ML20041C177

Forwards Amend 2 to Fsar,Providing Response or Schedule for 811231 Request for Addl Info.Status Summary for Items Noted in NRC 810805 Ltr Encl

ML20041C177
Person / Time
Site:	River Bend
Issue date:	02/24/1982
From:	William Cahill GULF STATES UTILITIES CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML20041C178	List: ML20041C177
References
RBG-12-163, NUDOCS 8202260305
Download: ML20041C177 (8)

Text

I e GULF STATES UTILITIES COMPANY POST OFFICE box 295; UCAUMONT. TEXAS 77704 AREA CODE 713 838-3843 Feb ruary 24, 1982 RBG- 12,163 File G9.5 62 4 Mr. Darrell G. Eisenhut, Director y

Division of Licensing U. S. Nuclear Regulatory Commission OECggjg Washington, D. C. 20555 9 i FEB o5 L

Dear Mr. Eisenhut:

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' L" NM*my kqn %3 River Bend Station-Units 1 and 2 4" "

Docket Nos. 50-458/50-459 4

'tgIti Enclosed are sixty (60) copies of Amendment 2 to the River Bend Station Final Safety Analysis Report. This amendment provides a response or schedule for each request for additional information attached to your letter of December 31, 1981; responses to various previous requests; and various corrections, changes and additional information which have resulted from our continued review of the FSAR. Also enclosed is a status summary for each of the items noted in Enclosure 4 of your August 5, 1981 letter.

Sincerely, I

{

. J. Cahill, Jr.

Senior Vice President River Bend Nuclear Group WJC/WJR/kt Enclosures

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION STATE OF LOUISIANA I PARISH OF WEST FELICIANA l In the Matter of I Docket Nos. 50-458 .

50-459 GULF STATES UTILITIES COMPANY l (River Bend Station, Units 1 & 2)

AFFIDAVIT W. J. Cahill, Jr., being duly sworn, states that he is a Vice President of Gulf States Utilities Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission the documents attached hereto; and that all such documents are true and correct to the best of his knowledge, information and belief.

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p . Cahill, Jr. f" Subscribed and sworn to before me, a Notary Public in and for the State and Parish above named, this JMday of MItem-z<, ,19[f.

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'd h A4 JN (nfW U, / Notary Public in and for West Feliciana Parish, Louisiana l

My Commission is for Life.

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UNITED STATES OF #! ERICA NUCLEAR REGULATORY COMMISSION In the Matter of )

) DOCKET NOS. 50-458 GULF STATES UTILITIES COMPANY ) 50-459

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River Bend Station, Units 1 and 2 )

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AFFIDAVIT OF SERVICE F em.* 8e P. L ' b e r cew e*c z , being duly sworn, on oath, deposes and says that the following document:

AMENDMENT 2 TO THE FINAL SAFETY A\ LYSIS REPORT in the above-captioned proceeding has been served upon the persons shown on the attached list by depositing copies thereof in the United States mail on Fabea <5 12 , 1982, with proper postage affixed for first class mail.

DATED: Felora ar1 13 , i T f L-Stone & Webster Engineering Corporation P.O. Box 2325 Boston, Massachusetts 02107 Subscribed and sworn to before me this 2 day of F.km araj , 1982.

otary I'GSlic in and for the Commonwealth of Massachusetts lay Ccmm.ss;cn Ei;:ves se- W~ 21,170(

l AMENDMENT 2 TO Tile FINAL SAFETY ANALYSIS REPORT Distribution List Set No.

STATE Administrator, Nuclear Energy Division 110 Of fice of Environmental Af fairs 4845 Jamestown Avenue P.O. Box 14690 Baton Rouge, LA 70898 FEDE RAL U.S. Environmental Protection Agency 111 Attn: EIS Coordinator Region VI Office 1201 Elm Street First International Building Dallas, TX 75270 LOCAL President of West Feliciana 112 Police Jury P.O. Drawer N St. Francisville, LA 70775 LA BORATORY Argonne National Laboratory 113 9700 South Cass Avenue Argonne, IL 60439 Attn: Ira Charak NRC Assistance Project Maylin Dittmore 114 Mail Stop: L-97 Lawrence Livermore 'Jational Laboratory P.O. Box 808 Live rmo re , CA 94550

ATTACHMENT I As requested by Mr. Bob Perch of your staff, this attachment is provided to address the areas identified in Enclosure 4 of D. G.

Eisenhut's letter of August 5, 1981.

(1) Environmental Qualification of Safety Related Electrical Equipment - Commission Memorandum and Order of May 23, 1980 defines the current staff requirements for qualification of this equipment Additional guidance on this matter was provided in a subsequent NRR Order dated November 26, 1980 (concerning record requirements), Supplements 2 and 3 dated September 30, 1980 and October 24, 1980, respectively to IE Bulletin No.79-01B, and a generic letter to all holders of cps and OLs dated October 1, 1980.

STATUS

SUMMARY

This guidance is reflected in the Environmental Qualification Document (EQD) submitted as part of the Final Safety Analysis Report (FSAR). The EQD presently addresses Class 1E electrical equipment purchased through Stone & Webster, the Architect Engineer for River Bend Station. A qualification program for equipment purchased through General Electric, the NSSS supplier, is currently under development and will utilize this guidance.

(2) Emergency Preparedness - Guidance on the preparation of emergency plans is presented in NUREG-0654 (FEMA-REP-1), " Criteria for Preparedness in Support of Nuclear Power Plants". The requirements for the emergency response facilities are included in NUREG-0696, " Functional Criteria for Emergency Response Facilities." Further guidance on emergency preparedness is provided in the revised Appendix E to 10 CFR Part 50.

STATUS

SUMMARY

FSAR Section 13.3, Emergency Planning, has been developed in accordance with the provisions of 10CFR50.34, Appendix E to 10CFR50 and NUREG-0654 (FEMA-REP-1).

Section 13.3.6 is currently under revision to include details of the emergency facilities provided for River Bend Station as required by NUREG-0696.

(3) Safety-Related Structures, Systems and Components (Q-list)

Controlled by the QA Program - Staff requests for additional information regarding this issue have been sent to a number of OL applicants. A recent request regarding the Diablo Canyon is provided as Enclosure 5.

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STATUS

SUMMARY

The structures, systems and components centro 11ed by the QA program are those identified as such in Section 3.2, and are controlled as described in Section 17.2.2.1. Other items, such as fire protection equipment and instrument calibration, are controlled by the QA program as described in the appropriate sections of Chapter 17.

1 (4) Fracture Prevention of Containment Pressure Boundary (GDC 51) -

Enclosure 6 provides clarification on how the staff determines compliance with GDC 51.

STATUS

SUMMARY

The following toughness requirements were specified for the ferritic materials of the containment pressure boundary to meet GDC-51, which requires that under operating, maintenance, testing and postulated accident conditions the containment pressure boundary material shall behave in a nonbrittle manner.

Toughness tests (Charpy V-Notch) were required for all ferritic materials greater than 5/8 in. thickness which form part of the containment, mat liter, mat embedments, containment vessel,

containment vessel equipment hatch and personnel air locks, drywell combination equipment hatch and personnel door, drywell personnel air lock, and attachments to these components. The I tests were performed at 0 F for all ferritic materials except bolts, which were tested at 30 F. The tests conformed to ASME III, Class MC, NE-2300 requirements.

All ferritic steel plates for the above components that are less

than 5/8 in. thick (except for backing strips and gas test channels) were impact tested in accordance with ASTM A-20 and the test temperature was not more than 0 F.

Class 1 and Class 2 ferritic forgings and piping with process piping (thicker portion) thickness greater than 5/8 in. were toughness tested (Charpy V-Notch) for acceptance purposes at 40 F or lower in accordance with ASME III, subsection NB 7300. Class 1 and Class 2 ferritic forgings and piping with process pipe

! (thicker portion) thickness less than or equal to 5/8 in, were toughness tested (Charpy V-Notch) for information only at 40 F or lower in accordance with ASME III, subsection NB-2300, except that subsize specimens were allowed in accordance with SA-370.

Ferritic forging penetrations with process piping (thicker portion) thickness greater than 5/8 in, were drop weight tested at 10 F in accordance with ASME III, subsection NB-2300. The

, test specimens were taken from each end of tne penetration and in

{ the vicinity of the outside diameter of the flued head of the penetrations produced as singles. For penetrations produced as multiples, the test specimens were taken at each end of the forging and in the vicinity of the outside diameter of one of the flued heads.

__ _ _ . . _ __._-_ _._ . _ _ - - _ _ _ . - _ _ _ - - _ _ . . . - - _ . . _ ~ ~ - , .

The isolation valves on Class 1 piping comply with the NB-2300 criteria. The isolation valves, of the containment pressure boundary, for all the Class 2 piping did not require toughness testing since the walls of the connecting pipes were less than 5/8 in. thick.

By imposing the above requirements, the River Bend Station design addresses the toughness criteria of subarticle NC-2300 of ASME Section III, 1977 Summer addenda.

Additionally, information to support your review of this topic has been provided in our letter of February 19, 1982, as requested in your letter of December 17, 1981.

(5) Seismic Qualification of Instrumentation and Electrical Equipment Including Dynamic Loading for BWR's - A staff request for additional information in the review area has been sent to a number of pending OL applicants. A copy of that request is provided as Enclosure 7.

STATUS

SUMMARY

Seismic qualification of safety-related instrumentation and electrical equipment is discussed in FSAR Section 3.10.

Seismic qualification of safety-related mechanical equipment is discussed in FSAR Section 3.9.2.2.

Data sheets similar to the " Qualification Summary of Equipment" sheets included in Enclosure 7 will be compiled and provided for each selected piece of equipment, upon request of the SQRT.

(6) Fire Protection - The current requirements for the fire protection programs are defined in the new Appendix R to 10 CFR Part 50. As further guidance, a copy of a recent staff request for additional information on pending OL applications is provided as Enclosure 8.

STATUS

SUMMARY

An appendix to the FSAR is currently under preparation to address Appendix R to 10CFR50. This appendix is xpected to be submitted prior to May 1, 1982.

(7) Core Thermocouple Readouts in the Control Room (TMI Action Item II.F.2 in NUREG-0737) - Discussion of this item should address how core thermocouple readouts are provided in the control room including location and rate of printout (see Part (4) of Attachment I to Item II.F.2). Additional information on this

Item is provided in the Safety Evaluation Report Related to the Operation of La Salle County Station, Units 1 and 2, NUREG-0519.

STATUS

SUMMARY

Our review of this issue is provided as part of our TMI evaluation outlined in Appendix 1A. GSU endorses the BWROG position on this issue, and as a member of the BWROG, is working toward a final resolution. FSAR revisions will be provided as they are developed.

(8) Preservice and Inservice Inspections - Staff guidance in this review area has been sent to a number of pending OL applicants.

A copy of that guidance is provided as Enclosure 9.

STATUS

SUMMARY

This guidance will be utilized in development of the River Bend Station preservice and inservice inspection programs.

(9) Preservice Inspection and Testing of Snubbers - The staff has recently established requirements to ensure snubber operability which have been transmitted to pending OL applicants. A copy of those requirements is provided as Enclosure 10.

STATUS

SUMMARY

This guidance is currently under evaluation for use in the development of the River Bend Station preservice and inservice inspection programs identified in Item 8.

(10) Containment Integrity Regarding Ability to Withstand a Hydrogen Detonation - Staff requests for detailed analysis and results regarding this issue have been sent to a number of OL applicants.

A copy of that request is provided as Enclosure 11.

STATUS

SUMMARY

This guidance was previously provided by Mr. R. L. Tedesco's letter to our E. L. Draper dated March 30, 1981. Any FSAR changes required will be provided following completion of the program identified in our letter dated June 22, 1981.