ML17262A973
| ML17262A973 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/24/1992 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-80-24, NUDOCS 9209010277 | |
| Download: ML17262A973 (5) | |
Text
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i 'UBJECT: Special rept: on 920810i discovered that B Reactor Compartment Cooling Fan cooling coils developed SW leak.
Work Order package 9201643 developed to perform tube repairi per Procedure EM-745i "Repair of Containment Fan.... "
ACCESSION NBR: 9209010277 DOC. DATE: 92/08/24 NOTARIZED:
NQ DOCKET FACIL: 50-244 Robert Emmet Ginna Nuclear Planti Unit 1>
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05000244 AUTH. NAME AUTHOR AFFILIATION MECREDYI R. C.
Rochester Gas Zc Electric Corp.
AME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
DISTRIBUTION CODE:
ZE22D COPIES RECEIVED: LTR g ENCL g SIZE:
TITLE: 50. 73/50. 9 Licensee Event Report (LER)I Incident Rpt. etc.
NOTES: License Exp date in accordance with 10CFR2I 2. 109'(9/19/72).
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1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO RFDUCE WASTE! CONTACT THE DOCUiz(ENT CONTROL DESK.
ROOM PI-Si (EXT. 504-2065) TC ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF CQPEEB REQUIRED:
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lier Tote sra'st 89 EAST AVENUE ROCHESTER N.Y. 14649-0001 ROBERT C. MECREDY Vice P<esldenl Clnna NuClear PrOduCliOn TELEPHONE AREACODE 71B 546 2700 August 24, 1992 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Service Water Leak Inside Containment R.E.
Ginna Nuclear Power Plant Docket No. 50-244 In accordance vith the requirements of IE Bullet'n No.
SO-24, (Prevention of Damage Due to Water Leakage Inside Containment),
the attached 14 day report is hereby submitted.
Very truly yours, xc:
Robert C.
Mec edy U.S. Nuclear Regulatory Commission Region I=
475 Allcndale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector ggp09$
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++2 2, 9209010277 920824 PDR ADOCK 05000244 S
14 Da Re ort of Service Water Leak Inside Containment PRE-EVENT PLANT CONDITIONS The plant was at approximately 974 steady state reactor power.
Investigations were underway -to determine the source of the decrease in the actuation interval of the Containment (CNMT) sump A Sump pump.
Indications of a possible Reactor Coolant System (RCS) leak were not present; i.e.
no significant. unexplainable increases or changes were observed on radiation monitors R-11 and R-12, (CNMT Air Particulate Monitor and CNMT Radioactive Gas Monitor, respectively),
the CNMT dewpoint, or RCS leakage.
- However, samples of the Containment Sump A water did indicate the possibility of a Service Water (SW)
Leak inside CNMT.
II.
DESCRIPTION OF EVENT On August 10, 1992 at approximately 1930
- EDST, while systematically isolating fan coolers in CNMT investigating for a possible Service Water (SW) leak, it was discovered that the B Reactor Compartment Cooling Fan cooling coils had developed a
SW leak.
The Service Water to and from the B Reactor Compartment Cooling Fan Cooling Coils was isolated and held.
A Ginna Station Work Request or Trouble Report (WR/TR) was initiated (WR/TR f9201643) to repair the Service Water leak associated with the B
Reactor Compartment Cooling Fan cooling coils.
The Control Room operators notified higher supervision, the Nuclear Regulatory Commission (NRC),
and the NRC Resident Inspector of the event.
III.
CORRECTIVE ACTION A.
ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS:
Work Order package 9201643 was developed to perform a tube repair in accordance with procedure EM-745 (Repair Of Containment Fan Cooling Coils)
.and
.the Mechanical Engineering disposition of NCR 92-348 using general brazing specification 400 and qualified brazing specification BPS 400-6.
'2he location of the leak was on a first pass "U" bend section of the cooling coils.
The leak occurred at a "V"-notch dent in the tube.
A second similar dent was identified at a
"U" bend section two rows lower on the cooling coils with no leakage evident.
The leaking tube and the second dent were repaired using qualified brazing specification BPS 400-6.
The braze repairs were visually examined and leak tested at operating pressure to verify acceptability (no indication of leakage was apparent).
The "B" Reactor Compartment Cooling Fan was subsequently returned to service.
ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE The underlying cause of the event was determined to be a failure of the tube in the area of the dent.
The following actions to prevent recurrence have been taken:
0 0
The A Reactor Compartment Cooling Fan exposed cooling coils were visually inspected for damage.
None was noted.
The B Reactor Compartment Cooling exposed fan and cooling coils were visually inspected after repair.
No damage/leakage was noted.