ML20215E946
| ML20215E946 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/12/1986 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215E948 | List: |
| References | |
| TAC-62846, TAC-62847, NUDOCS 8612230183 | |
| Download: ML20215E946 (14) | |
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION t,
j WASHINGTON, D. C. 20665 c,
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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 NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment fo. 56 License No. NPF-10 1.
The Nuclear Regulatory Consnission (the Comission) has found that:
A.
The applications for amendment to the license for San Onofre Nuclear GeneratingStation, Unit 2(thefacility)filedbytheSouthern California Edison Company on behalf of itself and San Diego Gas and California (pany, The City of Riverside aad the City of Anaheim, Electric Com licensees)datedJune13andAugust 28, 1986, as supplemented by letter dated November 4,1986, comply with the standards and requirements of the Atomic Energy Act of 1954, as sended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the applications, as amended, the provisions of the Act, and the regulations of the Comission; 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 Consnission's regulations set furth 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.
P
. 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. 56, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, t
3.
The changes in the 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 5)ecifications existing at the time. The period of time during changeover stall be minimized.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
_C y
i Harry Rood, Senior Project Manager PWR Project Directorate No. 7 Division of PWR Licensino-B
Attachment:
Changes to the Technical Specifications Cate of Issuance: DEC 12 W a
1
12/12/86 I
s ATTACHMENT TO LICENSE AMENDMENT NO. 56 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 Peplace 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 3-25 3/4 3-26 3/4 9-6 3/4 9-5 o
I
%f
1 m
R TA8tE 3.3-4 (Continued)
A 8
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES
'?
E ALLOWABLE FUNCTIONAL UNIT TRIP VALUE VALUES
=
11.
FUEL HANDLING ISOLATION (FHIS) a.
Manual (Trip Buttons)
Not Applicable Not Applicable b.
Airborne Radiation
- i. Gaseous (8)
(8) ii. Particulate / Iodine 5 5.7 x 104 cpm **
1 6.0 x 104 cpe**
w1 c.
Automatic Actuation Logic Not Applicable Not Applicable m
- 12. CONTAllmENT PURGE ISOLATION (CPIS) 1 a.
Manual (Trip Buttons)
Mct Applicable Not Applicable b.
Airborne Radiation i.
Gaseous (6)(7)
(6)(7)
- 11. Particulate (6)(7)
(6)(7) iii. Iodine (6)(7)
(6)(7)
Ng c.
Containment Area Radiation (Gamma) i 325 mR/hr (M00ES 1-4)
$ 340 mR/hr (MODES 1-4)
R i 2.4 mR/hr (MDOE 6) 5 2.5 mR/hr (MODE 6) 4 d.
Automatic Actuation Logic Mot Applicable Not Applicable E
c
v.
TABLE 3.3-4 (Continued) g s
og TABLE NOTATION E
(1) Value may be decreased manually, to a minimum of greater than or equal to 300 psia, as pressurizer Q
pressure is reduced, provided the margin between the pressurizer and this value is maintained at less than or equal to 400 psia;* the setpoint shall be increased automatically as pressurizer pressure u
is increased until the trip setpoint is reached. Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer is greater than or equal to 400 psia.
1 I
(2) Value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi;* the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is l
reached.
(3) % of the distance between steam generator upper and lower level instrument nozzles.
m1 (4) Inverse time relay set value 3165V, trip will occur within the tolerances specified in Figure 3.3-1 m4 for the range of bus voltages.
cn (5) Actuated equipment only-does not result in CIAS.
l (6) The trip setpoint shall be set sufficiently high to prevent spurious alarms / trips yet sufficiently low to assure an alarm / trip should an inadvertent release occur.
(7) Prior to the completion of DCP 53N, the setpoints for Containment Airborne Radiation Monitor 2RT-7804-1 shall be determined by the ODCM.
(8) The trip setpoint shall be set sufficiently high to prevent spurious alare/ trips yet sufficiently low i
to assure an alare/ trip should a fuel handling accident occur.
E g
Variable setpoints are for use only during normal, controlled plant heatups and cooldowns.
m Above normal background.
.E l
REFUELkNGOPERATIONS #
3/4.9.5 COM UNICATIONS LINITING CON 0! TION FOR OPERATION 3.9.5 Direct communications shall be maintained between the control room and personnel at the refueling station,
,. ~
APPt,1CA8!LITY:
Ouring CORE ALTERATIONS.
ACTION:
When direct communications between the control room and personnel at the refueling station cannot be maintained, suspend all CORE ALTERATIONS.
i SURVEILLANCE REQUIREMENTS 4.9.5 Of rect communications between the control room and personnel at the refueling station shall be demonstrated within one hour prior to the start of and,at least once par 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS.
I 4
5AN ONOFRE-UNIT 2 3/4 9-5 S
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, -.. - - - - - - + - - - --
REFUELING OPERATIONS
.3/4.9.6 REFUELING MACHINE LIMITING CON 0! TION FOR OPERATION 3.9.6 The refueling machine shall be used for movement of fuel assemblies with or without CEAs and shall be OPERABLE with:
a.
A minimum capacity of 3200 pounds, and b.
An overload cut off limit of less than or equal to 3550 pounds.
The refueling machine auxiliary hoist may be used for the movement of CEAs without fuel bundles and shall be OPERABLE with an overload cut off limit of less than or equal to 1000 pounds.
APPLICA81LITY: During movement of CEAs and/or fuel assemblies within the reactor pressure vessel utilizing the refueling machine auxiliary hoist or refueling machine.
TI : With the requirements for the refueling machine OPERABILITY not sa s fed, suspend all refueling machine operations involving the movement of fuel assemblies with or without CEAs within the reactor pressure vessel. With the requirements for the refueling machine auxiliary hoist not satisfied, suspend all refueling machine auxiliary hoist operations involving the movement of CEAs within the reactor pressure vessel.
SURVEILLANCE REQUIREMENTS 4.9.6 The refueling machine used for movement of fuel assemblies with or without CEAs within the reactor pressure vessel shall be demonstrated OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of such operations by performing a load test of at least 3200 pounds and demonstrating an automatic load cut off when the refueling machine load exceeds 3550 pounds. The refueling machine auxiliary hoist used for movement of CEAs within the reactor pressure vessel shall be demonstrated OPERA 8tE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of such operations by demonstrating an automatic load cut off when the auxiliary hoist load exceeds 1000 pounds.
SAN ON0FRE - UNIT 2 3/4 9-6 ANENOMENT NO. 56
A UNITE 3 STATES f
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NUCLEAR REGULATORY COMMISSION g
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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 NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 45 License No NPF-15 l
1.
The Nuclear Regulatory Comission (the Comission) has found that:
l A.
The applications for amendment to the license for $an Onofre Nuclear Generating Station, Unit 3 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and California (pany The City of Riverside and the City of Anaheim, Electric Com licensecs) dated June 13 and August 28, 1986, as supplemented by letter dated November 4, 1986, 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; D.
The facility will operate in conformity with the applications, as amended, the provisions of the Act, and the regulations of the Comission; i
C.
There is reasonable asst.rance:
(1)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 Corsnission's regulations set forth in 10 CFR Chapter I; i
D.
The issuance of this license arandment 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 appitcable requirements have been satisfied.
+
4 2
2.
Accordingly, the license is 6 mended 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 ravised I
through Amendment No. 45, 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 the 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 5)ecifications existing at the time. The period of time during changeover siell be minimized.
4 This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION D
Ha y
- d. Senior Project Manager l
PWR Project Directorate No. 7 Division of PWR Licensing-B l
Attachment:
Changes to the Technical Specifications i
Date of issuance: DEC 121996 i
I J
P Y
2
12/12/86
, ATTACHMENT TO LICENSE AMENOMENT NO. 45 FACILITY OPERATING LICENSE NO. NPF-15 i
DOCKET NO. 50-362 Replace the following pages of the Appendix A Technical Specifications with the enclosed paces. 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 3-25 3/4 3-26 3/4 9-6 3/4 9-5 k_
TA8LE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTR 15ENTATION TRIP VALUES a
i m
1 5
ALLOWA8tE h
FUNCTIONAL UNIT TRIP VALUE VALUES
[
- 11. FUEL HANDLING ISOLATION (FHIS) a.
Manual (Trip Buttons)
Not Appitcable Not Applicable b.
Airborne Radiation
- i. Gaseous (8)
(8) li. Particulate / Iodine 5 5.7 x 104 cpm **
i 6.0 x 104 cpm **
c.
Automatic Actuation Logic Not Applicable Not Applicable
,s 12.
CONTAlloqENT PURGE ISOLATION (CPIS)
E$
a.
Manual (Trip Buttons)
Not Applicable Not Applicable b.
Airborne Radiation 1.
Gaseous (6)(7)
(6)(7) 11.
Particulate (6)(7)
(6)(7) lii. Iodine (6)(7)
(6)(7)
E c.
Containment Area Radiation (Gamma)
< 325 mR/hr (N00ES 1-4)
< 340 mR/hr (pe0ES 1-4) 52.4mR/hr(Mode 6) 32.5mR/hr(N00E6) z d.
Automatic Actuation Logic Not Applicable Not Applicable E
TABLE 3.3-4 (Continued) j E
l TABLE NOTATION o
E2
'?
(1) value may be decreased manually, to a minimum of greater than or equal to 300 psia, as pressurizer E
pressure is reduced, provided the margin between the pressurizer and this value is maintained at O
less than or equal to 400 psia;* the setpoint shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reacheda Trip may be mar.ually bypassed below 400 psia; o
bypass shall be automatically removed whenever pressorizer is greater than or equal to 400 psia.
(2) Value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi;* the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.
(3) % of the distance between steam generator upper and lower level instrument nozzles.
R (4) Inverse time relay set value 3165V, trip will occur within the tolerances specified in Figure 3.3-1 for the range of bus voltages.
Yg (5) Actuated equipment only; does not result in CIAS.
l (6) The trip setpoint shall be set sufficiently high to prevent spurious alarms / trips yet sufficiently l
low to assure an alarm / trip should an inadvertent release occur.
(7) Prior to the completion of DCP 53N, the setpoints for Containment Airborne Radiation Monitor 3RT-7804-1 shall be determined by the 00CM.
(8) The trip setpoint shall be set sufficiently high to prevent spurious alare/ trips yet sufficiently low to assure an alarm / trip should a fuel handling accident occur.
g
.Variable setpoints are for use only during normal, controlled plant heatups and cooldowns.
5 Above normal background.
.E O
k
[
REFUELING OPERATIONS 3/4.9.5 COMMUNICATIONS LIMITING CON 0! TION FOR OPERATION 3.9.5 Direct communications shall be maintained between the control room and personnel at the refueltng station.
APPLICA8!LITY: Ouring CORE ALTERATIONS.
ACTION:
When direct communications between the control room and personnel at the refueling station cannot be maintained, suspend all CORE ALTERATIONS.
=
f 50RVEIlL.ANCE REQUIREMENTS 4.9.5 Direct communications between the control rcom and personnel at the refueling station shall be demonstrated within one hour prior to the start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during COPE ALTERATIONS.
0 k
e a
D 4
SAN ONOFRE - UNIT 3 3/4 9 5
REFUELING OPERATIONS 3/4.9.6 REFUELING MACHINE LIMITING CONDITION FOR OPERATION 3.9.6 The refueling machine shall be used for movement of fuel assemblies with or without CEAs and shall be OPERABLE with:
i I
a.
A minimum capacity of 3200 pounds, and
(
b.
An overload cut off limit of less than or equal to 3550 pounds.
The refueling machine auxiliary hoist may be used for the movement of CEAs without fuel bundles and shall be OPERA 8LE with an overload cut off limit of less than or equal to 1000 pounds.
APPLICA81LITY: During movement of CEAs and/or fuel assemblies within the reactor pressure vessel utilizing the refueling machine auxiliary hoist or refueling machine.
ACTION: With the requirements for the refueling machine OPERABILITY not satisfied, suspend all refueling machine operations involving the movement of fuel assemblies with or without CEAs within the reactor pressure vessel. With the requirements for the refueling machine auxiliary hoist not satisfied, suspend all refueling machine auxiliary hoist operations involving the movement of CEAs within the reactor pressure vessel.
$URVE!LLANCE REQUIREMENTS 4.9.6 The refueling machine used for movement of fuel assemblies with or with-out CEAs within the reactor pressure vessel shall be demonstrated OPERA 8LE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of such operations by performing a load test of at least 3200 pounds and demonstrating an automatic load cut off when the refueling machine load exceeds 3550 pounds. The refueling machine auxiliary hoist used for movement of CEAs within the reactor pressure vessel shall be demonstrated OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of such operations by demonstrating an automatic load cut off when the auxiliary hoist load exceeds 1000 pounds.
SAN ONOFRE - UNIT 3 3/4 9-6 AMEN 0 MENT NO. 45
.