ML20078D839
| ML20078D839 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  (NPF-15-A-008, NPF-15-A-8) |
| Issue date: | 09/16/1983 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078D841 | List: |
| References | |
| NUDOCS 8310040642 | |
| Download: ML20078D839 (14) | |
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.~4p SOUTHERN CAllFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY
,T, HE CITY 0F RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment ;40. 8 License No. HPF-15 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for license for the San Onofre Nuclear Generating Station, Unit 3 (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) complies 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 Comission; 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The Southern California Edison Company
- is technically qualifled to engage in the activities authorized by this operating license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; E.
The issuance of this license anenduent will not be inimical to the comen defense and security or to the health and safety of the public;
- lhe Southern California Edison Company is authorized to act as agent for the other co-owners and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
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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.
2.
Paragraphs 2.C(1), 2.C.(2) and 2.C(20) of Facility Operating License No.
NPF-15,.are hereby amended to read as follows:
(1) Maximum Power Level Southern California Edison Company (SCE) is _ authorized to operat'e
' the facility at reactor core power levels not in excess of full
. power (3390 megawatts' thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A'and the Environmental _ Protection Plan contained in Appendix B, as revised through Amendment No. 8, are hereby incorporated in the license.
SCE'shall operate-the facility in accordance with the Technical
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4 Specifications and the Environmental Protection Plan.
(20) Qualification of Auxiliary Feedwater (AFW) Pump Motor Bearings I
Prior to startup following the first refueling outage, SCE shall install and make operational the lubrication oil cooling system for the auxiliary feedwater pump motor bearings described in SCE's 1etter cf March 7, 1983. Prior to installation of the lube oil cooling system, SCE shall perform daily visual inspection of the r
steam lines in the AFW pump room in accordance with SCE's letter.
of July. 12, 1962.
4 3.
Paragraphs 2.C.(23) through 2.C(26) are hereby added to Facility Operating
. License NPF-15, as follows:
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(23) Fuel Assembly Shoulder Gap Clearance (SCE letter of July.25,1983)
Prior to entering-Startup (Mode 2) after each refueling, SCE shall' 4
'either provide a report that demonstrates that the. existing fuel element assembly (FEA) has sufficient available-shoulder gap clearance for at least the next cycle of operation, or identify to the NRC and implement a modified FEA design that has adequate shoulder gap clearance for at least the next cycle of operation. This comitment will apply until the NRC concurs that the shoulder gap clearance provided is i
adequate for the design life of the fuel.
(24) Isolation Capability for Primary EOF
.By January 1,1984 the primary EOF ventilation system shall' be modified i
to provide isolation capability as described in the SCE letter of-July 22,1983.
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(25) Correction of CPC Software Error At the first available outage of sufficient' duration (7l days in Mode 5)
- after February 2,1984,.SCE shall correct the software error in the Core Protection Calculators discussed in the SCE letters dated March 7, 1983 and' July 22, 1983.
'(26) Reporting of AFWS Failures'
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Until the first refueling outage, SCE shall provide a monthly; report
- describing any occurrences resulting in the degradation (including,.
but not limited to component failures, maintenance errors, and operator errors) of: the auxiliary feedwater system. The report shall identify the cause of such occurences. - This monthly report does not relieve the licensee from any existing requirements for Licensee Event Reports (LERs).
4.
In accordance with the Memorandum and Order (Ruling on Off-site Medical Services Issue), ASLBP 78-365-010L dated August 12, 1983. Paragraph
'2.C(18)c of. Amendment No. 4 is hereby deleted.
- 5. ' This lice'nse amendment -is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COFNISSION
/s Darrell G. Eisenhut, Director Division of Licensing Office.of Nuclear Reactor Regulation Date of Issuance:
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3-(25) Correction of CPC Software Error At the first available outage of sufficient duration (7 dus
' after February 2,1984,.SCE shall correct the sof tware error,in Mode 5) in the Core Protection Calculators discussed in the SCE letters ' dated March 7, 1983 and July 22, 1983.
4.
In accordance with the Memorandum and Order (Rul'ing or Off-site Medical Services Issue), ASLBP 78-365-010L dated August 12 1983, Paragraph 2.C(18)c of Amen &ent No. 4 is hereby deleted.
5.
This license amendment is effective as of the date of issuance.
FOR TH NUCLEAR REGULATORY COPHISSION arrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Date of Issuance:
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. (25) Correction of CPC Software Error At the first available outage of sufficient duration (7 days in Mode 5)-
af ter February 2,1984, SCE shall correct the software error'in the Core Protection Calculators discussed in the SCE letters, dated lurch 7, 1983 and July 22, 1983.
,/
4.
This license amendment is effective as of the date of issu/ance.
FOR THE NUCLEAR REGULATORY COMMISSION
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i Darrell G. Eisenhut, Director Division,0f Licensing Office,of Nuclear Reactor Regulation
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Date of Issuance:
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SEP 161983 ATTACHMENT T0' LICENSE AMENDMENT ~NO. 8 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO.-50-362 I
Replace the following pages of the Appendix A Technical Specifications wit'h the enclosed pages. The revised pages are identified by Amendment number and contain-vertical lines indicating the area of change.
Also to be replaced
-arejhe following overleaf pages to the. amendment pages.
Amendment Page Overleaf Page 3/4 3-59 3/4 3-60 3/4 3-61 5
3/4 3-62 I '-
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3/4 3-63 3/4 3-64 3/4 7-32 3/4 7-31 4
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TABLE 3.3-11 (Continued) i Zone Instrument Location Early Warning e Actuation HEATFLAMESM0Kg HEAT FLAME SM0KE 11 S.E.B. Roof and Main Steam Relief Valves None 2 (Note 1) 12 control Building Elev 50' Cable Riser Gallery Rm 305 3_
42 Cable Riser. Gallery Rm 315 3
40 13A Control Building Elev 50' Emgy. HVAC Unit Rm 309A 1
138 Control Building Elev 50' Emgy. HVAC Unit Rm 309B 1
14 Radwaste Elev 24' Boric Acid Makeup Tank Rm 204B None Boric Acid Makeup Tank Rm 204A None t
15 Control Building Elev 50' ESF.Switchgear Rm 308A 2
ESF Switchgear Rm 308B 2
- 05 Radwaste Elev 37' & 50' Ion Exchangers None 17 Diesel Generator Bdf1 ding Train A 3
4 Train B 3
4 18 Diesel Fuel Oil Storage Tank Underground Vaults None 20 Condensate Storage Tank T-121 None 21 Nuclear Storage Tank T-104 None 22 Auxiliary Feedwater Pump Room 2
9 6
(Note 2) 23 Fuel Handling Bldg Elev 30' Spent Fuel Pools Heat Exchange Room 209.
None 28 Penetration Elev. 30' 2
8 (Note 1)
SAN ON0FRE-UNIT 3
.3/4 3-59 dMEN0MENTNO.8
i TABLE 3.3-11 (Continued)
N, Early Warning Actuation Zor.e Instrument Location HEAT FLAME SM0KE HEAT FLAME SM0KE 29 Control Building Elev 30' Cable Riser Gallery Rm 236 3
51 Cable Riser Gallery Rm 224 3
52 30 Electrical Tunnel Elev 30'6" 13 50 31 Control Building Elev 30' 29 32A Control Building Elev 30' Fan Room Rm 219 & Corridor Rm 221 2
1 32B Control Building Elev 30'
{
Fan Room Rm 233 & Corridor Rm 234 2
1 34 Radwaste Elev 9' & 24' Secondary Radwaste Tank Rms 126A,B & 127A,B None 35 Radwaste Elev 9' & 24' 4
Spent Resin Tank Rms 125A,B None 36 Fuel Handling Building Elev 17'6" Spent Fuel Pool Pump Rm 107 2
37 Radwaste Elev 24' Letdown Heat Exchanger Rms 209A,B None 38 Radwaste Elev 24' Letdown Control Valve Rms 218A,B None 39 Radwaste Elev 24' Filter Crvd Tank Rm 216 None 40 Radwaste Elev 9' & 24' Primary Radwaste Tank Rms 211A,D None 41 Control Building Elev 9' Cable Spreaoing Rm 111A 17 36 Cable Spreading Rm 1118 14 36 42 Control Building Elev 9'
(
Cable Riser Gallery Rm 110 6
44 Cable Riser Gallery Rm 112 6
39 SAN ONOFRE-UNIT 3 3/4 3-60
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. TABLE 3.3-11 (Continued)
.c Early Warning Actuation Zone
, -Instrument Location -
-HEAT FLAME SM0KE
. HEAT FLAME SM0KE=
c 43-Control Building Elev 9'
,Emgy. Chiller Rm 115 2
Emgy. Chiller Rm 117 2
44 Intake Structure
-Pump Rm T2-106 4
-Pump Rm T3-106 4
.45 Penetration Area Elev 9' & 15' l
Piping Penetration. Area 15' 6 (Note 1) 48 Safety Equipment Building 9'
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CCW HX.and Piping Rm 022-025 None 50 Radwaste Elev 9' Charging Pump Rms 105A-F 6
51 Radwaste Elev 9' Boric Acid Makeup Tank d
Rms 105A-D None
.1 53 Electrical Tunnel Elev 9'6",
11'6", (-) 2'6" 21 54 54-Safety Eqpmt Bldg Elev 15'6" h down HX Rms 003, 004, 016, 018 None 55 Safety Eqpn.t Bldo Elev 8' Chemical: Storage Tank Rm 019 1
~56 Safety Eqpmt Bido Elev 8' Component Cooling Water Surge Tank Rms 020,.021 None 57 Safety Eqpmt Bldg Elev 15'6" Pump Rm 005 1
58 Radwaste Elev 37' Reactor Trip System Rms 308A-D,.309-A-C 9
59 Safety Eqpmt Bldg Elev 15'6" Pump Rm 001 1
SAN ONOFRE-UNIT 3' 3/4 3-61 AMENDMENT NO. 8 L-
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-TABLE 3.3-11 (Continued).
et Zone I Instrument Location Early Warning Actuation HEAT FLAME SM0KE HEAT FLAME SM0KE 60 Safety Eqpmt 81da Elev 15'6"
. Pump Rm 015 1
61 Safety Eqpmt Blda Elev 15'6" Component Cooling Water Pump.
Rms 006, 007, 008 3-62 Radwaste Elev 50' Volume Control Valve Rooms 2 (Note 1) 63 Control Building Elev 50'
' Corridor 12 64 Control Building Elev 50' Vital Power Distribution Rms 310A-H 8
65.
Control Building Elev 50' Battery Rms 3068-J 8
f,
,66 Control Building Elev 50' 4;;
Evacuation Rm 311 1
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67' Radwaste Elev 63'6" Cable Riser Gallery Rm 506A 2
4 Cable Riser Gallery Rm 506B 2
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68 Penetration 9' - 63'6" Cable Riser Shaft l'
21 s.,
69 Safety Eqpmt Bldg Elev 5'3" Salt Water Cooling Piping Rm~010 None 70 Radwaste Elev 24' Duct Shaft Rms 222A,B None 72 Control Building Elev 70' Corridor 401 4 (Note 3) 75 Refueling Water Storage Tank T-005 None 76 Refueling Water Storage Tank T-006 None SAN ONOFRE-UNIT 3 3/4 3-62
' AMENDMENT NO. 8 i
]
TABLE 3.3-11 (Continued)
Early Warning Actuation
-Zone Instrument Location HEAT FLAME SM0KE HEAT FLAME SM0KE 78 Control Building Elev 9' Corridor Rm 105 4
79 Control Building'Elev 50' ESF Switchgear Rm 302A 2
ESF Switchgear Rm 302B.
2 80 Radwaste Elev 37' & 50' Duct Shaft Rms None
-81 Radwaste Elev 63'6" Ouct Shaft Rms 527A,B None 83 Salt Water Cooling Tunnel
- 6*
84 Safety Eqpmt Bldg Elev 8' HVAC Rm 017 3
Technical Support Center (TSC) 5 1 (Note 3)
- 3 in UNIT 2, 3 in UNIT 3 Notes 1.
On completion of DCP 3-403E 2.
On completion of DCP 3-122M 3.
On completion of DCP 2-403E i
L SAN.ONOFRE-UNIT 3 3/4 3-63 AMENDMENT NO. 8
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INSTRUMENTATION
-RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION
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. 3.3.3.8 The radioactive liquid ' fluent monitoring instrumentation channels
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shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints-set to ensure-that the limits of_ Specification 3.11.1.1 are not exceeded.
The alarm /
trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (00CM).
APPLICABILITY:
At all times.
ACTION:
With a radioactive. liquid effluent monitoring instrumentation
. a.
channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive
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' liquid effluents monitored by the.affected channel or declare the channel inoperable.
r b.
With less than the minimum number of radioactive liquid effluent monitoring i.nstrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.
Additionally, if the inoperable-instruments-are not returned.to OPERABLE status.within 30 days, explain in the next Semi-annual-Radioactive Ef fluent Release Report why the inoperabilit*y was not corrected in a timely manner.
The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13b ara not c.
applicable.
s SURVEILLANCE-REQUIREMENf5 4.3.3.8.1 Each-radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.
4.3.3.8.2 At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at least one circulating w'ater pump shall be determined to be operating and provid'ng dilution to the discharge structure whenever dilution is required to meet the site radioactive effluent concentration limits of Specification 3.11.1.1.
SAN ONOFRE-UNIT 3 3/4 3-64
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F PLANT SYSTEMS R
- SURVEILLANCE ~ REQUIREMENTS-(Continued) 3.-
By a visual inspection of each spray / sprinkler head to verify -
the spray pattern is not obstructed,
'At least..once per 3' years by performing. an air flow test through e.
each open head spray / sprinkler _ header and verifying each open-head spray / sprinkler nozzle is unobstructed.
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- -SAN ONOFRE-UNIT 3 3/4 7.-31 1
TABLE 3.7-5 Safety Related Spray and/or Sprinkler Systems No. of Hazard Location Systems System Type Reactor Coolant Pumps Containment 4
Deluge-Water Spray R.R. Tunnel Fuel _ Hand. Bldg.
1 Wet Pipe Truck Ramp Radwaste Bldg.
1 Wet Pipe Cable Tunnel Section 1 1
Deluge-Water Spray
-Cable Tunnel
.Section 2 1
Deluge-Water Spray Cable Tunnel Section 3 1
Deluge-Water Spray Cable Tunnel Section 4 1
Deluge-Water Spray Cable Tunnel Section 5 1
Deluge-Water Spray Cable Tunnel Section 6 1
Deluge-Water Spray Cable Tunnel Section 7 1
Deluge-Water Spray Cable Tunnel Section 8 1
Deluge-Water Spray Cable Tunnel Cable Tunnel Section 9 1
Deluge-Water _ Spray Section 10 1
Deluge-Water Spray Cable Tunnel Riser Fuel Hand Bldg.
1 Deluge-Water Spray Cabl'e Gallery Radwaste Bldg.
2*
Deluge-Water Spray,
Cable Risers El. 9'ft.
Control Bldg.
2*
Deluge-Water Spray Cable Risers El. 30 ft.
Control Bldg.
2*
Deluge-Water Spray Cable Risers El. 50 ft.
Control Bldg.
2*
Deluge-Water Spray Cable Risers El. 70 ft.
Control Bldg.
2*
Deluge-Water Spray
'i Cable Spreading Room Control Bldg.
4*
Deluge-Water Spray W
Emergency A.C. Unit -
Train A Fuel Handling Bldg.
1**
Deluge-Water Spray Emergency A.C. Unit -
Train 8 Fuel Handling Bldg.
1**
Deluge-Water Spray Diesel Generator DG Bldg.
2 Pre-Action Sprinkler HVAC Room 309A and 309D Corridors 301 and 303 Control Building 50' 1
Wet Pjpe Auxiliary Feedwater Pump Tank Building 30' 1
Pre-action Sprinkler Fan Room 233 and 1#
Deluge-Water Spray Corridor 234 Control Building 30' 1
Wet Pipe Salt Water Cooling 1
Wet Pipe Pumps Intake Structure Salt Water Cooling Tunnel CCW Heat Exchangers and Piping Room; A/C Room 017 Safety Equipment Bldg.
1 Wet Pipe Corridor 401 Control Building 70' 1
Wet Pipe Corridor 105 Control Building 9' 1
Wet Pipe AOne half of these Systems are designated Unit 3 but are required to be OPERABLE for Unit 2 operation.
nnCharcoal filter deluge systems are manually actuated.
- 0n Completion of DCP 3-122M SAN ONOFRE-UNIT 3 3/4 7-32 AMENDMENT NO. 8 4