ML061520240
| ML061520240 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/31/2006 |
| From: | Plant Licensing Branch III-2 |
| To: | |
| References | |
| Download: ML061520240 (6) | |
Text
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 254, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Special Low Power Test Proqram 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. 254
EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - Tavg < 350°F SURVEILLANCE REQUIREMENTS 4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per applicable Surveillance Requirements of 4.5.2.
4.5.3.2 All safety injection pumps and centrifugal charging pumps, except the above required OPERABLE pump, shall be demonstrated to'be inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while in MODE 4 and the temperature of one or more of the RCS cold legs is less than or equal to 3120 F, MODE 5, or MODE 6 when the head is on the reactor vessel by either of the following methods:
- a.
By verifying that the motor circuit breakers have been removed from their electrical power supply circuits or,
- b.
By verifying that the pump is in a recirculation flow path and that two independent means of preventing RCS injection are utilized.
SALEM - UNIT 2 3/4 5-8 Amendment No. 254
EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)
With the RCS temperature below 3500 F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.
The limitation for a maximum of one safety injection pump or one centrifugal charging pump to be OPERABLE and the Surveillance requirement to verify all safety injection pumps except the allowed OPERABLE safety injection pump to be inoperable below 312'F provides assurance that a mass addition pressure transient can be relieved by the operation of a single POPS relief valve.
When running a safety injection pump with the RCS temperature less than 350OF with a potential for injecting into the RCS and creating a mass addition pressure transient, two independent means of preventing reactor coolant system injection will be utilized.
The two independent means can be satisfied by any one of the following methods:
(1) A manual isolation valve locked in the close position; or (2)
Two manual isolation valves closed; or (3)
One motor operated valve closed and its breaker de-energized and control circuit fuses removed.
The surveillance requirements, which are provided to ensure the OPERABILITY of each component, ensure that, at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained.
The safety analyses make the assumptions with respect to:
- 1) both the maximum and minimum total system resistance, and 2) both the maximum and minimum branch injection line resistance.
These resistances, in conjunction with the ranges of potential pump performance, are used to calculate the maximum and minimum ECCS flow assumed in the safety analyses.
The maximum and minimum flow surveillance requirements in conjunction with the maximum and minimum pump performance curves ensures that the assumptions of total system resistance and the distribution of that system resistance among the various paths are met.
The maximum total pump flow surveillance requirements ensure the pump runout limits of 560 gpm for the centrifugal charging pumps and 675 gpm for the safety injection pumps are not exceeded.
Due to the effect of pump suction boost alignment, the runout limits for the surveillance criteria are <
554 gpm for C/SI pumps,
- 664 gpm for SI pumps in cold leg alignment and
- 654 gpm for SI pumps in hot leg alignment.
The surveillance requirement for the maximum difference between the maximum and minimum individual injection line flows ensure that the minimum individual injection line resistance assumed for the spilling line following a LOCA is met.
3/4.5.4 SEAL INJECTION FLOW The Reactor Coolant Pump (RCP) seal injection flow restriction limits the amount of ECCS flow that would be diverted from the injection path following an ECCS actuation.
This limit is based on safety analysis assumptions, since RCP seal injection flow is not isolated during Safety Injection (SI).
SALEM - UNIT 2 B 3/4 5-2 Amendment No. 254 (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. '273 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. 273
EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - Tavg < 350°F SURVEILLANCE REQUIREMENTS 4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per applicable Surveillance Requirements of 4.5.2.
4.5.3.2 All safety injection pumps and centrifugal charging pumps, except the above required OPERABLE pump, shall be demonstrated to be inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while in MODE 4 and the temperature of one or more of the RCS cold legs is less than or equal to 312 0 F, MODE 5, or MODE 6 when the head is on the reactor vessel by either of the following methods:
- a.
By verifying that the motor circuit breakers have been removed from their electrical power supply circuits or,
- b.
By verifying that the pump is in a recirculation flow path and that two independent means of preventing RCS injection are utilized.
SALEM -
UNIT 1 3/4 5-6a Amendment No. 273
3/4.5 EMERGENCY CORE COOLING SYSTEMS BASES 3/4.5.1 ACCUMULATORS The OPERABILITY of each RCS accumulator ensures that a sufficient volume of borated water will be immediately forced into the reactor core through each of the cold legs in the event the RCS pressure falls below the pressure of the accumulators. This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures.
The limits on accumulator volume, boron concentration and pressure ensure that the assumptions used for accumulator injection in the safety analysis are met.
The accumulator power operated isolation valves are considered to be "operating bypasses" in the context of IEEE Std. 279-1971, which requires that bypasses of a protective function be removed automatically whenever permissive conditions are not met. In addition, as these accumulator isolation valves fail to meet single failure criteria, removal of power to the valves is required.
The limits for operation with an accumulator inoperable for any reason except an isolation valve closed minimizes the time exposure of the plant to a LOCA event occurring concurrent with failure of an additional accumulator which may result in unacceptable peak cladding temperatures.
If a closed isolation valve cannot be immediately opened, the full capability of one accumulator is not available and prompt action is required to place the reactor in a mode where this capability is not required.
3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABILITY of two independent ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration.
Either subsystem operating in conjunction with the accumulators is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest RCS cold leg pipe downward. In addition, each ECCS subsystem provides long term core cooling capability in the recirculation mode during the accident recovery period.
The limitation for a maximum of one safety injection pump or centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all safety injection pumps except the allowed OPERABLE pump to be inoperable below 3120F provides assurance that a mass addition pressure transient can be relieved by the operation of a single POPs relief valve.
When running a safety injection pump with the RCS temperature less than 350°F with a potential for injecting into the RCS and creating a mass addition pressure transient, two independent means of preventing reactor coolant system injection will be utilized.
The two independent means can be satisfied by any one of the following methods:
(1) A manual isolation valve locked in the close position; or (2)
Two manual isolation valves closed; or (3) One motor operated valve closed and its breaker de-energized and control circuit fuses removed.
SALEM - UNIT 1 B 3/4 5-1 Amendment No.273