ML20127D051

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Proposed Tech Specs,Authorizing Util to Become Licensed Operator of Facility
ML20127D051
Person / Time
Site: River Bend Entergy icon.png
Issue date: 01/13/1993
From:
GULF STATES UTILITIES CO.
To:
Shared Package
ML20127D040 List:
References
NUDOCS 9301150074
Download: ML20127D051 (21)
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Text

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NUCLE AR REOULATORY COMMISSION wuwmotow.o e tom GULF STATE 5 UTillT![E COMPANYcAt CAJUN ELECTifTC70WER COOPERATIVE ~ m C OTMG Y DOCKEl h0 50-455 OPGMw% IMC .

RIVERlIND STATION, UNIT 1 >

FACILITY OPERATING LICENSE License No. NPF-47

1. The Nuclear Regulatory Comission (the Comission 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, compiles with the standards and requirements of the Atomic Energy Act of 2954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter 1, and all required notifications tc other agencies or bodies have been duly made; B. ConstructionoftheRiverBendStation, Unit 1(thefacility) has been substantially completed in confomity with Construction Pemit 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 confomity with the application, as arended, the provisions of the Act, and the regulations of the Corrission; D. There is reasonable assurance: (1)thattheactivitiesauthorized 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 I; ptchns

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  • 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 Compa y cmd [01 nave satisfied the applicab e,and CajunofElectric provisions 10 CFRPower Cooperative, Part 140, "Finan-ial 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; E.0h1+* Gulf-States-Utilities-Company-is authorized to act asvagent forfajun Electric
  1. Power Cooperative and has exclusive responsibility and control ov6q the physical construction, operation and maintenance of the facility. \

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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 Opera-ting License No. NPF-47, subject to the conditions for protection of the environnent set forth herein, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable require-ments have been satisfied; and

1. The receipt, possession, and use of source, byproduct and special nuclear material'as authorized by this license will be in accordance with the Consnission's regulations in 10 CFR Parts 30, 40 and 70.
2. Based on the foregoing findings and approval by the Nuclear Regulatory Comission at a meetinst 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 Eol) and Cajun Electric Power Cooperative

% Gulf States Utilities Compagows:

(the licensees), to read as fo g yg q Eg A. This license applies to the River Bend Station Unit 1, a bc ling water nuclear reactor and associated equipment, owned bydlulf States Utilities Company and Cajun Electric Power Cooperative. 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 18 miles northwest of the city limits of Baton Rouge, Louisiana, ar.d is described in the licensees' " Final Safety Analysis Report," as supplemented and amended, ano in the licensees' Environmental Report-Operating License Stage, as supplemented and amended.

B. Subject to the conditions and requirements incorporated herein, the 1 Comission 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; E01 m(2) 45&, pursuant to Section 103 of the Act ano 10 toA CFR P use and operate the facility at the above designated location

[ in accordance with the procedures and limitations set forth in I

this license; (3 SE, 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 amounts
required for reactor operation, as described in the Final Safety i . Analysis Report, as supplemented and amended; l

3 EDT.I([)350, pursuant to the Act arid 10 CFR Parts 30, 40 and 70, to re-ceive, possess, and use at any time any byproduct, source and special nucitar material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radia-tion monitoring equipment calibration, and as fission detectors in amounts as required;

~4 EO L'4 -(5) GStt, pursuant to the Act and 10 f.FR 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 fom, for sample analysis or instrur4r.t calibration or associated with radioactive apparatus or cca-ponents; and LOL F(6) ~ $U,6 pursuant to the Act and 10 CFR Parts 30, 40 and 70, to pcssess, but not separate, such byproduct arid special nui; lear raterials as may be produced by the operation of the facility.

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

tions specified in the Comission'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 Comission now or here-after in effect; and is subject to the additional conditions specified

( or incorporated below:

(1) Maximum Power Level EUC-*G5tf is authorized to operate the facility at reactor core power levels not in excess of 2894 megawatts thermal (100% rated 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.

(2 L Technical Specifications and Environnental Protection Plan see attaened pages The Technica ications ccntained in Appendix tre 3A and 3B Environmental Protect on x 8 both of which are attached he e orated into this license operate the faci ity in ce with the

--Yettin cal Specifications and the Environmental Protec . a n .-

(3) Antitrust Conditions GSU shall comply with the antitrust conditions in Appendix C attached hereto, which is hereby incorporated into this license.

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SDC GULF STATES VTILITIES COMPANY v " %,

DOCKET NO. 50-458 "0t am . S RIVER BEND STATION. UNIT 1 I 2 1992 oe AMENDMENT TO FACILITY OPERATING LICENS g .'.l.t',";:, [

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Amen men No. 65 License No. NPF-47

1. The Niiclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Gulf States Utilities Company (the licensee) dated February 5, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I;

8. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-47 is hereby amended to read as follows:

(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 65 and -the Environmental Protection Plan >

contained in Appendix B, are hereby incorporated in the license. 669 EC21:

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

3. The license amendment is effective as of its aate of issuance to be ,

implemented within 30 days of issuance. '

FOR THE NUCLEAR REGULATORY COMMISSION Qw v

Suzanne C. Black, Director Project Directorate IV-2 Division of Reactor Projects !!!/IV/V Office of Nuclear Reactor Regulation-

Attachment:

Changes to the Technical Specifications Date of Issuance: October 2, 1992 i

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1 (4) Seismic and Dynamic Oua11fication of Seismic Category 1 Eechanical and Electrical Equipment (Section 3.10. SER and SSER 3)

Eol-- 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 j license.

(5) Mark !!! Related Issues (Section 6.2.1.9. SER and SSER 2)

MI ~~TUSU- shall not use the residual heat removal system in the steam condensing mode without prior written approval of the staff.

b. Prior to startu) following the first refueling outage, GSU shall furnish tie outstanding information identified in Appendix K of SSER 2 addressing the Mark !!! containment related issues.

(6) Inservice Inspection Program (Section 5.2.4.3 and 6.6.3 SER and SSER 3)

GSU shall submit the inservice inspection program for hRC staff review and approval by September 1,1986.

(7) Bypassed and Inoperable Status Indication (Section 7.5.2.2. SER and 55ER 3)

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 moni-tor 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 in a GSU letter dated March 5,1985.

(8) TDI Diesel Engines (Section 8.3.1 SSER 3)

Eo1 -+.GSU-shall implement the TDI diesel requirements as specified in Attachment 3. Attachment 3 is hereby incorporated into this

% license.

(9) 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.

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5-r (10)FireProtection(Section9.5.1,SERand$$ER3)

EUl -+ 699 shall comply with the requirements of the fire protection program as specified in Attachment 4. Attachment 4 is hereby incorporated into this licensa.

(11) Operating Staff Experience Requi_rements (5ection 13.1.2.1, $$ER 2)

EDI->G5U shall have a licensed senior operator on each shift, while 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. 5tation, including at least six ' weeks at power levels prester than 20% of full power, and who has had startup and shutdown experience.

(12) Post-Fuel-loading Initial Test Program (Section 14, $ER and 55tR 31 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.

(MTrMaastater Heating (5ection 15.1, SteV#

bl 3, The facility shall for t o extending the norma h partial feedwater heating without prior en approval of the staff.

(14) Emergency Response Capabilities fGeneric letter 82-33, supplement I to muuttii-0737, sect 4on 7.5.2.4, stR and 5$ER 3, Section 15. sta, s5tu z and sstu 31 Ear + 899 shall complete the requirements of NUREG-0737 Supplement #1 as specified in Attachment 5. Attachment 5 is hereby incorporated into this license.

(15) Sales A1W5 Event, Generic letter 83-28 (Section 7.2.2.5, $5ER 3)

EOl->G99 shall submit responses to and implement the requirements of Generic Le.tter 83-28 on a schedule which is consistent with that given in its letters dated August 3,1984 and May 20, 1985.

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GULF STATES UTILITIES COMPANY DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMENDMEMT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. NPF-47

1. The Nuclear Regulatory Cosmission (the Cosmission) has found that:

A. The application for amendment by Gulf States Utilities Company (the licensee) dated August 5,1988, as supplemented November 30, 1988, and January 17 and February 28,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Cornission'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 Cosmission; C. There is reasonable assurance: (1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such act'vities will be conducted in compliance with the Cosmission's regulations 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 Cosmission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is wended by changes to License Condition 2.C(13)ofFacilityOperatingLicenseNo.NPF-47. License Condition 2.C(13),,ts hereby amended to read as follows:

(13)PartialFeedwaterHeating(Section15.1.SER)

The facility shall not be operated with partial feedwater heating beyond the and of the normal fuel cycle without prior written a1 proval of the staff. During the normal fuel cycle, the facility stall not be operated with a feedwater heating capacity which would result in a rated thermal power feedwater temperature less 320*F without prior written approval of the staff.

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3. Accordingly, the license 12 also amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF.47 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 37 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. GSU shall operate the facility in accordance with the Technical Specifications and the Environrental Protection Plan.

4. The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY C0m!SS10N

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b. Nw Frederick J. Hebdon, Director Project Directorate - ly Division of Reactor Projects - !!!,

IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of 1ssuance: June 23, 1989 4

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0, hall fully implement and maintain in effect all provisions of l See attached pages the n approved physical security, guard training and quali.

6A and 63 fication,and s contingency plans, includin el s l

and revisions m de purs the authority of .W and 10 i CFk$0.54(p). These lans, uards-information protected under 10 CF Physical Securit 73.2: M e. *

'er Bend Station ining and ver Bend Station Secur Gu61tfi an' and " River Bend Station Safeguards Con P1 ..

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E. Except as otherwise provided in1the Technical Specifications or Environmental Protection Plan, SW shall report any violations of the requirements contained in Section 2.C of-this license-in the following mannert initial notification shall be ude 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 the_ procedures with written followup described in 10within thirty) days CFk 50.73(b , (c), and in accordance (e). with F. The licensees shall have and mintain financial protection of such type and in such amounts as the Comission 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 1ssuance and shall expire at midnight on August 29,2025. , .

FOR THE NUCLEAR REGULATORY COMMISSI0ff l so.

Harold R. Denton, Director Of fice of Nuclear. Reactor Regulation

Enclosures:

1. Attachraents 1-5
2. Appendix A - Technical Specifications (NUREG-1172)
3. Appendix B - Environmental Protection Plan
4. Appendix C - Antitrust Conditions Date of Issuance: November 20, 1985 c"; .. .

RECEIVED l MAY 111988 sDc

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHING TON, D. C. 20555

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.,.~..4 GULF STATES UTILITIES COMPANY DOCKET NO. 50-458 RIVER BEMD STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendrent No. 21 License No. NPF-A7

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

A. ThesubmittalsbyCulfStatesUtilitiesCompany(thelicensee) dated November 11, 1986 and November 6, 1987, comply with the standards and reouirements of the Atonic Erergy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comissinn; C. There is reesenable assurance: (1) that the activities authorized by this amendment can be cenducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this license amendment will not be inimical to the corron defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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. RECEIVED MAY 111988 soc

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  • Amendment 21 l
2. Accordingly, paragraph 2.0 of Facility Operating License No. NPF-47 is hereby amended to read as fnllows: )

C OI 9 6 shall fully implement and maintain in effert all provisions l of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including nendrents made pursuant to provisions of the Miscellaneous Am ndments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and10CFR50.54(p). The plans, which contain Safeguards Infomation protected under 10 CFR 73.21, are entitled:

" River Bend Physical fecurity Plan," with revisions submitted through November 6,19871 " River Rend Station Guard Training and Qualification Plan " with revisions submitted throuob December 16, 19861 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 fortu therein.

3. The license anendrent is effective as of its date of issuance.

FOP THE NtlCLEAR REGULATORY C0t911SSION-O. .. .

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/ Jose A. Calvo, Director Project Directorate - IV Division of Peactor Projects - III, IV,VandSpecialProjects Office of Nuclear Fractor Petulation Date of issuarec: April 26,1988

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, RECEIVED MAY 111988 soc

ATTACHMENT 1 T0-NPF 47 Prior to achieving the condition indicated on or before the date indicated, 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 PP0 GRAM
a. Verify the station electric distribution voltage analyses are in l accordance with the guidelines of Branch Technical Position PSB-1, l Position 4.
b. Perform an engineerina 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. O'UTSTANDING ITEM 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.
4. OUTSTANDING ITEMS TO BE ACCOMPLISHED PRIOR TO STARTUP FOLLOWING THE FIRST ATFUr 3G OUTAGE
a. unir or replace the control valves on HVAC chillers as delineated 1c the 10 CFR 50.55(e) report identified as DR-314.
5. OUTSTANDING ITEM TO BE ACCOMPLISHED BY MAY 31, 1988
a. Compit.te installation of equipment improvements to the security radir communications system.
6. OUTSTANr,ING ITEM TO BE ACCOMPLISHED PRIOR TO START-UP FOLLOWING K 5UW.QUENT OUTAGE WITH A PLANNED DURATION OF SEVEN DAYS OR LONGER FELTdING MAY 31, 1988
a. Conduct testing to determine if adequate radio communication capability exists from appropriate plant areas.
7. OUTSTANDING ITEM TO BE ACCOMPLISHED PRIOR TO START-UP FOLLOWING THE SECOND REFUELING OUTAGE R E C E I V E Da. If during acceptance testing it is determined that further modifica-tions and/or testing are required, this shall be performed during a NOV 101987 subsequent outage of sufficient duration but prior to start-up-9 * '* ** "9
  • 9

SDC Amendment 16

ATTACHMENT 2 TO MPF-47 SEISMIC AND DYNM'C_0UALIFICATION OF SEISMIC CATEGORY I MECHANICAL AND ELECTRICAL E0VIFMENT LCD45U shall complete the folkwing requirements for seismic and dynamic avalific6 tion on the schedule noted below:

LDfll , b shall complete the seismic qualification of the in-vessel rack prior to its use.

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1 RECElVED. .

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SDC .

Amendment No.34

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ATTACHMENT 3 T0-NPF 47 TDI DIESEL ENGINES REQUIREMENTS LD L 9 95tf shall ccrrply with the following requirements related to the TDI diesel ergines.

1. Change 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.

The frequency of the major engine overhauls referred to in the license conditions below shall be consistent with Section IV.I. " Overhaul Frequency" in revision 2 of Appendix !! of the Design Review / Quality-Revalidation report which was transmitted by letter dated May 1,1986, from J. George Owners Group, to H. Denton, NRC.

2. Crankshafts shall be inspected as follows:

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 18: During the second and third refueling outage's, inspect l

. the fillets and oil holes of two of the three most heavily loaded

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crankpin journals in the manner just mentioned.

SD 1A and 18: 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 locatd between crankpin journals 5, 6 and 7. One engine may be inspected at the 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 approved by the NRC staff.

3. Cylinder. blocks shall be inspected for " ligament" cracks, " stud-to-stud" cracks and " stud-tc-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, i

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2 or " assumed" 11 ament cracks). The inspection intervals (i.e.,

/requency) shal$ not exceed the intervals calculated using the cumulative 1 .

damage index model in the subject FaAA repurt, in addition, inspection i

method shall be ccnsistent 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 F4AA l' 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 betwen 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' engine shall be considered inoperable. The engine shall not be restored to " operable status" until the proposed disposition and/or corrective  ;

actions have been approved by the NRC staff, ,

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 Systeas 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 that 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 !!! 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.

l RECElVED I Amendment 15 NOV 121987

. SDC b

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  • Group !!! heads continue to demonstrate leak free performane.e. This
should be confimed with TDI before air roll tests are discontinued.
5. The following act excessof3130KWgsarerequiredifSD1AorSD18isoperatedin
a) For indicated engine loads period less than two hours (g , no the range ofaction additional 3130 shall XW to be3200 KW for a <

required.

b) For indicated engine loads in the rangT29f 3130 KW to 3200 XW 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, e) for indicated engine log in the range of 3200 XW 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 belew shall be perfonned for the affected engine at the next refueling outage.

d) For indicated engine loads in the'rangI27 3200 f 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 safel shall be declared inoperable, and (3)y possible, (2) the crankshaft shallthe beengineinspec-ted. The cranks. haft inspection shall include crankptn journal numbers 5', 6, and 7 (the most heavily loaded) and the two main '

journals inbetween using florescent li4uid 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 actioni (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.

RECEIVED

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NOV 121987 sac m - . . - , - , - - , , , , - -,,,-,,-,,.,..-r--_--.,,,,c.,-.-r-e. ..,- . , - .- --r,,,n. ,[ ,

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  • Spectrographic and ferrographic engine oil analysis shall be perforned quarterly to provide early evidence of bearing degradation. Particular attention should be paid to copper level and particulate size, which could signify thrust bearing degradation.

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

In addition, these inspections should be performed for all turbochargers at each turbocharger overhaul (i.e., at approximately 5-yearintervals). 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.

Amendment 15 l RECEIVED t

NOV 121987 soc

ATTACH 1'Eh1 4 10 hPF 47 FIRE PROTECTION PROGRAM REQUlP REN15 G>14 650 shall comply with the following requirements of the fire protection program:

h. 65tf shall iniplement and maintain in effect all provisions of the approved fire protection program as describec in the final Safety Analysis Report for the facility through Amendnent 22 and as approved in the SER dated hay 1984 and Supplement 3 dated August 1905 subject to provisions 2 and 3 below.

O 2. I50 may make no change to the approved fire protection progran, which would significantly decrease the level of fire protection in the plant without prior approval of the Comission. To make such a change G.50 must submit an application for licenst: amendment pursuantto10KFR50.90.

E 01 L.. N

3. w may make changes to features of the approved fire protection program which do rot 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 Comission prior to license issuance. +5$shallmaintain,_ n g-in an auditable form, a current record of all siith~chingesi~,

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 10CFR50.71(e).

S 4

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ATTACWENT 5 TO NPF 47 EMERGENCY RE5PoM5E CAPABILITIES COE / 95tf shall complete the following requirements of NUREG-0737 Supplement No.1 on the schedule noted below:

1. Actions and schedules for correcting all humen engineering discrepancies (HEDs) identified in the ' Detailed control Room 1984 and
  • Design Supp'ements Review Sussiery dated May 14, JuneReport" 12, 1985, dated and Ju October 31,ly 31,1985, shall be implemented in accordance with the schedule cermitted to by 65U in the surenary report and supplements and accepted by the NRC staff in Section 18.1 of SSER 3.

Lor 2.

Prior to startup following the first refueling outage,)GSU shallimplementmodifications(installationorupgrade for those items listed below consistent with the guidance of Regulatory Guide 1.97, 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 letter of June 24,1985 .

are:

  • a coolant level in the reactors b suppression pool water levell e drywell atmosphere temperatures d primary system safety relief valve positient e standby liquid control system storage tank levelt f emergency ventilation damper position; and g airborne radiohalogens and particulates. ,

3.

bshallimplementmodifications(installationsorupkrade)for neutron flux monitoring consistent with the guidance o Regulatory i Guide 1.97, Revision 2 or the NRC Staff's Safety Evaluation Report oftheBWROwnersGroupLicensingTopicalReport(NED0-31558, position on MRC Regulatory Guide 1.97, Revision 3. Requirements forPost-AccidentNeutronMonitoringSystem). Modifications, if required, shall be coupleted 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 ne later than startup from refueling outage No. 4 unless otherwise notified in writing by the NRC staff.

Amendment H. 28,39

/ 'o, UNITED 8T ATES

! e NUCLE AR REGULATORY COMMISSION

$ I tv A$HING f DN, D. C. 70$$6

\.....J Docket No. 50-458 AHENOMENT TO INDEMNITY AGREEMENT NO. B-104 AMENDMENT NO. 2 Effective November 20, 1985, indemnity Agreement No. B-104, between Gulf States Utilities Company, Cajun Electric Power Cooperative, Inc., and the Nuclear Regulatory Comission, dated January 15, 1985, as amended, is hereby further amended as follows:

Item 3 of the Attachment to the indemnity agreer.ent is deleted in its entirety and the following substituted therefor:

Item 3 - License number or numbers SNM-1943 (From 12:01 a.m., January 15, 1985 to 12 midnig t August 28, 1985 inclusive NPF-40 (From12:01a.m., August 29, 1985 to 12 midnig t, Novembe r' 19,1985 inclusive NPF-47 (From12:01a.m., November 20, 1985 )

FOR THE U. S. NUCLEAR REGULATORY COMMISSION N '

'. g "/ o, .p

' Ja zman, Assis nt Dire 6 tor State and Licensee Relations Office of State Programs Accepted' Accepted By By GULF STATES UTILITIES COMPANY CAJUN ELECTRIC POWER COOPERATIVE, INC.

I l

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