ML20101F168

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Submits Final Response to NRC Bulletin 89-002 Re Stress Corrosion Cracking of high-hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor-Darling Swing Check Valves.No Cracking of Retaining Bolts Discovered
ML20101F168
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 06/18/1992
From: Shelton D
CENTERIOR ENERGY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2054, IEB-89-002, IEB-89-2, TAC-M74247, NUDOCS 9206240318
Download: ML20101F168 (2)


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CENTEMOR ENERGY Donald C. Shelton 300 Madison Avenue Vce President.Nuclew Toledo, OH 436520001 Davis Besse (419)249 2300 Docket Number 50-346 License Number NPP-3 Serial Number 2054 June 18,'1992

. United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C. 20555 Subj ect : Closcout of Toledo Edison's Action for NRC Bulletin Number 89-02, " Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350V Sving Check Valves or Valves of Similar Design."

Gentlemen:

On June 14, 1990, Toledo Edison (TE) responded (Seria. 1807)-to NRC Bulletin 89-02.

Toledo Edison reported that no Anchor Darling sving check valves are installed at Davis-Besse in safety-related applications, however, the review identified twelve Velan valves of similar design installed in safety-related systems.

Visual examination of eleven Velan valves during the sixth refueling outage (RFO) in 1990 identified no cracking of the retaining bolts.

-Modifications were also completed on the eleven identified valves as described in Serial 1807.

In addition, Serial 1807 stated that the remaining valve, Component Cooling Vater Valve, CC-91, vas not

-inspected during the sixth-RF0.

In a letter dated May 17, 1991 (Serial'1938) TE justified the deferral of the CC-91 inspection until the eighth RFO. The NRC issued a Safety Evaluation (SE) on June 11, 1991 (Log 3494) accepting the CC-91 deferral and closing NRC Bulletin 89-02 for-Davis-Besse.- The SE required that TE perform a reverse-flov

-test during the seventh RFO.

In addition, the cover letter to the SE stated that TE inform the NRC of the actions regarding valve CC-91 following 8RFO.

During the seventh RF0, emergent work placed the plant in_a condition which allowed lfor.the inspection of CC-91 internals. No cracking of the retaining bolts was found and the valve was reassembled with new bolting material (A193 B6X 410SS).

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.Page 2 Therefore, the requirements for NRC Bulletin 89-02 have been satisfied and TE considers.this issue closed for Davis-Besse.

If you have any questions concerning this. matter, please contact Mr. R. V. Schrauder, Manager - Nuclear Licensing, at (419) 249-2366.

Very truly_yours,

%,CD KAF/ed et:

V. Levis, NRC Region III,'DB-1 Senior Resident Inspector A. B. Davis, Regional Administrator, NRC Region III J. B. Hopkins, NRC/NRR DB-1 Senior Project Manager Utility Radiological Safety Board e

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