ML20024H616
| ML20024H616 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  (NPF-10-A-093, NPF-10-A-93, NPF-15-A-083, NPF-15-A-83) |
| Issue date: | 06/03/1991 |
| From: | Kokajko L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20024H617 | List: |
| References | |
| NUDOCS 9106070047 | |
| Download: ML20024H616 (10) | |
Text
po e%
/['
),
UNITED sTAl[s
'i NUCLE AR REGULATORY COMMISSION
{ g,W l
~+
neumoN,o e cons tA e
gv.....f SOUTHERN CALIFOP.NIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHE!M. CAllFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATlHG LICENSE Anendment No. 93 License No. NPF-10 1.
The Nuclear Regulatory Conmission (the Connission) has found that:
A.
The application for anendment by Southern California Edison Company, San Diego Gas and Electric Company, the City of Riverside,) (the California, and the City of Anaheim California (licensees licensee) dated April 8,1991, 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 !!
B.
The f acility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i
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 Connission'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 Connission's regulations and all applicable requirements have been satisfied.
1 0106070047 9106n3 PDR ADGCE 05000361 1
P POR
f l
~2*
i a
2.
Accordingly, the license is ownded by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of f acility Operating License No. NPT 10 is hereby amended to read as follows:
i 4
(2) Technical Specifications The Technical $pecifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 93, are hereby incorporated in the license.
Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental e
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 COMMIS$10N tlk b. b bV f
James E. Dyer, Director
]
Project Directorate V DivisionofReactorprojects!!!/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications-Date of Issuance: June 3,1991 i
i Y
,,, g n y w_,.
,.n.,,,,,_,,.,n--,--,n-_,,nn.~,,-,,,m.-w.,-,e.w,-,-,,,-n_.
A1TACHMENT TO QCEN!E Al:El DPEHT NO. 93 I M ILIT) (ILP/T'.f!G LICENSE NO. NPF-10 DLCLET NO.60-361 4
Revise Apreidix A Technical $pecifications by removing the pagts idtntified belcw and inserting the enclosed rages.
The revised pages are identified by the captioned etendment nutber and contain marginal lines indicating tLe areas of change. The corresponcir.g overleaf pages are also provictd to maintain document completenes>.
REMOVE IN$E_RT 3/4 6-2 3/4 6-2 B 3/4 6 1 D 3/4 6-1 t
i i
k I
I l
e l
8,a sum4, Ut/ITE D sT A f t s
/T
'n NUCLE AR RCGULATORY COMMISSION nasanoN, o a rotu
->u Y N. e!
s.....
SOUTHERN _CALIFORNI A EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE _ CITY OF RIVER $1DE. CAllFORNIA THE CITY OF ANAHE1M. CAllFORNIA DOCKET NO 50-362 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATIN,G LICENSE Amendnent No. 03 License No NPr.15 1.
The Nuclear Regulatory Corr.nission (the Conrnission) has found that:
A.
The application for amendment by Southern California Edison Company, San Diego Gas and Electric Company, the City of Riverside, California, and the City of Anaheim California (licensees) (the licensee) dated April 8,1991, conpItes with the standards and requirements of t1e Atomic Energy Act of 1954, as anended (the Act),
and the Connission'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 Connission's regulations; D.
The issuance of this amendment will not be inimical to the common i
defense and security or to the health and safety of the public; and E.
The issuance of this anendment is in accordance with 10 CFR part 51 of the Connission's regulations and all applicable requirenents have been satisfied.
I i
I w
._.4 w
...s w.w e
v..
+
i i
l 2
J l
I 2.
Accordingly, the license is amended by changes to the Technical Spect-fications as indicated in the attachnent to this license amendment, and paragraph 2.C(2) of racility Operating License No. NPr.15 is hereby amended to read as tollows:
1 (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix 0, as revised through Amendment No. 83, are hertby incorporated in the license.
Southern California Edison Company shall operate the facility in
~
accordance with the Technical Specifications and the Environmental Protection Plan.
4 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
$UdCf.
bV mes E. Dyer, Director Project Directorate V Division of Reactor Projects Ill/lV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of 1ssuance: June 3,1991 l
l I
L
\\a-
~ -....
...._ _ _ _ _.. _ _ _ ~ _ -. _ _ _ _. _ _
i l
ATT ACkf4ENT TO LICEli!L tl'El'N'ENT NO..
83 l
FACIL11Y Orff;AlltG L!CriSE f:0, f:PF-15 I
D_0CKET I0. 50-302 t
"evise Arpendix A Techtiical $pecifitoticus by removing the pagts it:tntified tolu: ($ tr. set tirig tit uiclosed pages. The rtvitod pages are identifh.d ty the captioned annendinetit nutter and contain riargirial lines itidicating tiet drecs of charige. The currespot.dirig overleaf pages are also provided tu laali,tain documtnt ccepleteness, kEt:0\\E INSERT r
3/4 6-2 3/4 6-2 L 3/4 6-1 b 3/4 6 1 b
I k
L
3/4.6 CONTAINMENT SYSTEMS l
3/4.6.1 PRIMARY CONTAINMENT i
CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION
- 3. 6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY:
MODES 1, 2, 3 and 4 ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in CO SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS
- 4. 6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
At least once per 31 days by verifying that all penetrations
- listed a.
in Sections A, B and C of Table 3.6-1 not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed.by valves, blind flanges, or automatie valves secured ** in their positions, except as provided in Table 3.b-1 of Specification 3.6.3.
b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.-
1 After each closing of each penetration subject to Type B testing, c.
except, containment air locks, if opened following a Type--A or B test, by leak rate testing the seal with gas at P, 55.7 psig and verifying that when the measured leakage rate for these sea $_ is added to the leakage rates determined pursuant to Specifica-
. tion 4.6.1.2.d for all other Type B and C_ penetrations, the combined leakage rate is-less_than 0.60 L,.
s t
- Except valves, blind. flanges,-and automatic valves which are located inside the cor*C nment and are locked, sealed or otherwise_ secured in the closed position.
These penetrations shall be verified closed during each COLD SHF.WN except that such verification need not be performed more often,than per 92 days.
o r '_
- L.Ked, sealed or otherwise p^revented from unintentional operation.
5 N ONOFRE-UNIT 2 3/4 6-1 AMENOMENT NO. 46
~~. - - -
j j
CONTAINFENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6,1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1.
Less than or equal to L 0
containmentairper24So,urs.10percentbyweightofthe at P,, 55.7 psig, or i
2.
Less than or equal to L 0
containmentairper24bo,urs.05percentbyweightofthe at a reduced pressure of P '
t 27.9 psig.
b.
A combined leakage rate of less than 0.60 L for all penetrations and i
3 valvessubjecttoType8andCtests,when$ressurizedtoP,.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With'either (a) the measured overall integrated containment leakage rate exceeding 0.75 L or 0.75 L, as applicable, or (b) with the measured combined leakagerateforallpenetrktions-andvalvessubjecttoTypesBandCtests a
exceeding 0.60 L, restore the overall integrated leakage rate to less than or equal to 0.75 L,or less than or equal to 0.75 L, as applicable, and the combinedleakaglrateforallpenetrationsandvllvessubjecttoTypeBandC tests to less than 0.60 L temperature above 200'F,, prior to increasing the Reactor Coolant System SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 - 1972:
a.
Three Type A tests (Overall Integrated Containment Leakage Rate)-
shall be conducted at 40 + 10 month intervals during shutdown at either P service $e(riod.55.7 psig) or at-Pg (27.9 psig) during each 10 year Prior'to the Type A tests--a visual inspection shall be conducted in accordance with Specification 4.6.1.6 to demonstrate the containment structural integrity.-
1 SAN ONOFRE-UNIT 2 3/4 6-2 AMENDMENT NO. 93
~
, 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses, lhis' restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.
3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, P,.
As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L, or less than or equal to 0.75 L, as applicable during g
performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix J of 10 CFR 50.
The following exception, however, applies:
The third Type A test of each 10 year inservice interval, need not be conducted when the urit is shutdown for the 10 year plant inservice inspection.
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.
Surveillance testing of the air lock seals provides assurance that the cverall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
l t
l l
SAN ONOFRE-UNIT 2 B 3/4 6-1 AMENDMENT NO. 93
CCNTAINPENT SYSTEMS P
BASES 3/4.6.1.4
!NTERNAL PRESSURE The limitations en contain?ent interrai pressure ensure that 1) the ton-tainnent stru:t.re is :revented fr: et:eecing its design regative pressure differential with respect to the outside ateosphere of 5.0 psig. 2) the-t:n-tainment ceak pressure coes not excee: tne cesign pressure of 60 psig curing LOCA or steam line break conditions, and 3) the assumptions used for tre initial conditions of the LOCA safety analysis remain valid.
The maximum peak pressure expected to be obtained from a LOCA or steam line creak event is 55.7 psig.
The limit of 1.5 psig for initial positive c ntaincent prissure will limit the total ;ressure to $7.2 psig anich is less than the cesign pressure and is consistent with the accicent analyses.
3/4.6.1.5 AIR TEMPERATURE The limitation on containment average air temperature ensur.; that the overall containment average air temperature doss not exceed the initial y
temperature condition assumed in the accident analysis for a steam line break accident.
3/4.6.1.6 CONTAINPENT STRUCTURAL INTEGR!TY This limitation ensures that the structural int:;rity of the containment will be maintained comparable to the original design standards for the life of the facility.
Structural integrity is required to ensure that the containment will withstand the maximum pressure of 55.7 psig in the event of a steam line break accident.
The measurement of containment tendon li'c of f force, the tensile tests of the ter. don wires or strands, the visual examination of ten-dons, anchorages and exposed interior and exterior surfaces of the contain-ment, the chemical and visual examination of the sheathing filler grease, and the Type A leakage tests are sufficient to demonstrate this capability.
The surveillance requirements for demonstrating the containment's struc-tural integrity are in compliance with the recommendations of Proposed Revi-sion 3 to Regulatory Guide 1.35, " Determining Prestressing Forces for Inspec-tion of Prestressed Concrete Containments," April 1979; and Proposed Regula-tory Guide 1.35.1, " Inservice Surveillance of Ungrouted Tendons in Prestressed Concrete Containment Structures," April 1979.
s SAN ONCcRE-UNIT 2 B 3/4 6-2 AMENDMENT NO.16
...