ML19257A268
| ML19257A268 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/13/1979 |
| From: | Hancock J FLORIDA POWER CORP. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| IEB-79-13, NUDOCS 8001030463 | |
| Download: ML19257A268 (3) | |
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Florida Power C 0 R 6 J R A T IO N December 13, 1979 File:
3-0-3-a-3 Mr. J. P. O'Reilly, Director U.S. Nuclear Regulatory Commission Office of Inspection & Enforcement 101 Marietta Street, Suite 3100 Atlanta, GA 30303
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 IE Bulletin 79-13, Revision 2 CRACKING IN FEEDWATER SYSTEM PIPING
Dear Mr. O'Reilly:
Enclosed please find our response to Item 2 of IE Bulletin 79-13, Revision 2.
Should you have any questions concerning our response, please contact this office.
Very truly yours, FLORIDA POWER CORPORATION Patsy Y. Baynard/for J. A. Hancock Director, Nuclear Operations PYBemhF03
""89 1668 337
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M General Office 3201 Tnirty fourtn street soutn. P O Box 14042. st P te rg. Flonda 33733 813 - 866-5151 8001030 b
RESPONSE TO IE BULLETIN 79-13, REVISION 2 Item 2a:
For steam generator designs with a common nozzle for both main and auxiliary feedwater systems, perform volumetric examination of the feedwater nozzle-to pipe welds, the feedwater piping welds to the first support, and the feedwater line-to-containment penetration welds in accordance with Item 1 above.
In addition, examine an area of at least one pipe diameter of the main feedwater line downstream at the auxiliary feedwater to main feedwater connection.
Response
The steam generator at Crystal River Unit 3 Nuclear Plant is not designed with a common nozzle for both main and auxiliary feedwater systems.
Item 2b:
For steam generator designs utilizing auxiliary feedwater systems connected by means of welded nozzle connections, perform volumetric examination of all auxiliary feedwater nozzle-to piping welds and the first adjacent outboard pipe-to pipe welds (risers) in accordance with Item 1 above.
For designs utilizing auxiliary feedwater systems connected to the steam generator by means of bolted flange connections, perform volumetric examination of the flanged nozzle to piping and first outboard pipe-to pipe welds (risers) in accordance with Item 1 above.
The examinations specified in 2.b above are not required provided that during startup, hot standby or cold shutdown operations, the feedwater level within the steam generator is maintained essentially constant and no intermittent cold auxiliary feedwater injection is utilized, i.e., auxiliary feedwater injection where used, is preheated during the forementioned operating modes.
Response
Item 2b, paragraph 3, eliminates the requirement for volumetric examinations of steam generator auxiliary feedwater piping for plants which maintain feedwater level in their steam generators essentially constant and do not intermittently inject cold auxiliary feedwater during start-up, hot standby or cold shutdown operations.
It can be interpreted that intermittent auxiliary feedwater injection does not apply to emergency and cold shutdown valve testing per ASME Section X1 functions.
At Crystal River Unit 3 Nuclear Plant, auxiliary feedwater injection occurs only during an emergency actuation and the performance of cold shutdown testing of FW valves per ASME Section XI.
Therefore, the volumetric examinations are not to be performed.
PYBemhF03 lhh8 338 DN89
RESPONSE TO IE BULLETIN 79-13, REVISION 2 (Continued) 4 Item 2c:
Perform a visual inspection of cl1 feedwater system piping supports and snubbers in containment to verify operability and conformance to design.
Response
The inspection of feedwater system piping supports and snubbers has been satisfied by the seismic hanger incpections per lE Bulletin 79-14, SEISMIC ANALYSES FOR AS-BUILT SAFETY-RELATED PIPING SYSTEMS.
1668 339 PYBemhF03 DN89
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