ML20137S669

Forwards Draft Full Power License NPF-40 for Review & Comment.Status Rept on Commitments Made in Low Power OL Requested.Weekly Repts Should Be Forwarded Beginning on 850927

ML20137S669
Person / Time
Site:	River Bend
Issue date:	09/25/1985
From:	Butler W Office of Nuclear Reactor Regulation
To:	William Cahill GULF STATES UTILITIES CO.
References
NUDOCS 8509300469
Download: ML20137S669 (18)

Text

1 UNITED STATES r

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. . . NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555 z

SEP 2 51985 Docket No.: 50-458 Mr. William J. Cahill, Jr.

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

SUBJECT:

REQUEST FOR INF0PMATION AND COMMENTS RE: FULL PCWER OPERATING LICENSE FOR RIVER BEND STATION On August 29, 1985, the U. S. huclear Regulatory Commission (NRC) issued a low power Facility Operating License (NPF-40) together with Technical Specifi-cations and Environmental Protection Plan for the River Bend Station, Unit 1.

License No. NPF-40 authorizes operation of River ~ Bend, Unit 1 at reactor power levels not in excess of 2894 megawatts thermal (100% rated power). However, pending Connission approval, operation is restricted to power levels not to exceed five percent of rated power (144.7 megawatts thermal).

Enclosed for your review cormient is a draf t of the full power operating license for River Bend Station, Unit 1. Please review this draft license and provide your written ccmments 14 days in advance of ycur anticipated need for this license. ,

For the NRC to issue a full power license, GSU must satisfy all conditions of the icw power license'which specify resolution prior to exceeding 5% ratec power as well as those cormiitments mace by GSU which are to be acccmplishec prior to exceeding 5% rated power. In order to effectively schedule the staff's review efforts to suppcrt your licensing schedule, we need to have status reports relative to your progress en these license conditions and other ccccitments.

Accordir. gly, we request that you forward a weekly report connencing on September 27, 1985, identifying tbcse license conditions and other commitments that have been completed during the previcus week and cumulatively sirice issuance of the icw power license.

8509300469 850925 PDR ADOCK 05000458 P PDR

.. Please send copies of the progress report to Stephen M. Stern, the staff's Project Manager for the River Bend Application, as well as the NRC's Region IV office and the NRC's Resident Inspector at River Bend.

Please contact Mr. Stern for any clarification of this request.

Sincerely, Walter R. Butler, Chief Licensing Branch No. 2 Division of Licensing

Enclosure:

As stated cc: w/ enclosure See next page

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J Mr. William O'. Cahill, Jr.

Gulf States Utilities Company River Bend Nuclear Plant cc:

Troy B. Conner, Jr. , Esq. Ms. Linda B. Watkins/Mr. Steven Irving Conner and Wetterhahn Attorney at Law 1747 Pennsylvania Avenue, NW 355 Napoleon Street Washington, D.C. 20006 Baton Rouge, Louisiana 70802 Mr. William J. Reed, Jr. Mr. David Zaloudek Director - Nuclear Licensing Nuclear Energy Division Gulf States Utilities Company Louisiana Department of P. O. Box 2951 Environmental Quality i Beaumont, Texas 77704 P. O. Box 14690 Baton Rouge, Louisiana 70898 Richard M. Troy, Jr. , Esq.

Assistant Attorney General in Charge Mr. J. David McNeill, III State of Louisiana Department of Justice William G. Davis, Esq.

234 Loyola Avenue Department of Justice New Orleans, Louisiana 70112 Attorney General's Office 7434 Perkins Road Resident' Inspector Baton Rouge, Louisiana 70808 ,

P. O. Box 1051 St. Francisville, Louisiana 70775 H. Anne Plettinger 3456 Villa Rose Crive Gretchen R. Rothschild Baton Rouge, Louisiana 70806 Louisianians for Safe Energy, Inc.

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

r P. O. Box 23571 -

Baton Rcuge, Lcuisiana 70893 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director

for Operations 611 Ryan Pia

a Drive, Suite 1000 ~'

Arlingten, Texas 76011 i

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GULF STATES UTILITIES COMPANY AND CAJUN ELECTRIC POWER COOPERATIV F g DOCKET NO 50-458

RIVER BEND STATION, UNIT 1 FACILITY OPERATING LICENSE l

License No. NPF-40

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

A. The application for license filed by Gulf States Util! ties Company, i acting on behalf of itself and Cajun Electric Power Cooperative, i complies with the standards and requirements of the Atomic Energy Act

- of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made;

8. Construction of the River Bend Station, Unit 1 (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-145 and the application, as amended, the provisions of the Act and the regulations of the Comission; C. The facility will operate .in confamity with the application. as amended, the provisions of the Act, and the regulations of tne Comission; D. There is reasonable assurance: (i) that the activities authorized by this opera, ting 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 I; E. Gulf States Utilities Company

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

, Protection Requirements and Indennity Agreements," of the Comission's regulations; G. The issuance of this license will not be inimical to the corron 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 control over the physical construction, operation and maintenance of the facility.

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 Facility Operating License No. NPF-40, subject to the conditions for protection of the environment set forth herein, is in accoroence 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 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 Gulf States Utilities Company and Cajun Electric Power Cooperative (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 Cajun Electric Power Cooperative. The facility is located approximately 2 miles east of the Mississippi River in t!est Feliciane Parish, Louisiana, approximately 2.7 miles 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 Rep ~ ort-Operating License Stage, e

as supplemented and amended.

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

(1) Gulf States Utilities Company (GSU) arid Cajun Electric Power Cooperative to possess the facility at the designated location in West Feliciana Parish, Louisiana, in accorunce with the procedures and limitations set forth in this 11 anse; (2) GSU, pursuant to Section 103 of the Act and 10 CFR Part 50, to use and operate the facility at the above designated location in accordance with the procedures and limitations sr.t forth in this license; (3)' GSU, pursuant to the Act and 10 CFR Part 70, to receive, possess and to use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and ancunts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; l

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4 (4) GSU, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time ar.y byproduct, source and special nuclear material as sealed neutrcn scurces 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 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) GSU, 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.

C. This license shall be deemed to contain and is subject to the condi-

! tions specified in the Commission's regulations set forth in 10 CFR L Chapter I and is subject to all applicable provisions of the Act end J to the rules, regulations and orders of the Commission now or here-after in effect; and is subject to the additional conditions specified or incorporated below:

) (1) Maximum Power level i

4 GSU is authorized to operate the facility at reactor core power j levels not in excess of 2894 megawatts thermal (100% rated l power) in accordance with the conditions specified herein.

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

l (2) Technical Specifications and Cnvironmental 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 cperate the facility in accordance with the Technical Specificaticns and the Environmental Protection Plan.

4 (3) Antitrust Conditions i GSU shall comply with the antitrust conditicns in Appendix C

! attached hereto, which is hereby incorporated into this license.

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

GSU shall submit a turbine system maintenance program by

-November 1, 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.

(5) Seismic and Dynamic Qualification of Seismic Category 1 Mechanical and Electrical Equipment (Section 3.10, SER and SSER 3)

GSU shall complete the requirements of the seismic and dynamic qualification of mechanical and electrical equipment as specified in Attachment 2. Attachment 2 is hereby incorporated into this license.

(6) Eculpment Qualification (Section 3.11, SER and SSER 3)

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

(7) Mark III Related Issues (Section 6.2.1.9, SER and SSER 2)

a. GSU shall not use the residual-heat removal system in the steam condensing mode.

b. Prior to startup following the first refueling outage, GSU.

shall furnish the outstanding information identified in Appendix K of SSER 2 addressing the Mark III. containment related issues.

(8) Inservice Ins)ection Program (Section 5.2.4.3 and 6.6.3, SER and SSER 3)

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

(9) Bypassed and Inoperable Status Indication (Section 7.5.2.2, SER and SSER 3)

Prior to startup following the first refueling outage, GSU shall implement design modifications to improve the capabilities of existing bypassed and incperable status indication used to r:cnitor the status of safety related systems. The specific design changes to be implemented are identified in a GSU letter cated December 3, 1984 as clarified in a GSU letter dated March 5,1985.

• 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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(10) TDI Diesel Engines (Section 8.3.1 SSER 3)

GSU shall complete the TDI diesel requirements as specified in

- Attachment 3. Attachment 3 is hereby incorporated into this license.

(11) Ultimate Heat Sink (Section 9.2.5, SER and SSER 3)

Prior to startup following the first refueling outage GSU shall have installed and operational in the ultimate heat sink a permanent temperature monitoring system acceptable to the NRC staff and Technical Specification modifications as required.

(12) Fire Protection (Section 9.5.1, SER and SSER 3)

GSU shall comply with the requirements of the fire protection program as specified in Attachment 4. Attachment 4 is hereby incorporated into'this license.

(13) Operating Staff Experience Requirements (Section 13.1.2.1, SSER 2)

GSU shall have a licensed senior operator on each shift who has had at least six months of hot operating experience on a plant comparable to River Bend Station, including at least six weeks at power levels greater than 207, 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 operato' at a comparable facility or its equiva-lent as approved by the staff. Use of advisors who were licensed only at the R0 level will be evaluated on a case by case basis.

Advisors shall be trained on plant procedures, Technical Speci-fications 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 shall be trained as to the role of the advisors.

(14) Post-Fuel-Loadir.g Initial Test Program (Section 14, SER and SSER 3)

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.

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i (15) Partial Feedwater Heating (Section 15.1, SER)

The facility shall not be operated with partial feedwater heating

! for the purpose of extending the normal fuel cycle.

(16) Emergency Response Capabilities (Generic Letter 82-33, Supplement 1 to NUREG-0737, Section 7.5.2.4, SER and SSER 3, Section 18, SER, SSER 2 and 55ER 3) ,

GSU shall complete the requirements of NUREG-0737 Supplement #1 as specified in Attachment.5. Attachment 5 is hereby incorporated into this license.

(17) Salem ATWS Event, Generic Letter 83-28 G5U shall submit responses to and implement the requirements of Generic Letter 83-28 on a schedule which is consistent with that given in its letters dated August 3, 1984 and May 20, 1985.

(18) Emergency Planning (Section 13.3, SER, SSER 2 and SSER 3)

In the event the NRC staff finds that the lack of progress in j completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive 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. GSU shall fully implement and maintain in effect all provisions of the

Comission-approved physical security, guard training and qualification, i 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 licens&. These plans, which contain safeguards infor-mation 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."

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1 E. Except as otherwise provided in the Technical Specifications or i

Environmental Protection Plan, GSU 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 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 Emergency Notification System with written followup within thirty days in accordance with the

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

f' F. Tbc licensees 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.

G. This license is effective as of the date of issuance and shall expire at midnight on August 29, 2025 FOR THE NUCLEAR REGULATORY COMMISSION i

Harold R. Denton, Director Office of Nuclear Reactor Regulation

Enclosures:

1. Attachments 1-5

2. Appendix A - Technical Specifications (NUREG-1142)

3. Appendix B - Environmental Protection Plan

4. Appendix C - Antitrust. Conditions i

. Date of Issuance: -

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i E. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, GSU 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 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 Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).

F. The licensees 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.

G. This license is effective as of the date of issuance and shall expire at midnight on August 29, 2025 FOR THE NUCLEAR REGULATORY COMMISSION

. Harold R. Denton Office of Nuclear. Reactor Regulation

Enclosures:

1. Attachments 1-5 .

2. AppendixA-TechnicalSpecifications(NUREG-1142)

3. Appendix B - Environmental Protection Plan 4 Appendix C - Antitrust Conditions Date of Issuance:

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l ATTACHMENT 1 To-NPF 40 Prior to achieving the condition indicated on or before the date indi-cated, the following items shall be completed to the satisfaction of Region IV:

1. OUTSTANDING ITEMS TO BE ACCOMPLISHED PRIOR TO COMPLETION OF THE INITIAL TEST PROGRAM .

a. Verify the station electric distribution voltage analyses are in

.accordance with the guidelines of Branch Technical Position PSB-1, Position 4.

b. Perfonn an engineering evaluation and complete modifications on the battery powered lighting system used in areas of the plant outside the main control room required for safe shutdown and personnel evacuation to upgrade those areas identified as deficient with regard to the requirements contained in FSAR Table 9.5-2

2. OUTSTANDING ITEM TO BE COMPLETED PRIOR TO THE FIRST REFUELING OUTAGE

a. Complete and have operational the fuel building sampling system.

Off-loading of. irradiated fuel prior to the first refueling outage shall be performed as described in GSU's letter dated June 13, 1985.

3. OUTSTANDING ITEMS TO BE COMPLETED PRIOR TO FIRST DESIGN USE OR PRIOR TO STARTUP FOLLOWING THE FIRST REFUELING OUTAGE (WHICHEVER IS.FIRST)

a. Complete a load test which meets all the OSHA requirements for load handling capability on all remaining cranes and hoists not previously tested.

b. Install and have operational the chlorination systems for the nonnal and standby service water systems for Asiatic clam control prior to first introduction of Mississippi River water into these i systems.

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4. OUTSTANDING ITEMS TO BE ACCOMPLISHED PRIOR TO STARTUP FOLLOWING THE FIRST REFUELING OUTAGE

a. Rework fuse block connectors as delineated in the 10 CFR 50.55(e)

report identified as OR-287.

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b. Repair or replace the control valves on HVAC chillers as delineated i

in the 10 CFR 50.55(e) report identified as DR-314.

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! c. Verify that adequate radio coninunication capability exists from all l

appropriate plant areas.

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ATTACHMENT 2 To-NPF 40 SEISMIC DYNAMIC QUALIFICATION OF SEISMIC CATEGORY 1 MECHANICAL AND ELECTRICAL EQUIPMENT GSU shall complete the following requirements for seismic and dynamic quali-fication on the schedule noted below:

1. GSU shall, prior to startup following the second refueling outage, have completed modifications to the hydraulic control units.to install an additional brace as used in the qualification testing of the hydraulic control unit as described in GSU's letter dated i May 15, 1985.

2. GSU 'shall complete the seismic qualification of the in-vessel rack prior to its use.

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ATTACHMENT 3 To-NPF 40 TDI DIESEL ENGINES REQUIREMENTS GSU shall comply with the following requirements related to the TDI diesel engines.

1. Changes to the maintenance and surveillance program for the TDI diesel' engines, as identified and approved by the NRC staff in '

Supplement 3 to the SER, shall be subject to the provisions of 10 CFR 50.59,

2. Crankshafts shall be inspected as follows:

SD 18: During the first refueling outage, inspect the fillets and oil holes 07 the three most heavily loaded crankpin journals (Nos. 5, 6, and 7) with fluo.rescent liquid penetrant and ET as appropriate.

SD 1A and 18: During the second and subsequent re- .

fueling outages, inspect the fillets and oil holes of two of the three most heavily loaded crankpin journals in the manner,just mentioned.

SD 1A and 18: _ During each major engine overhaul, inspect the fillets and oil holes of the two main bearing journals between crankpin Nos. 5, 6, and 7, using fluorescent liquid penetrant and ET as appropriate. This inspection is in addition to the crankpin inspections.

3. Cylinder blocks shall be inspected at intervals calculated using the cumulative damage index (CDI) model and using inspection methodologies described by Failure Analysis Associates, Inc. in Design Review of TDI'R-4 and RV-4 Series Emergency Diesel Generator Cylinder Blocks (FaAA-84-9-11-1). Liquid penetrant inspection of cylinder liner landing area shall be perfonned any time _ cylinder liners are removed. Visual daily inspection between adjacent cylinder heads and the general block top during any period of continuous operation following automatic diesel generator startup.

4. GSU shall roll the engines over with the air start system prior to any planned starts, unless that planned start occurs within 'four hours of a shutdown. In addition, after engine operation, the engines shall be rolled over on air after four hours but not more than eight hours after engine shutdown and then rolled over once again approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each shutdown. In the event an engine is removed from service for any reason other than the rolling over procedure prior to expiration of the eight hour or 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> periods noted above, that engine need not be rolled over while it is out of service. Once the engine is returned to service, GSU shall roll it over with air once at the time that it is returned to service.

Any head which leaks due to a crack shall be replaced.

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5. ' If inspection of diesel generators IA and/or IB should reveal cracks in the crankshaft or in the cylinder block between stud holes of adjacent cylinders, this condition shall be reported promptly to the NRC staff and the affected engine (s) shall be con-sidered inoperable. The engine (s) shall not be restored to

" operable" status until the proposed disposition and/or corrective actions have been approved by the NRC staff.

6. The following action { re required if SD 1A or SD 1B is operated in excess of 3130 KW  :

a) For indicated engine loads in the range g)3130 KW to 3200 KW for a period less than two hours , no additional action shall be required.

b) For indicated engine loads in the range of 3{jg KW to 3200 KW i- for a period equal to or exceeding two hours , a crank-shaft inspection pursuant to Item d below shall be perfomed at the next refueling outage.

c) For indicated engine leads in(ge range of 3200 KW to 3500 KW for a period less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> , a crankshaft inspection pursuant to item d below shall be performed for the affected engine at the next refueling outage.

d) For indicated engine loads in the range of(jj00 KW to 3500 KW for periods equal to or exceeding one hour , and for engine loads exceeding 3500 KW for any period of time, (1) the engine shall be removed from service as soon as safely possible, (2) the engine shall be declared inoperable, and (3) the crankshaft shall be inspected. The crankshaft ins 7 (pection the mostshall include heavily crankpin loaded) journal and the numbers two main 5, 6,inand journals between using fluorescent liquid penetrant and eddy current as appropriate.

7. Operation beyond the first refueling outage is subject to NRC staff approval based on the staff's final review of the

.0wners Group generic findings and of the overall design review and quality revalidation program at River Bend.

(1) Momentary transients (not exceecing 5 seconds) due to changing cf bus loads need not be considered as an overload.

(2) If there are multiple overload events within a given load range since the previous crankshaf t inspection, then the time period criterion applies to the total accumulated time in that load range.

ATTACHMENT 4 To-NPF 40

. FIRE PROTECTION PROGRAM REQUIREMENTS GSU shall comply with the following requirements of the fire protection program

1. GSU shall implement and naintain in effect all provisions of the approved fire protection program as described in the Final Safety i Analysis Report for the facility through Amendment 21 and as approved in the SER dated May 1984 and Supplement 3 dated August 1985 subject to provisions 2 and 3 below.

2. GSU may make no change to the approved fire protection program which i

- would significantly decrease the level of fire protection in the .

plant without prior approval of the Commission. To make such a change GSU must submit an application for license amendment pursuant to 10 CFR 50.90.

3. GSU may make changes to features of the approved fire protection ,

program which do not significantly decrease the level of fire protection without prior Commission 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 Conmission prior to license issuance. GSU 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 inspectors upc4 request. All changes to the ,

approved program shall be reported to the Director of the Office  ;

of Nuclear Reactor Regulation, along with the FSAR revisions required by 10 CFR 50.71(e).

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l ATTACHMENT 5 l To-NPF 40 i EMERGENCY RESPONSE CAPABILITIES i

l GSU shall complete the following requirements of NUREG-0737 Supplement #1 on the schedule noted below:

1. The Safety Parameter Display System shall be installed and opera-

! tional prior to March 1, 1986.

2. Actions and schedules for correcting all human engineering

discrepancies (HEDs) identified in the " Detailed Control Room Design Review Sumary Report dated October 31, 1984 and Supplements

dated May 14, June 12, 1985, and July 31, 1985, shall be implemented in accordance with the schedule comitted to by GSU in the sumary report and supplements and accepted by the NRC staff in SER j Section 18.1.

3. Prior to startup following the first refueling outage, GSU shall implement modifications (installation or upgrade) for those items listed below consistent with the guidance of Regulatory Guide 1.97, f

Revision 2 unless prior approval of an alternate design of these items is granted by the NRC staff. These items as listed in GSU's j letter of June 24, 1985 are:

a)neutronflux; b) coolant level in the reactor; I c) suppression pool water level; d) drywell atmosphere temperature; ]

e primary system safety relief valve position; f standby liquid control system storage tank level; g emergency' ventilation damper position; and h airborne radiohalogens and particulates.

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Please send copies of the progress report to Stephen M. Stern, the staff's .

Project Manager ~for the River Bend Application, as well as the NRC's Region IV [

! and the NRC's Resident Inspector at. River Bend.

Please contact itr. Stern for any clarification of this request.

Sincerely, 4

i l Ortsteal s!emed byt' ,

Walter R. Butler, Chief Licensing Branch No. 2 Division of Licensing

Enclosure:

As stated 1

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