ML20137W374

Responds to 851030 Request for Analysis of Main Steam Pipe Vibration & Description of Proposed Pipe Mod.Forwards Wyle Test Data for Main Steam Safety Valves & Re Analyses & Encl W/Drawings of Proposed Design Change

ML20137W374
Person / Time
Site:	Davis Besse
Issue date:	11/30/1985
From:	Williams J TOLEDO EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
1217, TAC-59419, TAC-59425, NUDOCS 8512100232
Download: ML20137W374 (12)

Text

.- -o Docket No. 50-346 TOLEDO License No. NPF-3 EDISON Serial No. 1217 JOE WituAMS, JR Smur Vce Presders-Nudvar November 30, 1985 [*j$js Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

NRC letter dated October 30, 1985 (Log 1844) requested additional inform-ation regarding main steam piping. Specifically, Question No. 5 requested:

" Provide an analysis of main steam pipe vibration due to dynamic loadings such as steam hammer, particularly as it affects main steam safety valve, atmospheric vent valve, and main steam isolation valve operability of proposed piping modifications."

Toledo Edison's response dated October 30, 1985 (Serial No. 1208) committed to providing the analysis of main steam pipe vibration and a description of

_ proposed piping modification. This letter is in response to that commitment.

Main Steam Line A exits Steam Generator No. 2 (SG-2) and Main Steam Line B exits Steam Generator No. 1 (SG-1). Operation and maintenance data indicated more wear and setpoint drift occurred in the Main Steam Safety-Valves (MSSVs) of Line A when compared to Line B. The setpoint deta from Wyle Laboratory (attached) is consistent with this drift.

Toledo Edison has evaluated this data and determined a mod:'.fication to Line A is appropriate to be consistent with the dynamic cha m ceristics of Line B. The proposed piping modification consists of the addition of a 5" hydraulic shock suppressor (snubber) between PSV SP17Al and PSV SP17A7.

These valves are the second and third MSSVs from the turbine on Line A.

This snubber will be installed prior to restart.

Analyses of the lines with the proposed design change to Line A, SG-2 result-in almost identical natural frequencies of 13.55 Hzs. The attached letter (BT-15977) from Bechtel to Toledo Edison dated November 20, 1985, discusses these analyses and provides drawings of the proposed design change (FCR 85-224).

Very truly yours, Joe WAA A j JW:RRS:m3 8512100232 851130 PDR P

ADOCK 05000346 PDR l [ l g ec: DB-1 NRC Resident Inspector ,

THE TOLEDO EDISON COMPANY ED! SON PLAZA 300 MADISON AVENUE TOLEDO OHIO 43652 i

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Wyle Test Data g g Valve P i P2nition Parameter Run 1 Run 2 Run 3 Run 4 Rua 5 Rua 6 Leakage Disposition 1 Disc lift 1.16 0.20 1.16 1.18 Al Setpoint 1024- 995 993 1009 No Leakage Rebuild

, Blowdown 3.8 NH 1.1 2.8 i

j Dise lift 1.06 1.06 1.04 -

{ A2 Setpoint 1020 1025 1015 Yes Rebuild Blowdown 4.3 19.0 2.7

, Disc lift 1.13 1.14 0.25 1.14 A3 ./ Setpoint 1025 1020 1031 1025 No Leakage Rebuild Blowdown 1.3 2.5 NH 1.8 Dise lift 0.62 1.12 1.12 1.12 A4 ., Setpoint 1014 1015 1006 1005 No Leakage Rebuild Blowdows NH 5.3 5.7 5.2 Dise lift 1.15 1.14 1.16 NM 1.14 51 Setroint 1042 1941 1044 1044 1040 Yes Rebuild Blowdown 4.6 4.5 5.2 5.2 19.7 Disc lift 1.12 1.09 1.10 1.09* 1.10 1.10 82 Setpoint 1051 1037 1037 1042 1043 1949 No Leakage Passed Blowdown 4.8 3.2 2.7 2.6 2.8 3.1 ,

Dise lift 1.16 1.20 1.20 1.20 83 Setpoint 1974 1070 1977 1970 Yes Rebuild Blowdown 1.8 2.8 2.4 3.4 r

,l Disc lift 1.20 1.20 1.18 B4 Setpoint 1080 1071 1969 Yes Rebuild Blowdown 3.3 2.5 2.3 All disc lifts in inches All setpoints in psi All blowdown la percent NH Indicates the parameter was not measured

• Compression screw was adjusted one flat clockwise prior to this rua.

5 cm b/40 <

< Bechtel Associates Professional Corporation (Ohio) 15740 Shady Grove Road Please address reply to: Caithersburg, Maryland 20877-1454 301-258-3000 Mr. J. F.. Helle -

NOV 2 0 Igs Director, Nuclear Facility Engineering

The Toledo Edison Company P. O. Box 929 ,

Toledo, Ohio 43652

Dear Mr. Helle:

The Toledo Edison Company Davis-Besse Nuclear Power Station Bechtel Job 12501 FCR No.85-224 MAIN STEAM SYSTEM ,

File: 0270, 1496 BT-15977 (A218)

Main Steam Line B in the Auxiliary Building was reanalyzed per FCR No.85-224 in October, 1985. A snubber in the Z-direction (.similar to line A) was added on the main header between safety valves PSV-SP-17A7 and SP-17A1. A complete FCR package was issued by letter BT-15919 on November 8, 1985.

Mr. R. Kies recently informed us that the safety relief valves on the main steam line have been designed for a first natural frequency of 17 Hz which should be modeled in-the stress analyses to determine if the piping is still within the code allowables. Both steam lines were then reanalyzed with the safety relief valves -

first natural frequency of 17 Hz.

The results of the analyses showed that the first natural frequency had dropped considerably when compared with the previous analyses. This drop was due to the

-change in the model of the safety relief valve. The acceleration input for the excitation of the valves were witL n the design criteria. Both the lines (A and B) 2 had'almost identical first natural frequencies of 13.55 Hzs. and the stresses were -

found to be within the code allowables.

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NOV 2 01985 Mr. J. F. Helle 2 BT-15977 If you have any questions, please contact us.

Very truly yours.

E. J. y ,,

Project Engineer EJR/NT/jil ec: J. K. Wood T. P. Beeler C. T. Daft J. W. Fay, Jr. .

sR. D. Kies Records hanagement - Mail Stop 3021 R. Zeigler 4

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1. STRUCTURAL MEPEERS AND PLATES SHALL BE ASTM A-36 FURNISHED IN ACCORDANCE WITH SPECIFICATION 12501-C-303Q AND FABRICATED IN ACCORDANCE WITH SPECIFICATION 12501-C-403Q.

2. GROUT SHALL BE FIVE STAR NON-SHRINK GR'0UT AS MANUFACTURED BY U. S.

GROUT CORP., FURNISHED IN ACCORDANCE WITH SPECIFICATION 12501-C-401Q AND INSTALLED IN ACCORDANCE WITH THE MANUFACTURER'S WRITTEN INSTRUCTIONS.

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