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Technical Specification Pages Re Power Distribution Limits, Surveillance Requirements
	ML061460433
Person / Time
Site:	Salem
Issue date:	05/25/2006
From:	Stewart Bailey; Plant Licensing Branch III-2
To:	;
References
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(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. 272 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. 272

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.2 FY 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 FY computed (Fcy) obtained in b, above to:

1.

The FY limits for RATED THERMAL POWER (FRTP,)

for the appropriate measured core planes given in e and f below, and

2.

The relationship:

FYL = FxyRTP [1+PFy (l-P)]

where FL Y is the limit for fractional THERMAL POWER operation expressed as a function of FTPXY, PFY is the power factor multiplier for FY in the COLR, and P is the fraction of RATED THERMAL POWER at which Fy was measured.

d.

Remeasuring FY according to the following schedule:

1.

When Fc, is greater than the FRT* limit for the appropriate measured core plane but less than the FLX relationship, additional core power distribution measurements shall be taken and FC,,

compared to F RTP X and FL a) Either within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding by 20% of RATED THERMAL POWER or greater, the THERMAL POWER at which FcY was last determined, or SALEM - UNIT 1 3/4 2-6 Amendment No.272

TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION INSTRUMENT

1. AREA MONITORS

a. Fuel Storage Area MINIMUM CHANNELS OPERABLE

2.

PROCESS MONITORS

a. Containment

1) Gaseous Activity a)

Purge & Pressure -

1#

Vacuum Relief Isolation b) RCS Leakage 1

Detection

2) Air Particulate Activity a)

(NOT USED)

APPLICABLE MODES 1,2,3,4&5 1,2,3&4 ALARM/TRIP SETPOINT

15 mR/hr per ODCM Control 3.3.3.9 N/A MEASUREMENT RANGE 10-1-104 mR/hr 101_106 cpm 101-106 cpm 19 I

ACTION 23 20 b)

RCS Leakage Detection 1

1,2, 3&4 N/A 101_106 CpM 20 With fuel in the storage pool or building.

The plant vent noble gas monitor may also function in this capacity when the purge/pressure-vacuum relief isolation valves are open.

SALEM -

UNIT 1 3/4 3-36 Amendment No.272

Table 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNELS SOURCE CHECKS CHECKS INSTRUMENT

1.

AREA MONITORS

a.

Fuel Storage Area CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVEILLANCE REQUIRED S

M R

Q I

2.

PROCESS MONITORS

a.

Containment Monitors

1) Gaseous Activity a)

Purge & Pressure VacuumRelief Isolation b)

RCS Leakage Detection

2)

Air Particulate Activity a)

(NOT USED) b)

RCS Leakage Detection S

S M

M R

R Q

Q Q

1, 2,

3, 4 & 5 1,

2, 3 & 4 1,

2, 3 & 4 S

M R

With fuel in the storage pool or building.

SALEM - UNIT 1 3/4 3-38 Amendment No.272

TABLE 3.3-11 (CONTINUED)

ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT

13.

PORV Block Valve Position Indicator

14. Pressurizer Safety Valve Position Indicator

15. Containment Pressure - Narrow Range

16. Containment Pressure - Wide Range

17. Containment Water Level -

Wide Range REQUIRED NO.

OF CHANNELS 2/valve**

2/valve**

2 2

2 MINIMUM NO.

OF CHANNELS ACTION 1

1 1

1, 2 1, 2 1, 2 7,

2 7, 2 1, 2 8,

9

18. Core Exit Thermocouples 4/core quadrant 2/core quadrant

19. Reactor Vessel Level Instrumentation System (RVLIS)

20. Containment High Range Accident Radiation Monitor 2

I 2

2 10

(**)

Total number of channels is considered to be two (2) with one (1) of the channels being any one (1) of the following alternate means of determining PORV, PORV Block, or Safety Valve position:

Tailpipe Temperatures for the valves, Pressurizer Relief Tank Temperature Pressurizer Relief Tank Level OPERABLE.

SALEM -

U/NIT 1 3/4 3-55 Amendment No.272

TABLE 3.3-11 (continued)

TABLE NOTATION ACTION 6 With the number of OPERABLE channels less than the Minimum Number of channels shown in Table 3.3-11, restore the inoperable channel(s) to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 7 With the number of OPERABLE channels one less than the Required Number of Channels shown in Table 3.3-11, operation may proceed until the next CHANNEL CALIBRATION (which shall be performed upon the next entry into MODE 5, COLD SHUTDOWN).

ACTION 8 With one RVLIS channel inoperable, restore the RVLIS channel to OPERABLE status within 30 days, or submit a special report in accordance with Specification 6.9.4.

ACTION 9 With both RVLIS channels inoperable, restore one channel to OPERABLE status within 7 days or submit a special report in accordance with Specification 6.9.4.

ACTION 10 With the number of OPERABLE Channels less than required by the minimum channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or

2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the actions taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

SALEM - UNIT 1 3/4 3-56a Amendment No.272

S[

ACCII INSTRUMENT

12.

PORV Position Indicator 13, PORV Block Valve Position Indicator

14. Pressurizer Safety Valve Position Indicator

15. Containment Pressure - Narrow Range

16. Containment Pressure - Wide Range

17. Containment Water Level -

Wide Range

18. Core Exit Thermocouples

19. Reactor Vessel Level Instrumentation System (RVLIS)

20. Containment High Range Accident Radiation Monitor TABLE 4.3-11 (Continued)

JRVEILLANCE REQUIREMENTS FOR DENT MONITORING INSTRUMENTATION CHANNEL CHANNEL CHECK CALIBRATION M

N.A.

M N.A.

M M

M S

R R

R**

R R

CHANNEL FUNCTIONAL TEST R

Q*

R N.A.

N.A.

Q R

Unless the block valve is closed in order to meet the requirements of Action b, or c in specification 3.4.3.

- A one-time extension to this surveillance requirement is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (IR13).

The surveillance is to be completed at the appropriate time during the 1R13 outage, prior to the unit returning to Mode 4 upon outage completion.

SALEM - UNIT I 3/4 3-57a Amendment No. 272 (2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 253, 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.

253

TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS OPERABLE APPLICABLE MODES INSTRUMENT ALARM/TRIP SETPOINT MEASUREMENT RANGE ACTION

1. AREA MONITORS

a.

Fuel Storage Area

2.

PROCESS MONITORS a, Containment

1) Gaseous Activity 1

15 mR/hr 10-1_104 mR/hr 23 I

a) Purge & Pressure Vacuum Relief Isolation 1, 2, 3, 4&5 per ODCM Control 3.3.3.9 101-106 cpm 101-106 cpm 26 24 b) RCS Leakage Detection 1

1,2, 3&4 N/A

2) Air Particulate Activity a)

(NOT USED) b)

RCS Leakage Detection 1

1,2, 3&4 N/A 101-l06 cpm 24 With fuel in the storage pool or building.

The plant vent noble gas monitor may also function in this capacity when the purge/pressure-vacuum relief isolation valves are open.

SALEM - UNIT 2 3/4 3-39 Amendment No.253

TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNELS SOURCE CHECKS CHECKS CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVEILLANCE REQUIRED INSTRUMENT

1. AREA MONITORS

a.

Fuel Storage Area

2.

PROCESS MONITORS

a.

Containment Monitors

1) Gaseous Activity S

M R

Q a)

Purge & Pressure Vacuum Relief Isolation b)

RCS Leakage Detection

2)

Air Particulate Activity a)

(NOT USED)

M M

R R

Q Q

1, 2,

3, 4 & 5 1,

2, 3 & 4 S

b)

RCS Leakage Detection S

M R

Q 1,

2, 3 & 4

With fuel in the storage pool or building.

SALEM -

UNIT 2 3/4 3-41 Amendment No.253

TABLE 3.3-11 (Continued)

ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT

13.

PORV Block Valve Position Indicator

14.

Pressurizer Safety Valve Position Indicator

15. Containment Pressure - Narrow Range

16. Containment Pressure - Wide Range

17. Containment Water Level - Wide Range

18.

Core Exit Thermocouples

19. Reactor Vessel Level Instrumentation System (RVLIS)

20. Containment High Range Accident Radiation Monitor REQUIRED NO.

OF CHANNELS 2/valve**

2/valve**

MINIMUM NO.

OF CHANNELS 1

1 ACTION 1, 2 1, 2 2

2 1

1 2

4/core quadrant I

2/core quadrant 1,

7, 7,

1, 8,

10 2

2 2

2 9

2 2

1 2

(**)

Total number of channels is considered to be two (2) with one (1) of the channels being any one (1) of the following alternate means of determining PORV, PORV Block, or Safety Valve position:

Tailpipe Temperatures for the valves, Pressurizer Relief Tank Temperature Pressurizer Relief Tank Level OPERABLE.

SALEM -

UNIT 2 3/4 3-51a Amendment No. 253

TABLE 3.3-11 (continued)

TABLE NOTATION ACTION 6 With the number of OPERABLE channels less than the Minimum Number of channels shown in Table 3.3-11, restore the inoperable channel(s) to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 7 With the number of OPERABLE channels one less than the Required Number of Channels shown in Table 3.3-11, operation may proceed until the next CHANNEL CALIBRATION (which shall be performed upon the next entry into MODE 5, COLD SHUTDOWN).

ACTION 8 With one RVLIS channel inoperable, restore the RVLIS channel to OPERABLE status within 30 days, or submit a special report in accordance with Specification 6.9.4.

ACTION 9 With both RVLIS OPERABLE status accordance with channels inoperable, restore one channel to within 7 days or submit a special report in Specification 6.9.4.

ACTION 10 With the number of OPERABLE Channels less than required by the minimum channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or

2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the actions taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

SALEM - UNIT 2 3/4 3-51c Amendment No. 253

ACC]

INSTRUMENT

12.

PORV Position Indicator

13.

PORV Block Valve Position Indicator

14. Pressurizer Safety Valve Position Indicator

15. Containment Pressure - Narrow Range

16. Containment Pressure - Wide Range

17. Containment Water Level - Wide Range

18. Core Exit Thermocouples

19. Reactor Vessel Level Instrumentation System (RVLIS)

20. Containment High Range Accident Radiation Monitor TABLE 4.3-11 (Continued)

SURVEILLANCE REQUIREMENTS FOR

[DENT MONITORING INSTRUMENTATION CHANNEL CHECKS C

M M

M CHANNEL ALIBRATION N.A.

N.A.

CHANNEL FUNCTIONAL TEST R

Q*

M M

M R

R R

R N.A.

N.A.

S Q

Unless the block valve is closed in order to meet the requirements of Action b, or c in specification 3.4.5.

SALEM - UNIT 2 3/4 3-52a Amendment No.253

ML061460433

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