ML20094P498

Amends 194 & 77 to Licenses DPR-66 & NPF-73,respectively, Revising Administrative Controls Section of BVPS-1 & BVPS-2 TSs to Make Amends Consistent W/Requirements of ODCM

ML20094P498
Person / Time
Site:	Beaver Valley
Issue date:	11/21/1995
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co
Shared Package
ML20094P501	List: ML20094P498 ML20094P503 ML20094P511
References
DPR-66-A-194, NPF-73-A-077 NUDOCS 9511290186
Download: ML20094P498 (11)

Text

.

~

c uzg g$p 94 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 2088H001

/

DUOVESNE LIGHT COMPANY OHIO EDIS0N COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION. UNIT NO. 1 1

AMEN 9 MENT TO FACILITY OPERATING LICENSE Amendment No.194 License No. DPR-66 1.

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

A.

The application for amendment by Duquesne Light Company, et al. (the licensee) dated September 13, 1995, as supplemented October 16, 1995, complies with the standards and requirements of the Atomic _r Energy Act of 1954, as amended (the Act), and the Commission's rules j

and 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 rules and 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; 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.

9511290186 951121 PDR ADOCK 05000334 P

pgp

.. ~ ~. - _ -. -

l.

! 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised-through Amendment No.194, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

l 3.

This license amendment is effective as of the date of its issuance, to be implemented within 10 days.

FOR THE NUCLEAR REGULATORY COMMISSION i

f o

. Stolz, Directhr r ject DirectorateJ-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: November 21, 1995

ATTACHMENT TO LICENSE AMENDMENT N0.194

-I FACILITY OPERATING LICENSE N0. DPR-66 DOCKET NO. 50-334 i

Replace the following pages of Appendix A Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert-6-14 6-14 6-15

~6-15 l

l

DPR-66

' ADMINISTRATIVE CONTROLS f

6.8.6 The following programe shall be established, implemented, i

and maintained:

)

i a.

Radioactive Effluent Controls Procram

-A program shall be provided conforming with 10 CFR 50.36a for.

the control of radioactive affluents and for maintaining the doses to MEMBERS OF THE PUBLIC.'from radioactive effluents as low as reasonably achievable.

The program (1) shall be contained in the ODCM, (2) shall be implemented-by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.

The program shall include th,e following elements:

1)

Limitations on the operability of radioactive liquid and-gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 2)

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICFED AREAS conforming to 10 times 10 CFR Part 20, Appendix l

B, Table 2, Column 2, 3)

Monitoring,

sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the

ODCM, 4)

Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid affluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5)

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parametera in the ODCM at least every 31 days, 6)

Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, BEAVER VALLEY - UNIT 1 6-14 Amendment No.19-4

'DPR-66'

a ADMINISTRATIVE CONTROLS 7)

Limitations on the dose rate resulting from radio-active material released in gaseous effluents to areas beyond the SITE BOUNDARY shall. be limited to the following:

+

a)

For noble. gases:

Less than or equal to 500 mrea/ year to the total body and less than or equal to 3000 mrem / year to the skin and, b)

For Iodine-131, 'for Iodine-133,;for tritium, and for all radionuclides in particulate form with half-lives greater than 8

days:

Less than or

' equal to 1500 mrem / year to any organ, 4

8)

Limitations on the annual and' quarterly -air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to-Appendix I to 10 CFR Part 50, 9)

Limitations on the annual and quarterly doses to a MEMBER OF.THE PUBLIC from Iodine-131, - Iodine-133,

tritium, and all radionuclides in particulate fprm i

with half-lives greater than 8

days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I.to 10 CFR Part 50, 10)

Limitations on the annual dose or dose commitment to' any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation.from uranium fuel cycle sources' conforming to 40 CFR Part 190.

b.

Radioloaical Environmental Monitorina Procram A

program shall be provided to monitor the radiation and radionuclides in the environs of the plant.

The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1)

Monitoring,

sampling, analysis, and reporting or radiation and radionuclides in the environment in accordance with the methodology and parameters in the

ODCM, 2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and BEAVER VALLEY - UNIT 1 6-15 Amendment No.194

[p uruq

\\

t UNITED STATES NUCLEAR REGULATORY COMMISSION l

WASHINGTON, D.C. 2006H001

\\

DUOVESNE LIGHT COMPANY OHIO EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 773 License No. NPF-73 i

1.

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

A.

The application for amendment by Duquesne Light Company, et al. (the licensee) dated September 13, 1995, as supplemented October 16, j

1995, complies with the standards and requirements of the Atomic 1

Energy Act of 1954, as amended (the Act), snd the Comission's rules and regulations set forth in 10 CFR Chapte.- I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health i

and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission'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 Comission's regulations and all applicable requirements have been satisfied.

.. -. ~ _.. -.... -. -.

.- ~

l I

i 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-73 is hereby l

-amended to read as follows:

(2) Technical Soecifications l

The Technical' Specifications contained in Appendix A, as revised l

through Amendment No. 77, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLC0 shall operate the facility in accordance with the Technical Specifications and the l

Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance, to be implemented within 10 days.

FOR THE NUCLEAR REGULATORY COMMISSION L

r J rIF. Stolz, Direct

.ect Directorate I-vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: Noveinber 21, 1995 i

i t

1

l ATTACHMENT TO LICENSE AMENDMENT NO.77 i

l FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 l

Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 6-14 6-14 1

6-15

'6-15 6-16 6-16 1

9 i

)

l NPF-73 ADMINISTRATIVE CONTROLS i

(

PROCEDURES (Continued)

]

i 1

6.8.5 A program.for monitoring of secondary' water chemistry to inhibit-steam generator tube degradation shall be implemented. This program shall be described in the station chemistry manual and shall include:

a.

Identification of a

sampling schedule for the critical parameters and control points for these parameters; b.

Identification of the procedures used to measure the values of the critical parameters; c.

Identification for process sampling points; d.

Procedures for the recording and management of data; e.

Procedures defining corrective actions for off control point chemistry conditions; and f.

A procedure identifying:

1) the authority responsible for the interpretation of the data, and 2) the sequence and timing of administrative events required to initiate corrective action.

6.8.6 The following programs shall be established, implemented, and maintained:

a.

Radioactive Effluent Control Procram A

program shall be provided conforming with 10 CFR 50.36a for the control of radioactive affluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive affluents as low as reasonably achievable.

The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.

The program shall include the following elements:

1)

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 2)

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 times 10 CFR Part 20, Appendix B, l

Table 2, Column 2, BEAVER VALLEY - UNIT 2 6-14 Amendment No. 77

.. -. - ~.. - -. -. -. _ -, _. -. _,.-

J

'NPF-73 ADMINISTRATIVE CONTROLS PROCEDURES (Continued)

I 3)

Monitoring, sampling, and analysis of radioactive liquid and gaseous affluents.in accordance with-10 CFR 20.1302 and with the methodology and parameters in the ODCM, j

4)

Limitations on the annual and quarterly doses or dose commitment to a

MEMBER OF THE PUBLIC from radioactive materials in liquid affluents released from each unit to UNRESTRICTED AREAS-conforming to Appendix I to le CFR Part 50, 5)

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)

Limitations on the operability and use of the liquid and gaseous effluent l treatment systems' to ensure that the appropriate. portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual-dose or dose commitment conforming to Appendix I to 10 CFR Part 50, 7)

Limitations on the dose rate resulting from radioactive material released in gaseous affluents to areas beyond i

the SITE BOUNDARY shall be limited to the following:

a)

For noble gases:.

Less than or equal to 500 mram/ year to the total body and less than or equal to 3000 mrea/ year to the skin and, b)

For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:

Less than or equal to 1500 mrem / year to any organ, 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous affluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133,

tritium, and all radionuclides in particulate form with half-lives greater than 8

days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, BEAVER VALLEY - UNIT 2 6-15 Amendment No. 77

\\

1 "NPF-73 ADMINISTRATIVE CONTROLS

}

{

PROCEDURES (Continued) 10)

Limitations on the annual dose or dose commitment to any i

MEMBER OF THE -PUBLIC due to releases of' radioactivity and to radiation from. uranium fuel cycle sources conforming to 40'CFR Part 190.

1 I

b.

Radioloaical Environmental Monitorina Proaram A

program shall be provided to monitor the radiation and' radionuclides in the environs of the plant.

The program shall provide (1) representative measurements of radioactivity in the highest potential' exposure pathways, and-(2) verification of the accuracy of the affluent monitoring

. program and modeling of environmental exposure. pathways.

The I

program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1)

Monitoring,

sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the

ODCM, 2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if 1

required by the results of this census, and 3)

Participation in' an Interlaboratory Comparison Program.

to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality

' assurance program for environmental monitoring.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk.

STARTUP REPORTS 6.9.1.1 A

summary report of plant startup and power escalation testing will be submitted following (1) receipt of an operating

license, (2) amendment to the license involving a planned increase in power

level, (3) installation of fuel that has a different design or had been manufactured by a

different fuel

supplier, and (4) modifications that may have significantly altered the

nuclear, thermal, or hydraulic performance of the plant.

BEAVER VALLEY - UNIT 2 6-16 Amendment No. 77