ML20126A823

Forwards Draft OL for Facility,For Info & Comment.Since NRC Still Reviewing Numerous Outstanding SER Issues,Conditions on License Not Definite at Present.Comments Requested within 5 Days of Ltr Date

ML20126A823
Person / Time
Site:	River Bend
Issue date:	06/04/1985
From:	Novak T Office of Nuclear Reactor Regulation
To:	William Cahill GULF STATES UTILITIES CO.
References
NUDOCS 8506130481
Download: ML20126A823 (20)

Text

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JUN 4 1985 Docket No. 50-458 Mr. llilliam J. Cahill, Jr.

-Senior Vice President River Bend Nuclear Group Gulf States Utilities Company Post Office Box 2951 Beaumont, Texas 77704 ATTN: Mr. J. E. Booker

SUBJECT:

RIVER BEND STATION, UNIT 1 DRAFT LICENSE Enclosed is a draft copy of the operating license for River Bend Station Unit 1.

It is provided for your information and cent.1ent to ensure that it accurately reflects the commitments required of you as described in the FSAR, SER and other documentation. However, since the staff is still reviewing numercus outstanding SER issues, the conditions on this license are not definite at

.this time.

We request that you exanine the draft license and provide any ccnments in i writing within five days of the date of this letter.

Should you have questions regarding this draft license, please contact the River Bend Project Manager Stephen 11. Stern at (301) 492-8349.

Sincerely, Celpf Nnl nietmd byi Thomas M. Novak, Assistant Director for Licensing Division of Licensing

Enclosure:

As stated cc: See next pace Distribution: Docket File NRC PDR Local PDR PRC Systcm NSIC LTf2 Reading EHyl ton SStern TNovak JSaltzaan,SAB Dewey,0 ELD CMiles HDenton JRutberg AToalston WNiller.LFMB JPartlow BGrimes EJordan LHarnon

• Previously concurred:

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UNITED STATES

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..... M 4 ' $65 Docket No. 50-458 Mr. William J. Cahill, Jr.

Senior Vice President River Beni Nuclear Group Gulf States Utilities Company Post Office Box 2951 Beaumont, Texas 77704 ATTN: Mr. J. E. Booker

SUBJECT:

RIVER BEN 6 STATION, Ul:IT 1 DRAFT LICENSE Enclosed is a draft copy cf the operating license for River Bend Station Unit 1.

It is provided for your information and corrent to ensure that it accurately reflects the commitments required of you as described in the FSAR, SER and cther documentation. However, since the staf f is still reviewing nurcrcus outstanding SER issues, the conditions on this license are not definite at this time.

We request that ycu examine the draft license and provide cry contrents in writing within five days of the cate of this letter.

Shculd you have questions regarding this cratt license, please contact the River. Bend Project Manager Stephen it. Stern at (301) 492-8349.

Sincerely,

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Thomas M. Novak, Assistant Director

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for Licensing Division of Licensing

Enclosure:

As stated cc: See next page e

Mr. William J. Cahill, Jr. River Bend Nuclear Plant Gulf States Utilities Company cc: Troy B. Conner, Jr., Esq. Ms. Linda B. Watkins/Mr. Steven Irving Conner and Wetterhahn Attorney at Law .

1747 Pennsylvania Avenue, N. W. 355 Napoleon Street Washington, D.C. 20006 Baton Rouge, Louisiana 70802 Mr. William J. Reed, Jr.

Director - Nuclear Licensing Gulf States Utilities Company Post Office Box 2951 Beaumont, Texas 77704 Mr. David Zaloudek Nuclear Energy Division H. Anne Plettinger Louisiana Department of -

3456 Villa Rose Dr. Environmental Quality Baton Rouge, Louisiana 70806 Post Office Box 14690 Baton Rouge, Louisiana 70898 Richard M. Troy, Jr. , Esq.

Assistant Attorney General in Charge State of Louisiana Department of Justice 234 Loyola Avenue New Orleans, Louisiana, 70112 Mr. J. David McNeill, III Dwight D. Chamberlain William G. Davis, Esq.

Resident Inspector Department of Justice Post Office Box 1051 Attorney General's Office St. Francisville, Louisiana 70775 7434 Perkins Road Baton Rouge, Louisiana 70808 Gretchen R. Rothschild Louisianians for Safe Energy, Inc.

1659 Glenmore Avenue Baton Rouge, Louisiana 70775 James W. Pierce, Jr., Esq.

P. O. Box 23571 Baton Rouge, Louisiana 70893 Mr. Robert D. Martin U.S. NRC, Region IV Parkway Central Plaza Building 611 Ryan Plaza Drive, Sutie 1000 Arlington, Texas 76011

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'/ GULF STATES UTILITIES COMPANY AND CAJUN ELECTRIC POWER COOPERATIVE DOCKET NO 50-458 RIVER BEND STATION, UNIT 1 FACILITY OPERATING LICENSE License No. NPF-40

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

A. The application for license filed by the Gulf States Utilities Company, actin Cooperative, (g on behalf of itself and the Cajun Electric Powerthe licensees)

. nents of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 River Bend Station, Unit 1 (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-106 and the application, as amended, the provisions of the Act and the regulations of the Comission;

f. C. The facility will operate in conformity with the application, as y5 amended, the provisions of the Act, and the regulations of the Commision (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);

E. The G' ulf States Utilities Company

• is technically qualifiec' to l engage in the activities authorized by this license in accordance with the Comission's regulations set forth in 10 CFR Chapter I; F. The Gulf States Utilities Company and Cajun Electric Power Corporative have satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements", of the Comission's l

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; i

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Gulf States Utilities Company is authorized to act as agent for Cajun Electric Power Cooporative and has exclusive responsibility and control over the physical construction, opt ation and maintenance of the facility.

(4) GSU, 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 monitor-ing equipment calibration, and as fission detectors in amounts as required; (5) GSU, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical fom, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) GSU, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuc' lear materials as may be produced by the operation of the facility.

. C. This license shall be deemed to contain and is subject to the condi-tions specified in the Conraission's regulations set forth in 10 CFR Chapter 1 (except as exempted from compliance in Section 2.D. below) and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Comission now or hereaf ter in effect; and is subject to the additional conditions specified or H(

incorporated below:

(1) Maximum Power Level 3 GSU is authorized to operate the facility at reactor core power levels not in excess of 2894 megawatts thertnal (100% rated power) in accordance with the conditions specified herein. Pending Comission approval this license is restricted to power levels not to exceed five percent of rated power (144.7 megawatts themal).

(2) Deferred items

.The items identified in Attachment I to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license. ,

(3) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the En-vironmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.

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

(4) Oil and Gas Exploration (Section 2.2.2, SER and SSER- )*

GSU shall promptly notify the NRC staff in writing of any new oil or gas wells or pipelines planned for locations within a 2 mile radius of the unit reactor centerline. Prompt notification shall be deemed to be within 30 days of becoming aware of such plans, the potential safety impact of such wells or pipeline shall be addressed in this notification.

(5) Turbine System Maintenance Program (Section 3.5.1 and 3.3, SER)

GSU shall submit a turbine system maintenance program by

• October 26, 1987. Prior to review and soproval of that program by the NRC staff, GSU shall volumetrically inspect all low pressure turbine rotors at the second refueling outage and every other (alternate) refueling outage thereafter.

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(6) Inservice Testing of Pumps and Valves (Section 3.9.6, SER and SSER- )

Pursuant to 10 CFR Part 50.55a the relief identified in the Pump and Valve Inservice Testing Program Plan for the River Bend Station Unit 1. Revision dated that GSU has requested from the pump and valve testing re Part 50 Section 50.55a (g)(2) and (g)(4)(i)quirements is grantedoffor 10that CFR portion of the initial 120-month period during which the staff completes its review.

(7) Equipment Qualification (Section 3.11, SER)

All electrical equipment within the scope of 10 CFR 50.49 must be environmentally qualified by November 30, 1985.

(8) knservice Ins)ection Program (Section 5.2.4.3

.and 6.6.3, SER and SSER-3)

The licensee shall submit the inservice inspection program for NRC staff review and approval by one year from date of this license.

l (9) Steam Bypass of the Suppression Pool (Section 6.2.1.7, SER)

The operating procedures shall contain provisions for instructing

the operator to actuate the ADS whenever the containment to annulus differential pressure reaches 5 psi.

(10) Hydrogen Control (Section 6.2.5, 5ER and 55ER-2)

(Tobeprovided)

! *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.

(11) ICSB Issues (Sections 7 )

(To be provideo)

(12) Fire Protection (Section 9.5, SER, SSER-2)

a. The ifcensee shall implement and maintain in effect all provisions of the approved fire protection prograta as described in the Final Safety Analysis Report for the facility (or as described in submittals dated )

and as approved in the SER dated (and Supplements dated ) subject to provisions 2 and 3 below,

b. The licensee may make no change to the approved fire protection program which would significantly decrease the level of fire protection in the plant without prior approval of the Commission. To make such a change the licensee must' submit an application for license amendment pursuant to 10 CFR 50.90.

c. The licensee may make changes to features of the approved fire protection program which do not significantly decrease the level of fire protection without prior Comission approval provided (a) such changes do not otherwise' involve a change in a license condition or technical specification or result in an unreviewed safety question (see 10 CFR 50.59), and (b) such changes do not result in failure to complete the fire protection program approved by the Comission prior to license issuance. The licensee shall maintain, in an auditable form, a current record of all such changes, including an analysis of the effects of the change on the fire protection program, and shall make such records available to NRC inspec-tors upon request. All changes to the approved program shall be reported annually to the Director of the Office of Nuclear Reactor Regulation, along with the FSAR revisions required by 10 CFR 50.71(e).

(13) Post Accident Samplina (Section 10.4.6/Till Itw II.B.3, SER)

Prior to exceeding five percent rated power cpcration, Gulf States utilities shall h6ve instclied and operational the post-acc&r t ..

sampling system.

Prior to five percent rated power operation, (30 shall: (1) describe provisions for sampling during loss of offsite power (i.e.,

designate an alternative beckup power source, not necesscrii) the vital [ Class IE) bus, that can be er.crgi:ed in sufficient tiir.e tc ueet the three-hour sampling and anclysis time limit); (2) verify that valves which are not accessible after an accident are enviru.-

thentally qualified for the conditions in which they must operate; (3) demonstrate applicchility of procedures and instrutaentation in the post-accident water chemistry and radiation cnvironment, and retraining of operators on semi-annual basis.

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s 6-(14) Operating Staff Experience Requirements (Section 13.1.2.1, SSER #2)

At all times the plant is in an operating condition other than cold shutdown or refueling, GSU shall have a licensed senior operator on each shift who has had at least six months of hot operating experience on a same type plant, including at least six weeks at power levels greater than 20% of full power, and who has had startup and shutdown experience. For those shifts where such an individual is not available on the plant staff, an advisor shall be provided who has had at least four years of power plant experience, including two years of nuclear plant experience, and who has had at least one year of experience on shift as a licensed senior operator at a similar type facility.

• Advisors, as a minimum, shall be trained on plant procedures, technical specifications and plant systems, and shall be examined on these topics at a level sufficient to assure familiarity with

. the plant. For each shift, the remainder of the shift crew sha'l be knowledgeable of the role of the advisors. The training of the advisors and remainder of the shift crew shall be completed prior to achieving criticality. Prior to achieving criticality, the licensee shall certify to the NRC the names of the advisors who have been examined and have been determined to be competent to provide advice to the operating shifts. These advisors or Cy! suitably qualified replacements shall be retained until at least one of the senior operators on each shift has the required experience.

The NRC shall be notified at least 30 days prior to the release of 3

any special assigned advisors.

(15) Post- Fuel- Loading Initial Test Program (Section 14, SER)

Any changes to the Initial Test Program described in Section 14 of the'FSAR 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.

(16) Partial Feedwater Heatino (Section 15.1, SER)

The facility shall not be operated with partial feedwater heating for the purpose of extending the normal fuel cycTe.

(17) Salem ATWS Event, Generic Letter 83-28 GSU shall submit responses and implement the requirements of Generic Letter 83-28 on a schedule which is consistent with that given in its letters dated - -- .

(18) Emergency Response Capabilities (Generic Letter 82-33, Supplement I to NUREG-0737)

GSU shall complete the requirements of NUREG-0737 Supplement #1 as specified in Attachment 2.

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(19) Emergency Planning In the event the NRC finds that the lack of progress in comple-tion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantial problem exists in achieving or. maintaining an

' adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.

D. The facility requires exemptions from certain requirements *of Appendices and to 10 CFR Part 50. Theseinclude(a) exemption from General Design Criteria (GDC) of Appendix A, l 1

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These e.xemptions are' authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest. Therefore these exemptions are hereby granted pursuant to 10 CFR 50.12. 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.

E. The licensee shall fully implement and ceintain in effect all provisions of the Conmission-approved physical security, guard training and qualification, and safeguards contingency plans, including all amendnents and revisions made pursuant to.the authority of 10 CFR 50.90 and 10 CFR 50.54(p), which are part of the licenso. These plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: " River Bend Station Physical Security Plan," " River Bend Station Security Training and Qualification Plan" rnd " River Bend Station Safeguards Contingency Plan."

Except as otherwise provided in the Technical Specifications or F.

Environmental Protection Plan, the licensee shall report any violations of the requirements contained in Section 2.C of this license in the following manner: initic.1 notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Energency Notification System with written followup within thirty days in accordar.cc with the procedures described in 10 CFR 50.73(b), (c), and (e).

G. The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accord-ance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

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ATTACHMENT 1 To-NPF 40 DEFERRED ITEMS This attachment identifies items which must be completed to the satisfaction of the staff in accordance with the operational modes as identified below.

1. OUTSTANDING ITEMS TO BE ACCOMPLISHED PRIOR TO COMPLETION OF THE POWER ASCENSION PROGRAM

2. OUTSTANDING ITEMS TO BE CORRECTED BY THE FIRST REFUELING OUTAGE' l'

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(Note - This attachment will be developed in concert with Region IV)

ATTACHMENT 2

, EMERGENCY RESPONSE CAPABILITIES GSU shall complete the following requirements of NUREG-0737 Supplement #1 on the schedule noted below:

1)- Prior to July 30, 1985 provide responses to the staff request for information dated August 30, 1984 and the audit agenda dated October 5, 1984 for the safety parameter display system (SPDS).

2) By February 28, 1986 the SPDS should be operational.

3) Prior to issuance of an SER by the staff the SPDS should not be considered operational.

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2% ***** / GULF STATES UTILITIES COMPANY AND CAJUh ELECTRIC POWER COOPERATIVE DOCKE1 NO 50-458 RIVER BEND STATION, UNIT 1 FACILITY OPERATING LICENSE License No. NPF-40

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

A. The application for license filed by the Gulf States Utilities Company, acting on behalf of itself and the Cajun Electric Power Cooperative. (the licensees) complies with the standards and require-

. ments of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 River Bend Station, Unit 1 (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-106 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 i

amended, the orovisions of the Act, and the regulations of the Comision (except as exempted from compliance in Section 2.0. 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 Comission's regulations set forth in 10 CFR Chapter 1 (except as exempted from compliance in Section 2.D.

below);

E. The Gulf States Utilities Company

• is technically qualified to engage in the activities authorized by this license in accordance with the Comission's regulations set forth in 10 CFR Chapter 1; F. The Gulf States Utilities Company and Cajun Electric, Power Corporative have satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements", of the Comission's regulations; G. The issuance of this license will not be inimical to the comon defense and security or to the health and safety of the public; Gulf States Utilities Company is authorized to act as agent for Cajun Electric Power Cooporative and has exclusive responsibility and contiol over the physical construction, oper'ation and maintenance of the facility.

4 2-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-40, 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 Comission's regulations and all applicable requirements. have been satisfied; and I. The receipt, possession, and use of source, byproduct and s"pecial nuclear material as authorized by this license will be in accordance with the Comission's regulations in 10 CFR Parts 30, 40 and 70.

2. Based on the foregoing findings Facility Operating License NPF-40 is

• hereby issued to the Gulf States Utilities Company and the Cajun Electric

, Power Cooperative Company (the licensees), to read as follows:

A. This license applies to the River Bend Station, Unit 1, a boiling water nuclear reactor and associated equipment, owned by Gulf States Utilities Company and the Cajun Electric Power Cooperative.

The facility is located approximately 2 miles east of the Mississippi River in West Feliciona Parrish, Louisiana, approximately 2.7 miles

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southeast of St. Francisville, Louisiana and approximately 18 miles northwest of the city limits of Baton Rouge, Louisiana, and is described in the licensees' " Final Safety Analysis Report," as supplemented and amended, and in the licensees' Environmental Report-Operating License Sta@e, as supplemented and amended.

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

(1) The Gulf States Utilities Company (GSU) and the Cajun Electric Power Cooperative to possess the facility at the designated location

,in West Feliciana Parrish, Louisiana, in accordance with the procedures and limitations set forth in this license; (2) GSU, pursuant to Section 103 of the Act and 10 CFR Part 50, to pos-sess, use, and operate the facility at the above, designated location  ;

in accordance with the procedures and limitations set forth in this

- license; (3) GSU, pursuant to the Act and 10 CFR Part 70, to receive, possess and to ust 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 1 Report, as supplemented and amended;

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3-(4) GSU, 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 monitor-ing equipment calibration, and as fission detectors in amounts as required; (5) GSU, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical fonn, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and v (6) GSU, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuc' lear materials as may be produced by the operation of the facility. .

C. This license shall be deemed to contain and is subject to the condi-tions specified in the Conynission's regulations set forth in 10 CFR Chapter 1 (except as exempted from compliance in Section 2.D. below) and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Consnission now or hereafter in W.

( effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level 3 GSU is authorized to operate the facility at reactor core power levels not in excess of 2894 megawatts thennal (100% rated power) in accordance with the conditions specified herein. Pending Consnission approval this license is restricted to power levels not to exceed five percent of rated power (144.7 megawatts thermal).

(2) Deferred items

.The items identified in Attachment I to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license. ,,

(3) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the En-vironmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.

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

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(4) Oil and Gas Exploration (Section 2.2.2, SER and SSER- )*

GSU shall promptly notify the NRC staff in writing of any new oil or gas wells or pipelines planned for locations within a 2 mile radius of the unit reactor centerline. Prompt notificatior-shall be deemed to be within 30 days of becoming aware of such plans. The potential safety impact of such wells or pipeline shall be addressed in this notification.

(5) Turbine System Maintenance Program (Section 3.5.1 and' 3.3, SER)

GSU shall submit a turbine system maintenance program by

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October 26, 1987. Prior to review and approval of that program by the NRC staff, GSU shall volumetrically inspect all low pressure turbine rotors at the second refueling outage and every other (alternate) refueling outage thereafter.

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(6) Inservice Testing of Pumps and Valves ~

(Section 3.9.6, SER and SSER- )

Pursuant to 10 CFR Part 50.55a the relief identified in the Pump and Valve Inservice Testing Program Plan for the River Bend Station Unit 1, Revision dated that GSU has j(( requested from the pump and valve testing re Part 50, Section 50.55a (g)(2) and (g)(4)(i)quirements is grantedoffor 10that CFR portion of the initial 120-month period during which the staff completes its review.

(7) Equipment Qualification (Section 3.11. SER) i All electrical equipment within the scope of 10 CFR 50.49 must be environmentally qualified by November 30, 1985.

(8) knservice Ins >ection Program (Section 5.2.4.3

.and 6.6.3, SER and 55ER-3) i The licensee shall submit the inservice inspection program for l NRC staff review and approval by one year from date of this license.

i (9) Steam Bypass of the Suppression Pool (Section 6.2.1.7, SER)

The operating procedures shall contain provisions for instructing the operator to actuate the ADS whenever the containment to annulus differential pressure reaches 5 psi.

(10) Hydrogen Control (Section 6.2.5, 5ER and 55ER-2)

(To be provided)

• 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.

(11) ICSB Issues (Sections 7 )

(To be provideo) -

(12) Fire Protection (Section 9.5, SER, SSER-2) a '. The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility (or as described in submittals dated )

and as approved in the SER dated (and Supplements dated ) subject to provisions 2 and 3 below.

b. The licensee may make no change to the approved fire protection program which would significantly decrease the level of fire protection in the plant without prior approval of the Comission. To make such a change the licensee must submit an application for license amendment pursuant to 10 CFR 50.90.

c. The licensee may make changes to features of the approved fire protection program which do not significantly decrease the level of fire protection without prior Comission approval provided (a) such changes do not otherwise involve a change in a license condition or technical specification or result in an unreviewed safety question (see 10 CFR 50.59), and (b) such changes do not result in failure to complete the fire protection program approved by the Comission prior to license issuance. The licensee shall maintain, in an auditable form, a current record of all such changes, incluaing an analysis of the effects of the change on the fire protection program, and shall make such records available to NRC inspec-tors upon request. All changes to the approved program shall be reported annually to the Director of the Office of Nuclear Reactor Regulation, along with the FSAR revisions required by 10 CFR 50.71(e).

(13) Post Accident Samplina (Section 10.4.6/THI Iten ll.B.3, SER)

Prior to a cceding five percent rated power cperation, Gulf States Utilities shall have instclied and operational the post-accicer.t sampling system.

Prior to five percent rated power operation, GSU shall: (1) .

describe provisions for sampling during loss of offsite power (i.e.,

designate an alternative backup power source, not necesscrii) the vital [ Class IE] bus, that can be er.crgized in sufficient time tc meet the three-hour sampling and antlysis time limit); (2) verify that valves which are not accessible after an accident are envirci.-

mentally qualified for the conditiuns in which they must operate; (3) demonstrate applicchility of procedures and instrutaer.tation in the post-accident water chemistry and radiation cnvironment, and retraining of operators on semi-annual basis.

-E. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard trdining and qualification, and safeguards contingency plans, including all amendments and revisions made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p), which are part of the license. These plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: " River Bend Station Physical Security Plan," " River Bend Station Security Training and Qualification Plan" and " River Bend Station Safeguards Contingency Plan."

F. Except as otherwise provided in the Technical Specifications or

' Environmental Protection Plan, the licensee shall report any violatier.s of the requirements contained in Section 2.C of this license in the following manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the flRC Operations Center via the Energency Notification System with written follcuup within thirty days in accordancc with the procedures described in 10 CFR 50.73(b), (c), and (e).

G. The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accord-ance with Section 170 of the Atomic Energy Act of 1954, as amended, to-cover public liability claims.

l ATTACHMENT 1 j To-NPF 40 DEFERRED ITEMS This attachment identifies items which must be completed to the satisfaction of the staff in accordance with the operational modes as identified below.

1. OUTSTANDING ITEMS TO BE ACCOMPLISHED PRIOR TO COMPLETION OF THE POWER ASCENSION PROGRAM

2. OUTSTANDING ITEMS TO BE CORRECTED BY THE FIRST REFUELING OUTAGE'

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(Note - This attachment will be developed in concert with Region IV)

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-ATTACHMENT 2 EMERGENCY EE5PONSE CAPABILITIES GSU shall complete the following requirements of NUREG-0737 Supplement #1 on the schedule noted below: ,

1) Prior to July 30, 1985 provide responses to the staff request for information dated August 30, 1984 and the audit agenda dated October 5, 1984 for the safety parameter display system (SPDS).

2) By February 28, 1986 the SPDS should be operational.

3) Prior to issuance of an SER by the staff the SFDS should not be considered operational.

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. Docket.No.' 50-458~

.Mr. William J.. Cahill, Jr.

. Senior. Vice' President River Bend Nuclear Group Gulf States. Utilities Company-Post Office Box 2951

. Beaumont, Texas 77704' ATTN: Mr. J. E. Booker

SUBJECT:

-RIVER BEND STATION, UNIT 1 DRAFT LICENSE Enclosed is a' draft copy of the operating license for River Bend Station Unit 1.

It-is provided for your infomation and coment to ensure that it accurately reflects and connitments required of you as described in the FSAR, SER and

other documentation.- ~llowever, since the staff is still reviewing numerous outstanding SER issues, the conditions on this license are not definite at this time.. - ,

' We request that you examine the draft license and provide any coments in writing within_ five days of the date of this letter.

Sh'ould.you.have questions regarding this draft license, please contact the.

River. Bend Project Manager Stephen M. Stern at (301) 492-8349.

Sincerely, Thomas M. Novak, Assistant Director

• for Licensing Division of Licensing

Enclosure:

As stated

'cc: ~See next page

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