ML20155H340

Forwards Safety Evaluation Re Relief Authorization from Requirements of ASME Section XI for Second 10-yr ISI Interval,Request for Relief RR2-0001,RR2-0002 & RR2-0003

ML20155H340
Person / Time
Site:	River Bend
Issue date:	11/03/1998
From:	Hannon J NRC (Affiliation Not Assigned)
To:	Edington R ENTERGY OPERATIONS, INC.
Shared Package
ML20155H344	List: ML20155H340 ML20155H349
References
TAC-MA0620, TAC-MA620, NUDOCS 9811100084
Download: ML20155H340 (4)

Text

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j NUCLEAR REGULATORY COMMISSION l WASHINGTON, D.C. 30686 6 1 November 3, 1998 k*****

Mr. Randall K. Edington l Vice President - Operations

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l Entergy Operations, Inc.  !

River Bend Station P. O. Box 220 St. Francisville, LA 70775

SUBJECT:

RIVER BEND STATION, UNIT 1 - RELIEF AUTHORIZATION FROM THE i REQUIREMENTS OF ASME SECTION XI FOR THE SECOND TEN-YEAR INSERVICE INSPECTION INTERVAL, REQUESTS FOR RELIEF RR2-0001, RR2-0002 AND RR2-0003 (TAC NO. MA0620)

Dear Mr. Edington:

By letter dated January 7,1998, Entergy Operations, Inc. (Entergy or EOl), requested relief from the requirements of ASME Section XI, " Rules for Inservice inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers Boiler and Pressure .

l Vessel Code (ASME Code) for the second inservice inspection (ISI) interval at the River Bend Station (RBS), Unit 1 in accordance with Paragraph 50.55a(a)(3) of Title 10 of the Code of  ;

Federal Regulations, Part 50. Additional information was provided by Entergy in its letter dated  !

July 8,1998.

l In the January 7,1998 letter, EOl requested relief from ASME Code weld examinations for three specific areas: l l

(1) (RR2-0001) ASME Code,Section XI, Examination Category B-A, item B1-22 requires that essentially 100% of the accessible length of all reactor pressure vessel (RPV) meridional welds be volumetrically examined as defined by Figure IWB-2500-3. However, access to RPV meridional head Welds B13 D001-DG and DH is restricted by the control rod drive assemblies and the RPV support structure. Relief from the ASME Code requirement was requested since I imposition of this requirement would cause a considerabie burden on the licensee.

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(2) (RR2-0002) ASME Code,Section XI, Examination Category C-8, item C2.22 j requires 100% volumetric examination of Class 2 pressure retaining nozzle

inside radius sections that are either welded to or integrally cast in vessels that i connect to piping runs. However, the physical configuration of Nozzle Inner

! Radius Sections N3 (E12-EB001X-3.743-A) and N4 (E12-EB0011X-3.744-A) for Residual Heat Removal (RHR) Heat Exchangers A, B, C, and D would limit l meaningful volumetric examination results. Surface examination would alco l require the heat exchanger tube bundle to be removed to access the inside radius sections of the nozzles. Therefore, the Code-required volumetric examination is impractical at RBS.

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1 Randall K. Edington (3) (RR2-0003) ASME Code,Section XI, Examination Category C-G, item C6.10 requires, in part, that Class 2 pump casing welds receive a 100% surface examination of welds from either the inside or outside surface of the component.

EOl requested relief from Code required surface examination of the pressure-retaining welds on the following Class 2 pumps installed in the RHR, High Pressure Core Spray (HPCS) and Low Pressure Core Spray (LPCS) systems:

(a) E12-PC002A (RHR)

(b) E12-PC002B (RHR)

(c) E12-PC002C (RHR)

(d) E22-PC001 (HPCS)

(e) E21-PC001 (LPCS)

The pump casing welds for the above components are encased in concrete, and would require significant disassembly or redesign of the pump in order to perform the Code-required examinations. Consequently, the imposition of this requirement is impractical and would cause a considerable burden on the licensee.

)

As required by regulations, the ISI for ASME Code Class 1,2 and 3 components at nuclear i power plants shall be performed in accordance with Section XI of the ASME Code and applicable addenda as required by 10 CFR 50.55a(g), except where specific written relief has i been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). Or, as stated in 10 CFR 50.55a(a)(3), alternatives to the requirements of paragraph (g) may be used, when authorized by the Commission, if (i) the proposed attematives would provide as acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

In the enclosed Safety Evaluation, the staff concludes that your proposed relief from the

-inservice inspection requirements of the ASME Code is acceptable and is authorized pursuant to 10 CFR 50.55a(g)(6)(i). This is based upon the determination by the Commission, as stated -

in the Safety Evaluation, that the implementation of proposed alternatives will provide an l acceptable level of quality and safety at RBS.

Sincerely, 7

John N. Hannon, Director  !

Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket No. 50-458

Enclosure:

Safety Evaluation cc w/ encl: See next page

. . Rand:ll K. Edington .

(3) (RR2-0003) ASME Code,Section XI, Examination Category C-G, Item C6.10 requires, in part, that Class 2 pump casing welds receive a 100% surface examination of welds from either the inside or outside surface of the component.

EOl requested relief from Code required surface examination of the pressure-retaining welds on the following Class 2 pumps installed in the RHR, High Pressure Core Spray (HPCS) and Low Pressure Core Spray (LPCS) systems:

(a) E12-PC002A (RHR)

(b) E12-PC002B (RHR)

(c) E12-PC002C (RHR)

(d) E22-PC001 (HPCS)

(e) E21-PC001 (LPCS)

The pump casing welds for the above components are encased in concrete, and would require significant disassembly or redesign of the pump in order to perform the Code-required examinations. Consequently, the imposition of this requirement is impractical and would cause a considerable burden on the licensee.

As required by regulations, the ISI for ASME Code Class 1,2 and 3 components at nuclear power plants shall be performed in accordance with Section XI of the ASME Code and applicable addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55A(g)(6)(i). Or, as stated in 10 CFR 50.55a(a)(3), alternatives to the requirements of paragraph (g) may be used, when authorized by the Commission, if (i) the proposed alternatives would provide as acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

In the enclosed Safety Evaluation, the staff concludes that your proposed relief from the inservice inspection requirements of the ASME Code is acceptable and is authorized pursuant to 10 CFR 50.55a(g)(6)(i). This is based upon the determination by the Commission, as stated in the Safety Evaluation, that the implementation of proposed alternatives will provide an acceptable level of quality and safety at RBS.

Sincerely, ORIGINAL SIGNED BY:

John N. Hannon, Director Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket No. 50-458

Enclosure:

Safety Evaluation cc w/ encl: See next page DISTRIBUTION: Docket File. PUBLIC PD4-1 r/f JHannon CHawes RFretz TGwynn, RIV GHill(2) ACRS OGC (15B18) THarris(TLH3) EAdensam (EGA1) DLange, RIV Document Name: RBA0620.REL g OFC PM/PD4-1 LA/PD4-1 Ph D4-1 NAME RFretz h CHawesN JHkrbon DATE // / 3 /98 $/'h /98 h /98 l COPY (fES)NO YES/NO YEhhO OFFICIAL RECORD COPY G

Mr. Randall K. Edington Entergy Operations, Inc. River Bend Station ,

1 cc:

Winston & Strawn Executive Vice President and 1400 L Street, N.W. Chief Operating Officer Washington, DC 20005-3502 Entergy Operations, Inc.

P. O. Box 31995 Manager - Licensing _ Jackson, MS 39286

. Entergy Operations, Inc.

River Bend Station General Manager - Plant Operations P. O. Box 220 Entergy Operations, Inc.

St. Francisville, LA 70775 River Bend Station P. O. Box 220 l Senior Resident inspector St. Francisville, LA 70775 P. O. Box 1050 St. Francisville, LA 70775 Director- Nuclear Safety J

Entergy Operations, Inc.

President of West Feliciana River Bend Station Police Jury P. O. Box 220 P. O. Box 1921 St. Francisville, LA 70775 St. Francisville, LA 70775 Vice President - Operations Support Regional Administrator, Region IV Entergy Operations, Inc.

U.S. Nuclear Regulatory Commission P. O. Box 31995 611 Ryan Plaza Drive, Suite 1000 Jackson, MS 39286-1995 Arlington,TX 76011 Attomey General

• I; H. Anne Plettinger State of Louisiana 3456 Villa Rose Drive P. O. Box 94095 Baton Rouge, LA 70806 Baton Rouge, LA 70804-9095 Administrator Wise, Carter, Child & Caraway Louisiana Radiation Protection Division P. O. Box 651 P. O. Box 82135 Jackson, MS 39205 Baton Rouge, LA 70884-2135

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