.nt and Paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 62, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The changes in Technical Specifications are to become effective within 30 days of issuance of the amendment.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the-time. The period of time during change over shall be minimized.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION W
George W. Knighton, Director Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 17, 1987 1
I
a i
~ ATTACHMENT TO LICENSE AMENDl4ENT NO. 62 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 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 area of change. Also to be replaced are the following overleaf pages to the amended pages.
Amendment Pages Overleaf Pages 3/4 2-11 3/4 2-12 B3/4 2-4 B3/4 2-3 B3/4 2-5 1-I N__.____.-_____
~
~~ ~~
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n POWER DISTRIBUTION LIMITS AXIAL SHAPE INDEX LIMITING CONDITION FOR OPERATION 3.2.7 The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
a.
-0.27 1 ASI $ + 0.27 l
a.
-0.20 $ ASI $ + 0.20 APPLICABILITY:
MODE 1 above 20% of RATED THERMAL POWER
- ACTION:
With the core average AXIAL SHAPE INDEX (ASI) exceeding its limit, restore the 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 20%
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 REQUIREMENTS 4.2.7 The core average AXIAL SHAPE INDEX shall be determined to be within its limit by continuously monitoring the ASI with COLSS, or with COLSS OUT OF SERVICE, by verifying at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that the core average ASI is within the COLSS OUT OF SERVICE ASI limit using any operable CPC channel.
i "See Special Test Exception 3.10.2.
SAN ONOFRE-UNIT 2 3/4 2-11 AMENDMENT NO. 62
- s. : " >
/
i POWER DISTRIBUTION LIMITS PRESSURIZER PRESSURE LIMITING CONDITION FOR OPERATION 3.2.8 The average pressurizer pressure shall be maintained between 2025 psia and 2275 psia.
APPLICABILITY:
MODE 1 ACTION:
'With the average pressurizer pressure (xceeding its limit, 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 reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the nextg4 hours.
SURVEILLANCE REQUIREMENTS
/
4.2.8 The average 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 />,
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i SAN ONOFRE-UNIT 2 3/4 2-12
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__ _ _ _. _ _ _ _ _ _ _ ______________________j
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POWER DISTRIBUTION LIMITS
(
BASES AZIMUTHAL POWER TILT - T (Continued)
T is the peak fractional tilt amplitude at the core periphery q
g is the radial normalizing factor 0 is the azimuthal core location O is the azimuthal core location of maximum tilt g
/P tilt untilt is the ratio of the power at a core location in the presence of a tilt to the power at that location with no tilt.
3/4.2.4 DNBR MARGIN
/
The limitation on DNBR as a function of AXIAL SHAPE INDEX represents a conservative envelope of operating Eonditions consistent with the safety analysis assumptions and which have been analytically demonstrated adequate to maintain an acceptable minimum DNBR throughout all anticipated operational occurrences, of which the loss of flow transient is the most limiting.
Opera-tion of the core with a DNBR at or above this limit provides assurance that an
(
acceptable minimum DNBR will be maintained in the event of a loss of flow transient.
Either of the two core power distribution monitoring systems, the Core Operating Limit Supervisory System (COLSS) and the DNBR channels in the Core Protection Calculators (CPCs), provide adequate monitoring of the core power distribution and are capable of verifying that the DNBR does not violate its limits. The COLSS performs this function by continuously monitoring the core power distribution and calculating a core operating limit corresponding to the allowable minimum DNBR.
The COLSS calculation of core power-operating limit based on the minimum DNBR limit includes appropriate penalty factors which provide, with a 95/95 probability / confidence level, that the core power limit calculated by COLSS (based on the sinumum DNBR limit) is conservative with respect to the actual core power limit.
These penalty factors are determined from the uncertainties associated with planar radial peaking measurement, engineering design factors, state parameter measurement, software algorithm modelling, computer processing, rod bow and core power measurement.
Parameters required to maintain the margin to DNB and total core power are also monitored by the CPCs.
In the event that the COLSS is not being used, the DNBR margin can be maintained by monitoring with any operable CPC l
channel so that the DNBR remains above the predetermined limit as a function of Axial Shape Index.
The above listed uncertainty penalty factors are also included in the CPCs, which assume a minimum of 20% of RATED THERMAL POWER.
The 20% RATED THERMAL POWER threshold is due to the excore neutron flux detector system being less accurate below 20% core power.
Core noise level at low power
!b is too large to obtain usable detector readings.
The additional uncertainty i
terms taken into account in the CPCs for transient protection are removed from Figures 3.2-1 and 3.2-2 since the curves are intended to monitor the LCO only during steady state operation.
SAN ONOFRE - UNIT 2 B 3/4 2-3 AMEN 0 MENT NO. 47 E
4 POWER DISTRIBUTION LIMITS BASES DNBR Margin (Continued)
The DNBR penalty factors listed in sectica 4.2.4.4 are penalties used to accommodate the effects of rod bow. The amount of rod bow in each assembly is dependent upon the average burnup experienced by that assembly.
Fuel assemblies that incur higher average burnup will experience a greater magnitude of rod bow.
Conversely, lower burnup assemblies will experience less rod bow.
The penalty for each batch required to compensate for rod bow is determined from a batch's maximum average assembly burnup applied to the batch's maximum integrated planar-radial power peak.
A single net penalty for COLSS and CPC is then determined from the penalties associated with each batch, accounting for the offsetting margins due to the lower radial power peaks in the higher burnup batches.
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 LOCA safety analyses.
3/4.2.6 REACTOR 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.
2.4.2.7 AXIAL SHAPE INDEX i
The Axial Shape Index (ASI) is a measure of the power generated in the lower half of the core less the power generated in the upper half of the core -
divided by the sum of these powers. This specification is provided to ensure that the core average ASI is maintained within the range of values assumed as t
an initial condition in the safety analyses. This range is specified as
-0.3 5 ASI 5 0.3.
The ASI can be determined by utilizing either the Core Operating Limit Supervisory System (COLSS) or any operable Core Protection Calculator (CPC) channel.
The real time monitoring capability and accuracy of COLSS allows COLSS to monitor power limit margins closely.
Consequently, the ASI limit is broader than it would be with the same core without COLSS. The COLSS con-tinuously calculates the ASI and compares the calculated value to the param-eter established for the COLSS ASI alarm limit.
In addition, there is an uncertainty associated with the COLSS calculated ASI; therefore the COLSS ASI alarm limit includes this uncertainty.
If the LCO is exceeded, COLSS alarms are initiated. The ASI safety setting is selected so that no safety limit will be exceeded as a result of an anticipated operational occurrence, and so that the consequence of a design basis accident will be acceptable.
SAN ON0FRE - UNIT 2 B 3/4 2-4 AMENDMENT NO.62
l I
POWER DISTRIBUTION LIMITS BASES AXIAL SHAPE INDEX (Continued)
With COLSS out of service, any operable CPC channel may be used to calcu-late the ASI (using three axially spaced excore detectors).
The axial shape synthesis in the CPC's shows the relative power produced as a function of 4
core height in each third of the core.
Due to the uncertainty associated with l
the CPC estimate, the ASI is restricted to a smaller range than the range cal-culated using the COLSS.
The 20% rated thermal power threshold is imposed due to the inaccuracy of the neutron flux detector below the threshold.
Core noise level is too large to obtain usable detector readings.
3/4.2.8 PRESSURIZER PRESSURE This specification is provided to ensure that the actual value of pressurizer pressure is maintained within the range of values used in the j
safety analyses.
SAN ONOFRE - UNIT 2 B 3/4 2-5 AMENDMENT NO. 62
4
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o UNITED STATES g
8" NUCLEAR REGULATORY COMMISSION n
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WASHINGTON, D. C. 20565 SOUTHERN CALIFORNIA EDIS0N COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET N0. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 51 License No. NPF-15 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment to the license for San Onofre Nuclear Generating Station,' Unit 3 (the facility) filed by the Southern California Edison Company (SCE) on behalf of itself and San Diego Gas and Electric Company,)The City of Riverside and The City of Anaheim, California (licensees dated August 5, 1987, and September 18, 1987 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applications, as amended, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(i) that the t.ctivities 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirerrents have been satisfied.
o l
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this amendment and Paragraph 2.C(2) of Facility Operating License No. NPF-15 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 51, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The changes in Technical Specifications are to become effective upon initial startup for Cycle 4 cf operation.
In the period between issuance of the amendment and the effective date of the new Technical Specific-ations, the licensees shall adhere to the Technical Specifications existing at the time. The period of time during change over shall be minimized.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
$l.
lM George W. Knighton, Director Project Directorate V l
Division of Reactor Projects - III, IV, V and Special Projects l
Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 17, 1987
s.
~ l l
ATTACHMENT TO LICENSE AMENDMENT NO. 51 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 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 area of change. Also to be replaced are the following overleaf pages to the amended pages.
Amendment Page Overleaf Page 3/4 2-11 3/4 2-12 B3/4 2-4' B3/4 2-3 B3/4 2-5 t
i 1
______________O
~,.
POWER DISTRIBUTION LIMITS AXIAL SHAPE INDEX LIMITING CONDITION FOR OPERATION 3.2.7 The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
a.
-0.27 5 ASI 5 + 0.27 a.
-0.20 $ ASI $ + 0.20 l
APPLICABILITY:
MODE 1 above 20% of RATED THERMAL POWER
- ACTION:
~
With the core average AXIAL SHAPE INDEX (ASI) exceeding its limit, restore the 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 20%
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 REQUIREMENTS 4.2.7 The core average AXIAL SHAPE INDEX shall be determined to be within its limit by continuously monitoring the ASI with COLSS, or with COLSS OUT OF SERVICE, by verifying at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that the core average ASI is within the COLSS OUT OF SERVICE ASI limit using any operable CPC channel.
"See Special Test Exception 3.10.2.
1 SAN ON0FRE-UNIT 3 3/4 2-11 AMENDMENT NO. 51 e
n.*
I POWER DISTRIBUTION LIMITS i
\\
l l
PRE 55URIZER PRESSURE i
LIMITING CONDITION FOR OPERATION i
3.2.8 The pressurizer pressure shall be maintained between 2025 psia and j
2275 psia.
l APPLICABILITY: ' MODE 1 ACTION:
With the pressurizer pressure exceeding i,ts limit, 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 reduce THERMAL POWER to less than 5% 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 />.
1 4
SURVEILLANCE REQUIREMENTS 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 />.
l e
M 1
(
SAN ONOFRE-UNIT 3 3/4 2-12
. _ - _ _ _ - _ _ ___- - _a
i 4
o i
POWER DISTRIBUTION LIMITS BASES
(
AZIMUTHAL POWER TILT T (Continued)
T is the peak fractional tilt amplitude at the core periphery q
g is the radial normalizing factor 6 is the azimuthal core location O is the azimuthal core location of maximum tilt g
P
/P is the ratio of the power at a core location in the presence tilt untilt of a tilt to the power at that location with no tilt.
3/4.2.4 DNBR MARGIN The limitation on DNBR as a funct on of AXIAL SHAPE INDEX represents a conservative envelope of operating'cbnditions consistent with the safety analysis assumptions and which have been analytically demonstrated adequate to maintain an acceptable minimum DNBR throughout all anticipated operational occurrences, of which the loss of flow transient is the most limiting.
Opera-tion of the core with a DNBR at or above this limit provides assurance that an acceptable minimum DNBR will be maintained in the event of a loss of flow transient.
Either of the two core power distribution monitoring systems, the Core
/
Operating Limit Supervisory System (COLSS) and the DNBR channels in the Core Protection Calculators (CPCs), provide adequate monitoring of the core power distribution and are capable of verifying that the DNBR does not violate its limits.
The COLSS performs this function by continuously monitoring the core power distribution and calculating a core operating limit corresponding to the allowable minimum DNBR. The COLSS calculation of core power _ operating limit based on the minimum DNBR limit includes appropriate penalty factors which provide, with a 95/95 probability / confidence level, that the core power limit calculated by COLSS (based on the minumum DNBR limit) is conservative with respect to the actual core power limit.
These penalty factors are determined from the uncertainties associated with planar radial peaking measurement, engineering design factors, state parameter measurement, software algorithm modelling, computer processing, rod bow and core power measurement.
Parameters required to maintain the margin to DNB and total core power are also monitored by the CPCs.
In the event that the COLSS is not being used, the DNBR margin can be maintained by monitoring with any operable CPC channel so that the DNBR remains above the predetermined limit as a function of Axial Shape Index.
The above listed uncertainty penalty factors are also included in the CPCs, which assume a minimum of 20% of RATED THERMAL POWER.
The 20% RATED THERMAL POWER threshhold is due to the excore neutron flux detector system being less accurate below 20% core power.
Core noise level at low power is too large to obtain usable detector readings.
The additional uncertainty terms taken into account in the CPCs of transient protection are removed from Figures 3.2-1 and 3.2-2 since the curves are intended to monitor the LCO only during steady state operation.
s SAN ONOFRE - UNIT 3 8 3/4 2-3 AMENDMENT NO. 36
c POWER DISTRIBUTION LIMITS q
BASES DNBR Margin (Continued)
A DNBR penalty factor has been included in the COLSS and CPC DNBR calculation to accommodate the effects of rod bow.
The amount of rod bow in each assembly is dependent upon the average burnup experienced by that assembly.
Fuel assemblies that incur higher average burnup will experience a greater magnitude of rod bow.
Conversely, lower burnup assemblies will experience less rod bow.
In design calculations, the penalty for each batch required to compensate for rod bow is determined from a batch's maximum average assembly burnup applied to the batch's maximum integrated planar-radial power peak.
A single net penalty for COLSS and CPC is then determined from the penalties associated with each batch, accounting for the offsetting margins due to the lower radial power peaks in the higher burnup batches.
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 LOCA safety analyses.
3/4.2.6 REACTOR 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.
2.4.2.7 AXIAL SHAPE INDEX The Axial Shape Index (ASI) is a measure of the power generated in the lower half of the core less the power generated in the upper half of the core divided by the sum of these powers.
This specification is provided to ensure that the core average ASI is maintained within the range of values assumed as an initial condition in the safety analyses.
This range is specified as
-0.3 $ ASI $ 0.3.
The ASI can be determined by utilizing either the Core Operating Limit Supervisory System (COLSS) or any operable Core Protection Calculator (CPC) channel.
The real time monitoring capability and accuracy of COLSS allows COLSS to monitor power limit margins closely.
Consequently, the ASI limit is broader than it would be with the same core without COLSS.
The COLSS con-tinuously calculates the ASI and compares the calculated value to the param-eter established for the COLSS ASI alarm limit.
In addition, there is an uncertainty associated with the COLSS calculated ASI, therefore the COLSS ASI alarm limit includes this uncertainty.
If the LC0 is exceeded, COLSS alarms are initiated. The ASI safety setting is selected so that no safety limit will be exceeded as a result of an anticipated operational occurrence, and so that the consequence of a design basis accident will be acceptable.
SAN ON0FRE - UNIT 3 B 3/4 2-4 AMENDMENT NO. 5)
e t
POWER DISTRIBUTION LIMITS BASES AXIAL SHAPE INDEX (Continued)
With COLSS out of service, any operable CPC channel may be used to cal-culate the ASI (using three axially spaced excore detectors). The axial shape synthesis in the CPC's shows the relative power produced as a function of core height in each third of the core.
Due to the uncertainty associated with the CPC estimate, the ASI is restricted to a smaller range than the range calcu-lated using the COLSS.
The 20% rated thermal power threshold is imposed due to the inaccuracy of the neutron flux detector below the threshold.
Core noise level is too large to obtain usable detector readings.
3/4.2.8 PRESSURIZER 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.
t 4
SAN ON0FRE - UNIT 3 B 3/4 2-5 AMENDMENT NO. 51
_ _ - _ - _ _ _