ML17304A549

Amends 36,23 & 12 to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Revising Tech Specs to Modify Monitoring Requirements for Hydrogen & Oxygen in Waste Gas Holdup Sys

ML17304A549
Person / Time
Site:	Palo Verde
Issue date:	09/06/1988
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML17304A551	List: ML17304A549 ML17304A553
References
NUDOCS 8809230134
Download: ML17304A549 (42)

Text

~p,R REGS P

~O 0

0 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. 36 License No. NPF-41 1.

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

A.

The application for amendment, dated April 6, 1988 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; The facility will operate in conformity with the application, the provisions of Act, and the regulations of 'the Commission; C.

There is reasonable assurance (i) that the activities 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; 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 changes 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:

8809230l34 880906 PDR ADOCK 05000528 P

PDC

I (2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 36

, 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.

FOR THE NUCLEAR REGULATORY COMMISSION

Enclosure:

Changes to the Technical Specifications George

. Knig ton, rector Proje t Directorat V

Division of Reactor Projects - III, IV, V and Special Projects Date of Issuance:

September 6,

1988

(

ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.

36 TO FACILITY OPERATING LICENSE NO.

NPF-41 DOCKET NO.

STN 50-528 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

Each revised page is identified by Amendment number and contains vertical lines indicating the area of change.

Also to be replaced are the following overleaf pages to the amended pages.

Amendment Pa e

3/4 3-64 3/4 3-69 3/4 3-70 3/4 3-71 3/4 3-72 3/4 11-14 Overleaf Pa e

3/4 3-63 3/4 11-13

I

RA>:OA"TIVE EF=LUEN.S GASEOUS RAOi'-'5 E

TREATMEN LIMIT?h3 CONDITION FOR OPERATION 3 11.2.4 The GASEOUS RADMASTE SYSTEM and the VENTILATION EXHAUST TREAit'.="'T S>STEM shall be used to reduce radioactive materials in gaseous waste prior their discharge when the projected gaseous effluent air doses due to gaseo.s effluent releases, from each reactor unit, from the site (see Figures

5. 1-1 anc 5, 1-3),

when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.

The VENTILATION EXHAUST TREAT4,'Es.

SYSTEt'hall be uSed tO reduCe radiOaCtiVe materialS in gaSeOuS WaSte priOr to their discharge when the projected doses due to gaseous effluent releases.

from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figures

5. 1-1 and

5. 1-3) when averaged over 31 days would exceed 0.3 mrer. tc any organ of a MEK8ER OF THE PUBLIC.

APPLICABILITY: At all times.

A: JO.':

Pith radioactive gaseous

~aste being discharged without treatment and in excess of the above limits, prepare and submit to the Comttis-sion within 30 days, pursuant to Specification 6.9.2, a Special Repcrt which includes the following information:

2.

Identification of the inoperable equipment or subsystems and the reason for inoperability, Action(s) taken to restore the inoperable equipment to OPERA8LE

status, and 3.

Summary description of action(s) taken to prevent a recurrence.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREKEHTS 4.11.2.4 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and parameters in the ODCM.

PALO VERDE; UNIT 1 3/4 11-13

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION

3. 11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2X by volume.

APPLICABILITY:

Whenever the waste gas holdup system is 'in service.

ACTION:

a.

C.

With the concentration of oxygen in the waste gas holdup system greater than 2X by volume but less than or equal to 4X by volume, reduce the oxygen concentration to the above limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

With the concentration of oxygen in the waste gas holdup system greater than,4X by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than 4X by volume within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS

4. 11.2.5 The concentration of oxygen in the waste gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitors required OPERABLE by Table 3.3-12 of Specification 3.3.3.8.

PALO VERDE - UNIT 1 3/4 11-14 AMENDMENT NO. 36

IN STP UIYE V>>ATI ON RADIOACTIVE GASEOUS EFFLU NT MONITORING INSTRUMENTATION LIYsTING COND TiON FOP OPERATION 3.3.3.e The radioactive gaseous effluent monitorino instrumentation channe'.s shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification

3. 11.2. 1 are not exceeded.

The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCY.

APPLICABILITY:

As shown in Table 3.3-12.

ACTION:

a

~

b.

co Kith a lov ranoe radioactive gaseous effluent monitoring instrumer:.a-tior. channel alarm/trip setpoint less conservative than required by the above Specification, imediately suspend the release of radioac-tive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION showr, in Table 3.3-12.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Ser:-

annual Radioactive Effluent Release Report why this inoperability was not corrected within the time speci fied.

The provisions of Specifications 3,0.3 and 3.0.4 are not applicable.

SURVEILLANCE >EQUIREYENTS 4.3.3.8 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE

CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

PALO VERDE - UNIT 1

3/4 3-63 AMENDMENT NO.

TABLE 3.3-12 IC)

I INSTRUMENT 1.

GASEOUS RADWASTE SYSTEM a.

Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release

¹RU-12 MINIMUM CHANNELS OPERABLE APPLICABILITY b.

Flow Rate Monitor RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ACTION 35 2.

GASEOUS RADWASTE SYSTEM EXPLOSIVE GAS MONITORING SYSTEM a.

Oxygen Monitor 39

TABLE 4.3-8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS m

C7m Q

INSTRUMENT 1.

GASEOUS RADWASTE SYSTEM CHANNEL SOURCE CHANNEL CHECK CHECK CALIBRATION CHANNEL MODES IN WHICH FUNCTIONAL SURVEILLANCE TEST I5 REISUIREO a.

Noble Gas Activity Monitor-

Providing Alarm and Automatic Termination of Release RU-12 b.

Flow Rate Monitor N.A.

R(3) q(1), (2), PAN g, PO'N 2.

GASEOUS RADWASTE SYSTEM EXPLOSIVE GAS MONITORING SYSTEM IQl tD a.

Oxygen Monitor (Surge tank) b.

Oxygen Monitor (Waste gas header)

D N.A.

N.A.

Z(4) 0(4)

TABLE 4.3-8 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT 3.

CONDENSER EVACUATION SYSTEM (RU-141 and RU-142)

CHANNEL SOURCE CHANNEL CHECK CHECK CALIBRATION CHANNEL MODES IN MHICH FUNCTIONAL SURVEILLANCE EKE

~EIIIE a.

Noble Gas Activity Monitor

b. Iodine Sampler

c. Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Measuring Device D(5)

N.A.

N.A.

D(6)

D(6)

N.A.

N.A.

N.A.

N.A.

R(3)

N. A.

N.A.

q(2)

N.A.

N.A.

]

2 3 AAA 4k**

]

2 3

AAA 4***

]

2 3 *A%'*RA 3 *RA 4%*A' 3 *A'4'***

C) 4.

PLANT VENT SYSTEM (RU-143 and RU-144) a.

Noble Gas Activity Monitor

b. Iodine Sampler

c. Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Measuring Device D(5)

N.A.

N.A.

D(6)

D(6)

N.A.

N.A.

N.A.

N.A.

R(3)

N.A.

N.A.

O(2)

N.A.

N.A.

TABLE 4.3-8 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS I

Q INSTRUMENT 5.

FUEL BUILDING VENTILATION SYSTEM (RU-145 and RU-146)

CHANNEL SOURCE CHANNEL CHECK CHECK CALIBRATION CHANNEL MODES IN WHICH FUNCTIONAL SURVEILLANCE TEST

~ES EE ESSES a.

Noble Gas Actvity Monitor

b. Iodine Sampler

c. Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Measuring Device D(5)

N.A.

N.A.

D(6)

D(6)

N.A.

N.A.

N.A.

N.A.

R(3)

N.A.

N.A.

R u(~)

N.A.

N.A.

¹¹

¹¹

¹¹

¹¹

TABLE 4. 3-8 (Conti nued)

TABLE NOTATIONS

¹¹¹

¹¹¹ (2)

(3)

At al 1 times, During GASEOUS RADWASTE SYSTEM operation.

Whenever the condenser air removal system is in operation, or whenever turbine glands are being supplied with steam from sources other than the auxiliary boiler(s).

During waste gas release.

During MODES 1, 2, 3 or 4 or with irradiated fuel in the fuel storage pool.

Functional test should consist of, but not be limited to, a verification of system isolation capability by the insertion of a simulated alarm condition.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm/trip setpoint.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

l.

Instrument indicates measured levels above the alarm setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

4.

Instrument controls not set in operate mode.

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4)

The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

l.

One volume percent

oxygen, balance nitrogen, and 2.

Four volume percent

oxygen, balance nitrogen.

The channel check for channels in standby status shall consist of verification that the channel is "on-line and reachable."

(e)

Daily channel check not required for flow monitors in standby status.

PALO VERDE - UNIT 1 3/4 3-72 AMENDMENT NO. 36

gD+ ~<Cry~

P0

'40 "'O'NITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY, ET AL.

DOCKET NO.

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

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 23 License No.

NPF-51 1.

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

A.

The application for amendment, dated April 6, 1988 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 Act, and the regulations of the Commission; C.

There is reasonable assurance (i) that the activities 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 arid security or to the health and safety of the public; 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 changes 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 amended to read as follows:

0

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 23, 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.

FOR THE NUCLEAR REGULATORY COMMISSION eo ge W

Knigeton,

'ctor project irectorate Division of Reactor Projects - III, IV, V and Special Projects

Enclosure:

Changes to the Technical Specifications Date of Issuance:

September 6, 1988

l

ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO. 23 TO FACILITY OPERATING LICENSE NO.

NPF-51 DOCKET NO.

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

Each revised pages is identified by Amendment number and contains vertical lines indicating the area of change.

Also to be replaced are the following overleaf pages to the amended pages.

Overleaf Pa e

3/4 3-64 3/4 3-69 3/4 3-70 3/4 3-71 3/4 3-72 3/4 11-14 3/4 3-63 3/4 11-13

RADIOACTjVE EFFLUENTS GASEOUS RADlN'ASTE TREATHENT LIMITING CONDITION FOR OPERATION

3. 11.2.4 The GASEOUS RADAR'ASTE SYSTEM and the VENTILATION EXHAUST TREATHENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, from the site (see Figures

5. 1-1 and

5. 1-3),

when averaged over 31 days, would exceed 0.2 mrad for gamma radiatio'n and 0.4 mrad for beta radiation.

The VENTILATION EXHAUST TREATMENT SYSTEH shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figures

5. 1-1 and 5. 1-3) when averaged over 31 days would exceed 0.3 mrem to any organ of a

MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

ACTION:

Kith radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commis-sion within 30 days, pursuant to Specification 6.9.2, a Special Report

'hich includes the following information:

l.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action(s) taken to restore the inoperable equipment to OPERABLE

status, and 3.

Summary description of action(s) taken to prevent a recurrence.

b.

The provisions of Specifications 3.0 '

and 3.0.4 are not applicable.

SURVEILLANCE RE UIREHENTS

'.11.2.4 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and parameters in the ODCH.

PALO VERDE - UNIT 2 3/4 11-13

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION

3. 11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2X by volume.

APPLICABILITY: Whenever. the waste gas holdup system is in service.

ACTION:

a 0 b.

C.

With the concentration of oxygen in the waste gas holdup system greater than 2X by volume but less than or equal to 4X by volume, reduce the oxygen concentration to the above limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

With the concentration of oxygen in the waste gas holdup system greater than 4X by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than 4X by volume within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS

4. 11.2.5 The concentration of or oxygen in the waste gas holdup system shall be determined to be within the above limits by monitoring the waste gases in the waste gas holdup system in accordance with Specification 3.3.3.8.

PALO VERDE - UNIT 2 3/4 11-14 AMENDMENT NO. 23

RADIOt'CTIVE GASEO"S EFFLUENT t'ONITOPING INSTRUMENTATION Llt':TING CONDJTION FO~

OPERATION 3.3.3.8 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OpERABLE with their alarm/trip setpoints set to ensure that'the limits of Specification 3.I1.2.1 are not exceeded.

The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCY.

APPLICABILITY:

As shown in Table 3.3-]2.

ACTION:

a

~

b.

c

~

Kith a low ranoe radioactive gaseous effluent monitorino instrumenta-tion channel a1arm/trip setpoint less conservative than reauired by the above Specificatior, inrnediately suspend the release of radioac-tive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION showr.

in Table 3.3-12.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semi-annual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOU I REAGENTS 4.3.3.8 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE

CHECK, CHANNEL CALIBRATJON, and CHANNEL FUNCTIONAL TEST operations at, the frequencies shown in Table 4.3-8.

PALO VERDE - UNIT 2 3/4 3-63 AyENDHENT NO.

8

)

TABLE 3.3-12 CD(

I INSTRUMENT 1.

GASEOUS RADWASTE SYSTEM a.

Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release

¹RU-12 MINIMUM CHANNELS OPERABLE APPLICABILITY b.

Flow Rate Monitor RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ACTION 35 2.

GASEOUS RADWASTE SYSTEM EXPLOSIVE GAS MONITORING SYSTEM a.

Oxygen Monitor 39 m

CD m

CD

TABLE 4.3-8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS

(

m C7 Pal INSTRUMENT 1.

GASEOUS RADWASTE SYSTEM CHANNEL CHECK CHANNEL MODES IN WHICH SOURCE CHANNEL FUNCTIONAL SURVEILLANCE CHECK CALI8RATION TEST S

REIRRRRO a.

Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release RU-12 b.

Flow Rate Monitor N.A.

Q(l),(2), P¹¹¹

¹ Q,P¹¹¹ 2.

GASEOUS RADWASTE SYSTEM EXPLOSIVE GAS MONITORING SYSTEM LO a.

Oxygen Monitor (surge tank) 0 b.

Oxygen Monitor (waste gas header)

D N.A.

N.A.

Q(4)

Q(4)

TABLE 4.3-8 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS c=

INSTRUMENT 3.

CONDENSER EVACUATION SYSTEM (RU-141 and RU-142)

CHANNEL CHECK SOURCE CHANNEL CHECK CALIBRATION CHANNEL MODES IN WHICH FUNCTIONAL SURVEILLANCE TEST ES EEITEEEEE a.

Noble Gas Activity Monitor

b. Iodine Sampler

c. Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Measuring Device D(5)

N.A.

N.A.

D(6)

D(6)

N.A.

N.A.

N.A.

N.A.

R(3)

N.A.

N.A.

C(2)

N.A.

N.A.

]

2 3*4'*

4)kA)h 3**%'*'A*

2 3*%A 4*A%'AAA 4AAA 3*%'8 4%A'A m

ED 4.

PLANT VENT SYSTEM (RU-143 and RU-144) a.

Noble Gas Activity Monitor

b. Iodine Sampler

c. Particulate Sampler d.

Flow Rate Monitor

~ e.

Sampler Flow Rate Measuring Device D(5)

N.A.

N.A.

D(6)

D(6)

N.A.

N.A.

N.A.

N.A.

R(3)

N.A.

N.A.

C(2)

N.A.

N.A.

TABLE 4.3-8 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT 5.

FU'EL BUILDING VENTILATION SYSTEM (RU-145 and RU-146)

CHANNEL SOURCE CHANNEL CHECK CHECK CALIBRATION CHANNEL MODES IN WHICH FUNCTIONAL SURVEILLANCE EET I

RETEEIRE a.

Noble Gas Actvity Monitor

b. Iodine Sampler

c. Particulate Sampler

d. Flow Rate Monitor e.

Sampler Flow Rate Measuring Device D(5)

N.A.

N.A.

D(6)

D(6}

N.A.

N.A.

N.A.

N.A.

R(3)

N.A.

N.A.

0(2)

N.A.

N.A.

¹¹

¹¹

¹¹ CD m

CD

TABLE 4. 3-8 (Continued)

TABLE NOTATIONS

¹

¹¹

¹¹¹ (i)

(2)

(3)

At all times.

During GASEOUS RADMASTE SYSTEM operation.

Whenever the condenser air removal. system is in operation, or whenever turbine glands are being supplied with steam from sources other than the auxiliary boiler(s).

During waste gas release.

During MODES 1, 2, 3 or 4 or with irradiated fuel in the fuel storage pool.

Functional test should consist of, but not be limited to, a verification of system isolation capability by the insertion of a simulated alarm condition.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm/trip setpoint.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

l.

Instrument indicates measured levels above the alarm setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

4.

Instrument controls not set in operate mode.

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4)

The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

l.

One volume percent

oxygen, balance nitrogen, and 2.

Four volume percent

oxygen, balance nitrogen.

The channel check for channels in standby status shall consist of verification that the channel is "on-line and reachable."

Daily channel check not required for flow monitors in standby status.

PALO VERDE - UNIT 2 3/4 3-72 AMENDMENT NO. 23

~o.a FiEqy,

(,4 fp

~4 0

O.o 0

)0 p*y4 UNITED STATES 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.

12 License No.

NPF-74 1.

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

A.

The applicaTion for amendment, dated April 6, 1988 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; C.

The facility will operate in conformity with the application, the provisions of Act, and the regulations of the Commission; There is reasonable assurance (i) that the activities 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 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 changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-74 is hereby amended to read as follows:

0 l,

g

~ q r

r

~

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 22, 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.

FOR THE NUCLEAR REGULATORY COMMISSION

Enclosure:

Changes to the Technical Specifications eorge Knig ton,

'rector Projec Directorat Division of Reactor Projects - III, IV, V and Special Projects Date of Issuance:

September 6,

1988

I l

t j

f t

ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO. 12 TO FACILITY OPERATING LICENSE NO.

NPF-74 DOCKET NO.

STN 50-530 Overl ea f Pa e

Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

Each revised page is identified by Amendment number and contains vertical lines indicating the area of change.

Also to be replaced are the following overleaf pages to the amended page.

A~Ad 3/4 3-64 3/4 3-69 3/4 3-70 3/4 3-71 3/4 3-72 3/4 11-14 3/4 3-63 3/4 11-13

0 J

l t

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE SYSTEM and the VENTILATION EXMAUST TREATMENT SYSTEH shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, from the site (see Figures 5.1-1 and 5.1-3),

when averaged over 31 days, would exceed 0,2 mrad for gamma radiation and 0.4 mrad for beta radiation.

The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figures 5.1-1 and 5. 1-3) when averaged over 31 days would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

ACTION:

a ~

b.

With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commis-sion within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

.Action(s) taken to restore the inoperable equipment to OPERABLE

status, and 3.

Summary description of action(s) taken to prevent a recurrence.

The provisions of Specifications

3. 0. 3 and 3. 0.4 are not applicable.

SURVEILLANCE RE UIREMENTS

4. 11.2.4 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and parameters in the ODCH.

PALO VERDE - UNIT 3 3/4 11-13

0 RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION

3. 11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2X by volume.

APPLICABILITY: Whenever the waste gas holdup system is in service.

ACTION:

'a ~

b.

C.

With the concentration of oxygen in the waste gas holdup system greater than 2X by volume but less than or equal to 4X by volume, reduce the oxygen concentration to the above limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

With the concentration of oxygen in the waste gas holdup system greater than 4X by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than 4X by volume within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS

4. 11.2.5 The concentration of oxygen in the waste gas holdup system shall be determined to be within the above limits by monitoring the waste gases in the waste gas holdup system in accordance with Specification 3.3.3.8.

PALO VERDE - UNIT 3 3/4 11-14 AMENDMENT NO. 12

INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11.2. 1 are not exceeded.

The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY:

As shown in Table 3.3-12.

ACT10N:

Mith a low range radioactive gaseous effluent monitoring instrumenta-tion channel alarm/trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioac-tive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

C.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Restore the inoperable, instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semi-annual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.8 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE

CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

PALO VERDE - UNIT 3 3/4 3"63

S C7m I

INSTRUMENT 1.

GASEOUS RADMASTE SYSTEM a 0 MINIMUM CHANNELS OPERABLE APPLICABILITY Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release

¹RU-12 b.

Flow Rate Monitor TABLE 3.3-12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ACTION 35 36 2.

GASEOUS RADWASTE SYSTEM EXPLOSIVE GAS MONITORING SYSTEM VJ a.

Oxygen Monitor 39

U CD A7 CD INSTRUMENT 1.

GASEOUS RADWASTE SYSTEM CHANNEL SOURCE CHANNEL CHECK CHECK CALIBRATION CHANNEL MODES IN WHICH FUNCTIONAL SURVEILLANCE ElT I

EIEI ED TABLE 4.3-8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS C

4 a.

Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release RU-12 b.

Flow Rate Monitor N.A.

R(3)

Q(1), (2), P¹¹¹

¹ Q,P¹¹¹

¹ 2.

GASEOUS RADWASTE SYSTEM EXPLOSIVE GAS MONITORING SYSTEM lD a.

Oxygen Monitor (Surge Tank)

D b.

Oxygen Monitor (Waste Gas Header)

D N.A.

N.A.

Q(4)

Q(4)

CD 4

f CD TABLE 4.3-8 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS g

INSTRUMENT 3.

CONDENSER EVACUATION SYSTEM (RU-141 and RU-142)

CHANNEL CHECK SOURCE CHANNEL CHECK CALIBRATION CHANNEL MODES IN WHICH FUNCTIONAL SURVEILLANCE lEST IS RftSUIRED I

CD a.

Noble Gas Activity Monitor

b. Iodine Sampler

c. Particulate Sampler d.

Flow Rate Monitor e.

Sample Flow Rate Measuring Device D(5)

N.A.

N.A.

D(6)

D(6)

N.A.

N.A.

N.A.

N.A.

R(3)

N. A.

N.A.

0(2)

N.A.

N.A.

3%*A 4%*A 3AAA'***

3*** 4k**

3*%'A'k**

3*** 4*'AA 4.

PLANT VENT SYSTEM (RU-143 and RU-144) a.

Noble Gas Activity Monitor

b. Iodine Sampler

c. Particulate Sampler d.

Flow Rate Monitor e.

Sampler Flow Rate Measuring Device D(5)

N.A.

N.A.

D(6)

D(6)

N.A.

N.A.

N.A.

N.A.

R(3)

N.A.

N.A.

O(2)

N.A.

N.A.

I CD TABLE 4. 3-8 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT 5.

FUEL BUILDING VENTILATION SYSTEM (RU-145 and RU-146) a.

Noble Gas Actvity Monitor CHANNEL CHECK D(5)

SOURCE CHANNEI CHECK CALIBRATION R(3)

CHANNEL MODES IN MHICH FUNCTIONAL SURVEILLANCE TEST

~lf TEES

b. Iodine Sampler

c. Particulate Sampler

d. Flow Rate Monitor e.

Sampler Flow Rate Measuring Device N.A.

N.A.

D(6)

D(6)

N.A.

N.A.

N.A.

N.A.

N.A.

N. A.

N.A.

N.A.

¹¹

¹¹ CD

TABLE 4. 3-8 (Continued)

TABLE NOTATIONS At all times.

¹

¹¹

¹¹¹ (1)

(2)

(3)

During GASEOUS RADWASTE SYSTEM operation.

Whenever the condenser air removal system is in operation, or whenever turbine glands are being supplied with steam from sources other than the auxiliary boiler(s).

During waste gas release.

During MODES 1, 2, 3 or 4 or with irradiated fuel in the fuel storage pool.

Functional test should consist of, but not be limited to, a verification of system isolation capability by the insertion of a simulated alarm condition.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm/trip setpoint.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

4.

Instrument controls not set in operate mode.

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sourc'es that have been related to the initial calibration shall be used.

(4)

The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

l.

One volume percent

oxygen, balance nitrogen, and 2.

Four volume percent

oxygen, balance nitrogen.

The channel check for channels in standby status shall consist of verification that the channel is "on-line and reachable."

(e)

Daily channel check not required for flow monitors in standby status.

PALO VERDE - UNIT 3 3/4 3-72 AMENDMENT NO. 12