ML19261B205

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Summarizes 790123 Meeting Held to Discuss Containment Liner Weld Channels at Facility.Nrc Requested Util Formally Document Info Presented Orally.Supporting Documentation Encl
ML19261B205
Person / Time
Site: Beaver Valley
Issue date: 01/29/1979
From: Wiggington D
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
TAC-11055, NUDOCS 7902140166
Download: ML19261B205 (25)
v • d • e


Text

.

f UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20565

$g" T f 8 January 29, 1979 Docket No. 50-334 LICENSEE: Duquesne Light Company FACILITY Beaver Valley Power Station, Unit No.1

SUBJECT:

MEETING SUFMARY - CONTAINMENT LINER WELD B0XES (CHANNELS)

The licensee with its architect engineers for Beaver Valley Unit No.1, the Stone and Webster (S&W) Company, met with the NRC staff on January 23, 1979 to discuss the containment liner weld channels at the Beaver Valley Power Station (BVPS), Unit No. 1.

See Attachment 1 for the attendance list.

Background

On December 5,1978, we met with the licensee to discuss containment leak testing with the containment liner weld channels unvented during the integrated leak rate testing (ILRT).

(For more complete details, see " Meeting Sumary - Containment Liner Weld Boxes (Channels)"

dated December 21,1978.) At that meeting, the licensce was told that unless additional information can be developed to otherwise demonstrate the integrity of the channel boxes and pipe thread plugs we would be giving consideration to (1) requiring limited testing of some of the channel box / liner seam weld barriers during the next refueling outage, (2) requiring replacement of all existing threaded (and plugged) holes in the liner seam welds (those with channel boxes outside containment) with qualified filler welds during the next refueling outage, and (3) venting of all reasonably accessible channel boxes during the next ILRT. The integrity of the repaired liner seam welds could be established by a pressure test before sealing the threaded holes and by applying a pressure / vacuum test on the filler welds.

Meeting Summary Subsequent to the meeting on December 5,1978, we developed a preliminary request for information (see Attachment 2) based on the licensee's oral request to present additional information that would demonstrate the integrity of the channels as a leakage barrier. Attachment 2 was used at the January 23 meeting as a guide for the licensee's presentation. The licensee's position continues to be that the channels are not load carrying members, were designed, fabricated, and installed to a comparable level of confidence as the liner seam welds, and were originally tested to static pressures in excess of that 7 9 0 214 01 (oCo

e Meeting dummary for Duquesne Light Company Jan 'ary 29, 1979 required by the ILRT. To support the licensee's position, S&W has analyzed the channel boxes for loss of coolant accident (LOCA), seismic, and other loads and provided oral responses with visual aids (see Attachment 3) to Attachment 2.

The discussion centered on condensation / corrosion, structural integrity, fabrication / construction /

testing, and surface treatment of the liner, the seam welds and the channel boxes.

The following procedures were referenced in the discussions and are part of the records on the construction and testing procedures main-tained by DLC for the Beaver Valley Power Station, Unit No.1:

  • Radiographic Examination Procedure for ASME Section III, Class A and B Construction, Revision 3/24/69
  • Leakage Detection Test (Br Graves), R:"hion 5/11/70
  • Procedure Specification for Shieldea Metal Arc Welding, Revision 11/3/71
  • Procedure Specification for Metallic Arc Welding Manual Method, dated 6/17/69 At the conclusion of the meeting, we requested DLC to formally document the infomation presented orally and submit it for our review. DLC was further requested to emphasize and elaborate on four areas. These are the cleanliness of all areas inside the channel boxes; the basis for structural integrity of the fillet welds holding the channel boxes on tne liner; the stress analysis of the channel boxes including an outline of the analysis, the resulting calculated stresses and the bases for concluding that an acceptable margin exists in all cases; and plug leak tightness including measures which assure continued leak tightness.

The formal documentation was requested of DLC to allow time for the staff review and evaluation before the BVPS Unit No.1 refueling (now scheduled for April 1979). DLC expected to be able to submit documentation to us the first week of March 1979 provided S&W input is received in 30 days.

"w Dave Wigginto, roject Manager Operating Reactors Branch #1 Division of Operating Reactors Attachments:

As Stated

Meeting Sumary for 3-January 29, 1979 Duquesne Light Company Docket File NRC PDR Local PDR ORBI Reading NRR Reading H. Denton E. Case V. Stello D. Eisenhut B. Grims D. Davis D. Ziemann P. Check G. Lainas A. Schwencer R. Reid T. Ippolito V. Noonan D. Brinkman D. Wigginton OELD OI&E(3)

ACRS (16)

C. Parrish NRC Participants TERA J. R. Buchanan Licensee I

ATTACHMENT 1 CONTAINMENT LEAK TEST WITH CONTAINMENT LINER WELD CHANNELS UNVENTED Meeting January 23, 1979 between the Nuclear Regulatory Commission, Duquesne Light Company, and Stone and Webster.

DLC NRC J. J. Carey D. Wigginton G. W. Moore D. Becknan J. C. Higgins S&W H. J. Wong S. B. Hosford J. J. Healy Y. Huang J. R. Cavollo D. Neighbors A. L. VanSickel R. E. Lipinski J. J. L. Kennedy E. A. Reeves Otto Drolshagen S. Brown D. T. King J. Shapaker J. J. Moran R. E. Shewmaker C. F. Grochmal B. C. Buckley F. Almeter Others H. F. Conrad M. J. Holley, Jr.

A. Schwencer Robert Factora Richard LaRhette Eugene S. Grecheck David L. Benson John R. Weeks

ATTACHMENT 2 PRELIMINARY Information Request on Containment Liner Channel Boxes A.

Wall Boxes In order to determine the acceptability of these channel boxes as part of the containment leakage barrier, the following information and analyses are requested.

1.

Materials Identification and Construction Procedures Provide the details of the materials used and procedures for construction for all wall boxes and specify, by elevation or location, where differences occur. Provide procedure 205 used in the welding of horizontal and vertical test channels.

Provide the procedures for welding the test connection to the channel boxes and the procedures for tightening (torquing) the plugs.

2.

Testing and Inspection Provide identification of the channel welds that were tested (pressure and non-destructive examination, e.g., penetrant or mag-particle testing) and the procedures used in the test.

List and describe any deviations from Reg. Guide 1.19 (listed as Safety Guide 19 in Beaver Valley Unit No.1 Final Safety Analysis Report). Describe the testing, if any, of the leak lightness of the installed plugs.

3.

Structural Integrity of Channel Boxes (For Mairtaining Leak Tightness Provide an analysis which would demonstrate that the channels and channel welds will be capable of carrying the differential movement or expansion of the liner. Consider liner buckling or bulging due to Loss of Coolant Accident (LOCA) temperature and dynamic pressure effects and seismic loads. Provide a comparative analysis to demonstrate leak channels and their welds meet the requirements of the ASME Boiler and Pressure Vessel Code Section 3, Div. 2 as appropriate.

. 4.

Surface Treatment Describe the surface treatment to the inside walls of the containment on the wall channels, plugs, and liner. Pro-vide details of application, inspection, periodic mainten-ance, and surveillance. Describe any treatment to the liner, welds, and interior of the channel boxes.

5.

Condensation and Corrosion Inside Boxes For plugged boxes with an undetected failed box weld or loose plug, provide analysis of condensation inside the box, chemical analysis of any condensed liquid, and corrosion rates of the liner, welds and channel boxes inside the boxes.

6.

Surveillance and Removal of Failed Boxes Describe the surveillaace for failed channel boxes and loose plugs and provide procedures for removal of damaged boxes, inspection and testing of the uncovered liner seam weld, and preparation of the exposed liner surface.

8.

Dome Boxes In order to determine the acceptability of the dome configuration as a containment leak barrier for the service life of the plant, the following information and analyses are requested.

1.

Materials Identification and Construction Description Provide as-built descriptions and drawings of the dome channel details specifically the plug assembly in the liner seam welds.

Provide construction assembly procedures and address the immediate surroundings of the channel boxes on the exterior of the liner.

Provide the basis for assuming these channel welds will hold against the shear forces if the liner moves against the concrete structure.

. 2.

Testing and Inspection Provide the procedures for tightening the plugs, including any torquing requirements, and subsequent testing for leaks around the plug.

3.

Structural Integrity of Dome Seal with Plug Provide an analysis of the ability of the seal welds in the dome with plugs to withstand LOCA dynamic pressures and temperature effects and seismic loads.

If the analysis does not support welds with pl,ugs in place, provide procedures for weld replacement of plugs, inspection and testing.

4.

Dome Surface Preparation and Protective Coating Provide the details of the coating on the dome including the surface preparation, construction application, and any testing or qualification of the coating to withstand operational atmospheres and LOCA dynamic pressures and temperatures. Pro-vide information on the coating adhesion to the dome liner, welds, and specifically, the plugs. Provide an ane'ysis of the coatings' ability to seal leaks and provide anti-rotational fix on the dome plugs. Describe the surveillance requirements on the dome coating to assure its integrity.

C.

Floor Mat Boxes Assuming nothing further is done to the boxes beneath the floor and on top of the mat liner, the following information is requested.

1.

Describe the provisions to prevent water seepage thru the plugs or plug extensions into the channel boxes. Describe the surveillance procedures in effect or contemplated to assure the plugs or extensions remain intact.

NOTE:

In all of the above where procedures are requested but may not exist, describe the information or process in sufficient detail to permit NRC evaluation.

ATTACHMENT 3 CONTAINMENT STRUCTURE BEAVER VALLEY POWER STATION-UNTT NO.1 DUQUESNE LIGHT COMPANY UNER PLATE TEST CHANNEL LMATERIAL SPECIFICATION.

(el EL 690'-II" TG 720"-11" ASTS-A537, GR. 9 ASTN-AT31, GR. C (SliELL)

QUENCHED & TEMPERED IMPACT TEST ON THE A80VE-INN NOTT-50

  • F N/A CHEMICALS AND PHYSICALS YES YES (b) EL 720'-11" TO 813' (SHELL ASTM-A516, GR. 60, FINE ASTM-A131, GR.C DOME AND BOTTOM PLATEl GRAINED AND NORMAUZED IMPACT TESTS MIN NOW-20'F N/A CHEMICALS AND PHYSICALS YES YES
2. WELDING (s) METHOD FULL PENETRATION BUTT FILLET (b) CODE (WELDING QUAUFICATIONS) 80lLER & PRESSURE VESSEL BOILER & PRESSURE CODE, SECT. IX, SEC.ll!

YESSEL CODE, SECT. IX, SEC.111 (c)

PROCEDURE NO. (SHELL RING 4) i - VERTICAL 205 205 2 - HORIZONTAL 13T 205

3. TESTING AND INSPECTIONS (a) VISUAL - 100%

YES YES (b) MAG. PARTICLE NO.

N0 (c) DYE PENETRANT-100 o YES YES (d) RADIOGRAPH - 2% (R.US FIRST PARA. UW52, SECT Ylli N/A 10 FT EACH WELDER R)R EACM PRESSURE VESSEL CODE POSITION-l0O %)

(e) AIR PRESSURE TEST-50 PSI YES YES (f) HALOGEN LEAK TEST-50 PSI YES (A30VE EL 720'-11")

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