ML20034A755
| ML20034A755 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/12/1990 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034A756 | List: |
| References | |
| NUDOCS 9004240225 | |
| Download: ML20034A755 (29) | |
Text
.
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UNITED STATES y
r NUCLEAR REGULATORY COMMIS$10N l
3 I
wAsHmorow. p. c.acess i
k.,.....
l i
l SOUTHERN CALIFORNIA EDIS0N COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA o,
'THE CITY OF ANAHEIM. CALIFORNIA i
DOCKET NO. 50-361
~
SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 2 i
AMENDMENT TO FACILITY OPERATINC LICENSE Amendment No. 86 License No. NPF-10
{
t 1.
The Nuclear Reguistory Comission (the Commission) has found that:-
t A.
The r.pplications for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by Southern California Edison Company (SCE) on behalf of itself and San Diego Gas and Electric Com)any, the City of Riverside, California and the City of Analeim, California (licensees) dated October 19, 1989 and supplemented February 9, 1990, complies with the standards and. requirements of the j
Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapt *.r I;
B.
The facility will operate in conformity with:the applica-tion, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance (i) that the activities author-ized by this amendment can be conducted without endangering-the health and safety of the public, and (ii) that such
.t activities will be conducted in compliance with the Comission'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 q
t 7
9004240223 900412 PDR ADOCK 05000361 F
PDC Ij
l E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable reouirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby amended to read as follows:
(2) Technical Specifications l
The Technical Specifications contained in Appendix A, and l
i the Environmental Protect?on Plan contained in Appendix B, as revised through Amendment No. 86
, are hereby incorporated in the license. SCE shall operate the facility in accordance with the Technical Specificetions and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and must be fully implemeckd no hter than 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COPMISSION i
vit h.
l f,%M Charles M. Trammell, 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: April 12, 1990 I'
l
Messrs Ray and Cotton San Onofre Nuclear Generating Southern California Edison Company Station, Units 2 and 3 cc Charles R. Kocher, Esq.
Mr. Richard J. Kosiba, Project Mantatr James A. Beoletto, Esq.
Bechtel Power Corporation Southern California Edison Company 12440 E. Imperial Highway Irvine Operations Center Norwalk, California 90060 23 Parker Irvine, California 92718 Mr. Robert G. Lacy Manager, Nuclear Dnot tment Orrick, Herrington & Sutcliffe San Diego Gas & Electric Company ATTN:. David R. Pigott, Esq.
P. 0. Box 1831 600 Montgomery Street San Diego, California 92112 San Francisco, California 94111 Pr. John Hickman Alan R.' Wetts, Esq.
Senior Health Physicist Rourke & Woodruff Environmental Radioactive Egmt. Unit 701 S. Parker St. No. 7000 Environmental Management Branch Orange, California 92668-4702 State Department of Health Services 714 P Street, Room 616 Mr. Sherwin Harris Sacramento, California 95814 Resource Project Manager Public Utilities Department City of Riverside Resident Inspector, San Oncfre NPS 3900 Main Street c/o U.S. Nuclear Regulatory Commission Riverside, California 92522 Post Office Box 4329 San Clemente, California 92672 Mr. Charles B. Brinkman Combustion Engineering, Inc.
Payor City of San Clemente 12300 Twinbrook Parkway, Suite 330 SanClemente, California 92672 Reckville, Maryland 20852 Regional Administrutor, Region V Mr. Phil Johnson U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission 1450 Maria Lane / Suite 210 Region V Walnut Creek, California 94596 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Chairman, Board of Supervisors San Diego County Mr. Don Womeldorf 1600 Pacific Highway, Room 335 Chief. Environmental Management Branch San Diego, California 92101 California Department of Health 714 P Street, Room 616 Sacramento, California 95814 (14)
+.
e,
'E TABLE 4.3-3 (Continued) i o
-1 5
RADIATION MONITORING INSTRUNENTATION SURVEILLANCE REQUIREMENTS 2
m CHANNEL NODES FOR WNICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE I
E INSTRUNENT CHECK CALIBRATION TEST IS REQUIRED
- 'I PROCESS MONITORS (Continued) w 3.
Noble Gas Monitors a.
Piant Vent Stack D
R q
1,2,3,4 3
i (2/3 RT-7808, 2RT-7865-1, 3RT-7865-1) w b.
Condenser Evacuation System O
R 1
Q 1,2,3,4(1) l Y
i i
l NOTES:
f
- In accordance with Table 4.3-2 sowveillance requirements for these instrument channels.
4
- With irradiated fuel in the storage pool.
4 l
(1) With any main steam isolation valve and/or any main steam isolating valve bypass valve not fully closed.
}
(2) At least once per refueling interval.
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T.
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e.........,__
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--........ -. -. _ - - - ~.
- h e.
1 l
.)
1 1
l l
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1 i
f 4
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i 1
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3675 t 110 VOLTS 100 1
u 7
I g
e k
1 s
l O
l l
v e
10 s
1 l
/-
/
j t
/
1 2
F 2000 VOLTS 2.810,13 SECONDS O VOLTS.
I 1.0 t.05 SECONDS l
1.0 d
2400 2000 3200 3000 4000 SUS VOLTAGE i
Figure 3,3-1 i-DEGRADED BUS VOLTAGE TRIP SETTING S
l' f-SAN ONOFRE-UNIT 3 3/4 3-40
-]
e-s TABLE 3.3-6 (Continued)
ACTION STATEMENTS ACTION'13 With the number of channels OPERA 8LE less than required by the-ainimum channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control reos emergency air cleanup system in the emergency (except as required by ACTIONS 14, 15) mode of operation.
ACTION 18 With the number. of channels OPERABLE less than required by the ainimum channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12.
ACTION 17 With the numbet of channels OPERA 8LE less than required by the-aintaus channels OPERA 8LE requirement operation may continue
-providedthatthepurgevalvesaremaIntainedclosed.-
ACTION 17a -
With the number of channels OPERA 8LE less than required by tne minimum channels CPERABLE requirement, comply with the ACTION requirements of Specification 3.4.5.1. (Mode 1, 2, 3, 4 only) i ACTION 17b -
With the number of channels CPERABLE-less.than required by the minimum channels CPERABLE requirement, close each of the con-tainment purge penetrations providing direct accats from the containment atmosphere to the outside atmosphere.
1 ACTION 18 With the number of channels CPERABLE one less than Minimum Channels CPERABLE requirembat, either restore the inoperable channel to CPERABLE status within 30 days, or be in NOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 184 -
With both channels. inoperable', restore the. inoperable channel (s) l to OPERA 8LE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 19 With the number of OPERA 8tt Channels less' than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel (s) to CPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />,- r:
j 1)
Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and 2)
Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following initiation of the pre planned alternate outlining the-action taken, the cause of the inoperatiility and the plans and schedule for restoring the system to OPERABLE status.
- In accordance with Engineered Safety Feature trip value specified by Table 3.3 4 With irradiated fuel in the storage pool.
ACTIONS 13, 16, 17, 174 and 17b are repeated from, Table 3.3-3 for reference.
{
SAh ON0FRE-UNIT 3 3/4 3-37 AMEN 0 MENT NO. 20
-_r
_ :2_ __ -_- :
l w
3; TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS m
E CHANNEL MODES FOR WilCH f
CHANNEL' CHANNEL FUNCTIONAL SURVEILLANCE E
INSTRUMENT CHECK CALIBRATION TEST IS REQUIRED
.Z 1.
Area Monitors w
a.
Containment - High Range S
(2)
M 1, 2, 5, 4 j
(3RT-7820-1, 3RT-7820-2) l b.
Containment - Purge Isolation 5
(2)
M 1,2,3,'4,6 i
(3RT-7856-1,3RT-7857-2) i c.
R M
1,2,3,4 (3RT-7874A, 3RT-7875A, m
)
J, 2.
Process Monitors i
a.
Fuel Storage Pool Airborne (3RT-7822-1,3RT-7823-2).
i i.
Gaseous b.
Containment Airborne (3RT-7804-1, 3RT-7807-2) 1.
Gaseous 1,2,3,4,6
~
ii.
. Particulate 1,3,3,4,6 111.
Iodine' 6
E c.
Control Room Airtporne (2/3RT-7824-1, 2/3RT-7825-2) i x
1.
Particulate All
(
- 11. Gaseous ATI P
4 4.
n l
~ '
i i
A.
.rm
.L.-
m ww.~..
-.m
.,...,-ww-.*--e,-+-i.-,,3-us
--w
-,,-re
- .. - = -
w..-s--.--eive.
.....-..-e,,.+
.-e
- -,. + +
<. - > -. - ~
...-..m,---.-w--
--u-..
i
".r
,-v-v.--
i E
TAdLE 3.3-6 RADIATIOM MONITORING INSTRUMENTATION N
MINIMUM E
CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT O INSTRUMENT OPERABLE MODES SET *0 INT RANGE ACTION w
1.
Area Monitors t
a.
Containment - High 2
1, 2, 3 -
10 R/hr 1-10s R/hr 18 18a Range 4
10 R/hr 49 (3RT-7820-1 and 3RT-7820-2)-
b.
Containment - Purge 1
1,2,3,4 10 1-105 mR/hr 17 w
Isolation 6
1 (3RT-7856-1 or 3RT-7857-2) 17b W
J, c.
Main Steam Line 1/11ne 1, 2, 3 1 mR/hr (low);
10 1-104 mR/hr; 18 i
A channel consists of 1 R/hr (high) 3RT-7874A and 3RT-7875A or 4
1 mR/hr (low);
19 3RT-78748 and 3RT-78758 1 R/hr (high) 2.
Process Monitors a.
Fuel Storage Pool Airborne-(3RT-7822-1 or 3RT-7823-2) s 1.
Gaseous' 1
-let -107 cpu 16 l
b.
' Containment Airborne-k (3RT-7804-1 or 3RT-7807-2)
E 1.
Gaseous 1
1,2,3,4 101 -107 cpm 17a j!!
6 17b -
2i 11.
Particulate 1
1,2,3,4~
108 -107 cpm 17a 2
6 17b P
111.
Iodine 1
6 108 -107 cpm -
17b A
c.
Control Room Airborne j
(2/3 RT-7824-1 or 2/3 RT-7825-2) 2 i.
Particulate / Iodine 1 All 108 -107 cpm 13 ii. Gaseous 1
All 101 -107 cpm 13 vs
L i
TABLE 3.3-6 (Continued)
IC RADIATION MONITORING INSTRUNENTATION l
E
- i
?
A i
J.
MININUM 2
CHANNELS APPLICABLE ALARM / TRIP MASUREMENT INSTRUNENT DPERABLE N00E5 SETPOINT RANGE ACTION w
3.
Noble Gas Monitors a.
Plant Vent Stack Wide Range (2RT-7865-1 1
1, 2, 3 Per 00CM 10 7 - 105 pCi/cm3 19 or 3RT-7865-1)
Normal Range (2/3R1-7808 1 4
Per 00CM 10 8-- 10 8 pCi/cm3 19 or 2RT-7865-1 or 3RT-7865-1) w1 b.
. Condenser Evacuation System w
J, Wide Range (3RT-7870-1) 1 1, 2, 3(1)
Per 00CM 10 7 - los pcg/co. 19 s
i-Normal Range (3RT-7818 1
4 (1)
Per 00CM 10 8 - 102 pCi/cm3 19 or 3RT-7370-1)
(1) With any main steam line isolation valve and/or any main steam isolating valve bypass valve not fully closed.
i 1
k
. s M
4 l
. g.
co O
i M.
e
>,#eww=-,-
=we..
-,g.-.
3 Hy., =, W e e
e ty+=.-werw.--
aw w,
e--m' a
ye
h TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUNENTATION SURVEILLANCE REQUIRENENTS R.
m CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTICMAL SURVEILLANCE g
FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED
~-a
- 11. FUEL HANDLING ISOLATION (FHIS) a.
Nanual (Trip Buttons)
N.A.
N.A.
R N.A.
b.
Airborne Radiation l
- i. Gaseous S
R M
c.
Automatic Actuation Logic M.A.
N.A.
R(3)
- 12. CONTAINNENT PURGE ISOLATION (CPIS) a.
Nanual (Trip Buttons)
N.A.
N.A.
(6)
N.A.
b.
Airborne Radiation
.}
1.
Gaseous S
(6)
M 1,2,3,4,6 ii. Particulate W
(6)
N 1,2,3,4,6 g,
iii. Iodine W
(6)
M 6
w c.
Containment Area Radiation (Gamma) 5 (6)
M 1,3,3,4,6 d.
Automatic Actuation Logic N.A.
N. A.,
(3), (6) '
1,2,3,4,6 TABLE NOTATION (1) Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(2) Deleted.
(3) Testing of Automatic Actuation Logic shall include energization/de-energization of each initiation
,g relay and verification of the OPERABILITY of each initiation relay.
l (4) A subgroup relay test shall be performed which shall include the energization/de-energization of each g
subgroup relay and verification of the OPERABILITY of each subgroup relay.- Relays exempt from testing during plant operation shall be limited to only those relays associated with plant equipment which
-4 g
cannot be operated during plant operation.
Relays not testable during plant operation shall be tested during ecch 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.
y* -(5) Actuated equipment only; does not result in CIAS.
(6) At least once per refueling interval.
With irradiated fuel in the storage pool.
i; INSTRUWENTATION 3/4.3.3 MDNITORING INSTRUMENTATION-RADIATION MDNITORING IN$TRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitorino instrumentation channels shown in 7J1e 3.3 6 shall be OPERABLE with their alarm /tripr setpoints within the specified limits.*
APPLICA31LITY: As shown la Table 3.3-8.
ACTION:
With a radiation sonitoring channel alara/ trip a.
value shown in Table 3.3-6, adjust the setpoint to within the 11a' tsetpo within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.
j b.
With one or more radiation monitoring channels inoperable, take the ACTION shown {n Table 3.3-8.
t The provisions of Specifications 3.0.3 and 3.0.4 are not applicable, c.
i 1
SUtvEILLANCE REQUIREMENTS
/*
4.3.3.1 Each radiation monitoring instrumentation channel nM1 be demonstratedOPERABLEbytheperforsanceoftheCHANNELCHD, CHANNEL l
CALIERATION and CHANNEL FUNCTIONAL TEST operations for theMDES and at i
frequencies shown in Table 4.3-3.
' i i
i
- Continuous monitoring and sampling of the containment purge exhaust dire from the pur and 42 inch)ge stack shall be provided for the low and high volume (8 inch.
containment purge prior to startup following the first refueling outage.
Containment airborne monitor 3RT-7804-1 or 3RT-7807-2 and asso sampling media shall perform these functions prior to initial criticality.
i containment airborne monitor 3RT-78041 and associate perform the above required functions.
j l
I
$AN ONDFRE UNIT 3 3/4 3-34 AMENDMENT NO. 20 l
I t
s c.s !.S.
- . M-h5 j
t w
~E TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES M
Ali.0WA8tE E FUNCTIONAL UNIT TRIP VALUE VALUES w '11.
FUEL HANDLING ISOLATION (FHIS)
- a.
Manual (Trip Buttons)
Not Applicable Not Applicable b.
Airborne Radiation
- i. Gaseous (8)-
(8) 1.
c.
Automatic Actuation Logic Not Appilcable.
Not Applicable
- 12. 'CONTAINNENT PURGE ISOLATION (CPIS) w a.
Manual-(Trip Buttons)
Not. Applicable Not Applicable b.
Airborne RadfeiA n 1.
Gaseous (6)(7)
(6)(7)
- 11. Particulate (6)(7)
(6)(7) 111. Iodine (6)(7)
(6)(7);
c.
Containment Area Radiation (Gamma)
< 325 mR/hr (N00ES 1-4)
< 340 mR/hr (fe0ES 1-4) k
'32.4mR/hr(Mode 6) 32.5mR/hr(MDDE6) 5%
d.
Automatic Actuation Logic--
Not Applicable Not' Applicable
'i 5
~
4 v
t TABLE 3.3-4 (Continued)
.G TA8tE NOTATION i
o
,m g
(1) Value may be decreased manually, to a minimum of greater than or equal to 300 psia, as pressurizer E
presswee is reduced, provided the margin between the pressurizer and this value is maintained at i
O less than or equal to 400 psia;* the setpoint shall be increased automatically as pressurizer pressere is increased until the trip setpoint is reacheda Trip may be aanvally bypassed below 400 psia; bypass shell be automatically removed whenever pressurizer is greater than or equal to 400 psia.
[
w l
(2) Value may be decreased manually as steam generator pressere 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 untti the trip setpoint is l
[
reached.
(3) % of the distance between steam generator apper and lower level instrument nozzles.
j t*
(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.
l l.
w il g
(5) Actuated equipment only; does not result in CIAS.
l l
(6) The trip setpoint sha11 be set sufficiently high to prevent spurloos alarms / trips yet sufficiently i
Iow to assure an alarm / trip should an inadvertent release occur.
(7) Prior to the completion of OCP 53N, the setpoints for Containment Airborne Radiation Manitor 3RT-7904-1 shall be determined by the 00CM.
l (8) The trip setpoint shall be set sufficiently high to prevent sperlows alare/ trips yet sufficiently low l
to assure an alare/ trip should a feel handling accident occur.
l E-a
[
g Variable setpoints are for use only during normal, controlled plant heatups and cooldowns.
g or, rn 5 Above normal background.
- 5 i
m.
I 51*b i
e a
Y
- }
...-,.._.~.__.-._.._....-..._..~.-..~m.._._._..
..-..-..-....m.
~
-. ~
.. -.. -. _.... _ =..
l j
o*
i e
I' e
TABLE 3.3-3 (Continued) i
.l l
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTIRSOj% TION A
c MINInuM TOTAL NO.
CHANNELS CNANNELS APPLICA8tE i
i FUNCTIONAL UNIT-0F CHANNELS TO TRIP OPERABLE M00ES ACTION w
\\
9.
CONTRGi. 200M ISOLATION l
(CRIS) i a.
Manual CRIS (Trfp l
n ttons) 2 1
1 All 13*#
u b.
Mar sel 5145 (Trip s
Buttons) 2 sets of 2/ unit I set of 2 2 sets of 2/untt 1,2,3,4-8 r
c.
Airborne Radiation t
1.
Particulate / Iodine 2
1 1
All 13 4 1
- 11. Geseous 2
1 1-All 13*#
4 w
d.
Automatic ActuetIon
.l Logic 1/ train 1
1 All 13*#
w i
10.
T0XIC GAS ISOLATION (TGIS) t a.
Manuel (Trip Buttons)
.2 1-1 All 14*#, 15*#
l b.
Chlorine - High 2,
1 1-All 14*#, 15*#
i.
c.
Ammonta - High 2-1 1
All 14*#, 15*#
d.
Butane #,J :--. - High 2
1 1
All 14*#, 15*#
e.
Automatic Actuation Logic 1/ train 1
1-All 144.-15*#
1 Y
i l
- P1 @
'sm i%K b
lg?.
.?.
1.as 4
- Q 1
t v.
E-TABLE 3.3-3 (Continued) i o5 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION m
MINIMUM E
TOTAL NO.
CHANNELS CHANNELS APPLICABLE Z FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MDDES ACTION i
w 11.
FUEL HANDLING ISOLATION (FHIS) i 1
a.
Manual (Trip Buttons) 2 1
1 16*#
b.
Airborne Radiation
- i. Gaseous 2
1 1
16*#
l c.
Automatic Actuation Logic 1/ train 1
1 16*#
4 w
- 12. CONTAINNENT PURGE ISOLATION w*
(CPIS)-
co a.
Manual (Trip Buttons) 2 1
1 6
17b*#
o.
Airborne Radiation
{
(3RT-7804-1 or 3RT-7807-2 1.
Gaseous' 2
1 1
1,2,3,4 17a 6
17b*#
11.
Particulate :
2 1
1 1,2,3,4 17a i
6 17b*#
111. Iodine
-2 1
1 6
17b*#
c.
. Containment Area Radiation (Gamma) 2 1
1 1,2,3,4 17 k
(3RT-7856-1.or 3RT-7857-2) 6 17b*#
8 d.
Automatic Actuation
.iR Logic
.1/ train' 1
1 1,2,3,4 17 e
~ 2i 6
17b*#
5 4
'g l
's.
l s
ATTACHMENT TO LICENSE AMENDMENT NO. 76 FACILITY OPERATING LICENSE N0. NPF l DOCKET NO. 50-362 s
Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by 1
amendment number and.contain marginal lines indicating the area of' change.-
Also enclosed are the following overleaf pages to the amended pages.
AMENDMENT PAGE OVERLEAF PAGE 3/4 3-18 3/4 3-25 ~
3/4 3 !
3/4 3-33 3/4 3-34 3/4 3-35 3/4 3-36 3/4 3-38 D
l' f
i i
I 1
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- exto
/
'l 9,,
UP;.TED STATES l
NUOLEAR REGULATORY COMMISSION j
,g wAssoworow. o. c. rosss j
....+/
i i
SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY h
j THE CITY OF RIVERSIDE, CALIFORNIA.
THE CITY OF ANAHEIM CALIFORNIA DOCKET No. 50-362
-SAN ON0FRC NUCLEAR GENERATING STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE f
1 Amendment No. 76
. License No. NPF-15 4
1.
The Nuclear Regulatory Comission (the Comission)'has found that:
i A.
The applications for amendment to the license for San Onofre NuclearGeneratingStation, Unit 2(thefacility) filed by Southern California Edison Company (SCE) on behalf of 3
itself and San Diego Gas and Electric Company, the City of l
Riverside,) California and the City of Anaheim, California (licensees dated October 19, 1989 and supplemented February 9, 1990, 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.I; t
B.
The facility will operate in conformity with the'applica-tion, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance (i) that the activities author-ized 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-comoa defense and security or to the health and safety of the public; and
+
i
(
~.
f
i 1
' l e
E.
The issuance of this amendment is in accordance with 10 CFR I
Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by charges to the Technical Spect-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) Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 76, 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.
i FOR THE NUCLEAR REGULATORY COMMISSION
> /[.
/ rihm.i Charles M. Tramell,' Acting. Director l'
Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical 3
i Specifications Date of Issuance: April 12, 1990 a-r
~ _.
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=
TABLE 3.3-6 (Continued) l ACTION STATEMENTS l
l ACTION 13 With the number of channels OPERA 8LE less than required bylthe einious channels OPERA 8LE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate -
and saintain operation of the control rose emergency air cleanup systes'in the emergency (except as required by ACTIONS 14,15) mode of operation, c
ACTION 16 With the number of channels OPERA 4LE less than required'by the--
minimum channels OPERA 8LE requirement, comply with the ACTION' requirements of Specification 3.9.12.
ACTION 17 With the number of channels CPERA8LE 1ess than required by the sinimum channels OPERA 8LE. requirement, operation may continue provided that the purge valves are maintained closed.
I ACTION 174 -
With the number of channels OPERAILC 1ess than required by.the minimum cha pels OPERA 8LE requirement, comply with the ACTION j
requirements of Specification 3.4.5.1.
(Mode 1, 2, 3. 4 only)'
t ACTION 17b -
With the number of channels OPERA 8LE less than required by the.
l minimum channels OPERABLE requirement, close each of the contain-ment purge penetrations providing direct access from the contain-j ment atmosphere to the outside atmosphere.
i ACTION 18 With the number of channels OPERA 8LE one less than the Minimum l
Channels OPERABLE requirement..either restore the inoperable channel to CPERABLE status within 30 days, or be in. HOT-SHUTDOWN within the next 12-hours..
ACTION 184 -
With both channels inoperable, restore the inoperable channel (s) to OPERA 8tE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or be in NOT'5 NUT 00WN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 19 With the' number of CPERA8LE Channels less than required by the Minimum Channels CPERABLE requirement -either restore-the inoperable Channel (s) to CPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:
t 1)
Initiate the preplanned alternate method of monitoring the
~
appropriate parameter (s), and 2)
Prepare and submit a Special Report-to the Commission pur-
[
suant to Specification 6 9.2 within.14 days following initi-ation of the pre planned alternate outlining the action l'
L takeh, the cause of,the inoperability and the plans and.
i s
schedule for restoring the system to CPERA8LE status.
i fin accordance with Engineered Safety Feature trip value specified by. Table 3.3-4.
i "With irradiated fuel in the storage pool.
s ACTIONS 13,16,17,17a and 17b are repeated from Table 3.3-3 for reference.-
{*
SAN ONOFRE-UNIT 2 3/4 3-37 A M D m T NO. 31
/
- =
E-TABLE 4.3-3 o5 J
g RADIATION NONITORING INSTRUNENTATION SURVEILLANCE REQUIREENTS.
CHANNEL--
MODES FOR MfICH E
CHANNEL CHANNEL FUNCTIONAL sum'EILLANCE
.Z INSTRUNENT CHECK CALIBRATION TEST
'IS REQUIRED m
~
~
1.
Area Monitors
-a.
Containment -'High Range S
.. (2)
M' 1, 2, 3, 4 (2RT-7820-1,2RT-7820-2) b.
Containment - Purge Isolation S
(2)
M.-
-1 2,3,4,6
{2RT-7856-1,2RT-7857-2) w1 c.
R M
.1,2,3.4 (2RT-7874A, 2RT-7875A, m
J, 2RT-78748, 2RT-78758) co 2.
Process Monitors a.
Fuel Storage Pool Airborne (2RT-7922-1, 2RT-7823-2).
1.
- Gaseous b.
Containment Airborne-(2RT-7804-1,:-2RT-7807-2)-
1.
' Gaseous 1,2,3,4,6
- 11..
Particulate.
1.2,'3,4,6 k
111.
Iodine 6'
E
- g c.
Control Room Airborne 3
(2/3RT-7824-1, 2/3RT-7825-2)
,o
-1.
. Particulate-
' All ii. ~ Gaseous All
=. -
c O
- 1..
3 e.'.-
%g _. _ _ - -
__m._. _
--*"=h--"C--*-
^--"-W-
'" -' - " ' ' ~ ' '
m --
TABLE 3.3-6
- g
~
RADIATION MONITORING INSTRUMENTATION x
S' MINIMUM i
' Ni CHANNELS APPLICABLE.
ALARM / TRIP MEASUREMENT INSTRUMENT..
OPERABLE MODES-SETPOINT-RANGE ACTION C
}
1.
Area Monitors to a.
Contairewnt-- High 2
1,2,3 10 R/hr 1-10s R/hr
- 18. 18a
^
Range 4-10 R/hr 19 (2RT-7820-1 and 2RT-7820-2)
~
b.
Containment - Purge 1
1,2,3,4 10 8-105 mR/hr 17 Isolation 6'
17b (2RT-7856-1 or 2RT-7857-2) c.
' Main Steam Line 1/11ne 1, 2, 3 1 mR/hr?(low); 10 1-104 mR/hr; 18 A Channel-consist of 1..R/hr (high) w J,
-2RT-7874A and 4
1 mR/hr (low);
19 2RT-7875A 0F.
1 R/hr (high) 2RT-78?4B'and
-2RT-78758 2.
Process Monitors a.
Fuel, Storage Pool
. Airborne (2RT-7822e1 or' 2RT-7823-2) 1.
Gaseous-
'l-101 -107 cpm 16 R
b.
Containment Airborne
.I c
Q (2RT-7894-1 or 4
,2RT-7807-2)-
- i. ' _. Gaseous..
'1 1,-2, 3, 4~-
/# 1 ~
101'= 107 cpm _
17a d
6
-17b'
'5-Tii.. Particulate ~
.11 1,:2, 3. 4
- 101 - 107 M 17a
~
6
~ #-
.10' -l107 cpm 17b~
17b E
i11. Iodine.
1 ~
c.
' Control Rcom Airborne.
(2/3 RT-7824-1 or 2/3 RT-7825-2) 1 1.
Particulate 1
1All
'108.- 10 cpm '
7 ii. f>aseous ;-
1 Al l.
-108 - 107; cpm 13 q
7'7
- d
-^
~
+
~ 4 _h I
- - \\
s.
s 1
em O
M y
v v
(
M H
M' M
g 3
3 v
s v
s 8-s.
s.
s
.E.
1 1
-Y d
9 e
et -
P -
O O
O O
4 M
M M
,=4 I
4 I
I E
k 9
h 9
~#
9 8
8 9
O-O O
O 8
W i
g E
e M
M M
- .0 W
s A
N. -
e-o at W
-QE
>=
>= E
^E 2 8
-F
~
.- E T
4 >-
k.
k b
b
=J W
.W 88 e
W 4
4M A
A A
A
't O
>=
m w
C 2
O m
E v
4 k
I.
e I
E M.
C W
C
>=
.J w
M
- =
m A
g' N
S"4 M
E W
-WW v
v
.l m
M M.
.h g
3 a
g 4E E
A N
N.
4 t==
C ik C
M T
erg g.
b
>=
0 4
N C<
er WW
.d.J G
WG
=
IE e4 M
v=4
.=4 g
- Et EuC v=1 C
8 O
m 3
C 4
5 O
.ht W
!5
~ E. y_
.M F
O
- r_
4.
b m
O e DC b
4-O M^
^
e C es -
<e M
e M M@
W e=4 eat w
C mI 4 I O I - E e=4 C 4@ l e
C Wm Qt nrt #J b=O K,> tK ?% G Ve N - 03N WN C
O 9CW c E @w wN@
w e
a e rs N >=
r cc a N e
m CWW 4 I Os 4 @ l E >= t 3
C 9%EW - >= M ' 'C W >=
b E >=
Q m== **d N CEN CWE.
ONM h
A3vM XMN O AN 2 w N.
C
>=
g rv m w g.
E
.D g
.C 3
k M
M
=
ec 3
l m
a=%.
E
,=
M M
teir SAN ONOFRE-UNIT 2
'3/4 3-3'6 AMENDMENT.'O. 31 N
_3
- cf
'j b.-lj{-[ " 'f #f;j.j(jyQyffff$$t;(("f glg}{.)Q.,
TABLE 4.3-2 (Continued) w'g ENGINEERED-SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS o
g
?
CHANNEL M00ES FOR WHICH CHANNEL CHANNEL
- FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST 15 REQUIRED EQ 11.
FUEL HANDLING ISOLATION (FHIS) y a.
Manual (Trip Buttons)
. N.A.
N.A.
R
.N.A.
b.
Airborne Radiation
- 1. ~ Gaseous-S R
M I'
c.
Automatic Actuation Logic N.A.
N.A.
R(3)
W.
-CONTAINMENT PURGE ISOLATION (CPIS)
- a.
Mar.ual (Trip Buttons)
N.A.
N.A.
- (6)
N.A.
b.
Airborne Radiation i.
- Gaseous ~
S (6)
M-1,2,3,4,6 R
it. Particulate W
(6) -
M 1,2,3,4,6-ii1.. Iodine W
(6)
M 6
Y c.
Containment Area Radiation g
(Gamma)"
S (6)
M.
l1,2,3,4,6 d.
Automatic Actuation Logic N.A.
N.A.
(3),(6) 1,2,3,4,6 TABLE NOTATION (1) Each train or logic channelishall be tested at least every 62 days on a STAGGERED TEST BASIS.
(2) Deleted.
(3) Testing of. Automatic Actuation Logic shall include energization/de-energization of each initiation.
relay and verification of the OPERABILITY of each initiation relay..
~
A subgroup relay test shall.be perfomed which -shall include the _energization/de-energization of each -
k (4). subgroup; relay and verification of-the OPERABILITY of each subgroup. relay. Relays exempt from testing
-g during plant operation shall be' limited to only those. relays associated with plant equipment which jR cannot be operated during plant operation.. Relays not testable during plant operation shall be tested mi 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 w nths.
g (5) Actuated equipment only; does:not result'in CIAS.
h (6) At least.once per refueling interval.
~
~*
With-irradiated fuel in the" storage pool.
a'
h rm P''=
"^ "'
=^-W-""""Ws 4
- --eh"
- ' '^ - ' * ^
j-*d*'-
ad.N__
m______.-'___
- E'
-^h'--*
o'
[NSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3 1 The radiation monitorina f.astrumentation channels shown in Table 3.5-6 shall be OPERABLE with their alarm / trip setpoints within the specified limits.
A.PPLICABILITY: As shown in Table 3.3-6.
ACTION:
With a radiation monitoring channel alare/ trip setpoint exceeding the a.
value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.
b.
With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.
The provisions of Specifications 3.0.3 and 3.0.4 are not appli.751a.
c.
SURVEILLAWCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNE FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-3.
t SAN ONOFRE-UNIT 2 3/4 3-34 AMENDMENT N0. 83
.--.-.-.-,n-.
s
.. 1
'd
~..
s
- -p z
g TABLE 3.3-4 (Continued)
'b ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUNENTATION TRIP VALUES m
E ALLOWABLE Z FUNCTIONAL UNIT TRIP VALUE VALUES ro -
- 11. FUEL HANDLING ISOLATION (FHIS) a.
Manual (Trip Buttons)
Not Applicable Not Applicable b.
Airborne Radiation
- i. Gaseous (8)
- (8) ws c.
Automatic Actuation Logic Not Applicable Not Applicable
~
- 12. -CONTAINMENT PURGE ISOLATION-'(CPIS) a.
Manual (Trip Buttons)
Not Applicable Not. Applicable b.
Airborne Radiation 1.
- Gaseous (6)(7)
(6)(7) 11.
Particulate (6)(7).
(6)(7)
. 111.' Iodine
-(6)(7)
- (6)(7)
' k
- c.
Containment Area Radiation (Gamma)
< 325 e9/hr-(MODES-1-4)
< 340.mR/hr (MODES 1-4)
~7 2.5 mR/hr (MODE 6) 1 2.4 mR/hr (MODE 6)
E R
Automatic Actuation Logic.
Not Applicable
- Not' Applicable.
'i d.
g:
+
.w-
'""*'"-'"*---4d-'--"&"
" ' ' "' --^ '
r*-'
_.1.1_s.___,____,._,_
'""n
-h"
+'4W9
-' " ' 'd
1 h
TABLE 3.3-4 (Continued)
TABLE NOTATION Lh "g
(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 is increased until the trip setpoint is reached. Trip may be manually bypassed below 400 psia; u
bypass shall be automatically removed whenever pressurizer 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 ce equal to 200 psi;* the setpoint shall be incressed 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.
t) Inverse time relay set value 3165V, trip will occur within the tolerances specified in Figure 3.3-1 4
for the range of bus voltages.
')
Actuated equipment only; does not result in CIAS.
(6) The trip setpoint shall be set sufficiently high to prevent spurious alarms /teips 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 M rborne Raatation Monitor 2RT-7804-1 shall be determined by the 00CM.
(8) The trip setpoint shall be set sufficiently high to prevent spurious alarm / trips yet sufficiently low to assure an alare/ trip should a fuel handling accident occur.
es E ry Variable setpoints are for use only during normal, controlled plant heatups and cooldowns.
" 'I
- Above normal background.
to 8
a'il -
m%
(D
=
m
~
T, /.
- q..
TABLE 3.3-3 (Continued)'
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION L
M MINIMUM
' TOTAL AD.
CHANNELS CHANNELS APPLICABLE a8IT OF CHANNELS TO TRIP OPERABLE MODES
- ACTION, I
N FUNCTIONM 9.
CONTROL ROOM ISOLATION
. (CRIS) a.
Manual CRIS (Trip Buttons) 2 1
1 All 13*#
b.
Manual SIAS (Trip Buttons) 2 sets of 2/ unit I set'of 2 2 sets of 2/ unit 1,2,3,4 8
c.
Airborne Radiation
,g 1.-
Particulate / Iodine 2
1 1
All
-13*#
11.' Gaseous 2
1
.1 All 13*#~
Y D
- d.
Automatic Actuation
- Logic 1/ train 1-1 All 13*#
- 10. TONIC GAS! ISOLATION (TGIS)
=
-a.
Manual (Trip Buttons).
2 1
.1 All-14*#, 15*#-
b.
Chlorine.- High 2
I 1
All 14*#, 15*#-
- c. -
Ammonia -High 2
1 1
All 14*#, 15*#
d.
. Butane / Propane - High
'2 1
1
. All.
14*#, 15*#-
e.
Automatic Actuation
' d.
Logic 1/ train 1~
1 All
'14*#, 15*#
.l 9
pf yR
-98 f@g
'i.
3p a
4
_.--em.
_m m--
-*-a'm---
=
- n"
" - - + - - " " ' " " - - * * ' " "
- - ^ ^ " - - ^
' ' ' ~ ' '
~
~
p-
- j-.- -
U
~
~
- n ~
Tv ' :
x c;,
+
mg o
TABLE 3.3-3 (Continued).
5y ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM
~E TOTAL NO.
CHANNELS CHANNELS APPLICABLE Z FUNCTIONAL-UNIT OF CHANNELS TO TRIP OPERABLE
' MODES' ACTION m
11.
FUEL HANDLING ISOLATION (FHIS) a.
Manual-(Trip Buttons) 2 1
I 16*#
b.
Airborne Radiation 1.
Gaseous 2
1 1
-16*#
- c...
Automatic Actuation l
A 1
16*#-
Logic 1/ train 1
w
- 12. CONTAINMENT PURGE. ISOLATION w
(CPIS) a.
Manual (Trip Buttons) 2 1
-1 6
17b*#
b.
1 Airborne Radiation
- (2RT780a-1 or 2RT7807-2)'
i.
Gaseous 2
1 1
^
1,2,3,4 17a 6
~
17b*#
ii. Particulate 2
1 1
1,2,3,4-17a 6
'17b*#~
iii.' Iodine' 2
.I 1
6 17b*#
c.
Containment Area Radiation (Gamma) 2'
'1
~1 1,2,3,4 17 k-(2RT7856-1 or 2RT7857-2)
.6l 17b*#
5 d.
Automatic' Actuation J
Logic
~1/ train 11-
- - 1 1,2,3,4' 17 3
6 17b*#-
5 s.
-e Li '
.sq 4:. _.
--s-
-.L
~ ~ -
^
^ '
- ~ ^ - ~ ^ ^ " ^ ^ ' ' ' ' ~ ~ " ' ^ ~ ^ '
^
e 1
a
-0.
l
\\-
l
-i L
ATTACHMENT TO LICENSE AME_NDMENT NO.86 1
)
FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 3
Revise Appendix A Technical Specifications by. removing-the-pages identifiedL below and inserting the enclosed pages.- The revised pages are: identified by amendment number and contain marginal lines indicating'the area of change.
Also enclosed are the following overleaf pages.to the amended pages..
4
' AMENDMENT PAGE OVERLEAF'PAGE r
l 0
.3/4 3-18 1
3/4 3 '3/4 3-26
'3/4 3-33 3/4 3-34 i
3/4 3-35 3/4 3 3/4 3-38 L
4 l.
l
'i t
a e
I
, ~.
s
._.;,,.~
m
-