ML19031B067
| ML19031B067 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/28/1977 |
| From: | Schneider F Public Service Electric & Gas Co |
| To: | O'Reilly J NRC/IE, NRC Region 1 |
| References | |
| LER 1977-002-01 | |
| Download: ML19031B067 (4) | |
Text
Frederick W. Schneider Vice President Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/622-7000 Production
~\\egulatory Docket Fi Mr. James P. O'Reilly Director of USNRC Off ice of Inspections and Enforcements Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406 D~ar Mr. O'Reilly:
LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 77-02/3L Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence 77-02/3L.
This report is required within thirty (30) days of the occurrence.
CC:
Director, Office of Inspection and Enforcement (30 copies)
Director, Office of Management Information and Program Control (3 copies)
Sincerely yours, 1033
Report Number:
Report Date:
Occurrence Date:
Facility
- -02/3L 1/12/77 1/03/77 Salem Generating Station
- Public Service Electric & Gas Company Hancocks Bridge, New Jersey 080~8 IDENTIFICATION OF OCCURRENCE:
- Pipe failure on letdown vent line.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 3 operation, Plant pressure 2235 psig, Plant temperature 547°F.
DESCRIPTION OF OCCURRENCE:
No. 15 Containment Fan Coil Unit leak detection system alarmed and con-tainment humidity increased.
Normal letdown was in service.
The containment sump pumps started and makeup to the VCT increased.
Letdown flow indicated zero while charging flow was normal.
Normal letdown was isolated and excess letdown initiated.
All indications of a RCS leak terminated.
Investigation revealed a pipe break in the letdown vent line ahead of valve 1CV396.
Approximately 2400 gallons of reactor cool-ant spilled in the 78' elevation of the containment and drained into the containment sump.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
Excessive vibration of the 3/4" vent line caused the pipe to shear down-stream of the joint to the main letdown line.
ANALYSIS OF OCCURRENCE:
Airborne activity in the reactor containment was less than the maximum permissible concentration.
The spilled coolant drained into the contain-ment sump and was pumped to the waste holdup tanks for processing.
The leak rate was reduced to less than the Technical Specification limit of paragraph 3.4.1.2 within the allowed time and all action statements were cancelled.
At no time was there any danger to the general public or site personnel.
CORRECTIVE ACTION:
The 3/4" letdown and welded.
NDE ical.ly tested.
f ied and NDE was were identified.
vent line was removed.
The remaining socket was plugged was performed on the new weld and the system was hydrostat' Ten similar vent lines in the eve System were identi-performed on the 3/4" to header welds.
No indications
- l Report No. 77-02/3L ~
- 1/12/77 Page 2 FAILURE DATA:
Pipe:
3/4" Schedule 40 ASTM A-403 TP-304 Prepared by T. Spencer SORC Meeting No.
8-77
LICENSEE EVENT REPORT CONTROL BLOCK 6
LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE REPORT REPORT CATEGORY TYl'E SOURCE COCKET NUMBER EVENT CATE REPORT CATE fOTtl CON'T lE.lQj l.1J L!!.J t-1 57 5B 59 60
!Oili'Oi317171 69 74
~p I 51 0 I -I 0 I 2 I 71 2J I 0 111 1 I 2 I 7 17J 75 EVENT DESCRIPTION
@n]IDuring Mode 3 operation. nopnal letdown in service. a pipe break occurred!
1 89 ao
@)) in a vent line on the letdown header.
Alternate letdown was available.
7 8 9
@El 2400 gal of coolant leaked into the containment sump. Vent line was re-7 8
[Q]i]!moved, plugged and welded.
Hydrostatic test was satisfactory.
7 8 9
~1the first occurrence of this type.
(76-02/3L) 7 8 9 PRIME SYSTEM CAUSE COMPONENT COOE COOE COMPONENT CCOE SUPPLIER
@ill tR.J£j lEJ IZ I Z I Z I Z I Z-1ZJ llJ 7
8 9 10 11 12 17 43 CAUSE DESCRIPTION COMPONENT MANUFACTURER IU 10 18 10 I 44 47 VIOLATION l.NJ 48 This is I 80 1-ao
~1 9
Excessive vibration caused failure of 3/4" Sch. 40 yent line Simi 1 ar I
~I uQut liuei;; uuc;1e:r:weut NDE.
No indications noted..
7 8 9 so I ao
[Ifil':--~__,..~~--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
1 89 ao FACILITY STATUS
[ill]
l,gJ.
1 a.
g FORM OF
'JloPOWER 10 10 10 I 10 12 OTHE*R STATUS NIA 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY 0!J
~ ~ I N/A 7
8 9
10 11 PERSONNEL EXPOSURES METHOO OF CISCOVERV OISCOVERV CESCRIPTION I LJ I
Ni8 I
44 45 46 80 I
LOCATION OF RELEASE I
N/A I
44 45 so r:r.:I NUMBER TYPE CESCRIPTION l..!.l:..11010101 lk,J l~~----N~/~A
__________________________________ --;d 7
8 9 11 12 13 sJ PERSONNEL INJURIES I
so NUMBER CESCRIPTION
~I 0 I 0 I 0 I I N/A 7
8 9 h
12 J
OFFSITE CONSEQUENCES rtrsl I N/A
~9 LOSS OR DAMAGE TO FACILITY J
TYPE OESCRIPT*ION
~IZI I N/A 7
8 '§'"""
10 80 ao 80 NAME: ___
T_._L_._S-=p_e_n_c_e_r _________ _
PHONE: (609) 365-7000 Ext.Salem-528 1
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