ML20117F228

Proposed Tech Specs,Requesting NRC Approval for Operating Company to Be Formed by Owners,To Become Licensed Operator for STP & to Have Exclusive Control Over Operation & Maint of Facility

ML20117F228
Person / Time
Site:	South Texas
Issue date:	08/23/1996
From:	HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20117F225	List: ML20117F222 ML20117F228 ML20117F720
References
NUDOCS 9609030380
Download: ML20117F228 (24)

Text

ATTACHMENT 4

PROPOSED CHANGES TO THE UNIT 1 LICENSE i

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i HOUSTON LIGHTING & POWER COMPANY l CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DPCO l DOCKET NO. 50-498 SOUTH TEXAS PROJECT. UNIT 1 FACILITY OPERATING LICENSE License No. NPF-76 i

1. The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A. The aplication for a license filed by the Houston Lighting & Power Company *

[ del $1sg6Eid} (HL&P) acting on behalf of itself and for the City Public )

Service Board of San Antonio (CPS), Central Power and Light Company (CPL),  !

and City of Austin, Texas (COA) [tiilf@j) (:iccasccs) complies with the ,

standards and requirements of the Atomic Energy Act of 1954, as of 1954 as j amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; B. Construction of the South Texas Project, Unit 1, (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-128 and the application, as amended, the provisions of the Act, and the regulations of the Commission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Section 2.D. below);

D. There is reasonable assurance: (i) that the activities authorized by this operating license 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 set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D. below);

'I!aus en Ligh5g a Powcr Company ;s au:horized ;o act for :he Ci;y Public Scnicc "serd of San Antonio, Cca:ral Powcr and Light Company and Ci:y of Aus:in, Texas and has exclusive icspcasibility and control over :he physice: cons:ruc: on, operetion end main:cnance of the feethty

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l SOUTH TEXAS LICENSE

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E. I)PDO$ ::cus:ca Ligh::;.g i l'ower Corap;.r.y is technically qualified to engage in the activities authorized by this license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; i F. The ,iKsiIAIifi llccasces . have satisfied the applicable provisions of 10 CFR Part .l 140, " Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations;

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G. The issuance of this license will not be inimical to the common defense and security or to the healt and safety of the public; J l H. After weighing the environmental, economic, technical and other benefits of the

facility against environmental and other costs and considering available altematives, the issuance of this Facility Operating License No. NPF-76, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and l

I. The receipt, possession, and use of source, byproduct and special nuclear

! material as authorized by this license will be in accordance with the l

Commission's regulations in 10 CFR Parts 30,40 and 70.

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2. Based on the foregoing findings, and approval by the Nuclear Regulatory Commission at a meeting on March 21,1988, the License for Fuel Loading and Low Power Testing,

. License No. NPF-71 issued on August 21,1987 is superseded by Facility Operating

, License NPF-76, hereby issued to pFfCQ Houston Lighting & Power Company, City Public Service Board of San Antonio, Central Power and Light Company, and City of Austin, Texas (the licensees) to read as follows:

A. This license applies to the South Texas Project, Unit 1, a pressurized water reactor, and associated equipment (the facility) owned by Houston Lighting &

i Power Company, City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas SIf@3fidiidG)[M%D. The facility is located in Matagorda County, Texas, west of the Colorado River,8 miles north-northwest of the town of Matagorda and about 89 miles southwest of Houston and is described in the licensees' Final Safety Analysis Report, as l

supplemented and amended, and in the licensees' Environmental Report, as

! st.polemented and amended.

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SOUTil TEXAS LICENSE B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:

(1) DNd !!cus;on Lighting & Powcr Conipeny (IIL&P) pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the ,

designated location in Matagorda County, Texas, in accordance with the l procedures and limitations set fonh in this license; (2) N66566%Ij6if6EK2@d$rifjjiIy [HilhD di$ The City Public Service I Board of San Antonio (CPS), Central Power and Light Company (CPL), and the I City of Austin, Texas (COA), pursuant to the Act and 10 CFR Part 50, to possess the facility at the designated location in Matagorda County, Texas, in accordance with the procedures and limitations set forth in this license; (3) DNd-Hb&P, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; i

(4) DMC IIL&P, pursuant to the Act and 10 CFR Parts 30,40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material  !

as sealed neutron sources for reactor startup, sealed sources for reactor  !

instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) OPC(i IIL&P, pursuant to the Act and 10 CFR Parts 30,40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sansple analysis or i instrument calibration or associated with radioactive apparatus or components; l and (6) DIsd IIL&P, pursuant to the Act and 10 CFR Parts 30,40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility authorized herein.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level DND IIL&P is authorized to operate the facility at reactor core power levels not in excess of 3800 megawatts thermal (100% power) in accordance with the conditions specified herein.

SOUTH TEXAS LICENSE (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. QRQQ HE&P shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Antitrust Conditions Houston Lighting & Power Company, City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas

(@QyI6Ed shall comply with the antitrust conditions delineated in Appendix C to this license; Appendix C is hereby incorporated into this license.

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$pM5dNUdhiUMdeh5I (4) Initial Startup Test Procram (Section 14. SER)*

Any changes to the Initial Test Program described in Section 14 of the Final Safety Analysis Report made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.

(5) Safety Parameter Display System (Section 18. SSER No. 4)*

Before startup after the first refueling outage, HL&Pdd shall perform the necessary activities, provide acceptable responses, and implement all proposed corrective actions related to issues as described in Section 18.2 of SER Supplement 4.

• The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

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SOUTH TEXAS LICENSE (6) Supolementaiv Containment Purge Isolation (Section 11.5. SSER No. 4) l HL&P shall provide, prior to startup from the first refueling outage, control room indication of the normal and supplemental containment purge sample line isolation valve position. l D. Exemptions The following exemptions are authorized by law and will not endanger life or property or the common defense and security, and certain special circumstances are present. With the  ;

granting of these exemptions, the facility will operate, to the extent authorized herein, in j conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.  ;

l (1) The facility requires a technical exemption from the requirements of 10 CFR Part 50, Appendix J, Section III.D.2(b)(ii). The justification for this exemption is contained in Section 6.2.6 of Supplement 3 to the Safety Evaluation Report. The staff's environmental assessment was published on July 2,1987 (52 FR 25094). Therefore, pursuant to 10 CFR 50.12(a)(1),10 CFR 50.12(a)(2)(ii) and (iii), the South Texas Project Unit 1 is hereby granted an exemption from the quoted requirement and instead, is required to perform the overall air lock leak test at pressure P, prior to establishing containment integrity if air lock maintenance has been performed that could affect the air lock sealing capability.

(2) The facility requires a schedular exemption from the requirements of General Design Criterion 57, Appendix A to 10 CFR 50. The staff has described in detail in Supplement 4 to the Safety Evaluation Report the technical bases associated with this exemption. The staff's environmental assessment was published on June 18, 1987 (52 FR 23217). Therefore, pursuant to 10 CFR 50.12(a)(1) and 10 CFR 50.12(a)(2) and 10 CFR 50.12(a)(2)(v) the South Texas Project Unit 1 is hereby granted an exemption from the requirements of GDC-57 applicable to the essential component cooling water (CCW) piping which is also used by the non-essential reactor containment building chilled water system in providing cooling to the Reactor Containment Fan Coolers (RCFC). This exemption will expire at the end of the first refueling outage.

(3) The facility was previously granted exemption from the criticality monitoring requirements of 10 CFR 70.24 (See Materials License No. SNM-1972 dated December 29,1986 and Section 9.1.2 of SSER No. 3). The South Texas Project Unit 1 is hereby exempted from the criticality monitoring provisions of 10 CFR 70.24 as applied to fuel assemblies held under this license.

SOUTH TEXAS LICENSE (4) The facility has been granted a schedular exemption from Section 50.71(e)(3)(i) of 10 CFR 50 to extend the date for submittal of the updated Final Safety Analysis Report to no later than one year after the date of issuance of a low power license for the South Texas Project, Unit 2. This exemption is effective until August 1990. The staff's environmental assessment was published on December 16,1987 (52 FR 47805).

E. Fire Protection DPQOHL4P shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report through

. Amendment No. 55 and the Fire Hazards Analysis Report through Amendment No.7, and submittals dated April 29, May 7,8 and 29, June 11,25 and 26,1987, and as approved in the SER (NUREG-0781) dated April 1986 and its Supplements, subject to the following provision:

DM I! lap may make changes to the approved fire protection program without prior approval of the Commission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

F. Physical Security DPCC !! lap shall fully implement and maintain in effect all provisions of the physical security, guard training and qualificatica, and safeguards contingency plans previously approved by the Commission and all amendments and n: visions to such plans made pursuant to the authority under 10 CFR 50.90 and 10 CFR 50.54(p).

The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: " South Texas Project Electric Generating Station Physical Security Plan,"

with revisions / amendments submitted through March 4,1988; " South Texas Project Electric Generating Station Security Personnel Qualification and training Plan" with revisions submitted through March 4,1988, and " South Texas Project Electric Generating Station Safeguards Contingency Plan," with revisions / amendments submitted through July 24,1987.

SOUTH TEXAS LICENSE G. Reporting To The Commission Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, D@y 1&&P shall report any violations of the requirements contained in Section 2.C of this license in the following manner: initial notification shall be made within twenty-four (24) hours to the NRC Operations Center via the Emergency Notification System with written follow-up within 30 days in accoidance with the procedures described in 10 CFR 50.73(b), (c), and (e).

H. Financial Protection The pyiGH liccasccs shall have and maintain financial protection of such type and in d

such amounts as the Commission shall require in accordance with Section 170 of the 4 Atomic Energy Act of 1954, as amended, to cover public liability claims.

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I. Effective Date and Expiration f This license is effective as of the date of issuance and shall expire at midnight on August 20,2027.

FOR THE NUCLEAR REGULATORY COMMISSION )

! Thomas E. Murley, Director Office of Nuclear Reactor Regulation l 1

Enclosures:

i L Appendix A, Technical Specifications (NUREG-1305) j 2. Appendix B, Environmental Protection Plan  ;

j 3. Appendix C, Antitmst Conditions 1

Date of Issuance: March 22,1988 l

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J * .m - _-e ATTACHMENT 5 PROPOSED CHANGES TO UNIT 2 LICENSE

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HOUSTON LIGHTING & POWER COMPANY 1 CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS i 1

DPCQ DOCKET NO. 50499 i

SOUTH TEXAS PROJECT. UNIT 2 FACILITY OPERATING LICENSE License No. NPF-80

1. The Nuclear Regulatoiy Commission (the Commission or the NRC) has found that: l 1

A. The aglication for a license filed by the Houston Lighting & Power Company

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[debe M4] (HL&P) acting on behalf of itself and for the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL), and City of Austin, Texas (COA) [@$$) (liccascca) 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, and all required notifications to other agencies or bodies have been duly made; B. Construction of the South Texas Project, Unit 2, (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-129 and the application, as amended, the provisions of the Act, and the regulations of the Commission; 1

C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Section 2.D. below);

D. There is reasonable assurance: (i) that the activities authorized by this operating  !

license 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 set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D. below);

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E. DNO3 IIous:ca L;ghdag & Powcr Company is technically qualified to engage in the activities authorized by this license in accordance with the Commission's  !

regulations set forth in 10 CFR Chapter I; F. The pi$Is@censcc3 have satisfied the applicable provisions of 10 CFR Part 140,

" Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G. The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; H. After weighing the environmental, economic, technical and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of this Facility Operating License No. NPF-80, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and I. The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30,40 and 70.

2. Based on the foregoing findings, and approval by the Nuclear Regulatory Commission at a meeting on March 28,1989, the License for Fueling Loading and Low Power Testing, License No. NPF-78 issued on December 16,1988 is superseded by Facility Operating License NPF-80, hereby issued to D@ Houston Lighting & Power Company, City  :

Public Service Board of San Antonio, Central Power and Light Company, and City of I Austin, Texas (the licensees) to read as follows:

A. This license applies to the South Texas Project, Unit 2, a pressurized water reactor, and associated equipment (the facility) owned by Houston Lighting & Power Company, City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas R$IEllid'Sy,"ONd. The facility is located in Matagorda County, Texas, west of the Colorado River,8 miles north-northwest of the town of Matagorda and about 89 miles southwest of Houston and is described in the licensees' Final Safety Analysis Report, as supplemented and amended, and in the licensees' Environmental Report, as supplemented and amended.

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l B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:

l (1) y@D IIccMon Lighting & Pcws Ccnipany (!!L&P) pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the designated location in Matagorda County, Texas, in accordance with the procedures and limitations set forth in this license; (2) Hyi[63%ijEIEjXPhi&M55iiEiH@h)%di8 The City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL), and the City of Austin, Texas (COA), pursuant to the Act and 10 CFR Pan 50, to possess the facility at the designated location in Matagorda County, Texas, in accordance with the procedures and limitations set forth in this license; (3) DMD3HL-&P, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4) DPdd HL-&P, pursuant to the Act and 10 CFR Parts 30,40 and 70, to receive, 1 possess, and use at any time any byproduct, source and special nuclear material  ;

as sealed neutron sources for reactor startup, sealed sources for reactor l instrumentation and radiation monitoring equipment calibration, and as fission 1 detectors in amounts as required; )

l (5) UNd HE&P, pursuant to the Act and 10 CFR Parts 30,40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) DNd Hb&P, pursuant to the Act and 10 CFR Parts 30,40 ano 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility authorized herein.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions l specified or incorporated below:

(1) Maximum Power Level l DPCs HE&P is authorized to operate the facility at reactor core pawer levels not in excess of 3800 megawatts thermal (100% power) in accordance with the conditions specified herein.

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(2) Technical Specifications and Environmental Protection Plan .

The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both which are attached hereto, are hereby l incorporated into this license. QND]HL-&P shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Antitrust Conditions Houston Lighting & Power Company, City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas [Q[U,i"M] shall comply with the antitrust conditions delineated in Appendix C to this license; Appendix C is hereby incorporated into this license.

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(4) Initial Stanup Test Procram (Section 14. SR)*

Any changes to the Initial Test Program described in Section 14 of the Final Safety Analysis Report made in accordance with 50.59(b) within one month of such change.

D. Exemptions The following exemptions are authorized by law and will not endanger life or property or the common defense and security, and certain special circumstances are present. With the granting of these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

(1) The facility requires a technical exemption from the requirements of 10 CFR Part 50, Appendix J, Section III.D.2(b)(ii). The justification for this exemption is contained in Section 6.2.6 of Supplement 3 to the Safety Evaluation Report. The staffs environmental assessment was published on December 16,1986 (53 FR 5%05). Therefore, pursuant to 10 CFR 50.12 (a)(1),

• The parenthetical notation following the title of may license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

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l 10 CFR 50.12(a)(2)(ii) and (iii), the South Texas Project Unit 2 is hereby granted an exemption from the quoted requirement and instead, is required to perform the overall air lock leak test at pressure P, prior to establishing containment integrity if air lock maintenance has been performed that could affect the air lock sealing capability.

(2) The facility was previously granted exemption from the criticality monitoring requirements of 10 CFR 70.24 (See Materials License No. SNM-1983 dated August 30,1988 and Section III.E. of the SER dated August 30,1988). The South Texas Project Unit 2 is hereby exempted from the criticality monitoring provisions of 10 CFR 70.24 as applied to fuel assemblies held under this license.

(3) The facility requires a temporary exemption from the schedular requirements of the decommissioning planning rule,10 CFR 50.33(k) and 10 CFR 50.75. The justification for this exemption is contained in Section 22.2 of Supplement 6 to the

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5'afety Evaluation Report. The staff's environmental assessment was published on December 16,1988 (53 FR 50604). Therefore, pursuant to 10 CFR 50.12(a)(1),

50.12(a)(2)(ii) and 50.12(a)(2)(v), the South Texas Project, Unit 2 is hereby granted a temporary exemption from the schedular irquirements of 10 CFR 50.33(k) and 10 CFR 50.75 and is required to submit the decommissioning plan for both South Texas Project, Units 1 and 2 on or before July 26,1990.

E. Fire Protection O

' PCO HE&P shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report through -

Amendment No. 62 and the Fire Hazards Analysis Report through Amendment No.

7, and submittals dated April 29, May 7,8 and 29, June 11,25, and 26,1987, and as approved in the SER (NUREG-0781) dated April 1986 and its Supplements, subject to the following provisions:

DPCO HE&P may make changes to the approved fire protection program without prior approval of the Commission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

F. Physical Security D000 Hb&P shall fully implement and maintain in effect all provisions of the physical security, training and qualification, and safeguards contingency plans

! previously approved by the Commission and all amendments and revisions to such plans made pursuant to the authority under 10 CFR 50.90 and 10 CFR 50.54(p).

The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: " South Texas Project Electric Generating Station Physical Security Plan " ,

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with revisions / amendments submitted through September 30,1988; " South Texas i Project Electric Generating Station Security Personnel Qualification and Training Plan" with revisions submitted through March 4,1988, and " South Texas Project Electric Generating Station Safeguards Contingency Plan," with j revisions / amendments submitted through July 18,1988.

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i G. Reoortine To The Commission l

. l Except as otherwise,provided in the Technical Specifications or Environmental 5 Protection Plan, QljC6M shall report any violations of the requirements l contained in Section 2.C of this license in the following manner: initial notification <

!' shall be made within twenty-four (24) hours to the NRC Operations Center via the 3 Emergency Notification System with written follow-up within 30 days in accordance

with the procedures described in 10 CFR 50.73(b), (c), and (e).

l H. Financial Protection The pi@Isi@iccascca shall have and maintain financial protection of such type and  ;

in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

I. Effective date and Expiration This license is effective as of the date of issuance and shall expire at midnight on  !

I December 15,2028.

FOR THE NUCLEAR REGULATORY COMMISSION I James H. Sniezek/for l Thomas E. Murley, Director l Office of Nuclear Reactor Regulation I

Enclosures:

1. Appendix A, Technical Specifications (NUREG-1346)

2. Appendix B, Environmental Protection Plan

3. Appendix C, Antitrust Conditions Date of Issuance: March 28,1989

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i ATTACHMENT 6 PROPOSED CHANGES TO THE TECHNICAL SPECIFICATIONS

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ADMINISTRATIVE CONTROLS i

6.1 RESPONSIBILITY

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6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor (or during his absence from the control room, a designated individual) shall be responsible for the control room command function. A management directive to this effect, signed by the R6sidsh6I(pliiREissistiEOffi6es Group Vice '

Prcsidcat, Nuclcer shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION  !

l OFFSITE AND ONSITE ORGANIZATIONS 6.2.1 Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating i organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization chans, functional descriptions of depanmental responsibilities and relationships, and job descriptions for key personnel positions, or equivalent forms of documentation.

These requirements shall be documented in the FSAR.

b. The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. The Vice President, Nuclear DEdEMf6ii, P! sat Opersticas, shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety,

d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

UNIT STAFF 6.2.2 The unit staff shall be as follows:

a. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; SOUTH TEXAS - UNITS 1 & 2 6-1 Unit 1 - Amendment No. 3

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1 ADMINISTRATIVE CONTROLS I RESPONSIBILITIES (Continued) )

6.5.1.7 The PORC shall I

a. Recommend in writing to the Plant Manager approval or disapproval of items l considered under Specification 6.5.1.6a. through e. prior to their implementation, and items  !

considered under Specification 6.5.1.6i. through 1.

b. Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6a. through e. and o. constitutes an unreviewed safety question; and

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the p[isidEE6AfidMf5(EiEdiii6 Uffice,,r Croup Vicc Picsidcnt-Nucicar and the Nuclear Safety Review Board of disagreement between the PORC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.

RECORDS 6.5.1.8 The PORC shall maintain written minutes of each PORC meeting that, at a minimum, ,

l document theseJechnical theSpecifications.

results of allCopies PORCshall activities performed be provided under the Preside sedthe resp @onsibility provisl

[Culeffiksilis Officed Group Vwc Presiden:-Nucl car and the Nuclear Safety Review Board.

6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)

FUNCTION 6.5.2.1 The NSRB shall function to provide independent review and audit of designated activities in the areas of:

a. Nuclear power plant operations,

b. Nuclear engineering,

c. Chemistry and radiochemistry,

d. Metallurgy,

e. Instmmentation and control,

f. Radiological safety,

g. Mechanical and electrical engineering,

h. Civil engineering,

i. Training,

j. Nuclear assurance,

k. Nuclear licensing,

1. Plant security, and

m. Environmental impact.

The NSRB shall report to and advise the PIEsidEEf!EEdhdREiB66iiEDifiEf Group Vice Picsident-Nucicar on those areas of responsibility specified in Specifications 6.5.2.7 and 6.5.2.8.

SOUTH TEXAS - UNITS 1 & 2 6-9 2

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

l i

ADMINISTRATIVE CONTROLS i  :

COMPOSITION

6.5.2.2 The NSRB shall be composed of at least five members I appointed in writing by the NEldshif3s(Cfilsf;EisiGilROffi5i Cicap Vice Picsidcat, Nucicar selected from senior managers 4 reporting to at least the vice president level in the STPEGS

Management Organization. Additional members shall be appointed in -1 j writing by the Prleaildsh{fss(Cliisf,EiB6stijilDffissi Croup Vice Prc3iden:, Nucicer so the l

NSRB collectively has the capability to review technical matters listed in Technical

. Specification 6.5.2.1. The NSRB Chairman shall be appointed in writing from among these members by the h61d5btsid%hRFIE6iME@ilii Group -

Vice Pic3ldca;, Nuclcer. I i

ALTERNATES i 6.5.2. All alternate members shall be appointed in writing by the MiM56fd53"dili{

Execu}tIR0fficer Croup Vice PrcsidenbNue:cer to serve on a temporary basis; howeve

more than two altemates shall participate as voting members in NSRB activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSRB Chairman to provide expen advice to the NSRB.

MEETING FREQUENCY 6.5.2.5 The NSRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months thereafter.

QUORUM 6.5.2.6 The quorum of the NSRB necessary for the performance of the NSRB review and audit functions of these Technical Specifications shall consist of the Chairman or his designated attemate and at least a majority of NSRB members including attemates. No more than a minority of the quorum shall have line responsibility for operation of the unit.

REVIEW 6.5.2.7 The NSRB shall be responsible for the review of:

a. The safety evaluations for: (1) changes to procedures, equipment, or systems; and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question;

b. Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; SOUTH TEXAS - UNITS 1 & 2 6-10 Unit 1 - Amendment No. 20 Unit 2 - Amendment No.10 f

i l ADMINISTRATIVE CONTROLS i

AUDITS (Continued) l l

, i l h. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures;

, i. The PROCESS CONTROL PROGRAM and implementing procedures for processing i and packing of radioactive wastes ;

j. The performance of activities required by the Quality Assurance Program for effluent I

and environmental monitoring; and i

j k. Other activities and documents as requested by the NSRB or the 6~/22iis,'Jiif)Mif i

! WMnOffGii Croup Vic; Pics:-m_. .. . ,

i l j RECORDS j i  :

j 6.5.2.9 Records of NSRB activities shall be prepared, approved, and distributed as indicated  !

d below:  ;

i

! a. Minutes of each NSRB meeting shall be prepared, approved, and forwarded to the 1 l$Isi3&II%idjCSiffis!$6EiMDfficif Croup Vice PicaidenLNucl car within 14 days  !

j following each meeting; l

1

b. Repons of reviews encompassed c .

approved, and forwarded to the Pingident3,,by id . 7.ificationS6.5.2.7Croup 9EOffidsjf shall be Viceprepared,  ;

j Pic;ldenLNuc cer within 14 days following completion of the review; and  !

, c. Audit re orts encompassed by Specification 6.5.2.8 shall be forwarded to the I

Pr,,esid, e,,,s,,@,Mndi DRifiiiislKORi6@'irj Croup Vice Pic;ldcaLNucl car and to the management ,

! positions responsible for the areas audited within 30 days after completion of the audit by the

~

auditing organization.

1 l 6.5.3 TECHNICAL REVIEW AND CONTROL

?

] ACTIVITIES 6.5.3.1 Activities that affect nuclear safety shall be conducted as follows:

a. Procedures required by Specification 6.8, and other procedures that affect nuclear safety, and changes thereto, shall be prepared, reviewed, and approved. Each such procedure, or change thereto, shall be reviewed by an individual / group other than individual / group who prepared the procedure, or change thereto, but who may be from the same organization as the individual / group who prepan:d the procedure, or change thereto. Procedures other than station administrative procedures shall be approved by the Plant Manger, Plant Superintendent, or the head of the responsible depanment prior to fapementation. The Plant Manager shall approve station administrative procedures, security plan implementing procedures, and emergency plan implementing procedures. Temporary changes to procedures, which clearly do not change the intent of the approved procedures, shall be approved prior to implementation by two members of the plant staff,

. SOUTH TEXAS - UNITS 1 & 2 6-12 Unit 1 - Amendment No. 4

+

I 1

7 ACTIVITIES (Continued) at least one of whom holds a Senior Reactor Operator's License. Changes to 3 procedures that may involve a change to the intent of the original procedure shall be approved a

by the individual authorized to approve the procedure prior to implementation of the change.

b. Proposed changes or modifications to safety-related stmetures, systems, and

components shall be reviewed as designated by the Plant Manager. Each such modification

!' shall be reviewed by an individual / group other than the individual / group who designed the modification, but who may be from the same organization as the individual / group who

)

3 designed the modification. Proposed modifications to safety-related structures, systems, and '

components shall be approved by the Plant Manager prior to implementation. l 6

c. Proposed tests and experiments that affect nuclear safety and that are not addressed

! in the Final Safety Analysis Report shall be prepared, reviewed, and approved prior to implementation. Each such test or experiment shall be reviewed by an individual / group other j than the individual / group who prepared the test or experiment but who may be from the same

organization as the individual / group who prepared the test or experiment. Proposed tests and

experiments shall be approved by the Plant Manager.

4

d. Individua.ls responsible for reviews performed in accordance with Specification 6.5.3.1 (a) through (c) shall be members of the plant management staff previously designated by the Plant Manager. Each review shall include a determination of whether or not additional, cross-disciplinary review is necessary. If deemed necessaiy, such review shall be performed by qualified personnel of the appropriate discipline.

e. Each review will include a determination of whether or not an unreviewed safety question is involved. Pursuant to 10 CFR 50.59, NRC approval of items involving an unreviewed safety question will be obtained prior to Plant Manager approval for implementation.

6.5.3.2 Records of the above activities shall be provided to the Plant Manager, PORC, and/or the NSRB as necessary for required reviews.

6.6 REPORTABLE EVENT ACTION 6.6.1 The fellowing actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and ,

b. Each REPORTABLE EVENT shall be reviewed by the PORC review shall be submitted to the NRSB and the f5%Risi(DiRNAd, 0ilEDff25 and Croup the results of t Vicc I'icsijc UNuc!cer.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

SOUTH TEXAS - UNITS 1 & 2 6-13 5-

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued)

a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within I hour. The 66)dsiiiiiidMdDiid6'tIRDific,er Croup Vicc Pics: den;-Nuc car and the NSRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />;

b. A Safety Limit Violation Repon shall be prepared. The repon shall be reviewed by the PORC.

This report shall describe: (1) applicable circumstances preceding the violation,(2) effects of the i violation upon facility components, systems, or structures, and (3) corrective action taken to prevent i recurrence; sidmk,The Pre.,

C- Safety Li,mit Violation Report shall be submitted to the Commission, the NSR

d. Operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978;

b. The emergency operating procedures required to implement the requirements of NUREG-0737 and Supplement I to NUREG-0737 as stated in Generic Letter No. 82-33;

c. Security Plan implementation;

d. Emergency Plan implementation;

e. PROCESS CONTROL PROGRAM implementation;

f. OFFSITE DOSE CALCULATION MANUAL implementation;

g. Quality Assurance Program for effluent and environmental monitoring; and

h. Fire Protection Program implementation.

6.8.2 Each procedures of Specification 6.8.1, and changes thereto, shall be reviewed and approved prior to implementation and reviewed periodically as set forth in Specification 6.5.3 and administrative procedures. <

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

a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the containment spray, Safety Injection, containment hydrogen monitoring, post-accident sampling and primary sampling. The program shall include the following:

SOUTH TEXAS - UNITS 1 & 2 6-14 Unit 1 - Amendment No. 4 I

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ATTACHMENT 7 l

PROPOSED CHANGES TO APPENDIX B 1

1

l APPENDIX B  !

TO FACILITY OPERATING LICENSE NON. NPF-I{G"dM807+

SOUTH TEXAS PROJECT 1

UNITS 1 AND 2 i

I i 1 i RQ :OusTON uC::T:NC & POWS COMPANY, ET AL.

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~

DOCKET NOS. 50-498 AND 50499 1

j ENVIRONMENTAL PROTECTION PLAN (NONRADIOLOGICAL)

MARCH 1989 l-

'I i

1 1

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