ML17254A248
| ML17254A248 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/06/1985 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0821, RTR-NUREG-821, TASK-02-03.B, TASK-03-05.B, TASK-2-3.B, TASK-3-5.B, TASK-RR NUDOCS 8503120493 | |
| Download: ML17254A248 (4) | |
Text
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ACCESSION NBRs8503120493 DOC ~ DRTE! 85/03/06 NOTARI'ZED!'NO
DOCKETI 0 FACIL!50-244 Rober't<<Emmet, Ginna<<Nuclear Pl anti Uni;t: ir Rochester
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KOBERrR AN ~
Rochester Gas 5 Electr ic Cor po RECIP ~ NAMEi, RECIPIENT AFFILIATION ZNOLINSKIrJ ~ A ~
Opei ating Reactors 8'ranch 5
SUBJECT; Discusses-'SEP topics addressed>>
in<< Suppl 1, to NUREG,082)i.
Table 3 ~ irinclqding II 3 BrFlooding Potential"',8 IIIi5 8, "I ipe Break Outside'ontainmeht-;"" Completion date for" Topic I'I 3; 8'hou l 1 be modi fied.
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8P,.::-'LECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 ROGER Wr KOBER IIICERRESIOENT ELECTRIC & STCAM PRODUCTION March 6 I 1985 TCI CIIHONC ARCA COOC Tld 546-2700 Director of Nuclear Reactor Regulation Attention:
Mr. John A. Zwolinskii Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission'ashington, D.C.
20555
Subject:
NUREG 0821I Supplement 1
R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Zwolinski:
The purpose of this letter is to discuss two SEP topics addressed in Supplement 1 to NUREG 0821< Table 3.1I "Integrated Assessment Summary":
II-3.BI "Flooding Potential"I and III-5.BI "Pipe Break Outside Containment".
II-3.B The completion date for the potential Deer Creek flooding modifications is stated to be August 1985 (for the block wall and doors).
Howeveri as discussed during the final resolution of Topic III-2I "Wind and Tornado Loadingsoi all of the flooding modifications are being implemented in conjunction with the Ginna Structural Upgrade Program.
Thusi the completion date for II-3.B should be modified.
III-5.B RGSE committed to provide pipe whip restraints and jet impingement protection for the steam heating line risers on the intermediate floor of the auxiliary building to protect systems required for safe shutdown.
RGGE evaluated the equipment located in the vicinity of the two risers and determined that protection from the postulated effects of the six-inch riser was required.
Proper pipe whip and jet impingement protection was thus installed during 1984.
The two-inch steam riser>
howeveri is not located in the vicinity of any safe shutdown equipment.
Only equipment associated with the boric acid system are located in the zone of influence of the postulated failure of the two-inch steam line.
As determined during the Systematic Evaluation Program (Topic III-4. AI et. al.)I the boric acid system is not required for safe shutdown.
Ratheri the charging pumps from the RWST are used to provide reactivity control for safe shutdown.
Thusi no protection has been required to be provided from the postulated failure effects of the two-inch steam line.
V truly yoursI 8503120493 850306 PDR ADOCK 05000244 P
R er W. Kober
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