ML17250B184

Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel (SS) Internal Pre-Load Bolting.... Valves Disassembled & 410 SS Studs Removed & Visually & Liquid Penetrant Examined

ML17250B184
Person / Time
Site:	Ginna
Issue date:	05/29/1990
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
IEB-89-002, IEB-89-2, NUDOCS 9006110350
Download: ML17250B184 (3)

Text

ACCELERATED DEMONS~TION SYSTEM DISTRIBUTION REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9006110350 DOC.DATE: 90/05/29 NOTARIZED: YES DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Responds to NRC Bulletin 89-002, "Stress Corrossion Cracking of High-Hardness Type 410...."

DISTRIBUTION CODE: IE32D TITLE: Bulletin Response COPIES RECEIVED:LTR 89-02 re Cracking g ENCL '0 SIZE:

of Hzgh-Hardness Type 410 Bolting NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA PD1-3 PD JOHNSON,A INTERNAL: AEOD/DOA AEOD/DSP/TPAB NRR/DET/ECMB9H NRR/DET/EMEB9H3 NRR/DOEA/OEABll NRR/DOEA/OGCB11 NRR/DREP/PEPB9D NRR/ DST 8 E2 NRR/EMCB/HERMAN NRR/MCLELLAN,T NRR/PMAS/ILRB12 NRR/ROOD H NRR/SELLERS,D.

RES/DSIR/EIB

~EXILE 02 EXTERNAL: LPDR NRC PDR NSIC NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL

ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE. ROCHESTER, N.Y. 14649-0001 QNc a@~ a ~~g ~

$ >>tj-2 QC~

May 29, 1990 U.S. Nuclear Regulatory Commission Document Control Desk Attention: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555

Subject:

Response to NRC Bulletin 89-02 Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Pre-loaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Design R.E. Ginna Nuclear Power Plant Docket Number 50-244

Dear Mr. Johnson:

NRC Bulletin 89-02 requires each licensee to disassemble and inspect all safety related Anchor Darling Model S350W swing check valves supplied with internal retaining block studs of ASTM specification A-193 Grade B6, Type 410SS. Valves of similar design from other manufacturer's should also be inspected.

Rochester Gas and Electric reviewed all safety related check valves installed at R.E. Ginna Nuclear Power Plant. Ten check valves were identified with A-193 Grade B6, Type 410SS retaining block studs. Four are Anchor Darling Model S350W swing check valves and six are Velan (three. and six inch) primary nuclear swing check valves. All the valves have been disassembled and the 410SS studs removed and visually and liquid penetrant examined.

None of the fasteners displayed any indication of cracking and all are receiving additional metallurgical examinations.

Disassembly and inspections were performed during the 1989 and 1990 annual inspection outages. The inspections were completed May 4, 1990.

The original studs have been replaced with ASTM A-564, TP630 (1100) stainless steel. These 17-4 PH stainless steel studs are heat treated to 1100 degrees fahrenheit, and have been installed, with the respective manufacturer's concurrence, under minor modifica-tions TSR 89-02 and TSR 90-04.

5'006110350 P00=,2~

~Pg(j S~

+DC~CK 0 Q)00244 9 F'DC

Page 2 NRC Bulletin 89-02

~

May 29, 1990 Very truly yours, vMc'obert C. Me redy Division Manager Nuclear Production Subscribed and Sworn before me on this

~

r,( "A day of

/

-.'ir',

LYNN L HAUCK 1990 SAry Ptkae in Ihe State oi New Yora MONROE COUNTY Canrnission Expires Nov. 30, t 9.'r:.;.

xc'.S.Region Nuclear 1

Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 NRC Senior Resident Inspector Ginna Station