ML17303A837

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Amends 26,15 & 3 to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Revising Table 3.3-6 in Tech Spec 3.3.3.1 by Changing Detectable Range of Main Steam Line Effluent Monitors
ML17303A837
Person / Time
Site: Palo Verde  
Issue date: 02/26/1988
From: Knighton G
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17303A838 List:
References
NUDOCS 8803150107
Download: ML17303A837 (23)


Text

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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

26 License No. NPF-41 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment, dated November 20, 1987, by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison Company, Public Service Company. of New Mexico, Los Angeles Department of Mater and

Power, and Southern California Public Power Authority (licensees),

complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.

There is reasonable assurance (i) that the activity authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, the license is amended by a change to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-41 is hereby amended to read as follows:

(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

26, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of issuance.

The change in the Technical Specifications is to become effective within 30 days of issuance of the amendment.

In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time.

The period of time during changeover shall be minimized.

FOR THE NUCLEAR REGULATORY COMMISSION George

. Knightof(, Director Project Directorate Y

Division of Reactor Projects - III, IV, V and Special Projects

Enclosure:

Chanoe to the Technical Specifications Date of Issuance:

February 26, l988,

February 26, 1988 ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO. 26 TO FACILITY OPERATING LICENSE NO.

NPF-41 DOCKET NO.

STN 50-528 Replace the folllowing page of the Appendix A Technical Specifications with the enclosed page.

The revised page is identified by Amendment number and contains a vertical line indicating the area of change.

Also to be replaced is 'the following over leaf page to the amended page.

Amendment Pa e

3/4 3-38 Overleaf Pa e

3/4 3-37

P r

INSTRUMENTATION 3/4 3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

APPLICABILITY:

As shown in Table 3.3-6.

ACTION:

With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.

b.

With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement, take the ACTION shown in Table 3.3-6.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4. 3-3.

PALO VERDE - UNIT 1 3/4 3-37

a Cl AT Rl Cl fTl 1.

W INSTRUMENT Area Monitors A.

Fuel Pool Area RU-31 B.

New Fuel Area RU-19 C.

Containment RU-148 8 RU-149 D.

Containment Power Access Purge Exhaust RU-37 8 RU-38 MINIMUM CHANNELS APPLICABLE OPERABLE MODES 1,2,3,4 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION ALARM/TRIP MEASUREMENT SETPOINT RANGE ACTION

<15m R/hr

<15mR/hr

<10R/hr

<2.5mR/hr 10-~ to 10-~mR/hr 25 10-to 10 mR/hr 22 8 24 10-to 10~mR/hr 22 1R/hr to 107R/hr 27 E.

Main Steam 1)

RU-139 A&B 2)

RU-140 A&B 2.

Process Monitors A.

Containment Building Atmosphere RU-1 1,2,3,4 1,2,3,4

¹¹¹¹ 10 to 10 mR/hr 27 10 to 10 mR/hr 27 23 8 27 1)

Particulate 2)

Gaseous Noble Gas Monitors Control Room Ventilation Intake RU-29 8 RU-30 B.

3.

Post Accident Sampling System 1¹¹¹

<2.3xl0- pCi/cc 10-to 10-4pCi/cc Cs-137

<6.6x10- pCi/cc 10-to 10- pCi/cc Xe-133 1,2,3 N.A.

N.A.

28 ALL MODES

<2xl0-spCi/cc 10-e to 10-~pCi/cc 26 "With fuel in the storage pool or building.

""With irradiated fuel in the storage pool.

¹When purge is being used.

¹¹Three (3) times background in Rem/hour.

¹¹¹The Minimum Channels Operable will be defined in the Preplanned Alternate Sampling Program.

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVIC COMPANY ET AL.

DOCKET NO.

STN 50-529 PALO VERDE NUCLEAR GENERATING STATION% UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 15 License No. NPF-51 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

TIIe application for amendment, dated November 20, 1987, by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California. Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and

Power, and Southern California Public Power Authority (licensees),

complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the CoIIIIission; C.

There is reasonable assurance (i) that the activity authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulation; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by a change to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-51 is hereby

'mended to read as follows:

(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

15, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.-

This license amendmer.t is effective as of the date of issuance.

The change in the Technical Specifications is to become effective within 30 days of issuance of the amendment.

In the period between issuance of the amendment ana the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time.

The period of time during changeover shall be minimized.

FOR THE NUCLEAR REGULATORY COMMISSION Enc'losure:

Change to the Technical Specifications George H: Knighton, Director Project Directorate Y

Division of Reactor Projects - III, IY, Y and Special Projects Date of Issuance:

February 26, 1988

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February 26, 1988 ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.

15 TO FACILITY OPERATING LICENSE NO. NPF-51 DOCKET NO.

STN 50-529 Replace the following page of the Appendix A Technical Specifications with the enclosed page.

The revised page is identified by Amendment number and contains a

vertical line indicating the area of change.

Also to be replaced is the following overleaf page to the amended page.

Amendment Pa e

3/4 3-38 Overleaf Pa e

3/4 3-37

I I

INSTRUMENTATION

~ 3/4. 3

~ 3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3. 1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

APPLICABILITY:

As shown in Table 3.3-6.

ACTION:

a.

With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.

b.

With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement, take the ACTION shown in Table 3.3-6.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3. 1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-3.

PALO VERDE - UNIT 2 3/4 3-37

IID(

m INSTRUMENT Area Monitors TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM/TRIP MEASUREMENT=

OPERABLE MODES SETPOINT RANGE ACTION A.

B.

C.

D.

Fuel Pool Area RU-31 New Fuel Area RU-19 Containment RU-148 8

RU-149 Containment Power Access Purge Exhaust RU-37 8

RU-38 1,2,3,4

<15mR/hr

<15mR/hr

<10R/hr 10-i to 104mR/hr 22 8 24 10-~ to 104mR/hr 22 1R/hr to 107R/hr 27

<2.5mR/hr 10-~ to 10-4mR/hr 25 E.

Main Steam 1)

RU"139 A8IB 2)

RU"140 A8IB 2.

Process Honitors A.

Containment Building Atmosphere RU-1 1,2,3,4 1,2,3,4 1,2,3,4

¹¹¹¹ 10o to 10smR/hr 27 10o to 10 mR/hr 27 23 4 27 m

ID m

1)

Particulate 2)

Gaseous B.

Noble Gas Monitors Control Room Ventilation Intake RU-29 8 RU-30 1

3.

Post Accident Sampling System 1¹¹¹

<2.3xl0- pCi/cc 10-to 10-4pCi/cc Cs"137

<6.6x10- pCi/cc 10-to 10- pCi/cc Xe-133 1,2,3.

N.A.

N.A.

28 ALL MODES

<2xlO-pCi/cc 10-to 10- pCi/cc 26 "With fuel in the storage pool or building.

""With irradiated fuel in the storage pool.

¹When purge is being used.

¹¹Three (3) times background in Rem/hour.

¹¹¹The Minimum Channels Operable will be defined in the Preplanned Alternate Sampling Program.

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UNITEDSTATES "

NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-530 PALO VERDE NUCLEAR GENERATING STATION, UNIT NO.

3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 3 License No.

NPF-74 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment, dated November 20,

1987, by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison
Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority (licensees),

complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.

There is reasonable assurance (i) that the activity authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment.will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2 2.

Accordingly, the license is amended by a change to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.(2) of Facilfty Operating License No.

NPF-74 is hereby amended to read as follows:

I (2) Technical S ecifications and Environmental Protection Plan L

The Technical Specifications contained in Appendix A, as revised through Amendment No.

3, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

APS shall operate the facility fn accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of issuance.

The change in the Technical Specifications is to become effective within 30 days of issuance of the amendment.

In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time.

The period of time during changeover shall be minimized.

FOR THE NUCLEAR REGULATORY COMYiISSION

Enclosure:

Change to the Technical Specifications George W. Knighton, Oirector Project Directorate Y

Division of Reactor Projects - III, IY, Y and Special Projects Date of Issuance:

February 26, 1988

J I

February 26, 1988 ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.

3 TO FACILITY OPERATING LICENSE NO. NPF-74 DOCKET NO.

STN 50-530 Replace the following page of the Appendix A Technical Specifications with the enclosed paoe.

The revised page is identified by Amendment number and contains a vertical line indicating the area of change.

Also to be replaced is the following overleaf page to the amended page.

Overleaf Pa e

3/4 3-38 3/4 3-37

I

INSTRUMENTATION 3/4. 3. 3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3. 1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

APPLICABILITY:

As shown in Table 3.3-6.

ACTION:

With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.

Mith the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement, take the ACTION shown in Table 3.3-6.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3. 1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-3.

PALO VERDE - UNIT 3 3/4 3-37 y

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m C7m INSTRUMENT TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE, OPERABLE MODES ALARM/TRIP MEASUREMENT SETPOINT RANGE ACTION 1.

C QP Area A.

B.

C.

D.

Monitors Fuel Pool Area RU-31 New Fuel Area RU-19 Containment RU-148 8

RU-149 Containment Power Access Purge Exhaust RU-37 8 RU-38 1,2,3,4

<15mR/hr

<15mR/hr

<10R/hr 10-~ to 104mR/hr 22 8 24 10-~ to 104mR/hr 22 1R/hr to 107R/hr 27

<2.5mR/hr 10-~ to 104mR/hr 25 E.

Hain Steam 1)

RU-139 A8EB 2)

RU-140 NS Process Monitors A.

Containment Building Atmosphere RU-1 1,2,3,4 1,2,3,4 1,2,3,4

¹¹¹¹ 10 to 10smR/hr 27 10 to 10 mR/hr, 27 23 8E 27 1)

Particulate 2)

Gaseous Noble Gas Monitors Control Room Ventilation Intake RU-29 8 RU-30 B.

m C7 3.

Post Accident Sampling System 1¹¹¹

<2.3xl0- pCi/cc 10-to 10-4pCi/cc Cs"137

<6.6x10- pCi/cc 10-to 10- pCi/cc Xe-133 1,2,3 N.A.

N.A.

28 ALL MODES

<2xl0- pCi/cc 10-to 10- pCi/cc 26 "With fuel in the storage pool or building.

""With irradiated fuel in the storage pool.

¹When purge is being used.

¹¹Three (3) times background in Rem/hour.

¹¹¹The Minimum Channels Operable will be defined in the Preplanned Alternate Sampling Program.