ML17256A768
| ML17256A768 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/09/1983 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8306170032 | |
| Download: ML17256A768 (4) | |
Text
REGULATORY (FORMATION DISTRIBUTION "S M (RIDS)
-AOCBSSION NBRse306170032
,DOC.DATEs 83/06/09 NOTARI'ZED:
NO DOCKET FAGIL:.50 '244 'Robert Emmet Ginna Nuclear tPlanti Uni,,t fi Rochester G
05000244 AUTH BYNAME AUTHOR A F F ILIATI ON MAIERgJ,'E ~
Rochester "Gas 8.Electric Corp'RBC IP ~ NAME i RECIPIENT AFFILIATION GRUTCHF IElDi D ~
Operating Reactors Branch,.5 SUBJECTs Discusses NRC 830428 ltr re 'blocking of <<safety injection signal: during cooldown ~ Tech 'Specs. will be submitted to reflect-clarification of permissible bypass conditions.No
'Tech Spec'Mod required for steam line isolation.
DISTRIBUTION lCODE s A001S COPIES 'RECEIVED s L'TR,
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OR Submittal!
General Distribution NOTESsNRR/DL/SEP fcy, 05000244 RED IP IENT
.ID CODE/NAME,.
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~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAIER Vice President TELEIPRONE ARE* cooE 7IE 546.2700 June 9,
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:
Blocking of Safety Injection Signal During Cooldown (Letter LS05-83-04-072 dated April 28, 1983)
R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
The enclosure to the above-referenced letter contained two comments regarding the Ginna facility Technical Specifications.
Review of the Technical Specifications has resulted in the conclusion that clarification of the permissible bypass conditions for the Safety Injection functions is in order.
Specifically, "permissible bypass conditions" should be shown for "Steam Generator Low Steam Pressure/
Loop" and "Pressurizer Low Pressure".
A permissible bypass condition should not be shown for "Manual" or for "High Containment Pressure".
A change in Technical Specifications will be submitted to you in the near future to reflect the above.
2.
Table 3.5-3 is correct in indicating no conditions under which Steam Line Isolation can be bypassed.
The safety injection signal can be bypassed as indicated in our response to your first comment.
Since this bypass is listed elsewhere in the technical specifications,
- however, we consider it inappropriate to list it in Table 3.5-3.
- Thus, no change to the Technical Specifications will be proposed concerning this item.
Very truly yours, J
n E. Maier
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