ML20084F033
| ML20084F033 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/24/1972 |
| From: | Amish K ROCHESTER GAS & ELECTRIC CORP. |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8304190297 | |
| Download: ML20084F033 (4) | |
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, ;b.( ' um ROCHL S1ER G A5 AND ELECTRIC CORPORATION e 89 EAST AVENUE. ROCHESTER N Y. l.s604
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Dr. Peter A. Morris, Director Division of Reactor Licensing
' ~#j U. S. Atomic Energy Commission
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7920 Norfolk Avenue h0 Bethesda, Maryland 20014 I
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Subject:
Information on Main tReam Header Docket No. 50-244 7\\
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Dear Dr. Morris:
The following report on an in.provement made to the Ginna facility secondary system safety and power operated relief valves is hereby submitted. This information has previously been given orally to your Staff and the Division of Compliance.
At Ginna, each of the two steamlines are protected by four safety valves and one power operated relief valve. The lines are 30 inches in diameter with a design pressure of 1085 peig and a design temperature of 600 F.
Pipe material is A155 GR C55 Class 1 Both the safety valves and the power operated relief valves are mounted perpendicular to the 30 inch line. The eight main steam safety valves have a combined rated capability of 6,380,000 lbs. /hr.
Each power operated relief valve is rated at 380,000 lbs. /hr.
On Friday afternoon, March 17, RG&E h'arned that a stress analysis, performed by Gilbert Associates, of the main steamline safety valve nozzle interface revealed that an undesirable stress l
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Dr. Peter A. Morris and by Sunday, 6:00 a. m., installation was complete. No difficulty was anticipated with the power operated relief valves. However, on Thursday, March 23, Gilbert Associates performed a stress analysis of this pipe-nozzle interface which revealed stress conditions higher than acceptable. Installation of supports similar to those used under the safety valves was complete by 8:00 p. m.
The attached sketches A and B indicate the valve-steamline configuration and the temporary support under the safety and power operated relief valves. Administrative procedure provides for backing cff the jacking bolts when the plant is cooled down, since the bolts are set for the operating condition.
It is planned to perform a permanent modification during our spring 1972 refueling shutdown and to remove the temporary modifi-cation. At present. however, the permanent design has not been finalized.
The supports were conservatively sized for the downward reaction resulting from blowing safety valves. Installation of the supports reduces the total circumferential and longitudinal stresses during blowing to acceptable values.
Very truly yours,
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/ Keith W. Ami Attachment
.i xc: James P. O'Reilly Director, Region I Division of Compliance I
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