ML20036B384
| ML20036B384 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/14/1993 |
| From: | TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20036B383 | List: |
| References | |
| NUDOCS 9305190342 | |
| Download: ML20036B384 (9) | |
Text
{{#Wiki_filter:-. 4 ATTACHMENT 3 to TXX-93207 AFFECTED TECHNICAL SPECIFICATION PAGES i (NUREG - 1468) (8 PAGES) l (3/4-1, 3/4-2, 3/4-5, 3/4-6, 3/5-7, 3/4-8, 3/4-11, and 3/4-12) Note: There are no changes on pages 3/4-1, 3/4-7 and 3/4-11. These t pages are included because they are on the back side in NUREG-1468 of the affected pages. h l I i i f i i i I 9305190342 930514 l DR ADOCK 05000445 p PDR
U to TXX-93207 Page 1 of 8 i 3/4.3 INSTRUMENTATION 1 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTAT'ON llMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE. APPLICABILITY: As shown in Table 3.3-1. ACTION: As shown in Table 3.3-1. I t SURVEILLANCE REOUIREMENTS 4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic.chall be demonstrated OPERABLE by the performance of the Reactor Trip System lastrumentation Surveillance Requirements specified in Table 4.3-1. 4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be demonstrated to be within its limit at least once par 18 months. Eacn test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months 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. 1 I COMANCHE PEAK - UNITS i AND 2 3/4 3-1 i I
m> TABLE 3.3_1 j,3 g n REACTOR TRIP SYSTEM INSTRUMENTATION N* M 5 MINIMUM co " m TOTAL NO. CHANNELS CHANNELS APPLICABLE g FUNCTIONAL UNIT OF CHANNELS 1.0 TRIP OPERABLE N00ES ACTION E l. Manual Reactor Trip 2 1 2 1, 2 1 k zZ 2 1 2 3*, 4*, 5" 9 8 ~ 2. Power Range, Neutron Flux R a. High Setpoint 4 2 3 1, 2 2 o b. Low Setpoint 4 2 3 l', 2 2 3. Power Range, Neutron Flux, 4 2 3 1, 2 2 High Positive Rate ui 4. Power Range, Neutron Flux, 4 2 3 1, 2 2 High Negative Rate u N 5. Intermediate Range, Neutron Flux 2 1 2 1*, 2 3 6. Source Range, Neutron Flux a. Reactor Trip and Indication 6 1) Startup 2 1 2 2 4 2) Shutdown 2 1 2 3,4,5 5.1 } b. Boron Dilution Flux Doubling
- 2 1
2 3",4, 5 5.1,5.2 7. Overtemperature N-16 4 2 3 1, 2 12 ~ 8. Overpower N-16 4 2 3 1, 2 12 d 9. Pressurizer Pressure--Low 4 2 3 I 6 g 10. Pressurizer Pressure -High 4 2 3-1, 2 6 h Onit i Cycic 3.
- gDJ1ut_lon Flux Doubling _ requirements become effective for Unit I ni-E.O'after criticality ford
?> wa y I N GE_sidtd m M E QC-irItili criticeMS to TXX-93207 Page 3 of 8 TABLE 3,3-1 (Continued) TABLE NOTATIONS
- Only if the reactor trip breakers happen to be in the closed position and the Control Rod Drive System is capable of rod withdrawal.
'Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint. 'Below de P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint. 8Above the P-7 (At Power) Setpoint ' Deleted. 'Above the P-8 (3-loop flow permissive) Setpoint. 'Above the P-7 and below the P-8 Setpoints. "The boron dilution flux doubling signals may be blocked during reactor startup.* 'Above the P-9 (Reactor trip on Turbine trip Interlock) 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 hours or be in HOT STANDBY within the next 6 hours. 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 satisfied: a. The inoperable channel is placed in the tripped condition within 6 hours, b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed fo: up to 4 hours for surveillance testing of other channels per Specification 4.3.1.1, and i c. Either, THEPRAL POWER is restricted to less than or equal to 75% of RATED THEPEAL POWER and the Power Range Neutron Flux i Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours per i Specification 4.2.4.2. j
- Boron Dilution Flux Doubgig_ egg,.Unitjg&.g.g t.
t-COMANCHE PEAK - UNITS 1 AND 2 3/4 2-5 Unit 1 - Amendment No. 19, 13,
' to TXX-93207 Page 4 of 8 TABLE 3.3-1 (Continued) ACTION STATEMENTS (Continued) ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level: Below the P-6 (Intermediate Range Neutron Flux Interlock) a. Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERML POWER above the P-6 Setpoint, b. Above the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing l THERMAL POWER above 10% of RATED THERMAL POWER. ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving i positive reactivity changes. ACTION 5.1-With the number of OPERABLE channels one less than the Minimum l J Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours or within the next hour open the I reactor trip breakers and suspend all operations involving positive reactivity changes. With no channels OPERABLE complete l the above actions within 4 hours. ACTION 5.2*- With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours or within the next hour verify either valve CS-8455 or valves CS-8560, FCV-1118, CS-8439, CS-84al, and CS-8453 are closed and secured in position, and verify this position at least once per 14 days thereafter. With no channels OPERABLE, complete the above actions within 4 hours and i verify the positions of the above valves at least once per 14 days thereafter. ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPEP.ATION may proceed provided the following conditions are satisfied: a. The inoperable channel is placed in the tripped condition within 6 hours, and b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours for surveillance testing of other channels per Specification 4.3.1.1. i ACTION 7 - With less than the Minimum Number of Channels OPERABLE, within I hour determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3. and Unit 2
- Boron Dilution Flux Doublino requirements-become effective _for Unit hh after_ criticality MCydd 3 ihd for Unit 2 six scaths _ after ; n i t itt-Qriticy iti.-{tNf I Cyc,Ie COMANCHE PEAK - UNITS 1 AND 2 3/4 3-6 Unit 1 - Amendment No, 10, 14
. to TXX-93207 Page 5 of 8 TABLE 3.3-1 (Continued) ACTION STATEMENTS (Continued) ACTION 8 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1 or maintenance, provided the other channel is OPERABLE. ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours or open the reactor trip breakers within the next hour. ACTION 10 - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours. ACTION 11 - With one of the diverse trip features (undervoltAge or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours or declare the breaker inoperable and apply ACTION 8. The breaker shall not be bypassed while one of the diverse trip fea-tures is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status, during which time ACTION 8 applies. ACTION 12 - 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 satisfied: i a. The inoperable channel is placed in the tripped condition within 6 hours, and b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours for surveillance testing per Specifications 4.3.1 1 or 4.2.5.4. ACTION 13 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours or be in at least HOT STANDBY within the next 6 hours; however, one channel may be bypassed for up to 4 hours for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE. P C0KANCHE PEAK - UNITS 1 AND 2 3/4 3-7 Unit 1 - Amendment No. 13
IN LAELE 4.3-1 %0 cn9 REAC10R TRIP SYSTEN INSTRUMENTATION SURVEILLANCE REQUIREMENTS b o8 M TRIP "' S M ANALOG ACTUATING H0 DES FOR c% CHANNEL DEVICE WillCil CllA*4NEL CilANNEL OPERATIONAL OPERATIONAL AC10AT10N SURVEllLANCE o g FUNCTIcNAL UNIT CilECK CAllBRATION TEST TEST LOGIC IIST IS REQUIRED _ g E 1. Nanual Reactor Trip N.A. N.A. N.A. R(14) N.A. i, 2, 3*, 4*,5* 0 m 2. Power Range, Neutron Flux S a. High Setpoint 5 0(2, 4), Q N.A. N.A. 1, 2 ~ R N(3,4), Q(4,6), R(4, 5) b. Low Setpoint 5 R(4) S/U(1) N.A. N.A. 1*, 2 3. Power Range, Neutron Flux, ft. A. R(4) Q N.A. N.A. 1, 2 g liigh Positive Rate 4. Power Range, Neutron Flux, N.A. R(4) Q N.A. N.A. 1, 2 'r' High Negative Rate os 5. Intermediate Range, S R(4, 5) S/U(1) N.A. N.A. 1*, 2 Neutron Flux 6 6. Source Range, Neutron Flux 5 R(4, 13) S/U(1),Q(9) R(12)* N.A. 2, 3, 4, 5 g 7. Overtemperature N-16 S D(2,4), Q N.A. N.A. 1, 2 N(3,4), Q(4,6), l R(4,5) ( ( 8. Overpower N-16 S D(2,4), Q N.A. N.A. 1, 2 R(4, 5) a d 9. Pressuc;zer Pressure--Low S R Q(8) N.A. N.A. I n (
- 10. Pressurizer Pressure--liigh 5
R Q N.A. N.A. 1, 2 x P i and OnW E Unit i.. Cycle 4. l L l Dilut ton Flux Doublina reautrements become effective for Unit I +4*-menW after criticality for l 5 3 :nd Yer "nf t'2 21,; i: nth;if tfr intthrWitidh ~ y
. t- -93207 Page 7 of 8 TABLE 4.3-1 (Continued) TABLE NOTATIONS "Only if the reactor trip breakers happen to be in the closed position and the r Control Rod Drive System is capable of rod withdrawal.
- Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
'Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint. dAbove the P-7 (At Power) Setpoint. 'Above the P-9 (Reactor trip on Turbine trip Interlock) Setpoint. (1) If not performed in previous 31 days. (2) Comparison of calorimetric to excore power and N-16 power indication above 15% of RATED THERMAL POWER. Adjust excore channel and/or N-16 channel gains consistent with calorimetric power if absolute difference of the respective channel is greater than 2%. The provisions of Specification 4.0.4 are not applicable for entry into MODE 1 or 2. (3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15% of RATED THERMAL POWER. Recalibrate if the absolute difference is greater than or equal to 3%. Fcr the purpose of these surveillance requirements, "M" is defined as at least once per 31 EFPD. The provisions of Specification 4.0.4 are not applicable for entry into MODE 1 or 2. (4) Neutron and N-16 detectors may be excluded from CRANNEL CALIBRATION. (5) Detector plateau curves shall be obtained and evaluated. For the Intermediate Range Neutron Flux, Power Raage Neutron Flux and N-16 channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 1 or 2. (6) Incore-Excore Calibration, above 75% of RATED THERMAL POWER. For the purpose of these surveillance requirements "Q" is defined as at least once per 92 EFPD. The provisions of Specification 4.0.4 are not applicable for l entry into MODE 1 or 2. I (7) Each train shall be tested at least every 62 days on a STAGGERED TEST 1 BASIS. (8) The MODES specified for these channels in Table 4.3-2 are more restrictive and therefore applicable. l CDMANCHE PEAX - UNITS 1 AND 2 3/4 3-11 j
. to TXX-93207 Page 8 of 8 TABLE 4.3-1 (Continued) TABLE NOTATIONS (Continued) (9) Quarterly surveillance in H0 DES 3', 4', and 5' shall also include verifica-tion that pemissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window. Quarterly surveillance shall include verification of the Boron Dilution Alarm Setpoint of less than or equal to an increase of twice the count rate within a 10-minute period.* (10) Setpoint verification is not applicable. (11) The TRIP ACTUATING DEVICE OPEPATIONAL TEST shall independently verify the OPEPABILITY of the undervoltage and shunt trip attachments of the reactor trip breakers. (12) At least once per 18 months during shutdown, verify that on a simulated Boron Dilution Flux Doubling test signal the nomal CVCS discharge valves close and the centrifugal charging pumps suction valves from the RWST open.* (13) With the high voltage setting varied as recommended by the manufacturer, an initial discriminator bias curve shall be measured for each detector. Subsequent discriminator bias curves shall be obtained, evaluated and compared to the initial curves. (14) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s). (15) Local manual shunt trip prior to placing breaker in service. (16) Automatic undervoltage trip. j 4 l i o, net unit ?. Dilution Flux Doubling g.._s become ef_fectiv_e for Unit 1 A*-fer Mt 2 Tif 5th! i. 7 fier criticality fon.,.... ([0r1!!:;lhy. Ohit 1} C.ycle]._ COMANCHE PEAK - UNITS 1 AND 2 3/4 3-12 Unit 1 - Amendment No. 19, 14}}