ML19353A867
| ML19353A867 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/21/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19353A868 | List: |
| References | |
| NUDOCS 8912080019 | |
| Download: ML19353A867 (18) | |
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- o, UNITED S TATES 8'
j NUCLEAR REGULATORY COMMISSION e
- E WASHING TON, D. C. 20555
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SOUTHERN CAllFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. E0-361 i
t SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 80 License No. NPF-10 1.
The Nuclear Regulatory Comission (the Commissicn) has found that:
A.
The applications for amendinent to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by Southern Califernia Edison 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 April 26,1988(2 letters) and December 19, 1988 comply with the standards ano req)uirertents of the Atomic Energy Act of195 forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applications, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorizeo by this amendment can be conducted without er.dangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission'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; end E.
The issuance of this amendirent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirernents have been satisfieo.
8912080019 891121 PDR-ADOCK 05000361 P
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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 Specification f
The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.80, 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 REGULA ORY COMMISSION forge /y Ofhton ' irector g
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Project Director (te V Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation l
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Attachment:
1 Changes to the Technical s
Specifications Date of Issuance: November 21, 1989 1
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4v ATTACHMENT TO LICENSE AMENDPENT NO. 80 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 Revise Appendix A Technical Specifications by removing the pages ioentified 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.
AMENDMENT PAGE OVERLEAF'PAGE 3/4 1-19 3/4 1-20 3/4 3-1 3/4 3-2 3/4 3-13 3/4 3-14 s
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I REACTIVITY CONTROL SYSTEMS f
POSITION INDICATOR CHANNEL - SHUTOOWN LIMITING CONDITION FOR OPERATION 3.1. 3. 3 At least one CEA Reed Switch Position Transmitter indicator channel shall be OPERABLE for each shutdown, regulating or part length CEA not fully inserted.
APPLICABILI_TYi MODES 3*, 4* and 5*.
ACTION:
With less than the above required position indicator channel (s) OPERABLE, inimediately open the reactor trip breakers.
SURVEILLANCE REQUIREMENTS 4.1.3.3 Each of the above required CEA Reed Switch Position Transmitter indicator channel (s) shall be determined to be OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at lesst once per refueling interval.
The provisions
+
of Technical Specification 4.0.2 are not applicable.
k With the reactor trip breakers in the closed position.
SAN ON0FRE-UNIT 2 3/4 1-19 AMENDMENT NO.80
3.1.3.4 Tre full length (shutdown and regulating) CEA arithmetic average anc the inci.idual CEA drop times, from a withdrawn position greater than or ecua!
to 145 inches, shall be within at least one of the limit sets of Table 3.1-1 Tne crop time shall be from when power is interrupted to 1r CEA drive mechanism until the CEA reaches its 90 percent insertion position with:
7,. greater than or equal to 520*F, and a.
All reactor coolant pumps operating.
b.
A0'L: Ca!l'2't:
MC0!$ 1 an: 2.
AC':~N:
a.
With eithee the arithmetic qverage CEA drop time OR any individual CEA drop time determined to exceed the limits, restore the CEA drop time to witnin the limits prior to proceeding to Modes 1 or 2.
SUR.El' LANCE REOUIREMENTS A.I.3.4.1 The CEA drop time of full length CEAs shall be demonstrated through I
measurement crier to reactor criticality:
For all CEAs following each removal and reinstallation of the vessel a.
l heat.
For all CEAs following any maintenance on or modification to the CEA b.
l crive system which could affect the drop time of those specific CEAs, and At least once per refueling interval.
c.
4.1.1.4.2 For each CEA drop time measurement performed under surveillance 4.1.3,4.1, confirm that the appropriate CPC and COLSS addressable constant adjustments that conservatively bound both the arithmetic average CEA drop time AND the slowest individual CEA drop time measured have been made prior to reactor criticality.
l SAN ONOFRE-UNIT 2 3/4 1-20 AMEN 0 MENT NO. 78
r 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.
APPLICABILITY:
As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protective instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CrtANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1.
4.3.1.2 The logic for the bypasses shall oe demonstrated OPERABLE prior to each reactor startup unless performed during the preceding 92 days. The total bypass function shall be demonstrated OPERABLE at least once per refueling interval for each channel affected by bypass operation.
The provisions of Technical Specification 4.0.2 are not applicable.
4.3.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per refueling interval. Each test shall include at least one channel per function such that all channels are tested at least once every N refueling interval where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.
The provisions of Technical Specification 4.0.2 are not applicable.
4.3.1.4 The isolation characteristics of each CEA isolation amplifier and each optical isolator for CEA Calculator to Core Protection Calculator data transfer shall be verified at least once per refueling interval during l
shutdown per the following tests:
a.
For the CEA position isolation amplifiers:
1-l 1.
With 120 volts AC (60 Hz) applied for at least 30 seconds across the output, the reading on the input does not exceed L
0.015 volts DC.
SAN ONOFRE - UNIT 2 3/4 3-1 AMENDMENT NO. 80
' INSTRUMENTATION r
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SURVEILLANCE REQUIREMENTS (Continued) t n
2.
With 120 volts AC (60 Hz) applied for at least 30 seconds i
i-across the input, the reading on the output dees not exceed 8 volts DC.
t-t b.
For the optical isolators:
Verify that the input to output.
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insulation resistance is greater than 10 megohms when tested using a F
megohmmeter on the 500 volt DC range.
L
.The provisions of Technical. Specification 4.0.2 tre not applicable.
l 4.3.1.5 The Core Protection Calculator System shall be determined OPERABLE at
'least once per 12l hours by verifying that less than three auto restarts have occurred on each calculator during the past 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.3.1.6 The Core Protection Calculator System shall be subjected to a CHANNEL FUNCTIONAL TEST to verify OPERABILITY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of receipt of a High CPC Cabinet Temperature alarm.
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SAN ON0FRE - UNIT 2 3/4 3-2 AMENDMENT NO. 80
i INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and bypasses shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.
APPLICABILITY:
As shown in Table 3.3-3.*
ACTION:
With an ESFAS instrumentation channel trip setpoint less conservative a.
than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.
SURVEILLANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-2.
4,3.2.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation.
The total bypass function shall be demonstrated OPERABLE at least once per refueling interval for each channel affected by bypass operation.
The provisions of Technical Specification 4.0.2 are not applicable.
4.3.2.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per refueling interval.
Each test shall include at least one channel per function such that all channels are tested at least once every N refueling interval where l
N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.
The provisions of Technical Specification 4.0.2 are not applicable.
1
- See Special Test Exception 3.10.5 l
SAN ONOFRE-UNIT 2 3/4 3-13 AMEN 0 MENT NO. 80 l
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W SAN ONOFRi UNIT 2 3/4 3-14 Amendment No. 4
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q'o UNITED STATES
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g NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20046 I
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SOUTHERN CALIFORNIA EDISON COMPANY I
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 NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 68 License No. NPF-15 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The applications for amendment to the license for San Onofre Nuclear Generating Station, Unit 3 (the facility) filed by Southern California Edison 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 April 26, 1988 (E letters) and December 19, 1988 comply i
with the standaros 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; B.
The f acility will operate in conformity with the applications, the provisions of the Act, and the regulations of the Conunission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health I
and safety of the public, and (ii) that such activities will be L
conducted in compliance with the Commission's regulations; D.
The issuance of this amendrrent will not be inimical to the common defense and security or to the bcalth and safety of the public; and E.
The issuance of this amenonent is in accordance with 10 CFR Part 51 of the Conimission's regulations and all applicable requirements have been satisfied.
l
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N ve b r 21, 1989 ELECTRICAL FCWER SYSTEM SURtEht ANCE REOUIREMENTS (Ceatinwe:)
a)
Masal
)
Sin.latec loss of effsite power by itself c)
Simulated loss of offsite power in conjun: tion with an E5r actuation test signal 5.
Verifying the generator is synchronized, loaded to greater than or ecual to 4700 kw in less than or equal to 77 secones", anc operates with a load greater than or equal to 4700 kW for at least an aceitional 60 minutes, and 6.
Verifying the diesel generator is aligned to provide stancey power to the associated emergency busses.
o.
At least once oer 31 cays and after each operation of the ciesel.nere the perio: of operation was greater than or equal to 1 nour by enecking for anc removing accumulated water from tne cay tank, c.1. At least once per 92 days and from'new fuel oil prior to accition to the storage tanks by verifying that a sample obtained in ac:orcan:e with ASTM-D4057-81 has a water and sediment content of less than or ecual to.05 volume percent and a kinematic viscosity 9 40*C of greater than or toual to 1.9 but less than or equal to 4.1 when teste:
in a::orcan:e witn ASTM-D975 81.
I 2.
At least once every 92 days by obtaining a sample of fuel oil L
in accordance with ASTM-D4057-81 and-verifying that particulate contamination is less than 10mg/ liter when checked in accordance with ASTM-D2276-83, Method A.
d.
At least once per refueling interval ** (The provisions of Technical Specification 4.0.2 are not applicable) by:
1.
Subjecting the diesel to an inspection in accordance with i
procedurespreparedinconjunctionwithitsmanufacturer's recommendations for this class of standby service.
2.
Verifying the generator capability to reject a load of greater than or equal to 655.7 kW while maintaining voltage at 4360 2 436 volts and frequency at 60 2 6.0 Hz.
ll 3.
Verifying the generator capability to reject a load of 4700 kW without tripping.
The generator voltage shall not exceed 5450 volta during and following the load rejection.
"All engine starts for the purpose of this surveillance testing may be preceeded by an engine prelube period and/or other warsup proce6ures recommended by the manufacturer so that mechanical stress and wear on the diesel engine is minimized.
- For cycle 4 only, this surveillance interval may exceed the 24 month refueling interval but may not exceed 25 months.
SAN ONOFRE - UNIT 2 3/4 8-3 AMEN 0 MENT No. 75
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i r.r: :::n ::.t: s<s rw s'.'8V!P.L AN!! 8!!'JI8!w! A*5 (Ceat4 ~ e:S 4
Si N1 sting a less of offsite power by itself, ane:
a)
Verifying de energitation of the emergency busses anc icac sheeding from the emergency busses.
b)
Verifying the diesel starts on the auto start signal,.
energizes the emergency busses with permanently conne:tec
+
Icats within 10 secones and operates for greater than or etual to 5 minutes while its generator is loaeed with sne pereanently connected loses.
Af ter energi24 tion, the stency state voltage and frequency of the emergency busses shall be maintaines at 4360 a 436 volts one 60 1.2 H:
caring this test.
t 5.
ve ifying that on an ESF test signal, without loss cf effsite p:.e, the ciesel generater starts on the auto start signal anc c:e ates on stand y for greater than or equal to l ninutes.
The steady state generator voltage and frequency shall be 4360 2 436 volts and 60 1.2 Hz within 10 seconds after the a.to" tart signal; the generator voltage and frequency shall te maintainee within these limits during this test.
6.
Le'etes.
7.
Simslating a loss of offsite power in conjunction with an f 58 test signal, and a)
Verifying de energitation of the emer9ency busses anc loac sheecing from the emergency busses,.
b)
Verifying the diesel starts on the auto start signal, energizes the emergency busses with permanently conne:tec loads within 10 secones, energizes the auto connectes emergency (accident) loads through the load sequence and operates for prester than or equal to 5 minutes while its I
generator is onded with the opergency leads. After l
loading, the steady state voltage and frequency of the emergency busses shall be maintained at 4360 a 436 volts I
and 60 + 1.2/ 0.3 H2 durin0 this test.
L c)
Verifying that all automatic diesel generator trips, except engine overspeed, generator differential and low lo.
lube oil pressure, are automatically bypassed.
SAN ON0FRE UNIT 2 3/4 4 4 AMENDM[NT NO. 59
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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-15 is hereby amended to read as follows:
(2) Technical Specification The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.68, 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
(/?
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eorge W Knighton, D 'ector Project irectorate Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 21, 1989
O r
ATTACHMENT TO LICENSE AllENDMENT NO. 68 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Revise Appendix A Technical Specifications by removing the pages identified belcw 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 followir.g overleaf pages to the amended pages.
AMENDMENT PAGE OVERLEAF PAGE 3/4 1-19 3/4 1-20 3/4 3-1 3/4 3-2 3/4 3-13 3/4 3-14 A
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REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNEL - SHUT 00WN i
L,,
LIMITING CONDITION FOR OPERATION P
3.1'.3.3. At least one CEA Reed Switch Position Transmitter indicator channel shall be OPERABLE for each shutdown, regulating.or part length CEA not fully inserted.
L
-APPLICABILITY:- MODES 3*, 4* and 5*.
ACTION:
With less than the above required position indicator channel (s) OPERABLE, immediately open the reactor trip breakers.
SURVEILLANCE REQUIREMENTS 4.1.' 3. 3 Each of the above required CEA Reed Switch Position Transmitter-
. indicator channel (s) shall be determined to be OPERABLE by performance of a CHANNEL-FUNCTIONAL TEST at least once per refueling interval.
The provisions
.of Technical Specification 4.0.2 are not applicable.
"With the' reactor trip breakers in the closed position.
_ SAN ONOFRE-UNIT.3 3/4 1-19 AMENDMENT N0. 58
i REACT:v!'r CON'ROL SYSTEMS CEA :400 TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The full length (shutdown and regulating) CEA arithmetic average anc the individual CEA drop times, from a withdrawn position greater than or equal to 145 inches, shall be within at least one of the limit sets of Table 3.1-1 The drop time shall be from when power is interrupted to the CEA drive mechan until the CEA reaches its 90 percent insertion position with:
T,y greater than or equal to $20*F, anc a.
All reactor coolant pumps operating.
b.
ADD :: E L!'*:
MODES 1 and 2.
L ACI]DN:
a'ith either the arithmetic average CEA drop time OR any indivicual a.
CEA drop time aetermined to exceed the limits, restore the CEA drop time to within the limits prior to proceeding to Modes 1 or 2.
I SURVEILLAN:E RE001REMENTS 4.1.3.4.1 Tne CEE drop time of full length CEAs sh611 be demonstrated througn l
measurener.t prior to reactor criticality:
Fer all CEAs following each removal and reinsta11ation of the a.
vessel head, l
For all CEAs following any maintenance on or modification to the CEA l
b.
drive system which could affect the drop time of those specific CEAs, and At least once per refueling interval.
c.
4.1.3.4.2 For each CEA drop time measurement performed under surveillance 4.1.3.4.1, confirm that the appropriate CPC and COL 55 addressable constant adjustments that conservatively bound both the arithmetic average CEA drop time AND the slowest individual CEA drop time measured have been made prior to reactor criticality.
SAN ONOFRE-UN]T 3 3/4 1-20 AMENDMENT NO. 66
3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION i
3.3.1 'As'a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.
I APPLICABILITY:
As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
-SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protective instrumentation channel shall be demonstrated i
OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1.
4.3.1.2.The logic for the bypasses shall be demonstrated OPERABLE prior to each reactor startup unless performed during the preceding 92 days. The total bypass function shall be demonstrated OPERABLE at least once per refueling interval for aach channel affected by bypass operation.
The provisions of Technical Specification 4.0.2 are not applicable.
4.3.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per refueling interval.
Each test shall include at least one channel per function such that
-_all channels are tested at least once every N refueling intervals where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total-No of Channels" column of Table 3.3-1.
The provisions of Technical Specification 4.0.2 are not applicable.
4.3.1.4 The isolation characteristics of each CEA isolation amplifier and t
each optical isolator for CEA Calculator to Core Protection Calculator data transfer shall be verified at least once per refueling interval during shutdown l
per the following tests:
a.
For the CEA position isolation amplifiers:
l 1.
With 120 volts AC (60 Hz) applied for at least 30 seconds across the output, the reading on the input does not exceed 0.015 volts DC.
l SAN ON0FRE - UNIT 3 3/4 3-1 AMENDMENT NO.68
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INSTRUMENTATION f
l SURVEILLANCE REQUIREMENTS (Continued)
L 2.
With 120 volts AC (60 Hz) applied for at least 30 seconds 6
across the input, the reading on the output does not exceed 8 volts DC.
b.
For the optkal isolators:
Verify that the input to output insulation resistance is. greater than 10 megohms when tested using a l
megohmmeter on the 500 volt DC range.
The provisions of Technical Specification 4.0.2 are not applicable.
l l
4.3.1.5 The Core Protection Calculator System shall be determined OPERABLE at L
least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that less than three auto restarts have occurred on each calculator during the past 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.3.1.6 The Core Protection Calculator System shall be subjected to a CHANNEL FUNCTIONAL TEST to verify OPERABILITY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of receipt of a High CPC Cabinet Temperature alarm, t
SAN ONOFRE - UNIT 3 3/4 3-2 AMENDMENT NO.68
n INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and bypasses shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.*
APPLICABILITY:
As shown in Table 3.3-3.
ACTION:
With an ESFAS instrumentation channel trip setpoint less conservative a.
than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value, b.
With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.
SURVEILLANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-2.
4.3.2.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation.
The total bypass function shall be demonstrated OPERABLE at least once per refueling interval for each channel affected by bypass operation.
The provisions of Technical Specification 4.0.2 are not applicable.
4.3.2.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per refueling interval.
Each test shall include at least one channel per function such that all channels are tested at least once every N refueling intervals where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.
The provisions of Technical Specification 4.0.2 are not applicable.
I' l
- Continuous monitoring and sampling of the containment purge exhaust directly f rom the purge stack shall be provided for the 13w and high volume (8-inch
)
and 42-inch) containment purge prior to startup following the first refueling outape.
Containment airborne monitor 3RT-7804-1 or 3RT-7807-2 and associated sampling media shall perform these functions prior to initial criticality.
From initial criticality to the startup following the first refueling outage containment airborne monitor 3RT-7804-1 and associated sampling media shall perform the above required functions.
I SAN ONOFRE - UNIT 3 3/4 3-13 AMEN 0 MENT N0. 68
- :~-
i i
w
'TA8t[ 3.3-3 E
o Ef1GINIERED SAFETY FEATURFS ^.luTION SYSTIM INSTRtBENTATION
,5 MINIMUM' i
TOTAL Dio.
CNANNELS
.CHANN[LS APPtICA8tE-j g
FUNCTIONAL UleIT or CNAfsELS TO TRIP OPERABLE N00t5 ACil0N L
M 1.
SAFETY INJECTION (SIAS)
{
a.
Manual (Trip Buttons) 2 sets of 2 1 set of 2 2 sets of 2 1,2.3.4 8'
b.
Containment Pressure -
j.
Nigh 4
2 3
- 1. 2. 3 9*.
10*
c.
Pressurizer Pressure -
Lou 4
2 3
1, 2. 3(a) 9*,
!O*
d.
Automatic' Actuation -
~
Logic 4
2 3
1.2.3.4 9*
10' w
2.
S CONTAlf0ENT SPRAY (CSAS)
?
l a.
Manual (Trip Buttons) 2 sets of 2 1 set of 2 2 sets of 2
- 1. 2. 3 8'
J.
b.
'Contalnuent Pressure --
l Migh - Hip 4
2(b) 3
- 1. 2. 3 9*
10*
i c.
Automatic Actuation I
4 Logic 4
2 3
- 1. 2, 3 9*,
10*
i 3.
CONTAll0ENT ISOLATION (CIAS) e a.
flanual CIAS (Trip Outtons) 2 sets of 2 I set of 2 2 sets of 2 1.2.3.4 8
l b.
finnual SIAS (Trip Buttons) (c) 2 sets of 2 1 set of 2 2 sets of 2 1.2,3.4 8
[
c.
Containment Pressure -
I Nigh 4
2 3
- 1. 2. 3 9*.
10*
d.
Automatic Actuation logic 4
2 3
1.2.3.4 9*.
10*
i e.
4
-=
M..
m.
RE:55 LED i
.j
.?
t November 21, 1989 1
ELECTRICAL POWER SYSTEM SURVEILLANCE REQUIREMENTS (continueei J
S.
Verifying the generator is synchronized, loaded to greater than or ecual to 4700 kW in less than or eoual to 77 seconds", and operates with a load greater than or~ equal to 4700 kW for at least an seditional 60 minutes, and 6.
Verifying the diesel generator is aligned to provide standby power to'the associated emergency busses.
b.
At least once per 31 days and after each operation of the diesel where the period of operation was greater than or equal to I hour by checking for and removing accumulated water from the day tank.
i c.1. At least once per 92 days and from new fuel prior to addition to the storage tanks by verifying that a e sple obtained in accordance with ASTM-04057-81 has a water and sedO.snt content of less than or equal to.05 volume percent and a kinematic viscosity @ 40'C of greater than or equal to 1.9 but less than or equal to 4.1 when tested in accoraance with ASTM-0975-81.
- 2. At least once every 92 days by obtaining a sample of fuel oil in accordance with ASTM-D4057-81 and verifying that particulate con-tamination is less than 10mg/ liter when checked in accordance with ASTM 02276-83, Method A.
c.
At least once per refueling interval (the provisions of Technical Specification 4.0.2 are not applicable) by:
1.
Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service.
L:
2.
Verifying the generator capability to reject a load of greater t5an or equal to 655.7 kW while maintaining voltage at 4360 ; 436 volts.and frequency at 60 + 6.0 Hz.
ll 3.
Verifying the generator capability to reject a load of 4700 kW without tripping.
The generator voltage shall not exceed 5450 volts during and following the load rejection.
i l
l "All engine starts for the purpose of this surveillance testing may be pre-ceded by an engine prelube period and/or other warmup procedures recommended by the manufacturer so that mechanical stress and wear on the diesel engine 1
is minimized.
SAN ONOFRE-UNIT 3 3/4 8-3 AMENOMENT NO.63 L
U,
,]
w-n,g ELECTRICAL Pow!R sv5TEps SURVEILLANCE REOUIREw!NTS (Centinued) 4
. Simulating a loss of offsite power by itself, and a)
Verifying de-energization of the emergency busses and Icad shedding from the emergency busses.
b)
Verifying the diesel starts on the auto-start signal, energizes the emergency busses with permanently connected
-loads within 10 seconds and operates for greater than or equal to 5 minutes while its generator is loaded with the permanently connected loads. After energitation, the steacy state voltage and frequency of the emergency busses shall be maintained at 4360 2 436 volts and 60
- 1.2 h:
curing this test.
5.
Verifying that on an ESF test signal, without loss of offsite power, the diesel generator starts on the auto start sional anc operates on standby for greater than or equal to 5 mihutes.
The steady-state generator voltage and frequency shall be 4360 2 436 volts and 60 21.2 Hz within 10 seconds after the auto start signal; the generator voltage and fregency shall be maintained within these limits during this test.
6.
Deleted 7.
Simulating a loss of offsite power in conjunction with an ESF test signal, and a)
Verifying de-energization of the emergency busses and lead shedding from the emergency busses.
t b)
Verifying' the diesel starts on the auto. start signal, energizes the emergency busses with permanently connected i
l loads within 10 seconds, energizes the auto-connected emergency (accident) loads through the load sequence and operates for (Ireater than or equal to 5 sinutes while its generator is ioaded with the emergency loads. After loading, the steady state voltage and frequency of the
- 2 emergency busses shall be saintained at 4360 1 436 volts 1
and 60 + 1.2/-0.3 Hz during this test, b
l c)
Verifying that all automatic diesel generator trips, except engine overspeed, generator differential, and low-low lube oil pressure, are automatically bypassed.
L l
SAN ONOFRE-UNIT 3 3/4 8-4 AMENDMENT MO. 48 N