ML070810420
| ML070810420 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/19/2007 |
| From: | Plant Licensing Branch III-2 |
| To: | |
| Ennis R, NRR/DORL, 415-1420 | |
| Shared Package | |
| ML070530283 | List: |
| References | |
| TAC MD1491 | |
| Download: ML070810420 (7) | |
Text
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4 -
(2)
Technical Specifications and Environmental Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.261, 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.
2 6 1
FUNCTIONAL UNIT
- 2.
Power Range, Neutron Flu
- 3.
Power Range, Neutron Flu High Positive Rate
- 4.
Deleted
- 5.
Intermediate
- Range, Neut Flux
- 6.
Source Range, Neutron Fl
- 7.
Overtemperature AT
- 8.
Overpower AT TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS TRIP SETPOINT ALLOWABLE VALUES Not applicable Not applicable ix Low setpoint -
- 25 % of RATED Low Setpoint -
- 26% of RATED THERMAL POWER THERMAL POWER High Setpoint
- 109% of RATED High Setpoint -
- 110% of RATED THERMAL POWER THERMAL POWER Lx,
- 5% of RATED THERMAL POWER with
- 5.5% of RATED THERMAL POWER a time constant Ž 2 second with a time constant Ž 2 second
- ron
- ux I
- 9.
Pressurizer Pressure--Low
- 10. Pressurizer Pressure--High
- 11. Pressurizer Water Level--
High
- 12.
Loss of Flow
- Design flow is 82,500 gpm per lo
< 25% of RATED THERMAL POWER
< 105 counts per second See Note 1 See Note 2 1865 psig 2385 psig 92% of instrument span 90% of design flow per loop*
- 30% of RATED THERMAL POWER 1.3 x 105 counts per second See Note 3 See Note 4
Ž 1855 psig
- 2395 psig
- 93% instrument span 89% of design flow per loop*
SALEM - UNIT 2 2-5 Amendment No. 2 6 1
.POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.
4.2.2.2 FxY shall be evaluated to determine if FQ(Z) is within its limit by:
- a.
Using the movable incore detectors to obtain a power distribution map:
- 1. When THERMAL POWER is
- 25%,
but > 5% of RATED THERMAL POWER, or
- 2.
When the Power Distribution Monitoring System (PDMS) is inoperable; and increasing the Measured FQ(Z) by the applicable manufacturing and measurement uncertainties as specified. in the COLR.
- b.
Using the PDMS or the moveable incore detectors when THERMAL POWER is
> 25% of RATED THERMAL
- POWER, and increasing the measured FQ(Z) by the applicable manufacturing and measurement uncertainties as specified in the COLR.
- c.
Comparing the Fx, computed (Fxyc) obtained in b, above to:
- 1.
The Fy limits for RATED THERMAL POWER (FxYRTP) for the appropriate measured core planes given in
- e. and f., below, and
- 2.
The relationship:
FxyL = FXYRTP
[1 + PFy(l-P)]
where FxyL is the limit for fractional THERMAL POWER operation expressed as a function of FXYRTP, PFY is the power factor multiplier for FxY in the COLR, and P is the fraction of RATED THERMAL POWER at which Fxy was measured.
- d.
Remeasuring Fxy according to the following schedule:
- 1.
When Fxyc is greater than the FxyRTP limit for the appropriate measured core plane but less than the F xL relationship, additional core power distribution measurements shall be taken and Fxyc compared to FXY and FxyL:
a)
Either within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding by 20% of RATED THERMAL POWER or greater, the THERMAL POWER at which FxYc was last determined, or b)
At least once per 31 EFPD, whichever occurs first.
SALEM -
UNIT 2 3/4 2-6 Amendment No.261
TO' FUNCTIONAL UNIT OF
- 1.
- 2.
Power Range, Neutron Flux
- 3.
Power Range, Neutron Flux High Positive Rate
- 4.
Deleted
- 5.
Intermediate Range, Neutron Flux
- 6.
Source Range, Neutron Flux A.
Startup B.
Shutdown
- 7.
Overtemperature AT
- 8.
Overpower AT
- 9.
Pressurizer Pressure-Low
- 10.
Pressurizer Pressure--High TAL N CHAN 2
4 4
TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM UMBER CHANNELS CHANNELS NELS TO TRIP OPERABLE 1
2 2
3 2
3 2
2 2
4 4
4 4
1 0
2 2
2 2
2 2
1 3
3 3
3 APPLICABLE MODES 1,2 and
- 1,2 and 3*
1,2 1,2 and
- 2##,
and
- 3,4 and 5 1,2 1,2 1,2 1,2 ACTION 12 2
2 3
4 5
6 6
6 6
SALEM -
UNIT 2 3/4 3-2 Amendment No.261
RE FUNCTIONAL UNIT
- 2.
Power Range, Neutron Flux
- 3.
Power Range, Neutron Flux, High Positive Rate
- 4.
Deleted TABLE 3.3-2 ACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES RESPONSE TIME NOT APPLICABLE
- 0.5 seconds*
NOT APPLICABLE 5.
6.
7.
8.
9.
10.
11.
Intermediate Range, Neutron Flux NOT APPLICABLE Source Range, Neutron Flux NOT APPLICABLE Overtemperature AT
- 5.75 seconds*
Overpower AT NOT APPLICABLE Pressurizer Pressure--Low 5 2.0 seconds Pressurizer Pressure--High
- 2.0 seconds Pressurizer Water Level--High NOT APPLICABLE
- Neutron detectors are exempt from response time testing.
Response
time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel.
SALEM -
UNIT 2 3/4 3-9 Amendment No.261
TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL FUNCTIONAL CALIBRATION TEST N.A.
R(9)
FUNCTIONAL UNIT
- 1.
Manual Reactor Trip Switch
- 2.
Power Range, Neutron Flux
- 3.
Power Range, Neutron Flux, High Positive Rate
- 4.
Deleted
- 5.
Intermediate Range, Neutron Flux
- 6.
Source Range, Neutron Flux CHANNEL CHECK N.A.
S N.A.
S S(7)
D (2),m (3) and Q(")
R (6)
R (6)
R( 6)
MODES IN WHICH SURVEILLANCE REQUIRED 1, 2, and
- 1, 2, and 3*
1, 2 Q
Q S/U(I 1
Q and S/U11) 7.
8.
9.
10.
11.
12.
Overtemperature AT Overpower AT Pressurizer Pressure--Low Pressurizer Pressure--High Pressurizer Water Level--High Loss of Flow -
Single Loop S
S S
S S
S R
R R
R R
R Q
Q Q
Q Q
Q 1,
2, 1,
1, 1,
1, 1,
1 2 and
- 3, 4,
5 and
- 2 2
2 2
2 SALEM -
UNIT 2 3/4 3-11 Amendment No261
3/4.9 REFUELING OPERATIONS BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 The boron concentration of the Reactor Coolant System, the fuel storage pool, the refueling canal, and the refueling cavity shall be maintained within the limit specified in the CORE OPERATING LIMITS REPORT (COLR).
APPLICABILITY:
MODE 6 (Only applicable to the refueling canal, the fuel storage pool and refueling cavity when connected to the Reactor Coolant System)
ACTION:
With the requirements of the above specification not satisfied, immediately
- a.
Suspend CORE ALTERATIONS and
- b. Suspend positive reactivity additions and
- c.
Initiate action to restore boron concentration to within limit specified in the COLR.
- d.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.1 Verify the boron concentration is within the limit of the COLR every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
SALEM -
UNIT 2 3/4 9-1 Amendment No.261