ML20137Z271
| ML20137Z271 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  (NPF-10-A-039, NPF-10-A-39, NPF-15-A-028, NPF-15-A-28) |
| Issue date: | 12/02/1985 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137Z277 | List: |
| References | |
| TAC-59743, TAC-59744, NUDOCS 8512110261 | |
| Download: ML20137Z271 (14) | |
Text
UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION t,
wasmworow. o.c. 2eens
\\...../
SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. NPF-10 1.
The Nuclear Regulatory Commission (the Commission) has found that:
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 on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and the City of Anaheim, California (licensees) dated August 23, October 10 and 16, 1985, 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 application, as amended, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(i)thattheactivitiesauthorized 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't regulations set forth in 10 CPR 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 Commission's reaulations and all applicable requirements have been satisfied.
0512110261 851202 PDR ADOCK 05000361 p
PDR 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-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. 39, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amenchnent is effective inmediately and is tn be fully imniemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION George W
- nighton,
.ctor PWR Pro,iect Directorate Nn. 7 Division of PWR Licensino-R
Attachment:
Changes to the Technical Specifications Date of Issuance: DEC 2 1995 i.
DEC 2 1985
. ATTACHMENT TO LICENSE AMENDMENT NO. 39 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 chan'ge. Also to be replaced are the following overleaf pages to the amended pages.
' Amendment Pages Overleaf Pages 5-6 5-5 5-7 5-8 l
l i
l l
l
-a
t SAll OssoFRC WUCLEAR Mis (AAYiset STAT 1088 vers ( tas
- - - =
=I.!
\\
\\
=:.:
/
ocALs a rest 4
s*
[
"/ssY er
(, Art avr j
I
(
,/
- 4. '* !
\\
g SITE BOUNDARY FOR LIQUID EFFLUENTS FIGURE 5.1-4
(
SAN ONOFRE-UNIT 2 5-5
--.,-.-..c
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 217 fuel assemblies with each fuel assembly containing a maximum of 236 fuel rods clad with Zircaloy-4.
Each feel rod shall have a nominal active fuel length of 150 inches and contain a maximum total weight of 1900 grams uranium.
The initial core loading shall have a maximum enrichment of 2.91 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.1 weight percent U-235.
l CONTROL ELEMENT. ASSEMBLIES 5.3.2 The reactor core shall contain 83 full length and 8 part length control element assemblies.
5.4 REACTOR COOLANT SYSTEM i
DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
a.
18.iccordance with the code requirements specified in Section 5.2 of (ps FSAR with allowance for normal degradation pursuant of the applicoale Surveillance Requirements, b.
For a pressure of 2500 psia, and c.
For a temperature of 650'F, except for the pressurizer which is 700'F.
SAN ONOFRE-UNIT 2 5-6 AMENDMENT NO, 39
.._...l
DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 11,800 + 600/-0 cubic feet at a nominal T,yg of 582.1 F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:
A k,ff equivalent to less than or equal to 0.95 when flooded with a.
unborated water, which includes a conservative allowance for uncer-tainties as described in the FSAR.
b.
A nominal 12.75 inch center-to-center distance between fuel assemblies placed in the storage racks.
5.6.2 The k,ff for new fuel for the first co e loading stored dry in alternate rows and columns in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 60'6".
CAPACITY 5.6.4 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 800 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
SAN ONOFRE-UNIT 2 5-7 AMENDMENT NO. 39
r TABLE 5.7-1 COMP 0NENT CYCLIC OR TRANSIENT LIMITS z
E S
DESIGN CYCLE CYCLIC OR l
p; l
/_
COMP 0NENT TRANSIENT LIMIT OR TRANSIENT from < 200 F z
Heatupcgcle-Tto > 545 F; coo 188Sn cycle -
El Reactor Coolant System 500 system heatup and cooldown cycles at rates < 100*F/hr.
T,yg from > 545*F to i 200 F.
500 pressurizer heatup and Heatup cycle - Pressurizer temperature from < 200*F to > 653*F; cooldown cooldown cycles at rates l
$ 200*F/hr.
> 653'F to 5 200'F 10 hydrostatic testing cycles.
RCS pressurized to 3125 psia with l
RCS temperature in accordance with l
Specification 3.4.8.
200 leak testing cycles.
RCS pressured to 2250 psia with RCS
'r temperature greater than minimum for hydrostatic testing, but less than co minimum RCS temperature for critically.
200 seismic stress cycles.
Subjaction to a seismic event equal to one half the design basis earthquake (DBE).
480 cycles (in any combination)
Trip from 100% of RATED THERMAL of reactor trip, turbine trip power; turbine trip (total load rejection) from 100% of with delayed reactcr trip, RATED THERMAL POWER followed or complete loss of forced by resulting reactor trip; reactor coolant flow.
simultaneous loss of all Reactor Coolant Pumps at 100% of RATED THERMAL POWER.
- M
'TMM M N'h NFtr-
o,,
UNITED 1 TAT 03
+
[
g NUCLEAR REGULATORY COMMISSION t
wAsmworow, p. c. 2 ossa
\\*...*/
t 10VTHERNCALIFORNIAEDISONCOMPANY
~
SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THECITYOFANAbEIM, CALIFORNIA DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY GPERATING LICENSE Amendment No. ')8 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 2 (the facility) filed by 'he Southern California Edison Company on behalf of itself and Sa1 Diego Gas and Electric Company, The City of Riverside and the City of Anaheim, California (licensees) dated August 23, October 10 ani 16,1985, comply with the standards and requirements of the Atonic Energy Act of 1951, as amended (the Act) and the Comission's regvlations as set forth in 10 CFR Chapter It 8.
The facility will operate in conformity with the applica, ion, as amended, the provisions of the Act, and the regulations of the Comission; C.
There is rsasonable assurance:
(i) that the activities authorized by this amendment can be conducted withcut endangering the health and safety of the public, and (ii) that such activities will le ~
conducted in complitnce with the Commission's regulations set' forth in 10 CPR Chapter It
\\
D.
The issuance of,tnis license amendment will not be inimical to th>r common defense and security or to the health and safety of the public; E.
The issuance of this amendment.$s in accordance with 10 CFR Part 51 of the Comission's regulations and 'all applicable requirements have been satisfied.
/
Y N
9 s
. 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. 28, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective immediately and is to be fully implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION orge
Attachment:
Changes to the Technical Specifications Date of Issuance:
DEC2 1985 f
I DEC 2 1985
- ,,. i ATTACHMENT TO LICENSE AMENDMENT HC.' 28 FACILITY OPERATING LICENSE NO. NPF-15 1
DOCKET NO. 50-362 t
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
'i 5-6 5-5 5-7 5-8 l
w F
p 4
f 1
9 s
SAN cuoFRE NUCLEAR SENERATING STATION UMTS1,243 O
OO g
g
=.:
\\
=.:
- idt, SCALE m PttT
/
== + in ese ans me (g*
s*
f f l#
erYea )&
w "aggy
{ r
(
s, r l
as r l
l I
i
/
)cv
/
~
m f
~.
,/
s SITE BOUNDARY FOR LIQUID EFFLUENTS FIGURE 5.1-4
(
SAN Of40FRE-UNIT 3 5-5
DESIGN FEATURES
- 5. 3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core'shall contain 217 fuel assemblies with each fuel assembly containing a maximum of 236 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of 150 inches and contain a maximum total weight of 1900 grams uranium. The initial core loading shall have a maximum enrichment of 2.91 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.1 weight percent U-235.
CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 83 full length and 8 part length control element assemblies.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
In accordance with the code requirements specified in Section 5.2 of a.
the FSAR with allowance for normal degradation pursuant of the applicable Surveillance Requirements, b.
For a pressure of 2500 psia, and For a temperature of 650*F, except for the pressurizer which is c.
700"F.
SAN ONOFRE-UNIT 3 5-6 AMENDMENT NO. 28
DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 11,800 + 600/-0 cubic feet at a nominal T,yg of 582.1*F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:
A k,ff equivalent to less than or equal to 0.95 when flooded with a.
unborated water, which includes a conservative allowance for uncer-tainties as' described in the FSAR.
b.
A nominal 12.75 inch center-to-center distance between fuel assemblies placed in the storage racks.
5.6.2 The k,ff for new fuel for the first core loading stored dry in alternate rows and columns in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 60'6".
CAPACITY 5.6.4 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 800 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
2, SAN ONOFRE-UNIT 3 5-7 AMENDMENT NO. 28
m,
.m._
TA8LE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS i
E*
DESIGN CYCLE E
CYCLIC OR E:-
COMPONENT TRANSIENT LIMIT OR TRANSIENT
-d Reactor Coolant System 500 system beat.up and cooldown Heatup cycle - T from t 200?F to > 545'F; coo 1850n cycle -
cycles at rat $s < 100*F/hr.
T,,
from 1 545?F to 1 200*F.
j 500 pressurizer heatup and Heatup cycle - Pressurizer temperature 1 653'F to i 200'F,53?F; cooldown from < 200?F to > 6 cooldown cycles at rates
_ 200*F/hr.
10 hydrostatic testing cycles.
RCS pressurized to 3125 psia with RCS temperature in accordance with
~
Specification 3.4.8.
T 200 leak testing cycles.
RCS pressured to 2250 psia with RCS temperature greater than minimum'for hydrostatic testing, but less than minimum RCS temperature for critically.
1 200 seismic stress cycles.
Subjection to a seismic event-equal i
to one half the design basis earthquake (DBE).
480 cycles (in any combination)
Trip from 100% of RATED THERMAL of reactor trip, turbine trip power; turbine trip (total with delayed reactor trip, load rejection) from 100% of RATED THERMAL POWER followed or complete loss of forced by resulting reactor trip; reactor coolant flow, simultaneous loss of all Reactor Coolant Pumps at 100% of RATED THERMAL POWER.
M 9
e,