ML17303A865

Amends 30,17 & 5 to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Revising Tech Spec Section 6 to Change Due Date Requirement for Annual Radiological Repts Required by Tech Spec 6.9.1.4

ML17303A865
Person / Time
Site:	Palo Verde
Issue date:	03/07/1988
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML17303A866	List: ML17303A865 ML17303A867
References
NUDOCS 8803180094
Download: ML17303A865 (21)

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

DOCKET NO.

STN 50-52B PALO VERDE NUCLEAR GEI'IERATING STATION, UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

30 License No.

NPF-41 1.

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

A.

The application for amendment, dated December 22,

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 Comission'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 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 CoIImIission'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:

8803i80094 880307 PDR ADOCK 05000529 PDR

I (2)

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

30, 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 Date of Issuance:

March 7, 1988 Georg

. Knigh 'n, Director Project Directorate V

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

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March 7, 1988 ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.

30 TO FACILITY OPERATING LICENSE NO.

NPF-41 DOCKET NO.

STN 50-528 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

6-17 Overleaf Pa e

6-18

ADMINISTRATIVE CONTROLS REPORTING RE UIREMENTS Continued

supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9. 1.2 The Startup Report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed.

ANNUAL REPORTS 6.9. 1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted within the first calendar quarter of each year.

The initial report shall be submitted within the first calendar quarter of the year following initial criticality.

6.9. 1.5 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their associated man-rem exposure according to work and job functions,"" e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling.

The dose assignments to various duty functions may be estimated based on pocket'dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20K of the individual total dose need not be accounted for.

In the aggregate, at least 80K of the total whole body dose received from external sources should be assigned to specific major work functions.

Annual reports shall also include the results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.7.

The following information shall be included:

(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior the the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one "A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station.

• "This tabulation supplements the requirements of 520.407 of the 10 CFR Part 20.

PALO VERDE " UNIT 1 6-17 AMENDMENT NO. 30

ADMINISTRATIVE CONTROLS ANNUAL REPORTS Continued analysis after the radioiodine activity was reduced to less than limit.

Each result should include date and time of sampling and the radioiodine concentra-tions; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a

function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

MONTHLY OPERATING REPORT 6.9. 1.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U. S. Nuclear Regulatory Coaeission, Washington, O.C. 20555, with a copy to the Regional Administrator of the Regional Office of the

NRC, no later than the 15th of each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT" 6.9. 1.7 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The initial report shall be submitted prior to May 1 of the year following initial criticality.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use censuses required by Specification

3. 12.2.

The Annual Radiological Environmental Operating Reports sh~ll include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.

In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following:

a summary description of the radiological environmental monitoring program; at least two legible maps""

• A single submittal may be made for a multiple unit station.

• • One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.

PALO VERDE - UNIT 1 6-18 AMENDMENT NO. 21

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 g )I,'P g ~ Ig~'tIt 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.

17 License No.

NPF-51 1.

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

A.

The application for amendment, dated Decembe~

22, 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.

D.

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; 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-51 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.

17, and the Environmental Protection Plan contained in Appendix 8, 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 George

. Knight n, Director Project Directorate V

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

Enclosure:

Changes to the Technical Specifications Date of Issuance:

~r<h 7, 1988

'I I. 'T'<

March 7, 1988 ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO. 17 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

Overleaf Pa e

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ADMINISTRATIVE CONTROLS REPORTING RE UIREMENTS Continued

supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

I 6.9. 1.2 The Startup Report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9. 1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is ear liest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation)'supplementary reports shall be submitted at least every 3 months until all three events have been completed.

ANNUAL REPORTSA 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted within the first calendar quarter of each year.

The initial report shall be submitted within the first calendar quar ter of the year following initial criticality.

6.9. 1.5 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their associated man-rem exposure according to work and job functions,"" e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling.

The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20K of the individual total dose need not be accounted for.

In the aggregate, at least 80X of the total whole body dose received from external sources should be assigned to specific major work functions.

Annual reports shall also include the results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.7.

The following information shall be included:

(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis "A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station.

"*This tabulation supplements the requirements of f20.407 of the 10 CFR Part 20.

PALO VERDE - UNIT 2 6"17 AMENDMENT NO. 17

ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued after the radioiodine activity was reduced to less than limit.

Each result should include date and. time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

MONTHLY OPERATING REPORT 6.9. 1.6 Routine reports of operating statistics and shutdown experience, including documentation'f all challenges to the safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, with a copy to the Regional Administrator of the Regional Office of the

NRC, no later than the 15th of each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT"

6. 9. 1. 7 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The initial report shall be submitted prior to May 1 of the year following initial criticality.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational

studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operati.on on the environment.

The reports shall also include the results of land use censuses required by Specification 3.12.2.

The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the Table and Figurqs in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.

In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following:

a summary description of the radiological environmental monitoring program; at least two legible maps""

"A single submittal may be made for a multiple unit station.

""One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.

PALO VERDE " UNIT 2 6-18

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+y*g4 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.

5 License No. NPF-74 1.

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

A.

The application for amendment, dated December 22,

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 Comission'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 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:

I

~

l (2)

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

5, and the Environmental Protection Plan contained in Appendix 8, 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 George

. Knighto, Director Project Directorate V

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

Enclosure:

Changes to the Technical Specifications Date of Issuance:

March 7, 1988

March 7, 1988 ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.

5 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 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

6-17 Overleaf Pa e

6-18

~

)

ADMINISTRATIVE CONTROLS REPORTING RE UIREMENTS Continued

supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9. 1.2 The Startup Report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values'ith design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the 'startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or 'commencement of commercial operation) supplementary reports shall be submi,tted at least every 3 months until all three events have been completed.

ANNUAL REPORTS" 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted within the first calendar quarter of each year.

The initial report shall be submitted within the first calendar quarter of the year following initial criticality.

6.9. 1.5 Reports required on an'annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their associated man-rem exposure according to work and job functions,** e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling.

The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20K of the individual total dose need not be accounted for.

In the aggregate, at least 80X of the total whole body dose received from external sources should be assigned to specific major work functions.

Annual'reports shall also include the results of specific activity analysis in which the primary coolant exceeded the limits of. Specification 3.4.7.

The following information shall be included:

(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis "A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station.

""This tabulation supplements the requirements of f20.407 of the 10 CFR Part 20.

PALO VERDE - UNIT 3 6"17 AMENDMENT NO.

5

ADMINISTRATIVE CONTROLS ANNUAL REPORTS Continued after the radioiodine activity was reduced to less than limit.

Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one-other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

MONTHLY OPERATING REPORT 6.9. 1.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, with a copy to the Regional Administrator of the Regional Office of the

NRC, no later than the 15th of each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*

6.9. 1.7 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of, each year.

The initial report shall be submitted prior to May 1 of the year following initial criticality.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational

studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use censuses required by Specification 3.12.2.

The. Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses and me'asurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.

In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following:

a summary description of the radiological environmental monitoring program; at least two legible maps""

"A single submittal may be made for a multiple unit station.

""One map shall cover stations near the SITE BOUNDARY; a'second shall include the more distant stations.

PALO VERDE - UNIT 3 6-18