ML20196C977
| ML20196C977 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 02/09/1988 |
| From: | Callan L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Goldberg J HOUSTON LIGHTING & POWER CO. |
| References | |
| NUDOCS 8802160300 | |
| Download: ML20196C977 (2) | |
Text
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In Reply Refer To:
FEB 9 1988 Dockets:
50-498/87-70 50-499/87-70 Houston Lighting & Power Company ATTN:
J. H. Goldberg, Group Vice President, Nuclear P.O. Box 1700 Houston, Texas 7701 Gentlemen:
Thank you for your letter of January 15, 1988, in response to our letter and Notice of Violation dated December 17, 1987.
We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation.
We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintained.
Sincerely.
Original Signed Dy.
A.B. Ucach L. J. Callan, Director Division of Reactor Projects cc:
Houston Lighting & Power Company ATTN:
M. Wisenberg, Manager Nuclear Licensing P.O. Box 1700 Houston, Texas 77001 Houston Lighting & Power Company l
ATTN: Gerald E. Vaughn, Vice President Nuclear Operations P.O. Box 1700 Houston, Texas 77001 IV:DRP/D D P/
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R. L. Range /R. P. Verret P.O. Box 2121 Corpus Christi, Texas 78403 City _Public Service Board ATTN:
R. J. Costello/M. T. Hardt P.O. Box 1771
' San Antonio, Texas
-78296 City of Austin ATTN:
M. B. Lee /J. E. Malaski P.O. Box 1088 Austin, Texas 78767-8814 Texas Radiation Control Program Director bec to DMB (IE01) bec distrib. by RIV:
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?,3 January 15, 1988 ST-HL-AE-2468 File No.: G2.4 10CFR2.201 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 South Texas Project Electric Generating Station i
Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Response to Notice of Violation Houston Lighting & Power Company has reviewed Notice of Violation 87-70-02 dated December 17, 1987 and submits the attached response pursuant to 10CFR2.201.
If you should have any questions on this matter, please contact Mr.
J. S. Phelps at (512) 972-7071.
k J. H. Gold er6 Group Vice Pre ident, Nuclear JSP/hg
Attachment:
Response to Notice of Violation 87-70-02 i
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'o ST-HL-AE-2468 Hous.. ton Lighting & Power Wny Fils No.: G2.4 Page 2 cc:
Regional Administrator, Region.IV Rufus S. Scott Nuclear Regulatory Commission Associate General Counsel 611 Ryan Plaza Drive, Suite 1000 Houston Lighting & Power Company Arlington, TX 76011 P. O. Box 1700 Houston, TX 77001 N. Prasad Kadambi, Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 Dan R. Carpenter Senior Resident Inspector / Operations e/o U.S. Nuclear Regulatory Commission P. O. Box 910 Bay City, TX 77414 Claude E. Johnson Senior Resident Inspector / Construction c/o U.S. Nuclear Regulatory Commission P. O. Box 910 Bay City, TX 77414 J. R. Newman, Esquire Newman & Hcitzinger, P.C.
1615 L Street, N.W.
Washington, DC 20036 R. L. Range /R. P. Verret Central Power & Light Company P. O. Box 2121 Corpus Christi, TX 78403 R. John Miner (2 copies)
Chief Operating Officer City of Austin Electric Utility 721 Barton Springs Road Austin, TX 78704 R. J. Costello/M. T. Hardt City Public Service Board P. O. Box 1771 San Antonio, TX 78296 Revised 11/20/87 L4/NRC/mp__
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January 15, 1988 Attach ~ ment ST-HL-AE-2468 File No.: G2.4 i
Page 1 of 2 i
Response to Notice of Violation 87-70-02 I. Statement of Violation An NRC inspection conducted from October 18, 1987 through November 20, 1987 (Inspection 87-70), identified a violation of NRC requirements. The violation involved the failure to translate design requirements, j
"Criterion III of Appendix B to 10 CFR Part 50 requires that the design basis be correctly translated into specifications, drawings, j
procedures and instructions.
This requirement is amplified by the approved Quality Assurance Program Description (QAPD) of South Texas Project (STP).
Contrary to the above, Westinghouse Spent Fuel Storage Rack Installation Precedure 2463A82 did not correctly incorpornte a design basis requirement.
Specifically, the procedural method described causes the bolt / nut combinations securing the rack to the floor to achieve a torque value of only 25-50 foot pounds whereas the design specification requires that a value of 1100 foot-pounds be achieved.
This is a Severity Level IV violation."
II. Reason for Violation The original design of the in containment fuel storage racks used bolt preloading on the support pads so that the shear force at the rack base could be absorbed by all four supports in a seismic event. As a result, a high torque value (1100 ft-lbs) was calculated to achieve the desired safety margin.
In order to achieve this torque value, the installation procedure was written to require a specific amount of angular rotation which, after applying the initial bolt torque, would provide the bolt preload assumed by the design calculation.
In actuality, the initial bolting torque of 25 ft lbs specified by the procedure resulted in an inadequate starting point for the subsequent angular rotation. Westinghouse has stated that use of this "Turn of the Nut" method is inappropriate where a set pretension is required by design.
For this reason, the installation procedure did not achieve the torque value of 1100 ft-lbs assumed in the calculation.
III. Corrective Action Taken and Results Achieved As described above, the original calculation utilized assumptions which caused a high torque value to be necessary to achieve the desired safety margin.
Westinghouse has performed a reanalysis assuming a bolt preload L4/NRC/mp
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January 15, 1988 Attcchm:nt ST HL AE-2468 d
File No.: G2.4 Page 2 of 2 1
resulting from an applied torque of 25 ft-lbs which, in a seismic event, would result in reacting the base moment with 2 bolts in tension and two pads in compression with the shear force applied to the two compression pads. This reanalysis demonstrated that an adequate margin of safety exists on the structural components.
IV. Corrective Steps Taken to Prevent Recurrence As stated above, the torque value actually achieved utilizing the installation procedure has been shown to be acceptable.
Listed below are corrective steps taken:
1.
Review of other field-erected equipment installation procedures has been conducted by Westinghouse.
Equipment installation procedures for the fuel handling machine, refueling machine, fuel transfer system and reactor internals were reviewed. The review identified that the torque values for bolted joints requiring preload have been specified in the installation procedures as required by design calculations. Also, the "Turn of the Nut" method is not used in these procedures.
2.
HL4P engineering has reviewed the Westinghouse reanalysis and has verified that an adequate margin of safety exists for the installed fuel racks.
3.
HLAP Quality Assurance is performing a independent review of selected Westinghouse installation procedures to determine that torque values for bolted joints requiring preload have been specified as required by the design of the Westinghouse supplied equipment.
This review will encompass installation procedures not included in the Westinghouse sampic.
This action will be completed by February 26, 1988.
This problem is not applicable to the racks installed in the spent fuel storage pool.
The spent fuel pool utilizes the fourteen-inch spaced (center-to center) free standing racks for which no anchor bolt torquing is required.
V. Date of Full Compliance STP is presently in full compliance.
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