ML18024A997
| ML18024A997 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/15/1979 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 7909120031 | |
| Download: ML18024A997 (10) | |
Text
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T~NQQSQK 'VALLEYAUTHORITY l I P t.'Me
'HATTANOOGA.TENNESSEE 37401 400 Chestnut Street Tower II
!0 l.';,'0 l7 Al0: 25 August 15, 1979 Mr. James P. O'Reilly, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region II Suite 3100 101 Marietta Street Atlanta, Georgia 30303
Dear Mr. O'Reilly:
OFFICE OF INSPECTION AND ENFORCEMENT BULLETIN 79 RII:JPO 50-259, 50-260, 50-296 BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 In response to your July 2, 1979, letter which transmitted IE Bulletin 79-14, we are enclosing the results of our investigations at Browns Ferry for item 1.
TVA's response for the plants under construction will be submitted on or before October 30, 1979.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Regulation and Safety Enclosure cc (Enclosure):
Mr. Victor Stello, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Director of the Division of Operating Reactors Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mashington, DC 20555 3o v 90exso>>
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An Equal Opportunity Employer
RESPONSE
TO ITEM 1 OF IE BULLETIN 79-14 FOR BROWNS FERRY NUCLEAR PLANT Attached is a listing of design documents used for Browns Ferry which provided input information for design criteria.
Additional information concerning the seismic analysis and quality assurance documentation can be found in Browns Ferry Nuclear Plant Final Safety Analysis Report, Volume 7, Responses to AEC Questions dated March 25, 1971,
Response
to Questions in Appendices C and D.
For the safety-related piping systems on units 2 and 3, a computerized lit ss rance program provides the documentation records to verify acceptability.
The documentation records resulting from Construct ion d
N BF-47 "Quality Assurance Program for Installation of tl eview at Principal Piping Systems and Documentation, are available for r the site in the records storage area.
For the safety-related piping on unit 1, the above procedure was not 1
however manually-recorded records were utilized.
In view of this, we have instituted an inspection program on t e sa ety-related systems as required by the bulletin.
This will entail taking the as-constructed drawings and inspecting the system to ensure the actual configuration is in accordance with the drawing.
This information will be compared to the design drawings to ensure that seismic consider-ations have been correctly addressed.
The documentation presen et d in the records for BF-47 has not been verified wt nte as i hi h
1 t year.
however controls have been incorporated in the ade to the d
e to ensure that any changes or modifications ma win s original systems undergo the necessary design review and the draw gs reflect the as-built configuration.
This plant procedure is Standard
-A28 "Plant Modifications and Work Plans."
With the existing documentation and controls, we believe that additiona nsp 1 ins ections on units 2 and 3 are not warranted at this time.
The results of the unit 1 inspection program as outlined in item 2 of the bulletin will be submitted within 60 days of the date of the bulletin as requested.
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BROOM FERRY NUCLEAR PLAbT
RESPONSE
TO NRC OIE 79-14 Desi n Information Desi n Document Document Dcscriotion 1.
Identify systems for seismic analysis BFNP Final Safety Analysis Report Volune 7 Responses to AEC Questions dated 3-25-71,
Response
to Question C. 1.
Provides a list of systems or equipment designed to Class I seismic criteria.
2.
Drawings for piping systems to be seismically analyzed a.
TVA drawings Physical piping layout Bills of material Piping flow diagram b.
Vendor drawings Piping and ins rumentation diagrams Valve drawings Equipment drawirgs Drawing Information System (DIS) - BFNP, dated 10-19-78.
Technical Information Center-Manufacturer's drawing list BFNP, dated 7-3-79.
Drawing Information Syste...
(DIS) - Prospect Vendor Drawing List - B":NP, dated 12-3'-78.
Provides a'.list of TVA drawings issued for CONST, co.piete with dr"wing na3er and title, revision
- level, and issue date, the issuing organization and the responsible supervisor within the issuirg organization, nd the construction st"tus.
Provides a list of vendor suppl ied documents sorted by drawing n~-..ber, contract nu.-..ber, descript'on of each doca-..ent and revision level.
Provides a 'ist of vendor crawi".."s so"".ed by cont act nu~ber, dr-.'"..-
n-..ber, and description and revis'on level.
c.
Insulation specifications and drawings Contract 69C58-91180 - Metallic Insulation Contract 71C53-92313 - Non=etallic Insulation Provides a list of systems to be insulated with the applicable
. specifications and scope of insulation coverage.
BRSPi'S FERRY NJCLEAR PLANT
RESPONSE
TO NRC OIE 79-14 Desi n Information Desi n Document T'ocu...en<<Descri.<<ion Documents of Design a.
Design Criteria and Reports BFhP Final Safety Analysis Report Volte 7 Responses to AEC Questions dated 3-25-71,
Response
to Question C.4.
VB-DC-40-31.1 - Design Criteria for Seis-mically QualifyiBg Mechanical and Electrical Equ 'ment Devic es RO da ted 2-28-72.
4B-DC-40-31.2 - Design Criteria for Seis-mically Qualifying Mechanical and Electrical Equipment Assemblies Rl dated 11-12-74 crd Design Input 8'emorand~~
dated 9-23-76.
Q-DC-40-31.12 - Design Criteria for Seis-mic Qualification of Category I and l(L)
Valves and other Inline Fluid System Components Rl dated 9-18-78.
BFN? Final Safety Analysis Report, Yolume 6, Appendix C "Structural Loading Criteria" Revised by Amendment 67.
CE System Design Specification 22A1406 Revision 2 dated 4-28-70 and 22hl406AB, Revision 1 da'ted 7-26-72, Pressure Integrity of Piping and Equipmcnt Pressure
- Parts, BFNP Design Criteria for Supporting Process Instrument Piping and Instrument Air Lines, dated 5-3-71 Revision 0.
Design cr'teria for seismic analysis of safety-related buried piping systems.
Guxdelines for seismic qualification of devices Cuidrlines Cor seismic qualification of asse...biles Guidelines for seismic qualification of valves and other inline fluid sys tern co"...poncnts Defines
...ethods us d, loading con-ditiors and safety margins, an lytical procedures nd results.
Criteria for determining the various loadir.g co-...binations.
A guide for suppor ting process and instrument air lines.
Criteria for Seismically Qualifying Field Run Pipina, dated'1-29-72 Revision 0.
Design criteria to serve as a gute for seismically supporting field fun piping.
BROtPiS FERRY hUCLEAR PLANT
RESPONSE
TO hRC OIE 79-14 Desi n Information 3.
Documents of Design, Continued Desi n Document TVA Specification 9463 for Principal Piping Systems and Appurtenances,
- BFNP, Units 1, 2, and 3 - Contract No. 68C37-91062.
Seismic Inertial Load, Voight Load, and Thermal Load Design Criteria for Small Diameter Class I'iping Systems, dated 5-1-70, Revision 0.
BFNP Earthquake and Dead Load Criteria for Small Diameter Carbon Steel and Aluminum Piping.
Docu..cnt Dcscri tion Design criteria for seismic qualifi-cation of valves.
A guide for the designer in analysis and support of piping systems.
Provides the data necessary to design supports to meet the require-ments for seismic, pressure, dcad-veight without a computer analysis.
Seismic Design of EECV Piping Supports, dated 2-22 71, Rev'sion 0.
A guide for the design and con-struction of Seismic Class I hangers, restraints and anchors for the EECii piping system.
Seismic Design of Containment Inerting System Piping Supports, dated 2-22-71, Revision 0.
EDS Report No. 06-000-02, BFNP Earthquake and Dead Load Criteria for Small Diameter piping, dated 1-10-70.
A guide for the design and ccn<<
struction of Seismic Class I n"ngers, restr"ints, and anchors for thc Containment Inerting Piping Syste...
Criteria for use in.. the design of selected small diameter piping to resist combined seismic and self<<vcight loading conditions.
EDS Users Manual - Seismic Analysis of Three Dimensional Piping Systems, dated.
1-10-70.
EDS computer program (PISOLT)
User's Manual.
Pipe Hanger Design and Engineering-Wcights of Piping Materials, ITT Grinnel Corporation, dated 1968.
Vyights of piping components not-available from vendor drawings.
BR(NNS FERRY NUCLEAR PLANT
RESPONSE
TO NRC OIE 79-14 S.
Documents of Design, Continued Design documents for preparation of i~stallation procedures by CONST Desi n Docunent CEB 76-20., Design Data for Rectangular Support Lug Attachments to Class 2 and 3 Piping Systems,I Revision 1, dated July 1977.
. Design Data for Pipe Attachnents - BFNP, Revision 0, dated 8-12-71.
TVA - BFNP - Report on the Earthquake Analysis of the Reactor Building Floor
Response
Spectra by John A. Blume and Associates, Engineers, dated 7-13-67, TVA.
BFNP - Diesel Generator Building Far hquake Analysis, dated 2-6-69.
Construction Specification No. G Support-and Installation of Piping
~ Systems in Category I Structures, Revision 4, dated 4-'-79.
Docu-...cnt Description Provides design data for selecting rectangular support lugs vhich vill meet the stress requirements of the qualified pipe.
Design information << Support lug attachments for axial and radial loads.
Provides acceleration response spe input data for analysis.
Provides acceleration response spectl inp.t data for z-..zlysis.
This specif'cation estab'ishes mir~wt recuirc-...cnts for the s pport and installation of p'ping systems in Categcry 1 struc" res to assure that the piping is ir.stalled in suc.".
a manner as to val date the analyses of the piping systems and ensure conformance vith the intended design support scheme.
his specificati(
also provides installation and fabrication tolcrances fcr pip'ng ard supports.
Construction Specification No. G-32 for Bolt Anchors Set in Hardened
- Concrete, revision 5, dated 7-21-77.
General Construction Specification G-28 for Construction of Piping Systems for BWR Nuclear Polar Plants, Revision 5, dated 1-22-79, Describes thc qualification, instal-lation and testing of anchors installed in nuclear plant Category I Structures.
r Defines the general requirements for construction,
- testing, and inspection of.piping systems.
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MSM FERRY NUCLEAR PLANT
RESPONSE
TO NRC OIE 79-14
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Desi Information Documentation foz control of changes Desi n Docunent Engineering P"ocedure EN DES-EP 1.26-Nonconformances
- Reporting and Handling by EN DES, Revision 2, dated 11-8-78.
f Engineering Procedure EN DES-EP'4'02-Handling of Engineering Change Notices (TVA-ECN), Revision 8, dated 7-6-78.
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Engineering Procedure EN DES-EP 4.03-Field Change
- Requests, Revision 3, dated 2-7-79.
Docu...ent Doser i tion Provides a system for recording and controlling charactezistics of hardware and/or'nformation which are found to.be not in conformance with prescribed require-...cats and applies to all structures,
- systems, components, and activities in the scope of the EN DES QA program.
Provides a method of initiating and processing engineering changes by means of an Ergi"..cering Change Koti~
(ECN).
This procedure provides the TVA engineering, construction, and plant operating divisions with a concise scope 0
an C.,g neerln3 charge in a imcly manner.
Provides a method of processing requests for charges from the TVA Construction {field) and plan" operating divisions that affect approved TUA and/oz ven"or drawings or documents that have been released for construction.
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