ML20033H257
| ML20033H257 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/26/1990 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033H258 | List: |
| References | |
| NUDOCS 9004190044 | |
| Download: ML20033H257 (8) | |
Text
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UNITED STATES
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1 NUCLEAR RE@ULATORY COMMISSION i
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- j I^L, SOUTHERN CALIFORNIA EDISON COMPANY i
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SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE CALIFORNIA I
q THE CITY OF ANAHEIM.-CALIFORNIA-DOCKET N0. 50-361-l SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 2 l
-AMENDMENT TO FACILITY OPERATING LICENSE a
Amendment No. 84
-License No. NPF-10
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The Nuclear Regulatory Comission (th'e Comission). hasLfound that:
A.
The application for amendment to the license for San Onofre-Nuclear Generating Station, Unit 2 (the facility) filed by Southern California Edisnn Company (SCE) on behalf of itself and.-San Diego. Gas and Electric Company, the City of Riverside,
. California and the City.of Anaheim,-California (licensees).
dated December 1, 1989, complies with.the standards and requirements.of the Atomic Energy Act of 1954, asiamended (the Act)', and the Comission's regulations set forth in-10 CFR. Chapter 1;-
B.
The facility will operate in conformity with the-application, the provisions of the Act, and'the regulations of.the Comission; C.
There is reasonable assurance (1) that:theiactivities 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;l 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 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-Speci-l-
fications as indicated in the attachment to this-license amendment, and paragraph 2.C(2)ofFacilityOperating-LicenseNo'.NPF-10ishereby amended to read as follows:
(2),TechnicalSpecifications' The Technical Specifications contained-in Appendix A, and the Environmental Protection Plan contained in Appendix B..
as revised through Amendment No. 84
,_are hereby incorporated in the' license. SCE shall operate the facility in accordance!
with the Technical' Specifications and the Environmental Protection Plan, 1
3.
This license amendment-is-effective as of the date of its' issuance and-must be fully implemented no 1ater than 30 days from the date of issuance,
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a FOR THE NUCLEAR REGULATORY COMMISSION D
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q Charles M. Trammell III, Acting Director Project Directorate V
~ Division of Reactor Projects - III, l
IV, Y and'Special' Projects.
t Office'of Nuclear Reactor Regulation.
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Attachment:
Changes to the Technical Specifications Date of Issuance:
February 26, 1990
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ATTACHMENT TO LICENSE AMENDMENT NO. 84 FACILITY-OPERATING LICENSE NO. NPF-10 j
DOCKET N0.250-361
. Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by-amendment' number and contain a marginal line indicating the area of. change, Also enclosed is the following overleaf page to the' amended page.
s AMENDMENT PAGE OVERLEAF PAGE 3/4 3-33 3/4 3-34
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TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUNENTATION SURVEILLANC
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CHAT! EEL N0 DES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E
FUNCTIONAL UNIT.
CHECK CALIBRATION TEST.
IS REQUIRED Q
11.
FUEL HANDLING ISOLATION (FHIS) m a.
Manual (Trip Buttons)
N.A.
N.A.
R.
M.A.
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b.
Airborne Radiation
- i. Gaseous S
R M
Automatic Actuation Logic N.A.
N.A.
R(3) c.
i 12.
CONTAlletENT PURGE ISOLATION (CPIS) j I
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a.
Manual (Trip Buttons)
N.A.
N.A.
-(6)
N.A.
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b.
Airborne Radiation i.
Gaseous S
(6)
M 1,2,3,4,6-
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R 11.
Particulate W
(6)
M 1,2,3,4,6 iii. Iodine W
(6)
.M 6
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Containment Area Radiation g
(Gamma)
S (6)
M-1,2,3,4,6 l
1 d.
Automatic Actuation Logic M. A.-
N. A.,
(3), (6) 1,2,3,4,6.
4 TABLE NOTATION i
(1) Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(2) Deleted.
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(3) -Testing of Automatic Actuation Logic shall include energization/de-energization of each initiation relay and verification of the OPERABILITY.of each' initiation relay..
j (4)
A subgroup relay test shall be performed which shall-include the energization/de-energization of each E
subgroep relay and verification of the OPERABILITY of g
during plant operation shall.be' limited to only those.each. subgroup relay. Relays ~ exempt from testing 3
relays associated with plant equipment which g
' cannot be operated-during plant operation.
Relays not testable during plant operation shall be tested during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless' tested during the previous 6 months.
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g (5) Actuated equipment only; does not. result in CIAS.
j (6) At least once per refueling interval.
With irradiated fuel in the storage pool.
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'4 NUCLEAR REGULATORY COMMISSION '
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.3 SOUTHERN CAllFORNIA EDISON COMPANY l-SAN DIEGO GAS AND ELECTRIC COMPANY.
THE CITY 0F RIVER $1DE. CALIFORNIA
.THE CITY OF: ANAHEIM, CALIFORNIA-DOCKET NO. 50-362' s
L SAN ONOFRE NUCLEAR GENERATING STATION, UNIT /NO 3 AMENDMENT TO FACILITY OPERATING LICENSE-d Amendment No. 74 License No. NPF-15 1.
The Nuclear. Regulatory Comission (the Comission) has found that:
A.
-The application for amendment to the license for-San Onofre NuclearGenerating' Station, Unit.3(thefacility)filedby-Southern California Edison Company (SCE) on behalf of itself and San Diego Gas and Electric Company, the City of Riverside, i-California and'the City of' Anaheim, California (licensees) dated December 1, 1989, complies with the standards,and requirements of the Atomic Energy Act of-1954, as amended (the Act), and the Comission'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 regulations of the Comission; C..
There.isreasonableassurance~(i).thattheactivities. 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;.
D.
The issuance of this amendment ~ will not~ be inimical / to the comon.
defense and security or to the heal.th and safety of the public; and i
E.
The issuance of this amendment is in accordance.with 10 CFR Part
[
51_ of 'the Comission's-regulations and a11' applicable requirements j
have been satisfied.
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2.
Accordingly, the license is amended by changes'to the Technical Speci-1 fications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-15'is hereby
. amended-to read as follows:
(2) Technica1' Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B,-
as, revised through Amendment.No. 74 =, are hereby incorporated in the. license..SCE shall operate the facility-in'accordance with the Technical Specifications and.the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and must be fully implemented no later than_30 days from the date of issuance.
FOR THE-NUCLEAR REGULATORY COMMISSION o
N(
Charles M. Trame11III, Acting Director Project Directorate V Division of Reactor, Projects'- III,
'IV, V and Special Projects Office of Nuclear Reactor Regulation.
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 26, 1990 t
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ATTACHMENT; TO LICENSE AMENDMENT NO.74' FACILITY OPERATING LICENSE NO. NPF-15 l:
DOCKET NO. 50-362 Revise Appendix A Technical Specifications by removing the page identified; below and inserting the enclosed page. The revised page is identified by amendment' number and. contain a marginal line indicating the area of change. '
j Also enclosed is the following overleaf.page to the' amended page.
AMENDMENT PAGE
- OVERLEAF PAGE' 3/4.3-33 3/4 3-34 b
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' TABLE 4.3-2 (Continued)
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l-ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION SURVEILLANCE REQUIREE NTS
=
CHANNEL MDOES FOR WICH.
i E
CHANNEL CHANNEL FUNCTIONAL-SURVEILLANCE l
Q FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED w
i 11.
FUEL HANDLING ISOLATION (FHIS)
~
i a.
Manual (Trip Buttons)
N.A.
N.A.
R N. A.~
b.
Airborne Radiation ~
- i. Gaseous S
R M
- 11. Particulate / Iodine 5
R M
c.
Automatic Actuation Logic N.A.
N.A.
R(3) 12.
CONTAIMENT PURGE ISOLATION (CPIS) l
'a.
Manual'(Trip Buttons)
-N.A.
N.A.
(6)
N.A.
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b.
Airborne Radiation '
1.-
Gaseous S
(6)
M
.1,2,3,4,6 wa 11.
Particulate W
'(6)
M 1,2,3,4,6 2
111. Iodine W
(6)
M 6
c-c.
Containment Area Radiation i
(Gamma).
5 (6)
M 1,3,3,4,6 d.
Automatic Actuation Logic M.A.
N.A.
(3),(6) 1,2,3,4,6-l.
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TABLE NOTATION i
(1) Each train or logic channel.shall be tested at least every 62 days on a STAGGEREE TEST BASIS.
I (2) Deleted.
.1 E
(3) Testing of Automatic Actuation Logic shall include energization/de-energization of-.each initiation:
g relay and1 verification of the 07ERABILITY of each initiation relay.
- $ _ '(4) A subgroup relay test shall be perfomed which shall include the energization/de-energization of each subgroup relay and verification of the OPERABILITY.of each subgroup relay.. Relays exempt from testing j
during_ plant operation shall be~1imited 'to only those relays associated with plant equipment which F
z 1
o cannot be operated during plant operation.
Relays not testable during plant' operation shall.be tested-l
-during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless'. tested during the. previous 6 months.
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(5) Actuated equipment only; does not result in CIAS.
(6) At least once per refueling interval.
With irradiated fuel in the storage pool.
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