ML20059A749

Amend 70 to License NPF-47 Revising Plant License to Include Entergy Operations as Licensee

ML20059A749
Person / Time
Site:	River Bend
Issue date:	12/16/1993
From:	Black S, Harold Denton Office of Nuclear Reactor Regulation
To:
Shared Package
ML20059A753	List: ML20059A749 ML20059A762
References
NUDOCS 9401030111
Download: ML20059A749 (20)

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UNITED STATES j

NUCLEAR REGULATORY COMMISSION

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'f WASHINGTON. D.C. 205564001 8

i hj %s.....f GULF STATES UTILITIES COMPANY **

CAJUN ELECTRIC POWER COOPERATIVE DOCKET NO. 50-458 P

RIVER BEND. STATION. UNIT _1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 70 License No. NPF-47 1.

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

A.

The application for amendment by Gulf States Utilities

• dated January 13, 1993, as supplemented by letter dated June 29, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10.CFR Chapter I; B.

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

There is reasonable assurance:

(1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; i

D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, Facility Operating License No. NPF-47 is hereby amended to read as follows:

i

• Gulf States Utilities Company under the present license is authorized to act as agent for Cajun Electric Power Cooperative and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

• • Gulf States Utilities Company, which owns a 70 percent undivided interest in River Bend, has merged with a wholly owned subsidiary of Entergy Corporation.

Gulf States Utilities Company was the surviving company in the merger.

9401030111 931216 PDR ADOCK 05000458 p

PDR 4

.. (a) The Title on page 1 of the license shall read:

Gulf States Utilities Company.

Riun Electric Power Cooperative and Enterov Operations. Inc.

Docket No. 50-458 River Bend Station. Unit 1 Facility Doeratino License (b)

Paragraph 1.E of the license shall read:

t Entergy Operations Inc. (E01) is technically qualified to engage in the activities authorized by this operating license in accordance with the Commission's regulations set forth in 10 CFR Chapter I:

(c)

Footnote

• on page 1 of the license shall read:

• E01 is authorized to act as agent for Gulf States Utilities Company, which has been authorized to act as agent for Cajun Electric Power Cooperative, and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

(d)

Paragraph 1.F of the license shall read:

Gulf States Utilities Company, Cajun Electric Power Cooperative, and E01 have satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; (e)

Paragraph 2 of the license shall read:

Based on the _ foregoing findings and approval by the Nuclear Regulatory Commission at a meeting on November 15, 1985, the License for fuel Loading and Low Power Testing, License No.

NPF-40, issued on August 29, 1985, is superseded by Facility Operating' License NPF-47 hereby issued to E01, Gulf States Utilities Company and Cajun Electric Power Cooperative (the licensees), to read as follows:

(f)

Paragraph 2.A of the license shall read:

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 and operated by E01. The facility is located approximately 2 miles east of the Mississippi River in West Feliciana Parish, Louisiana, approximately 2.7 miles southeast of St. Francisville, Louisiana and approximately IB miles northwest of the city limits of Baton Rouge, Louisiana, and is i

.- described in the " Final Safety Analysis Report," as supplemented and amended, and in the Environmental Report-Operating License Stage, as supplemented and amended.

1 (g) Paragraph 2.B.(2) of the license shall read:

EDI, pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the above designated location in accordance with the procedures and limitations set forth in this license; i

(h)

Paragraphs 2.B.(3), 2.B.(4), 2.B.(5), 2.B.(6), 2.C.(1), and 2.C.(2) shall each be modified by substituting "EDI" for "GSU" i

wherever the latter appears.

(i) Paragraph 2.C.(3) of the license shall read:

Antitrust Conditions a.

GSU shall comply with the antitrust license conditions set forth in Appendix C, attached hereto which is hereby incorporated in this license.

b.

E01 shall not market or broker power or energy from River Bend Station, Unit 1.

GSU is responsible and accountable for the actions of its agent, E01, to the extent said agent's actions affect the marketing or brokering of power or energy from River Bend Station, Unit I and, in any way, j

contravene the antitrust conditions of this paragraph or i

Appendix C of this license.

1 (j)

Paragraphs 2.C.(4) and 2.C.(5) shall be modified by substituting "E01" for "GSU" wherever the latter appears.

(k)

Paragraph 2.C.(5)b. of the license shall read:

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.

(1)

Footnote

• on page 4 of the license shall read:

• The original licensee authorized to possess, use and operate the facility was GSU. Consequently, historical references to certain obligations of GSU remain in the license conditions.

(m) Paragraphs 2.C.(8), 2.C.(10), 2.C.(11), 2.C.(14), 2.C.(15),

2.D, and 2.E shall be modified by substituting "E01" for "GSU" wherever the latter appears.

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(n) The last page of the license shall be marked " Revised:

December 16, 1993."

i 3.

This license amendment is effective as of its date issuance, and shall be implemented within 180 days.

FOR THE NUCLEAR REGULATORY COMMISSION l

l b

G7hd Suzann C. Black, Director Project Directorate IV-2 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation l

Attachment:

i Facility Operating License No. NPF-47 i

Date of Issuance: December 16, 1993 i

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i ATTACHMENT TO LICENSE AMENDMENT NO. 70-TO FACILITY OPERATING LICENSE NO. NPF-47 l

DOCKET NO. 50-458 Replace the following pages of the License with the attached pages. The l

revised pages contain vertical lines indicating the areas of change.

Remove Paae Insert Paoe 1

1 2

2 3

3 4

4 5

5 6

6 7

7 8

Replace Attachments 2, 3, 4, and 5 to License No. NPF-47 in their entirety.

Replace cover page of Appendix B - Environmental Protection Plan.

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION yi /fr f

WASHINGTON. D.C. 20556-0001 v(/

GULF STATES UTILITIES COMPANY.**

CAJUN ELECTRIC POWER COOPERATIVE AND ENTERGY OPERATIONS. INC.

j DOCKET NO. 50-458 RIVER BEND STATION. UNIT 1 FACILITY OPERATING LICENSE License No. NPF-47 1.

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

A.

The application for license filed by Gulf States Utilities Company, acting on behalf of itself and Cajun Electric Power Cooperative, 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 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 Commission, C.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; i

D.

There is reasonable assurance:

(1) 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 l

be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; j

E.

Entergy Operations, Inc.* (E01) is technically qualified to engage l

in the activities authorized by this operating license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; i

• E01 is authorized to act as agent for Gulf States Utilities Company, which has been authorized to act as agent for Cajun Electric Power Cooperative, and has exclusive responsibility and control over the physical construction,

)

operation and maintenance of the facility.

• • Gulf States Utilities Company, which owns a.70 percent undivided interest in River Bend, has merged with a wholly owned subsidiary of Entergy Corporation. Gulf States Utilities Company was the surviving company in the merger.

Amendment No. 70 i

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F.

Gulf States Utilities Company, Cajun Electric Power Cooperative, and EDI have satisfied the applicable provisions of 10 CFR Part 140, l' F

" 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 Facility Operating License No. NPF-47, subject to the conditions for protection of the environment set forth herein, 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 November 15, 1985, the License for Fuel Loading and Low Power Testing, License No. NPF-40, issued on August 29, 1985, is l

superseded by Facility Operating License NPF-47 hereby issued to EDI, Gulf l

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 and operated by E01.

The facility is located approximately 2 miles erst of the l

Mississippi River in West Feliciana 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 i

is described in the " Final Safety Analysis Report," as supplemented and amended, and in the Environmental Report-0perating License Stage, l

as supplemented and amended.

i B.

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

(1)

Gulf States Utilities Company (GSU) and Cajun Electric Power Cooperative to possess the facility at the designated location in West Feliciana Parish, Louisiana, in accordance with the procedures and limitations set forth in this license; (2)

E01, pursuant to Section 103 of the Act and 10 CFR Part 50, to l'

possess, use and operate the facility at the'above designated i

location in accordance with the procedures and limitations set forth in this license; 1

Amendment No. 70

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l (3)

E01, pursuant to the Act and 10 CFR Part 70, to receive, l

possess and to 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; 1

(4)

E01, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to l-receive, possess, and use at any time any byproduct, source and i

sp2cial nuclear material as sealed neutron sources for reactor startup, serled sources for reactor instrumentation and radiation ranitoring equipment calibration, and as fission detectors amounts as required; (5)

E01, pursuant to the Act and 10 CFR' Parts 30, 40. and 70, to

-l receive, possess, and use in amounts as required any byproduct, source or special nuclear material without reWiction to chemical or physical form, for sample analysis ',r instrument calibration or associated with radioactive apparatus or components; and (6)

EDI, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to l

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 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 E01 is authorized to operate the facility at reactor core power l

levels not in excess of 2894 megawatts thermal (100% rated power) in accordance with the conditions specified herein.

The items identified in Attachment I to this license shall be i

completed as specified. Attachment I is hereby incorporated into this license.

I (2)

Technical Specifications and Environmental Protection Plan The Technical Specifications containuo in Append;x A, as revised through Amendment No. 70 and the Environmental Protection Plan contained in Appendix B, are hereby i

incorporated in the license.

E01 shall operate the facility in l

accordance with the Technical Specifications and the Environmental Protection Plan.

Amendment No. 70 l

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(3)

Antitrust Conditions a.

GSU shall comply with t!

antitrust conditions in Appendix C, attached hereto, which is hereby incorporated in this license.

i b.

E01 shall not market or broker power or energy from River Bend Station, Unit 1.

GSU is responsible and accountable for the actions of its agent, E01, to the extent said agent's actions affect the marketing or brokering of power or energy from River Bend Station, Unit I and, in any way, contravene the antitrust conditions of this paragraph or Appendix C of this license.

(4)

Seismic and Dynamic Oualification of Seismic Cateaory 1 Mechanical and Electrical Ecuipment (Section 3.10. SER and SSER 3)

E01 shall complete the requirements of the seismic and dynamic l

qualification of mechanical and electrical equipment-as specified in Attachment 2. is hereby incorporated into this license.

(5)

Mark III Related Issues (Section 6.2.1.9. SER and SEER 2) a.

E01 shall not use the residual heat removal system in the j

steam condensing mode without prior written approval of the staff.

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.

(6)

Inservice Inspection Proaram (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 September 1,1986.

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• The original licensee authorized to passess, use and operate the facility was I

GSU.

Consequently, historical references to certain obligations of GSU remain in the license conditions.

Amendment No. 70

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(7) 8voassed and Inoperable Status Indication (Section 7.5.2.2. SER and SSER 31 Prior to startup following the first refueling outage, GSU shall implement design modifications to improve the capabilities of existing bypassed and inoperable status indication used to monitor the status of safety related systems. The specific design changes to be implemented are identified in a GSU letter dated December 3,1984 as clarified i

in a GSU letter dated March 5, 1985.

(8)

TDI Diesel Enaines (Section 8.3.1. SSER 3)

E01 shall implement the TDI diesel requirements as specified in l. is hereby incorporated into this license.

(9)

Ultimate Heat Sink (Section 9.2.5. SER and SSER 3) i 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.

(10)

Fire Protection (Section 9.5.1. SER and SSER 3)

E01 shall comply with the requirements of the fire protection l

program as specified in Attachment 4. is hereby incorporated into this license.

(11) Operatina Staff Experience Reauirements (Section 13.1.2.1. SSER 21 E01 shall have a licensed senior operator on each shift, while-l in Operating Condition 1, 2 and 3, 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 20% of full power, and who has had startup and shutdown experience.

(12) Post-Fuel-Loadina Initial Test Proaram (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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(13)

Partial:Feedwater Heatino (Section 15.1. SER)

The facility shall not be operated with partial' feedwater heating beyond the end of the. normal fuel cycle without-prior

. written approval of the staff. During the normal fuel. cycle.

the facility shall not be operated with a feedwater heating capacity which would result in a rated thermal power feedwater temperature less than 320*F without prior written approval of-the staff.

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(14) Emeroency Response Capabilities (Generic letter 82-33.

Spoolement 1 to NUREG-0737. Section 7.5.2.4. SER and SSER 3.

1 Section 18. SER. SSER 2 and SSER_]l E01 shall complete the requirements of NUREG-0737 Supplement #1 l

j as specified in Attachment 5. is hereby j

incorporated into this license.

(15)

Salem ATWS Event. Generic Letter 83-28 (Section 7.2.2.5. SSER 21 l

o E01 shall submit responses to and implement the requirements of l

Generic Letter 83-28 on a schedule which is consistent with that given in it: letters dated August'3, 1984 and May 20,.

1 1985.

(16) Mercer Related Reports l

GSU shall inform the Director, NRR:

a.

Sixty days prior to a transfer (excluding grants of security interests or liens) from GSU to-Entergy or any other entity of facilities for the production, transmission or distribution of electric. energy havirg a depreciated book value exceeding one percent (1%)'of GSU's consolidated net utility plant, as recorded on GSU's books of account.

b.

Of an award of damages in litigation iniciated'against GSU by Cajun Electric Power Cooperative regarding River Bend within 30 days of the~ award.

D.

E01 shall fully implement and maintain in effect all provisions of

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the Commission-approved physical security, guard training and qualification, and safeguards. contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822)'

and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).. The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:

" River Bend Physical Security Plan," with revisions.

Amendment No. 70

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'i submitted through November 6, 1987; " River Bend Station Guard

-l Training and Qualification Plan," with revisions submitted through j

December 16, 1986; and " River Bend Station Safeguards Contingency.

Plan,"'with revisions submitted through January 27, 1987. Changes made in accordance with 10 CFR 73.55 shall be implemented in.

accordance with the_ schedule set forth therein.

E.

Except as otherwise provided in the Technical Specifications or i~

Environmental Protection Plan, EDI shall report any violations of the li i

requirements contained in Section 2.0 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).

I F.

The licensees shall. have and maintain financial protection of such type and in such amounts as the Commission shall require-in j

I l-accordance with Section'170 of the' Atomic Energy Act of 1954, as amended, to cover public liability claims.

o G.

This license is effective as of the date of issuance and shall expire I

at midnight on August 29, 2025.

.j FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By.

t Harold R. Denton, Director Office of Nuclear Reactor _ Regulation i

Enclosures:

1 l

1.

Attachments 1-5 2.

Appendix A - Technical Specifications (NUREG-1172) 3.

Appendix B - Environmental Protection Plan 4.

Appendix C - Antitrust Conditions L

Date of Issuance: November 20, 1985 Revised:- December 16, 1993 i

Amendment No. 70 i

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ATTACHMENT 2 TO NPF-47 SEISMIC AND DYNAMIC O!'.!FICATION OF SEISMIC CATEGORY I MECHANICAL AND fifrTHICAL E0VIPMENT E01 shall complete the following requirements for seismic and dynamic I

qualification on the schedule noted below:

1.

E01 shall complete the seismic qualification of the in-vessel rack l

prior to its use.

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Amendment No. 70

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ATTACHMENT 3 TO NPF-47 TDI DIESEL ENGINES RE0VIREMENTS i

E01 shall comply with the following requirements related to the TDI diesel engines.

l.

Change to the maintenance and surveillance program for the TDI diesel i

engines, as identified and approved by the NRC staff in Supplement 3 to i

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

The frequency of the major engine overhauls referred to in the license conditions below shall be consistent with Section IV.1, " Overhaul l

Frequency" in revision 2 of Appendix II of the Design Review / Quality

-i Revalidation report which was transmitted by letter dated May 1,1986, l

from J. George, Owners Group, to H. Denton, NRC.

2.

Crankshafts shall be inspected as follows:

i SD 18: During the first refueling outage, inspect the fillets and oil holes of the three most heavily loaded crankpin journals (Nos. 5, 6, and

7) with florescent liquid penetrant and ET as appropriate.

SD 1A and IB: During the second and third refueling outages, inspect the fillets and oil holes of two of the three most heavily loaded crankpin journals in the manner just mentioned.

j SD 1A and IB: At approximate 5 year intervals subsequent to the third refueling outage, inspect the fillets and oil holes using florescent liquid penetrant and ET as appropriate, of the:

a) three most heavily loaded crankpin journals (Nos. 5, 6, and 7), and b) main journals located between crankpin journals 5, 6, and 7.

One engine may be inspected at the i

refueling outage closest to 5 years, and the other engine at the next refueling outage.

If cracks are found during inspections of crankshafts, this condition shall be reported promptly to the NRC staff and the affected engine shall be considered inoperable. The engine shall not be restored to " operable status" until the proposed disposition and/or corrective actions have been i

i approved by the NRC staff.

3.

Cylinder blocks shall be inspected for " ligament" cracks, " stud-to-stud" cracks and " stud-to-end" cracks as defined in a report

• by failure.

Analysis Associates, Inc. (FaAA) entitled, " Design Review of TDI R-4 and RV-4 Series Emergency Diesel Generator Cylinder Blocks" (FaAA report no.

]

FaAA-84-9-11.1) and dated December 1984.

(Noted that the FaAA report specifies additional inspections to be performed for blocks with "known"

• This report was transmitted to H. Denton, NRC, from C. L. Ray, Jr., TDI Owners Group, by letter dated December 11, 1984.

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or " assumed" ligament cracks). The inspection intervals (i.e., frequency) shall not exceed the intervals calculated using the cumulative damage index model in the subject faAA report.

In addition, inspection method shall be consistent with or equivalent to those identified in the subject FaAA report.

In addition to inspections specified in the aforementioned FaAA report, blocks with "known" or " assumed ligament cracks" (as defined in the FaAA report) should be inspected at each refueling outage to determine whether or not cracks have initiated on the top surface exposed by the removal of two or more cylinder heads. This process should be repeated over several-refueling outages until the entire block top has been inspected.

Liquid-penetrant testing or a similarly sensitive nondestructive testing technique should be used to detect cracking, and eddy current should be used as appropriate to determine the depth of any cracks discovered.

If inspection reveals cracks in the cylinder blocks between stud holes of adjacent cylinders (" stud-to-stud" cracks) or " stud-to-end" cracks, this condition shall be reported promptly to the NRC staff and the affected 1

engine shall be considered inoperable. The engine shall not be restored i

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

i 4.

The following air roll test shall be performed as specified below, except when the plant is already in an Action Statement of Technical Specification 3/4.8.1, " Electric Power Systems, A.C. Sources":

The engines shall be rolled over with the airstart system and with the cylinder stopcocks open prior to each planned start, unless the start occurs within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of a shutdown. The engines shall also be rolled over with the airstart system and with the cylinder stopcocks open after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but no more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, 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 i

an engine is removed from service for any reason other than the rolling over procedure prior to expiration of the 8-hour or 24-hour periods noted above, that engine need not be rolled over while it is out of service.

The licensee shall air roll the engine over with the stopcocks open at the time it is returned to service.) The origin of any water detected in the cylinder must be determined and any cylinder head which leaks due to a crack shall be replaced. The above air roll test may be discontinued following the first refueling outage subject to the following conditions:

All cylinder heads are Group III heads (i.e., cast after September 1980).

Quality revalidation inspections, as identified in the Design Review / Quality Revalidation report, have been completed for all cylinder heads.

Amendment No. 70

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3-Group III heads continue to demonstrate leak free performance. This should be confirmed with TDI before air roll tests are discontinued.

5.

The followi of 3130 KW'gg actions are required if SD 1A or SD IB is operated in excess i

a)

For indicated engine loads period less than two hours',in the range of 3130 KW to 3200 KW for a

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no additional action shall be required.

b)

For indicated engine loads in the rangg of 3130 KW to 3200 KW for a period equal to or exceeding two hours

), a crankshaft inspection pursuant to Item d below shall be performed at the next refueling outage.

c)

For indicated engine loads in the range of 3200 KW to 3500 KW for a period less than I hour'2), 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 rangg of 3200 KW to 3500 KW for periods equal to or uceeding 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 inspection shall include crankpin journal numbers 5, 6, and 7 (the most heavily loaded) and the two main journals inbetween using florescent liquid penetrant and eddy current.as appropriate.

6.

Periodic inspections of the turbochargers shall include the following:

The turbocharger thrust bearings should be visually inspected for excessive wear after 40 non-prelubed starts since the previous visual inspection.

Turbocharger rotor axial clearance should be measured at each refueling outage to verify compliance with TDI/Elliott specifications.

In addition, thrust bearing measurements should be compared with measurements taken previously to determine a need for further inspection or corrective action.

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

(2)

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

Amendment No. 70

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Spectrographic and ferrographic engine oil analysis shall be performed quarterly to provide early evidence of' bearing degradation.

1 Particular attention should be paid to copper level and particulate size, which could signify thrust bearing degradation.

i The nozzle ring components and inlet guide vanes should be visually inspected at each refueling outage for missing parts or parts showing distress on a one-turbocharger-per-refueling-outage basis.

In addition, these inspections should be performed for all turbochargers 1

at each turbocharger overhaul (i.e., at approximately 5-year i

intervals).

If any missing parts or distress is noted, the entire ring assembly should be replaced and the subject turbocharger should be reinspected at the next refueling outage.

7.

Operation beyond the first refueling outage is subject to NRC staff approval based on the staff's final review of the Owners Group generic findings and of the overall design review and quality revalidation program at River Bend.

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Amendment No. 70 l

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l ATTACHMENT 4 L

TO NPF-47 FIRE PROTECTION PROGRAM RE0VIREMENTS l

E01 shall comply with the following requirements of the fire protection

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l program:

l 1.

E01 shall implement and maintain in effect all provisions of the l

approved fire protection program as described in-the Final Safety 1

Analysis Report for the facility through Amendment 22 and as approved in the SER dated May 1984 and Supplement 3 dated August 1985 subject to provisions 2 and 3 below.

2.

EDI may make no change to the approved fire protection program which

-l would significantly decrease the level of fire protection in the plant without prior approval of the Commission.

To make such a change EDI must submit an application for license amendment pursuant l

to 10 CFR 50.90.

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3.

E0I may make changes to features of the approved fire protection l

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 Commission prior to license issuance.

E01 shall maintain, in an auditable form, a

_l 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 upon 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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Amendment No. 70 l

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i ATTACHMENT 5 TO NPF-47 EMERGENCY RESPONSE CAPABILITIES E01 shall complete the following requirements of NUREG-0737. supplement No.1 on l

the schedule noted below:

1.

Actions _ and schedules for correcting all human engineering discrepancies (HEDs) identified in the " Detailed Control Room Design Review Summary 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 committed to by GSU in the summary report and supplements ar.d accepted by the NRC staff in Section 18.1 of SSER 3.

2.

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, i

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 Tetter of June 24, 1985 are:

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coobnt leval in the reactor; b)

uppression pool water level; c;

drywell atmosphere temperature-d) primary system safety relief valve position; e) standby liquid control system storage tank level; f) emergency ventilation damper position; and g) airborne radiohalogens and particulates.

3.

E01 shall implement modifications (installations or upgrade) for l

neutron flux monitoring consistent with the guidance of Regulatory Guide 1.97, Revision 2 or the NRC Staff's Safety Evaluation Report of the BWR Owners Group Licensing Topical Report (NED0-31558, Position i

on NRC Regulatory Guide 1.97, Revision 3, Requirements for Post-Accident Neutron Monitoring System). Modifications, if required, shall be completed before restart from the next refueling outage.

starting after 18 months from the date of receipt-of the NRC Staff Evaluation Report on NED0-31558, but no later than startup from refueling outage No. 4 unless otherwise notified in writing by the NRC staff.

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4 Amendment No. 70

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APPENDIX B l

TO FACILITY OPERATING LICENSE NO. NPF-47 RIVER BEND STATION UNIT I ENTERGY OPERATIONS, INC.

DOCKET NO. 50-458 i

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ENVIRONMENTAL PROTECTION PLAN (NONRADIOLOGICAL) l Amendment No. 70

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