ML13331B175
| ML13331B175 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/09/1989 |
| From: | Nandy F SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8905170018 | |
| Download: ML13331B175 (5) | |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD.
CALIFORNIA 91770 F. R. NANDY TELEPHONE MANAGER OF NUCLEAR LICENSING May 9, 1989 (818) 302-1896 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Technical Specification Page Correction San Onofre Nuclear Generating Station Unit 1 As part of the issuance of Amendment No. 125 by NRC letter dated April 25, 1989, the "Table Notation" page for Table 3.5.1-1, Reactor Trip System Instrumentation, was modified to correct a typographical error in ACTION 1.
This typographical error was made by SCE and incorporated into the Technical Specifications by issuance of Amendment No. 121 by NRC letter dated April 4, 1989. Subsequent to issuance of the Amendment No. 125 with the typographical error corrected, SCE identified that the Table Notation page as issued did not include several unrelated changes made previously by Amendment No. 117.
The specific changes made by Amendment No. 117 but omitted by Amendment No. 125 include the following:
- 1. Action 2 - Condition (a) was revised to require the inoperable channel to be placed in the tripped condition within "1" hour versus "8" hours.
- 2. Action 2 - Condition (b) was revised to allow an inoperable channel to be "returned to the untripped condition" versus "bypassed" for surveillance testing.
- 3. Action 3 - A sentence was added to Action 3 as follows, "However, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.1, provided the other channel is OPERABLE."
Although all of these changes were approved by Amendment No. 117 by NRC letter dated December 13, 1988, SCE inadvertently omitted these changes when providing documentation to support the NRC for Amendment No. 125.
8905170018 890509 PDR ADOCK 05000206 P
Document Control Desk
-2 The purpose of this letter is to inform you of these omissions and request that these changes be reinstated into the Table Notation page. It should be noted that an additional change to this page to incorporate a footnote for the Intermediate Range, Neutron Flux Channels for the new Nuclear Instrumentation System (NIS) is currently under NRC review (Amendment Application No. 169 submitted by SCE letter dated April 11, 1989).
The proposed Table Notation page included with Amendment Application No. 169 includes the previously omitted changes. Therefore, issuance of this page as submitted in Amendement Application No. 169 will correct these omissions. However, if the changes requested by Amendment Application No. 169 are not deemed necessary by the NRC, it is requested that the NRC reissue the Table Notation page with the previous omissions included. Accordingly, Enclosure 1 to this letter contains two versions of this page. The first version (Enclosure 1A) is provided in the event the NRC considers it appropriate to issue Amendment Application No.
169. This version includes the change requested by Amendment Application No.
169 with a change bar to indicate the change, and also includes the previous omissions. The second version (Enclosure 18) is provided in the event Amendment Application No. 169 is not deemed necessary by the NRC. This version includes the previous omissions but does not include the amendment application change.
If you have any questions or require additional information, please let me know.
Very truly yours, Enclosure cc: J. B. Martin, Regional Administrator, NRC Region V F. R. Huey, NRC Senior Resident Inspector, San Onofre Units 1, 2 and 3 Two Versions of Table Notation Page For Table 3.5.1-1 A
TABLE 3.5.1-1 (Continued)
TABLE NOTATION With the reactor trip system breakers in the closed position, the control rod drive system capable of rod withdrawal.
A "TRIP" will stop all rod withdrawal.
Startup Rate Circuit enabled at 10-4% reactor power.
The provisions of Specification 3.0.4 are not applicable.
Below the Source Range High Voltage Cutoff Setpoint.
Below the P-7 (At Power Reactor Trip Defeat) Setpoint.
Above the P-7 (At Power Reactor Trip Defeat) Setpoint.
ACTION STATEMENTS ACTION 1 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE 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 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 2 -
With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are met:
- a. The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be returned to the untripped condition for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of other channels per Specification 4.1.
ACTION 3 -
With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
- a. Below the Source Range High Voltage Cutoff Setpoint, restore the inoperable channel-to OPERABLE status prior to increasing THERMAL POWER above the Source Range High Voltage Cutoff Setpoint.
- b. Above the Source Range High Voltage Cutoff Setpoint but below 10 percent of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10 percent of RATED THERMAL POWER.
However, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.1, provided the other channel is OPERABLE.
ACTION 4 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive reactivity changes.
Enclosure lB TABLE 3.5.1-1 (Continued)
TABLE NOTATION With the reactor trip system breakers in the closed position, the control rod drive system capable of rod withdrawal.
A "TRIP" will stop all rod withdrawal.
The provisions of Specification 3.0.4 are not applicable.
Below the Source Range High Voltage Cutoff Setpoint.
Below the P-7 (At Power Reactor Trip Defeat) Setpoint.
Above the P-7 (At Power Reactor Trip Defeat) Setpoint.
- Above the P-8 Setpoint.
ACTION STATEMENTS ACTION 1 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE 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 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 2 -
With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are met:
- a. The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be returned to the untripped condition for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of other channels per Specification 4.1.
ACTION 3 -
With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
- a. Below the Source Range High Voltage Cutoff Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the Source Range High Voltage Cutoff Setpoint.
- b. Above the Source Range High Voltage Cutoff Setpoint but below 10 percent of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10 percent of RATED THERMAL POWER.
However, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.1, provided the other channel is OPERABLE.
ACTION 4 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive reactivity changes.
ACTION 5 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.5.2 as applicable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.