ML20079S165
| ML20079S165 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek |
| Issue date: | 10/21/1994 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20079S158 | List: |
| References | |
| NUDOCS 9410260082 | |
| Download: ML20079S165 (3) | |
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Attachment IV to CO 94-0028 Page 1 of 3 Attachment IV l
Proposed Technical Specification Changes l
EBA 2288Bi! 8868A2 P
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Attachment IV to CO 94-0028 Page 2 of 3 i
INSTRUMENTATION 3/4.3 2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION i
3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their Trip Setpoints set consistent with the values shown in the Trip Setpcint 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:
- a. With an ESFAS Instrumentation or Interlock Trip Setpoint less conserva-tive than the value shown in the Trip Setpoint column but more conser-vative than the value shown in the Allowable Value column of Table 3.3-4 i
adjust the Setpoint consistent with the Trip Setpoint value.
- b. With an ESFAS Instrumentation or interlock Trip Setpoint less conserva-tive than the value shown in the Allowable Values column of Table 3.3-4, either:
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- 1. Adjust the Setpoint consistent with the Trip Setpoint value of 1
Table 3.3-4 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 was satisfied for the affected channel, or I
- 2. Declare the channelinoperable and apply the applicable ACTION statement requirements of Table 3.3-3 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
Equation 2.2-1 Z + R + S 5 TA Where:
Z = The value from Column Z of Table 3.3-4 for the affected channel, R = The "as measured" value (in percent span) of rack error for the affected channel, S = Either the "as measured" value (in percent span) of the sensor error, or the value from Column S (Sensor Error) of Table 3.3-4 for the affected channel, and TA = The value from Column TA (Total Allowance) of Table 3.3-4 for the affected channel.
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- c. With an ESFAS instrumentation channel or interlock inoperable, take the 1
ACTION shown in Table 3.3-3.
SURVEILLANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuation logic and relays shall be demonstrated OPERABLE by the performance of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3-2.
4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIM
- each ESFAS function shall be demonstrated to be within the limit at least once per 18 mo
- s. Each 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 per N times 18 months 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.
R-
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- The provisions of Specification 4.0.4 are not applicable for response time testing of the steam turbine-driven auxiliary feedwater pump for entry into MODE 3.
WOLF CREEK-UNIT 1 M3h
Attachment IV to CO 94-0028 Page 3 of 3 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- b. At least once per 31 days by:
- 1) Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position; and
- 2) Verifying that each automatic valve in the flow path is in the fully open position whenever the Auxiliary Feedwater System is placed in automatic control or when above 10% RATED THERMAL POWER
- c. At least once per 18 month y:
- 1) Verifying that each automatic valve in the ESW supply to the auxiliary feedwater pumps actuates to its full open position upon receipt of an Auxiliary Feedwater Pump Suction Pressure.
Low test signal,
- 2) Verifying that each auxiliary feedwater pump starts as designed automaticall n receipt of angFeedwater et tion test na he provisions of Speicification 4.4. Are not applicable for entry into Mode 3, n
- 3) Verifying that each auxiliary feedwater motor-operated discharge valve limits the flow to each steam generator from the motor-driven pump to less than or equal to 320 gpm.
4.7.1.2.2 An auxiliary feedwater flow path shall be demonstrated OPERABLE following each COLD SHUTDOWN of greater than 30 days prior to entering MODE 2 by venfying normal flow to at least two steam generators from one auxiliary feedwater pump.
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I WOLF CREEK - UNIT 1 3/4 7-5 Amendment No. 77 I
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