ML13331A526
| ML13331A526 | |
| Person / Time | |
|---|---|
| Site: | San Onofre |
| Issue date: | 12/21/1990 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13331A524 | List: |
| References | |
| NUDOCS 9012270168 | |
| Download: ML13331A526 (22) | |
Text
ATTACHMENT 1 EXISTING TECHNICAL SPECIFICATIONS 9012270168 901221 PDR ADOCK 05000206 p
APPENDIX A TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Page Amendment No.
Page Amendment No.
Page Amendment No.
i 139 3.0-1 43, 56, 64, 83 3.3-3 25, 38, 86, 124, ii 137 130.
130 iii 136 3.0-2 56, 64, 83, 130, 3.3-4 25, 37, 124, 130 iv 131 135 3.3-5 25, 130 v
90, 130, 131 3.0-3 135 3.3-6 25, 102, 120, 130 vi 90, 130, 131 3.0-4 135 3.3-7 25, 102, 130 vii 90, 102, 130, 131 3.1-1 29, 38, 70, 83, 3.3-8 25, 38, 122, 130 viii 90, 130 91, 96, 130 3.3-9 25, 38, 122, 130 ix 90, 91, 102, 130 3.1-2 29, 83, 96, 130 3.3-10 25, 130 131 3.1-3 43, 77, 103, 130 3.3-11 NRC Order x
90, 91, 130, 131 3.1-4 77, 130 4/20/81, 130 xi 55, 92, 102, 110, 3.1-5 77, 125, 130 3.3-12 NRC Order 111, 130, 131 3.1-6 77, 102, 130 4/20/81, 130 xii 56, 58, 71, 79, 3.1-7 77, 102, 103, 130 3.4-1 29, 82, 125, 130 83, 104, 117, 130, 3.1-8 43, 102, 103, 130 3.4-2 29, 130 131 3.1-9 77, 102, 130 3.4-3 82, 125, 130 xiii 31, 56, 58, 79, 3.1-10 Change No. 14, 38, 3.4-4 82, 125, 130, 138 83, 84, 91, 117, 102, 130 3.5-1 83, 117, 130 130, 131 3.1-11 Change No. 14, 38, 3.5-2 43, 56, 58, 83, xiv 131 102, 130 117, 128, 130 1.0-1 31, 56, 59, 83, 3.1-12 Change No. 14, 92, 3.5-3 43, 56, 58, 83, 117, 130 130 117, 121, 122, 130 1.0-2 31, 56, 59, 83, 3.1-13 Change No. 14, 92, 3.5-4 55, 58, 83, 117, 104, 117, 130 130 118, 121, 128, 130 1.0-3 31, 56, 59, 79, 3.1-14 Change No. 14, 3.5-5 83, 117, 130 83, 104, 117, 130 102, 130 3.5-6 7, 11, 25, 35, 55, 1.0-4 31, 56, 59, 79, 3.1-15 Change No. 14, 56, 111, 130 83, 117, 130 102, 130 3.5-7 7, 11, 25, 35, 49, 1.0-5 77, 79, 83, 117, 3.1-16 Change No. 14, 55, 56, 111, 122, 130 102, 130 130 1.0-6 79,.83, 96, 117, 3.1-17 Change No. 14, 3.5-8 11, 49, 111, 122, 130 102, 130 130 1.0-7 58, 83, 117, 130 3.1-18 Change No. 7, 37, 3.5-9 11, 25, 56, 111, 1.0-8 56, 83, 117, 130 55, 91, 119, 130 130 2.1-1 43, 55, 97, 117, 3.1-19 Change No. 7, 55, 3.5-10 56, 130 130 119, 130 3.5-11 56, 130 2.1-2 43, 97, 117, 121, 3.1-20 37, 55, 119, 130 3.5-12 56, 130 130 3.1-21 58, 59, 83, 130 3.5-13 56, 130 2.1-3 43, 117, 121, 122, 3.1-22 58, 130 130 3.1-23 83, 130 2.1-4 43, 117, 121, 122, 3.2-1 102, 130 130 3.2-2 25, 102, 130 2.1-5 43, 97, 117, 121, 3.3-1 25, 37, 86, 124 122, 130 130 2.1-6 55, 130 3.3-2 25, 130 SAN ONOFRE -
UNIT 1 i
AMENDMENT NO. 139
00 LIST OF EFFECTIVE PAGES (Cont.)
Page Amendment No.
Page Amendment No.
Page Amendment No.
4.1-7 25, 29, 36, 4.3-3 24, 58, 87, 118, 4.10-1 13, 94, 130 77, 103, 130 130 4.10-2 13, 94, 130 4.1-8 77, 125, 130 4.3-4 24, 87, 130 4.11-1 14, 109, 130 4.1-9 77, 122, 125, 130 4.3-5 24, 75, 87, 130 4.11-2 14, 109, 130 4.1-10 117, 130 4.3-6 75, 87, 130 4.12-1 91, 130 4.1-11 25, 130 4.3-7 58, 130 4.13-1 18, 113, 4.1-12 Change No. 5, 25, 4.3-8 58, 59, 83, 130 130 130 4.3-9 58, 83, 130 4.14-1 21, 33, 63, 81, 4.1-13 79, 130 4.4-1 Change No. 12, 25, 130 4.1-14 79, 90, 130 56, 82, 84, 95, 4.14-2 21, 63, 81, 130 4.1-15 79, 130 104, 123, 130, 136 4.14-3 21, 63, 81, 130 4.1-16 79, 130 4.4-2 25, 84, 130, 136 4.14-4 21, 63, 81, 105, 4.1-17 79, 90, 130 4.4-3 25, 56, 82, 84, 130 4.1-18 79, 130 117, 130, 134, 131 4.15-1 31, 37, 38, 44, 4.1-19 58, 130 4.4-4 25, 82, 84, 95, 130, 131 4.1-20 58, 130 104, 123, 124, 4.15-2 31, 44, 130, 131 4.1-21 58, 130 130, 134, ].3 4.15-3 31, 130, 131 4.1-22
-58, 83, 130 4.4-5 84, 130, 15 4.15-4 130, 131 4.1-23 58, 83, 117, 125, 4.4-6 25, 56, 84, 104, 4.15-5 130, 131 130 123, 130, LIE 4.15-6 31, 130, 131 4.1-24 58, 109, 130 4.4-7 25, 56, 84, 130, 4.15-7 31, 130, 131 4.1-25 58, 130 134, I3@
4.15-8 130, 131 4.1-26 58, 82, 125, 130 4.4-8 1E 4.15-9 130, 131 4.1-27 58, 82, 125, 130 4.4-9 13 4.15-10 130, 131 4.1-28 65, 82, 125, 130 4.4-10 LM 4.15-11 130, 131 4.1-29 65, 125, 130 4.5-1 Change No. 10, 38, 4.15-12 130, 131 4.1-30 82, 130 79, 130 4.16-1 31, 101, 115, 130, 4.1-31 83, 130 4.5-2 79, 90, 130 133 4.1-32 83, 130 4.5-3 79, 130 4.16-2 37, 101, 115, 130, 4.1-33 83, 130 4.5-4 79, 130 133 4.1-34 119, 130 4.5-5 79, 130 4.16-3 37, 101, 115, 130, 4.1-35 119, 130 4.5-6 79, 130 133 4.2-1 25, 37, 54, 114, 4.6-1 38, 79, 130 4.16-4 37, 55, 101, 115, 130 4.6-2 79, 90, 130 130, 133 4.2-2 25, 37, 114, 130 4.6-3 79, 130 4.16-5 37, 91, 101, 105, 4.2-3 25, 37, 114, 130 4.6-4 79, 130 115, 130, 133 4.2-4 25, 37, 114, 124, 4.6-5 79, 130 4.17-1 79, 130 130 4.6-6 79, 130 4.18-1 79, 130 4.2-5 25, 37, 114, 124, 4.6-7 79, 130 4.18-2 79, 130 130 4.6-8 79, 130 4.18-3 79, 130 4.2-6 37, 114, 130 4.6-9 79, 130 4.18-4 79, 130 4.2-7 NRC Order 4.7-1 Change No. 14, 46, 4.18-5 79, 130 4/20/81, 54, 130 130 4.18-6 79, 130 4.3-1 24, 58, 75, 130 4.8-1 91, 130 4.19-1 79, 105, 130 4.3-2 5, 24, 58, 75, 87, 4.9-1 Change No. 14, 130 118, 130 4.9-2 130 SAN ONOFRE - UNIT 1 iii AMENDMENT NO. 136
3.3 SAFETY INJECTIOPNO CONTAINMENT SPRAY SYSTEMS 3.3.1 OPERATING STATUS APPLICABILITY: Applies to the operating status of the Safety Injection and Containment Spray Systems.
OBJECTIVE:
To define those conditions necessary to ensure availability of the Safety Injection and Containment Spray Systems.
SPECIFICATION: A. The reactor shall not be made or maintained critical unless the following conditions are met. In addition, the reactor coolant system temperature shall not be increased above 200*F unless the containment spray system, the refueling water storage tank and the associated valves and interlocks are operable.
(1) Safety Injection Systems
- a. Refueling.tank water storage and boron concentration comply with Specification 3.3.3.
- b. ESF Switchover automatic trip channel is OPERABLE with the setpoint less than or equal to 20% and greater than or equal to 18% of RWST level.
- c. Two safety injection pumps are OPERABLE.
- d. Two feed water pumps are OPERABLE.
- e. Two recirculation pumps are OPERABLE, except as indicated in item D below.
- f. The recirculation heat exchanger is OPERABLE.
- g. Two charging pumps are OPERABLE.
- h. Two component cooling water pumps are OPERABLE.
- i. Two saltwater cooling pumps are OPERABLE. The reactor may be maintained critical with one saltwater cooling pump provided the auxiliary saltwater cooling pump or two screen wash pumps are available as backup. Return the inoperable pump to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in 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 COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. The backup pump(s) shall be demonstrated operable by test within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of declaring the saltwater cooling pump inoperable.
- j. A minimum of 5400 pounds of anhydrous trisodium phosphate is stored in the containment sump in racks provided.
SAN ONOFRE - UNIT 1 3.3-1 AMENDMENT NO:
25, 37, 86, 124, 130
(2) Containment Spray System
- a. Two refueling water pumps are OPERABLE.
- b.
Two hydrazine additive pumps are OPERABLE.
- c. Hydrazine tank level and hydrazine concentration comply with Specification 3.3.4.
(3) Valves and interlocks associated with each of the above systems are OPERABLE.
(4)
Effective leakage from the recirculation loop outside the containment shall be less than 625 cc/hr as calculated from the following formula.
Effective Leakage. al x Ll
- a2 x L2
- a3 x L3
- where, Ll -
pump and valve leakage which drains to auxiliary building sump L2 -
valve leakage in auxiliary building or doghouse L3.
valve leakage outside al i
iodine release factor for leakage in auxiliary building sump a2 -
iodine release factor for leakage in auxiliary building or doghouse a3 -
iodine release factor for leakage outside the auxiliary building or doghouse If effective leakage from the recirculating loop outside the containment exceeds 625 cc/hr, make necessary repairs to limit leakage to 625 cc/hr.
within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
B. During critical operation or when the reactor coolant system temperature is above 2000F, as appropriate per Item A above, maintenance shall be allowed on any one of the following items at any one time:
(1) One motor-operated valve at a time (MOV 11008 or 11000) in the recirculation loop upstream of the charging pump suction header for a period of time not longer than 72 consecutive hours.
SAN ONOFRE - UNIT 1 3.3-2 AMENDMENT NO:
25, 130
(2) One refueling water pump and/or its associated discharge valve at a time, for a period not longer than 72 consecutive hours.
(3) One hydrazine pump and/or its associated discharge valve (SV600 or 601) at a time, for a period of time not longer than 72 consecutive hours.
(4) One charging pump for a period of time not longer than 72 consecutive hours.
(5) One of the two required component cooling water pumps for a period of time not longer than 72 consecutive hours.
(6) One of the two saltwater cooling pumps with the auxiliary saltwater cooling pump or screen wash pumps available as backup for a period of time not longer than 72 consecutive hours. The backup pump(s) shall be demonstrated operable by test within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of declaring the saltwater pump inoperable.
(7) One train of ESF switchover automatic trip for a period of time not to exceed 72 consecutive hours.
C. Prior to initiating maintenance on any of the components, the duplicate (redundant) component shall be tested to demonstrate availability.
D. In the event of a failure of a recirculating pump, plant operation may continue provided operability of the remaining pump and its associated motive and control power are satisfactorily demonstrated on a daily basis, including verification that the containment spray bypass valves (CV517 and 518) are closed.
BASIS:
The requirements of Specification A assure that before the reactor can be made critical, or before the reactor coolant system heatup is initiated, adequate engineered safeguards are OPERABLE. The limit of 625 cc/hr for the recirculation loop leakage ensures that the combined 0-2 hr EAB thyroid dose due to recirculating loop leakage and containment leakage will not exceed the limits of 10 CFR 100. The formula for determining the leakage incorporates consideration of the significance of leakage in different plant areas. The iodine release factor adjusts actual pump or valve leakage to account for the fraction of the iodine in the leakage which would actually be released to the atmosphere. The iodine release factors in the auxiliary building sump, the auxiliary building or doghouse, and outside are 0.05, 0.5, and 1.0, respectively.
SAN ONOFRE - UNIT 1 3.3-3 AMENDMENT NO:
25, 38, 86, 124, 130
4.1.1 OPERATIONAL SAFETY ITEMS APPLICAM i:
Applies to surveillance requirements for items directly related to Safety Standards and Limiting Conditions for Operation.
QOflY=:
To specify the minimum frequency and type of surveillance to be applied to plant equipment and conditions.
SPECIFICATION:
A. Reactor Trip System instrumentation shall be checked, tested, and calibrated as indicated in Table 4.1.1.
B. Equipment and sampling tests shall be as specified in Table 4.1.2.
C. The specific activity and boron concentration of the reactor coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.1.2., Item la.
- 0. The specific activity of the secondary coolant system shall be determined to be within the limit by performance of the sampling and analysis program of Table 4.1.2.,
Item lb.
E. All control rods shall be determined to be above the rod insertion limits shown in Figure 3.5.2.1 by verifying that each analog detector indicates at least 21 steps above the rod insertion limits, to account for the instrument inaccuracies, at least once per shift during Startup conditions with Keff equal to or greater than one.
F. The position of each rod shall be determined to be within the group demand limit and each rod position indicator shall be determined to be OPERABLE by verifying that the rod position indication system (Analog Detection System) and the step counter indication system (Digital Detection System) agree within 35 steps at least once per shift during Startup and Power Operation except during time intervals when the Rod Position Deviation Monitor is inoperable, then compare the rod position indication system (Analog Detection System) and the step counter indication system (Digital Detection System) at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
G. During MODE 1 or 2 operation each rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.
H. Instrumentation shall be checked, tested, and calibrated as indicated in Table 4.1.3.
SAN ONOFRE -
UNIT 1 4.1-1 AMENDMENT NO:
29, 56, 83, 117,130'.
TABLE 4.1.1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ACTUATING DEVICE CHANNEL CHANNEL CHANNEL OPERATIONAL ACTUATION m
FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST C
- 1.
Manual Reactor Trip N.A.
N.A.
N.A.
R N.A.
- 2.
Power Range, Neutron Flux S
0 (2,3)
N N.A.
N.A.
R (3.4)
- 3.
Power Range, Neutron Flux, N.A.
N.A.
M N.A.
N.A.
Dropped Rod Rod Stop
- 4.
Intermediate Range.
S R (3,4)
S/U (1),
N.A.
N.A.
Neutron Flux H
- 5.
Source Range, Neutron Flux S
R (3)
S/U (1).
N.A.
N.A.
N
- 6.
NIS Coincidentor Logic N.A.
N.A.
N.A.
N.A.
M (5)
- 7.
Pressurizer Variable Low S
R N
N.A.
N.A.
Pressure
- 8.
Pressurizer Pressure S
R K
N.A.
N.A.
- 9.
Pressurizer Level S
R N
N.A.
N.A.
- 10.
Reactor Coolant Flow S
R Q
N.A.
N.A.
X
- 11.
Steam/Feedwater Flow S
R N
N.A.
N.A.
Mismatch o
- 12.
Turbine Trip-Low Fluid N.A.
N.A.
N.A.
S/U (1,6)
N.A.
Oil Pressure
- 13.
Reactor Coolant Pump Breaker S
R R
N.A.
N.A.
r4 Position*
- Applicable to Item 6 in Table 2.1 o
TABLE 4.1.1 (Continued)
TABLE NOTATION (1) -
If not performed in previous 31 days.
(2) -
Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference greater than 2 percent.
(3) -
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(4) -
The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(5) -
Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(6) -
Setpoint verification is not applicable.
SAN ONOFRE -
UNIT 1 4.1-3 AMENDMENT NO:
117, 130-.
TABLE 4.1.2 MINIMUM EQUIPMENT CHECK AND SAMPLING FREOUENCY Check Frecuency la. Reactor Coolant 1. Gross Activity At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Samples Determination Required during MODES 1, 2, 3 and 4.
- 2. Isotopic Analysis 1 per 14 days.
Required for DOSE EQUIVALENT only during MODE 1.
1-131 Concentration
- 3. Spectr9scopic 1 per 6 months(2) for E)
Required only during Determination MODE 1.
- 4. Isotopic Analy-a) Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />,( 3) sis for Iodine whenever the specific Including 1-131, activity exceeds 1-133, and 1-135.
1.0 gC/gram DOSE EQUIVALENT 1-131 or 100/ E (1) ).Ci/gram.
b) One sample between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a THERMAL POER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period.
- 5. Boron concentration Twice/Week (l) E is defined in Section 1.0.
(2) Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor was last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.
(3) Until the specific activity of the reactor coolant system is restored within its limits.
SAN ONOFRE - UNIT 1 4.1-4 AMENDMENT NO:
25, 2EN 70, o6, 117, 13.
TABLE 4.1.Z (continued)
Check Freguency 1.b Secondary
- 1. Gross Activity At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Coolant Determination Required only during Samples MODES 1, 2, 3 and 4.
- 2. Isotopic Analy-a) 1 per 31 days, whenever sis for DOSE the gross activity EQUIVALENT 1-131 determination indicates Concentration iodine concentrations greater than 10% of the allowable limit. Required only during MODES 1, 2, 3 and 4.
b) 1 per 6 months, whenever the gross activity determination indicates iodine concentrations below 10% of the allowable limit. Required only during MODES 1, 2, 3, and.4.
SAN ONOFRE - UNIT 1 4.1-5 AMENDMENT NO:
25, 29, 70, 96, 130.
TABLE 4.1.2 (continued)
Check Frequency
- 2. Safety
- a. Boron Concentration Monthly when the reactor is Injection Line critical and prior to return and RWST Water of criticality when a period Samples of subcriticality extends the test beyond 1 month
- 3. Control Rod
- a. Verify that all rods At each refueling shutdown Drop move from full out to full in, in less than 2.44 seconds
- 4. (Deleted)
- 5. Pressurizer
- a. Pressure Setpoint At each refueling shutdown Safety Valves
- 6. Main Steam
- a. Pressure Setpoint At each refueling shutdown Safety Valves
- 7. Main Steam
- a. Test for OPERABILITY At each refueling shutdown Power Operated Relief Valves
- 8. Trisodium
- a. Check for system At each refueling shutdown Phosphate availability as Additive delineated in Technical Specification 4.2
- 9. Hydrazine
- a. Hydrazine concentra-Once every six months when Tank Water tion the reactor is critical and Samples prior to return of critica lity when a period of subcriticality extends the test interval beyond six months
- 10.
Not used.
SAN ONOFRE - UNIT 1 4.1-6 AMENDMENT NO. 134
TABLE 4.1Z2 (continued)
Check FrequencY
- 11.
MOV-LCV-l100 C
- a. Verify that the fuse Same as Item 10 above Transfer Switch block for either breaker 8-1198 to MCC 1 or breaker 42-12A76 to MCC 2A is removed.
- 12.
Emergency Siren
- a. Verify that the fuse Same as Item 10 above Transfer Switch block for either breaker 8-1145 to MCC 1 or breaker 8-1293A to MCC 2 is removed
- 13. Communication
- a. Verify that the fuse Same as Item 10 above Power Panel block for either Transfer Switch breaker 8-1195 to MCC 1 or breaker 8-12938 to MCC 2 is removed 14a. Spent Fuel Pool Verify water level per
- a. Once every seven days Water Level Technical Specification when spent fuel is being 3.8 stored in the pool.
- b. Refueling Pool
- b. Within two hours prior Water Level to start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during movement of fuel assemblies or RCC's.
- 15.
Reactor
- a. Per Technical Specifi-
- a. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Coolant Loops/
cations 3.1.2.C and Residual Heat 3.1.2.0, in MODE 1 Removal Loops and MODE 2 and in MODE 3 with reactor trip breakers-closed, verify that all required reactor coolant loops are in operation and circulating reactor coolant.
- b. Per Technical Specifi cation 3.1.2.E. in MODE 3 with the reactor trip breakers open, verify SAN ONOFRE - UNIT 1 4.1-7 AMENDMENT NO:
25, 29, 36.
- 77.
103, 130.
ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATIONS
APPENDIX A TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Page Amendment No.
Page Amendment No.
Page Amendment No.
i,
3.0-1 43, 56, 64, 83, 3.3-3 25, 38, 86, 124, ii 137 130
- 130, iii 3.0-2 56, 64, 83, 130, 3.3-4 25, 37, 124, 130 iv 131 135 3.3-5 25, 130 v
90, 130, 131 3.0-3 135 3.3-6 25, 102,120, 130 vi 90, 130, 131 3.0-4 135 3.3-7 25, 102, 130 vii 90, 102, 130, 131 3.1-1 29, 38, 70, 83, 3.3-8 25, 38, 122, 130 viii 90, 130, 91, 96, 130 3.3-9 25, 38, 122, 130 ix 90, 91, 102, 130, 3.1-2 29, 83, 96, 130 3.3-10 25, 130 131 3.1-3 43, 77, 103, 130 3.3-11 NRC order x
90, 91, 130, 131 3.1-4 77, 130 4/20/81, 130 xi 55, 92, 102, 110, 3.1-5 77, 125, 130 3.3.12 NRC order 111, 130, 131 3.1-6 77, 102, 130 4/20/81, 130 xii 56, 58, 71, 79, 3.1-7 77,102, 103, 130 3.4-1 29, 82, 125, 130 83, 104,117, 130, 3.1-8 43, 102, 103,130 3.4-2 29, 130 131 3.1-9 77, 102, 130 3.4-3 82, 125, 130 xiii 31, 56, 58, 79, 3.1-10 Change No.14,38, 3.4-4 82, 125,130, 138 83, 84, 91, 117, 102, 130 3.5-1 83, 117, 130 130, 131 3.1-11 Change No.14,38, 3.5-2 43, 56, 58, 83, xiv 131 102, 130 117, 128, 130 1.0-1 31, 56, 59, 83, 3.1-12 Change No.14,92, 3.5-3 43, 56, 58, 83, 117, 130 130 117,121,122, 130 1.0-2 31, 56, 59, 83, 3.1-13 Change No.14,92, 3.5-4 55, 58, 83, 117, 104, 117, 130 130 118,121,128, 130 1.0-3 31, 56, 59, 79, 3.1-14 Change No. 14, 3.5-5 83, 117, 130 83, 104, 117, 130 102, 130 3.5-6 7,11, 25, 35,55, 1.0-4 31, 56, 59, 79, 3.1-15 Change No. 14, 56, 111, 130 83, 117, 130 102, 130 3.5-7 7, 11,25,35, 49, 1.0-5 77, 79, 83, 117, 3.1-16 Change No. 14, 55, 56,111, 122, 130 102, 130 130 1.0-6 79, 83, 96, 117, 3.1-17 Change No. 14, 3.5-8 11,49, 111, 122 130 102, 130 130 1.0-7 58, 83, 117, 130 3.1-18 Change No.7, 37, 3.5-9 11, 25, 56, 111 1.0-8 56, 83, 117, 130 55, 91, 119, 130 130 2.1-1 43, 55, 97, 117, 3.1-19 Change No. 7,55, 3.5-10 56, 130 130 119, 130 3.5-11 56, 130 2.1-2 43, 97, 117, 121, 3.1-20 37, 55, 119, 130 3.5-12 56, 130 130 3.1-21 58, 59, 83, 130 3.5-13 56, 130 2.1-3 43,117, 121, 122, 3.1-22 58, 130 130 3.1-23 83, 130 2.1-4 43,117, 121, 122 3.2-1 102, 130 130 3.2-2 25, 102, 130 2.1-5 43, 97, 117, 121 3.3-1 25, 37, 86, 124, 122, 130 130 2.1-6 55, 130 3.3-2 25, 130 SAN ONOFRE - UNIT 1 i
AMENDMENT NO:
139
LIST OF EFFECTIVE PAGES (Cont.)
Page Amendment No.
Page Amendment No.
Page Amendment No.
4.1-7 25, 29, 36, 4.3-3 24, 58, 87,118, 4.10-1 13, 94, 130 77, 103,130,_
130 4.10-2 13, 94, 130 4.1-8 77, 125, 130 4.3-4 24, 87, 130 4.11-1 14, 109, 130 4.1-9 77, 122,125,130 4.3-5 24, 75, 87, 130 4.11-2 14, 109, 130 4.1-10 117, 130 4.3-6 75, 87, 130 4.12-1 91, 130 4.1-11 25, 130 4.3-7 58, 130 4.13-1 18, 113, 130 4.1-12 Change No.5, 25, 4.3-8 58, 59, 83, 130 4.14-1 21, 33, 63, 81, 130 4.3-9 58, 83, 130 130 4.1-13 79, 130 4.4-1 Change No.12,25, 4.14-2 21, 63, 81, 130 4.1-14 79, 90, 130 56, 82, 84, 95, 4.14-3 21, 63, 81, 130 4.1-15 79, 130 104,123,130, 136 4.14-4 21, 63, 81, 105, 4.1-16 79, 130 4.4-2 25, 84, 130, 136 130 4.1-17 79, 90, 130 4.4-3 25, 56, 82, 84, 4.15-1 31, 37, 38, 44, 4.1-18 79, 130 117,130, 134,136 130, 131 4.1-19 58, 130 4.4-4 25, 82, 84, 95, 4.15-2 31, 44, 130, 131 4.1-20 58, 130 104, 123, 124, 4.15-3 31, 130, 131 4.1-21 58, 130 130, 134, 136 4.15-4 130, 131 4.1-22 58, 83, 130 4.4-5 84, 130, 136 4.15-5 130, 131 4.1-23 58, 83,117,125, 4.4-6 25, 56, 84, 104, 4.15-6 31, 130, 131 130 123, 130, 136 4.15-7 31, 130, 131 4.1-24 58, 109, 130 4.4-7 25, 56, 84, 130, 4.15-8 130, 131 4.1-25 58, 130 134, 136 4.15-9 130, 131 4.1-26 58, 82, 125, 130 4.4-8 136 4.15-10 130, 131 4.1-27 58, 82, 125, 130 4.4-9 136 4.15-11 130, 131 4.1-28 65, 82, 125, 130 4.4-10 136 4.15-12 130, 131 4.1-29 65, 125, 130 4.5-1 Change No.10, 4.16-1 31, 101,115,130, 4.1-30 82, 130 38, 79, 130 133 4.1-31 83, 130 4.5-2 79, 90, 130 4.16-2 37, 101,115,130, 4.1-32 83, 130 4.5-3 79, 130 133 4.1-33 83, 130 4.5-4 79, 130 4.16-3 37, 101,115,130, 4.1-34 119, 130 4.5-5 79, 130 133 4.1-35 119, 130 4.5-6 79, 130 4.16-4 37, 55,101, 115, 4.2-1 25, 37, 54, 114, 4.6-1 38, 79, 130 130, 133 130 4.6-2 79, 90, 130 4.16-5 37, 91, 101,105, 4.2-2 25, 37, 114, 130 4.6-3 79, 130 115, 130, 133 4.2-3 25, 37, 114, 130 4.6-4 79, 130 4.17-1 79, 130 4.2-4 25, 37, 114, 124, 4.6-5 79, 130 4.18-1 79, 130 130 4.6-6 79, 130 4.18-2 79, 130 4.2-5 25, 37, 114, 124, 4.6-7 79, 130 4.18-3 79, 130 130 4.6-8 79, 130 4.18-4 79, 130 4.2-6 37, 114, 130 4.6-9 79, 130 4.18-5 79, 130 4.2-7 NRC order 4.7-1 Change No.14, 4.18-6 79, 130 4/20/81, 54, 130 46, 130 4.19-1 79, 105, 130 4.3-1 24, 58, 75, 130 4.8-1 91, 130 4.3-2 5, 24, 58, 75, 4.9-1 Change No.14,130 87, 118, 130 4.9-2 130 SAN ONOFRE - UNIT 1 iii AMENDMENT NO:
136
(2 One refueling water pump an r its associated discharge valve at a time, for a period not longer than 72 consecutive hours.
(3) One hydrazine pump and/or its associated discharge valve (SV600 or 601) at a time, for a period of time not longer than 72 consecutive hours.
(4)
One charging pump for a period of time not longer than 72 consecutive hours.
(5)
One of the two required component cooling water pumps for a period of time not longer than 72 consecutive hours.
(6)
One of the two saltwater cooling pumps with the auxiliary saltwater cooling pump or screen wash pumps available as backup for a period of time not longer than 72 consecutive hours. The backup pump(s) shall be demonstrated operable by test within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of declaring the saltwater pump inoperable.
(7)
One train of ESF switchover automatic trip for a period of time not to exceed 72 consecutive hours.
(8)
One motor-operated valve at a time (MOV-1100C or MOV-1100E) in the VCT outlet line to the charging pump suction for a period of time not longer than 72 consecutive hours.
C. Prior to initiating maintenance on any of the components, the duplicate (redundant) component shall be tested to demonstrate availability.
D. In the event of a failure of a recirculating pump, plant operation may continue provided operability of the remaining pump and its associated motive and control power are satisfactorily demonstrated on a daily basis, including verification that the containment spray bypass valves (CV517 and 518) are closed.
BASIS:
The requirements of Specification A assure that before the reactor can be made critical, or before the reactor coolant system heatup is initiated, adequate engineered safeguards are OPERABLE. The limit of 625 cc/hr for the recirculation loop leakage ensures that the combined 0-2 hr EAB thyroid dose due to recirculating loop leakage and containment leakage will not exceed the limits of 10 CFR 100. The formula for determining the leakage incorporates consideration of the significance of leakage in different plant areas. The iodine release factor adjusts actual pump or valve leakage to account for the fraction of the iodine in the leakage which would actually be released to the atmosphere. The iodine release factors in the auxiliary building sump, the auxiliary building or doghouse, and outside are 0.05, 0.5, and 1.0, respectively.
SAN ONOFRE - UNIT 1 3.3-3 AMENDMENT NO:
25, 38, 86, 124, 130
TABLE 4.1.2 (continued)
Check Frequency
- 11.
(Deleted)
- 12.
Emergency Siren
- a.
Verify that the fuse Monthly, when the reactor Transfer Switch block for either is critical, and prior to breaker 8-1145 to returning reactor to MCC 1 or breaker critical, when period of 8-1293A to MCC 2 subcriticality extended is removed, the test interval beyond one month.
- 13.
Communication
- a.
Verify that the fuse Monthly, when the reactor Power Panel block for either is critical, and prior to Transfer Switch breaker 8-1195 to returning reactor to MCC 1 or breaker critical, when period of 8-1293B to MCC subcriticality extended 2 is removed the test interval beyond one month 14a.
Spent Fuel Pool Verify water level per
- a. Once every seven days Water Level Technical Specification when spent fuel is 3.8 being stored in the pool
- b. Refueling Pool
- b. Within two hours prior Water Level to start of and at lease once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during movement of fuel assemblies or RCC's.
- 15.
Reactor
- a.
Per Technical Specifi-a. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Coolant Loopss cations 3.1.2.C and Residual Heat 3.1.2.D, in MODE 1 Removal Loops and MODE 2 and in MODE 3 with reactor trip breakers closed, verify that all required reactor coolant loops are in operation and circulating reactor coolpant.
- b.
Per Technical Specifi cation 3.1.2.E, in MODE 3 with the reactor trip breakers open, verify SAN ONOFRE - UNIT 1 4.1-7 AMENDMENT NO:
25, 29, 36, 77, 103, 130
FIGURE 1 EXISTING CONFIGURATION FOR CHARGING PUMPS SUCTION
H 2 VCT LETDOWN MOV-1100C RWST SEAL INJECTION CHARGING COLD LEG MOV-1100B RECIRCULATION VCC-G-8A TO REFUELING VCC-G-8B WATER PUMPS MOV-1100D CHARGING PUMPS FCV-5051 FROM RECIRCULATION PUMPS Figure 1. Existing Configuration for Charging Pumps Suction
FIGURE 2 MODIFIED CONFIGURATION FOR CHARGING PUMPS SUCTION
H 2 VCT LETDOWN MOV-1100E3 MOV-1100C MOV-883 RWST SEAL INJECTION 2
CHARGING COLD LEG MOV-1100B RECIRCULATION VCC-G-8A TO REFUELING VCC-G-8B WATER PUMPS MOV-1100D CHARGING PUMPS FROM FCV-5051 RECIRCULATION PUMPS Figure 2. Modified Configuration for Charging Pumps Suction