ML17255A237
| ML17255A237 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/20/1983 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0821, RTR-NUREG-821, TASK-03-05.B, TASK-3-5.B, TASK-RR NUDOCS 8307260445 | |
| Download: ML17255A237 (6) | |
Text
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'AOGBSSION,,NBR; 8307260445 DOC ~ DATE; 83/07/20 NOTAR1ZED:,,tlO DOCKET
.FAGIL!50 '244 Robert-,Emmet<<>Ginna Nuclear
<<Pl anti Uni~t ii Rochester
'G 05000244 AOTHiNAMK<<AUTHORAFFILIATION MAIERrJ,E,
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'8 )El ectric >Corp, REC I'PiNAME REC IP IKNT AFF ILI'ATION
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Oper ating Reactors Branch
'.5 SUBJEOT: 'Proposes mod-,.to commi:tment made<< in.NUREG 0821>>per'SEP
)Top'ic III<<.5' tto protect. main >steam -safety 8 <<iTelief val.ves
.from'ef'fects of block>.wal 1'.failures,Bod.would <<ensune'>st>ructural
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ROCHESTER GAS AND ELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER. N.Y. 14649 JOHN 6 MAILER Vice President TCI.CPHONC AlICA CODC Vld 546.2700 July 20, 1983 Director of Nuclear Reactor Regulation Attention:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
SEP Topic III-5.B, Pipe Break Outside Containment (IPSAR Section 3.3.1.1)
R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
As noted in Section 3.3.1.1 of NUREG-0821, the R.
E. Ginna Integrated Plant Safety Assessment
- Report, December
- 1982, RGaE had committed to protect the main steam safety and relief valves from the effects of block wall failure.
RGGE has made a preliminary investigation of the conseguences of such an occurrence, and proposes a modification to our commitment.
Our analysis indicates that damage to the main steam safety and relief valves would not prevent safe
- shutdown, as long as the main steam isolation valves remained operable, and auxiliary feedwater flow could be maintained to the steam generators.
Ig such an event, the total break area would be approximately 2 ft
, which is substantially smaller than the design basis steam line break area of 4.37 ft Thus, reactor coolant system pressure, temperature, and reactivity responses are considered to be enveloped.
Auxiliary feedwater would be provided by the Standby Auxiliary Feedwater System (operator action time of 10 minutes is assumed).
Other emergency functions, such as Safety Injection System actuation, would be unaffected by damage to the Intermediate Building.
Auxiliary feedwater injection, with relief through the openings in the steam lines, would continue until the RHR system could be placed into operation, at which time normal cooldown to cold shutdown could commence.
In order to ensure safe 'shutdown capability in the event of the block wall failure in the Intermediate Building, RGaE thus proposes the following actions:
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ROCHESTER GAS AND ELECTRIC ORP.
DATE July 20, 1983 Mr. Dennis M. Crutchfield SHEET NO.
1) ensure that the main steam lines and feedwater lines would not lose their structural integrity 2) protect the main steam isolation valves, and accessories, as needed, to ensure operation, 3) protect the normal motor-driven and turbine-driven auxiliary feedwater connections to the main feedwater
- lines, up to and including the check valves.
This will ensure that standby auxiliary feedwater, which connects to the feedwater lines inside containment, would be routed to the steam generators.
RGGE proposes to perform the necessary analyses and modifi-cations in conjunction with our Structural Upgrade
- Program, which is presently being reviewed by the NRC.
Very truly yours, John E. Maier
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