ML062900271
| ML062900271 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/13/2006 |
| From: | Stewart Bailey NRC/NRR/ADRO/DORL/LPLI-2 |
| To: | |
| Bailey S N | |
| Shared Package | |
| ML062690463 | List: |
| References | |
| TAC MC9337, TAC MC9338 | |
| Download: ML062900271 (14) | |
Text
(1)
Maximum Power Level PSEG Nuclear LLC is authorized to operate the facility at a steady state reactor core power level not in excess of 3459 megawatts (one hundred percent of rated core power).
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 27 5 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Deleted per Amendment 22, 11-20-79 (4)
Less than Four Loop Operation PSEG Nuclear LLC shall not operate the reactor at power levels above P-7 (as defined in Table 3.3-1 of Specification 3.3.1.1 of Appendix A to this license) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation at power levels above P-7 has been granted by the Commission by Amendment of this license.
(5)
PSEG Nuclear LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report, and as approved in the NRC Safety Evaluation Report dated November 20, 1979, and its supplements, subject to the following provision:
PSEG Nuclear LLC may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
Amendment No.
275
REFUELING OPERATIONS INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, two source range neutron flux monitors shall be operating, each with continuous visual indication in the control room and one with audible indication in the containment and control room.
APPLICABILITY:
MODE 6.
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.2 Each source range neutron flux monitor shall be demonstrated OPERABLE by performance of:
- a.
A CHANNEL FUNCTIONAL TEST at least once per 7 days, and
- b.
A CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS.
SALEM - UNIT 1 3/4 9-2 Amendment No.
275
SPECIAL TEST EXCEPTION NO FLOW TESTS LIMITING CONDITION FOR OPERATION 3.10.4 The limitations of Specification 3.4.1.1 may be suspended during the performance of startup and PHYSICS TESTS, provided:
- a.
The THERMAL POWER does not exceed the P-7 Interlock Setpoint, and
- b.
The Reactor Trip Setpoints on the OPERABLE Intermediate and Power Range Channels are set 5 25% of RATED THERMAL POWER APPLICABILITY:
During operation below the P-7 Interlock Setpoint.
ACTION:
With the THERMAL POWER greater than the P-7 Interlock Setpoint, immediately open the reactor trip breakers.
SURVEILLANCE REQUIREMENTS 4.10.4.1 The THERMAL POWER shall be determined to be less than P-7 Interlock Setpoint at least once per hour during startup and PHYSICS TESTS.
4.10.4.2 Each Intermediate, Power Range Channel and P-7 Interlock shall be subjected to a CHANNEL FUNCTIONAL TEST prior to initiating startup or PHYSICS TESTS.
SALEM - UNIT.1 3/4 10-4 Amendment No.
275
SPECIAL TEST EXCEPTIONS PHYSICS TESTS LIMITING CONDITION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.4, and 3.1.3.5 may be suspended during the performance of PHYSICS TESTS provided:
- a.
The THERMAL POWER does not exceed 5% of RATED THERMAL POWER, and
- b.
The reactor trip setpoints on the OPERABLE Intermediate and Power Range Nuclear Channels are set at
- 25% of RATED THERMAL POWER.
APPLICABILITY:
MODE 2.
ACTION:
With the THERMAL POWER > 5% of RATED THERMAL POWER, immediately open the reactor trip breakers.
SURVEILLANCE REQUIREMENTS 4.10.3.1 The THERMAL POWER shall be determined to be
- 5% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.
4.10.3.2 Each Intermediate and Power Range Channel shall be subjected to a CHANNEL FUNCTIONAL TEST prior to initiating PHYSICS TESTS.
SALEM - UNIT 1 3/4 10-3 Amendment No. 275 (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 2.57, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Special Low Power Test Program PSE&G shall complete the training portion of the Special Low Power Test Program in accordance with PSE&G's letter dated September 5, 1980 and in accordance with the Commission's Safety Evaluation Report "Special Low Power Test Program", dated August 22, 1980 (See Amendment No. 2 to DPR-75 for the Salem Nuclear Generating Station, Unit No. 2) prior to operating the facility at a power level above five percent.
Within 31 days following completion of the power ascension testing program outlined in Chapter 13 of the Final Safety Analysis Report, PSE&G shall perform a boron mixing and cooldown test using decay heat and Natural Circulation.
PSE&G shall submit the test procedure to the NRC for review and approval prior to performance of the test. The results of this test shall be submitted to the NRC prior to starting up following the first refueling outage.
(4)
Initial Test Program PSE&G shall conduct the post-fuel loading initial test program (set forth in Chapter 13 of the Final Safety Analysis Report, as amended) without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:
(a)
Elimination of any test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential; (b)
Modification of test objectives, methods or acceptance criteria for any test identified in Chapter 13 of the Final Safety Analysis. Report, as amended, as essential; (c)
Performance of any test at a power level different by more than five percent of rated power from there described; and Amendment No.25 7
REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, two source range neutron flux monitors shall be operating, each with continuous visual indication in the control room and one with audible indication in the containment and control room.
APPLICABILITY:
MODE 6.
ACTION:
- a.
With one of the above required monitors inoperable, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
- b.
With both of the required monitors inoperable, determine the boron concentration of the reactor coolant system at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- c.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.2 Each source range neutron flux monitor shall be demonstrated OPERABLE by performance of:
a.*
A CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and
- b.
A CHANNEL FUNCTIONAL TEST at least once per 7 days.
SALEM - UNIT 2 3/4 9-2 Amendment No. 257
SPECIAL TEST EXCEPTIONS PHYSICS TESTS LIMITING CONDITION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.1.3, 3.1.1.4, 3.1.3.1, 3.1.3.4 and 3.1.3.5 may be suspended during the performance of PHYSICS TESTS provided:
- a.
The THERMAL POWER does not exceed 5% of RATED THERMAL POWER,
- b.
The reactor trip setpoints on the OPERABLE Intermediate and Power Range Nuclear Channels are set at less than or equal to 25% of RATED THERMAL POWER, and
- c.
The Reactor Coolant System lowest operating loop temperature (Tavg) is greater than or equal to 531 0 F.
APPLICABILITY:
MODE 2.
ACTION:
- a.
With the THERMAL POWER greater than 5% of RATED THERMAL POWER, immediately open the reactor trip breakers.
- b.
With a Reactor Coolant System operating loop temperature (Tavg) less than 531 0F, restore Tavg to within its limit within 15 minutes or be in at least HOT STANDBY within the next 15 minutes.
SURVEILLANCE REQUIREMENTS 4.10.3.1 The THERMAL POWER shall be determined to be less than or equal to 5% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.
4.10.3.2 Each Intermediate and Power Range Channel shall be subjected to a CHANNEL FUNCTIONAL TEST prior to initiating PHYSICS TESTS.
4.10.3.3 The Reactor Coolant System temperature (Tavg) shall be determined to be greater than or equal to 531OF at least once per 30 minutes during PHYSICS TESTS.
SALEM - UNIT 2 3/4 10-4 Amendment No. 257
SPECIAL TEST EXCEPTIONS NO FLOW TESTS LIMITING CONDITION FOR OPERATION 3.10.4 The limitations of Specification 3.4.1.1 may be suspended during the performance-of startup and PHYSICS TESTS, provided:
- a.
The THERMAL POWER does not exceed the P-7 Interlock Setpoint, and
- b.
The Reactor Trip Setpoints on the OPERABLE Intermediate and Power Range Channels are set less than or equal to 25% of RATED THERMAL POWER APPLICABILITY:
During operation below the P-7 Interlock Setpoint.
ACTION:
With the THERMAL POWER greater than the P-7 Interlock Setpoint, immediately open the reactor trip breakers.
SURVEILLANCE REQUIREMENTS 4.10.4.1 The THERMAL POWER shall be determined to be less than P-7 Interlock Setpoint at least once per hour during startup and PHYSICS TESTS.
4.10.4.2 Each Intermediate, Power Range Channel and P-7 Interlock shall be subjected to a CHANNEL FUNCTIONAL TEST prior to initiating startup or PHYSICS TESTS.
SALEM -
UNIT 2 3/4 10-5 Amendment No. 257