ML18092A378
| ML18092A378 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/15/1984 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18092A377 | List: |
| References | |
| NUDOCS 8411210024 | |
| Download: ML18092A378 (4) | |
Text
REACTOR COOLANT SYSTEM HOT STANDBY LIMITING CONDITION FOR OPERATION 3.4.1.2 a.
At least two of the reactor coolant loops listed below shall be OPERABLE:
- 1. Reactor Coolant Loop 21 and its associated steam generator and reactor coolant pump, 2 *. Reactor Coolant Loop 22 and its associated steam generator and reactor cool ant pump,
- 3. Reactor Coolant Loop 23 and its associated steam generator and reactor coolant pump,
- 4.
Reactor Coolant Loop 24 and its associated steam generator and reactor coo 1 ant pump.
- b.
At least one of the above coo 1 ant loops shal 1
- be in operations* when the rod control system is deener gi zed**.
- c. At least two of the above coolant loops shall be in operation when the rod control system is energized***
APPLICABILITY:
MODE 3 ACTION:
- a. With less than the above required reactor coolant loops OPERABLE, restore the required loops 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 SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- b.
With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operations.
SALEM - UNIT 1 3/4 4-2
'HOT STANDBY SURVEILLANCE RE~IREMENTS 4.4.1.2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined to *be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.
4.4.1.2.2 At least one cooling loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.4.1.2.3 The required steam generator(s) shall be determined OPERABLE by verifying secondary side water level to be greater than or equal to 5% (narrow range) at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- All reactor coolant pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided: (1) no operations are permitted that '1.0Uld cause dilution of the reactor coolant system boron concentration (2) core outlet temperature is maintained at least 10°F below saturation temperature, and (3) the rod control system is de-energized**
- The rod control system shall be considered de-energized when o ne or rm re of the fo 11 ow i n g co n di ti o n s ex i st :
- 1)
Both Rod Drive MG set motor breakers are open.
- 2)
Both Rod Drive MG set generator breakers are open.
- 3)
A combination of at least three of the Reactor Trip and/or Reactor Trip Bypass Breakers are open.
If none of the above conditions for de-energizing the rod control system are met; the system shall be considered energized.
SALEM - UNIT 1 3/4 4-2a
REACTOR COOLANT SYSTEM HOT STANDBY LIMITING CONDITION FOR OPERATION 3.4.1.2 a.
At least two of the reactor coolant loops listed below shall be OPERABLE:
- 1.
Reactor Coo 1 ant Loop 21 and its as so ci ated steam generator and reactor coo 1 ant pump,
- 2.
Reactor Coo 1 ant Loop 22 and its associated steam generator and reactor coo 1 ant pump,
- 3.
Reactor Coolant Loop 23 and its as so Ci ated steam generator and reactor coo 1 ant pump,
- 4.
Reactor Coolant Loop 24 and its as so ci ated steam generator and reactor coo 1 ant pump.
- b.
At least one of the above cool ant loops shall be operations* when the rod control system is deener gi zed**.
in
- c.
At least two of the above coolant loops shall be in operation when the rod control system is energized**~
APPLICABILITY:
MOOE 3 ACTION:
- a.
With less than the above required reactor coola.nt loops OPERABLE, restore the required loops 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 SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- b.
With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operations.
. SALEM - UNIT 2 3/4 4-2
- HOT STANDBY SURVEILLANCE REQUIREMENTS 4.4.1.2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.
4.4.1.2.2 At least one cooling loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.4.1.2.3 The required steam generator(s) shall be determined OPERABLE by verifying secondary side water level to be greater than or* equal. to 53 (narrow range) at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- All reactor coolant pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided: (1) no operations are permitted that w:>uld cause dilution of the reactor coolant system boron concentration (2) core outlet temperature is maintained at least l0°F below
- saturation temperature, and (3) the rod control system is de-energized**
- The rod control system shall be considered de-energized when one or more of the following conditions exist:
- 1)
Both Rod Drive MG set 1TDtor breakers are open.
- 2)
Both Rod Ori ve MG set generator breakers are open.
- 3)
A combination of at least three of the Reactor Trip and/or Reactor Trip Bypass Breakers are open.
If none of the above conditions for de-energizing the rod control system are met; the system shall be considered energized.
SALEM - UNIT 2 3/4 4-2a I