ML19031B179
| ML19031B179 | |
| Person / Time | |
|---|---|
| Site: | Salem  (DPR-070, DPR-075) |
| Issue date: | 02/15/1977 |
| From: | Schneider F Public Service Electric & Gas Co |
| To: | O'Reilly J NRC/IE, NRC Region 1 |
| References | |
| LER 1977-006-01 | |
| Download: ML19031B179 (4) | |
Text
I Frederick W. Schneider Vice President Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/622-7000 Production Mr. James P. O'Reilly "Director of USNRC Off ice of Inspections and Enforcements Region l 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. O'Reilly:
LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 77-06/3L February 15, 1977 Pursuant to the requirements of Salem Generating Station Unit No. l Technical Specifications, Section 6.9.l, we are submitting Licensee Event Report for.Report~ble Occurrence 77-06/3L.
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, 1°'1'
~~f
- 1
Report*Nurnber:
77-06/3L Report Date:
1-20-77 Docket FUe
...,.;..~
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Occurrence Date:
1-20-77 Facility:
Salem Generating Station Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
- 12 Reactor Coolant Flow Channel 1 inoperable.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 1 Reactor Power:
22%
Generator Load:
140 MWe DESCRIPTION OF OCCURRENCE:
At 0732 the RMS channel RllA (Containment Air Particulate} alarmed.
Channel RllA was reading approximately 3000 cprn verifying a valid alarm.
The Shift Supervisor implemented the Radiation Incident procedure.
No personnel were in the containment at the time of the occurrence.
The Shift Supervisor and Health Physics personnel entered the containment and found steam leaking in the area around No. 12 SI Accumulator.
Control Room personnel reported that No. 12 RC Flow Channel 1 was pegged high.
Operation personnel found the leak to be corning from No. 12 RC Flow Device.which was then isolated.
RC Flow Channel 1 Bistable was placed in the tripped condition as required by Tech. Spec. Action Statement 7 for Table 3.3-1.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
The apparent cause of this occurrence was improper installation of the "Swagelok" tube fitting during construction of the panel.
The fitting apparently backed off causing the leak.
ANALYSIS OF OCCURRENCE:
There are three (3) channels of flow instrumentation installed in each loop of the reactor coolant system.
Technical Specification Action Statement No. 7 for Table 3.3~1 allows Startup or Power Operation to continue with one channel inoperable until the perfor-mance of the next required channel function test, provided the failed channel is placed in the tripped.* condition.
No. 12 RC Flow Channel 1 was placed in the tripped condition, therefore the limiting condition for operation was not violated.
At no time was there any danger to.
the health and safety of the general public or site personnel.
Report 77-06/3L 1-20-77 CORRECTIVE ACTION:
The failed fitting was replaced from spares and tested.
The test was satisfactory.
FAILURE DATA:
Manufacturer:
Swagelok Size:
3/8 inch Material:
316 Stainless Steel Prepared by T. L. Spencer Manager -
~lem Generating Station SORC Meeting No.
13-77
CONTROL BLOCK LICENSEE.
NAME LICENSEE EVENT REPORT e 6
LICENSE NUMBER.
LICENSE TYP EVENT TYPE IO IO 1-1 o I o I o I o I o I -1 O I O~. ~ 41 11 11 11 lJo 10 11 I 15 2
~
REPORT REPORT.
REPORT DATE CATEGORY TYl'E SOURCE DOCKET NUMBER EVENT CATE
~
CON'T~; I OJ ~
. ~ bP I 51 0 I -1 0 I 2 I 71 2J
'3sOI 1121OI71 ~J 17501 JI 216171 !J EVENT DESCRIPTION
@:fill During Mode I operation, No. 12 Reactor Coolant Flow Channel 1 became 7
8 9
@:§]I inoperable due to a tube fitting failure.
Two (2) redundant flow 7
8 9
@El channels were operable in No. 12 Coolant Loop *. The tube fitting was 7
8 (iI!J I replaced from spares and -tested satisfactorily._
This is the first 7
89
~I occurrence cf this type (77-06/3L).
7 8 9 SYSTEM CODE
@mt :n.pl 7
8 9 10 CAUSE CODE l!Ll 1.1 CAUSE DESCRIPTION COMPONENT CODE II IN IS IT IR..J!Lj 12 17 PRIME COMPONENT SUPPLIER LL.I 43 COMPONENT MANUFACTURER IXl9!9!91 44 47 VIOLATION
~
rii'J8l I A "Swagelok" tube fitting backed off causing the leak.
This event W9 l2..l!l I was apparently caused by improper installation durimi construction.
7 8 9 I
80,.
80 I
80 I
[I]fil..,,_..._ ______________________________ """"'-______________________________ """"
1 a 9 ea FACILITV i."'i.'1 STATUS L!.1.:..1 Lfil.
7 0
9
. FORMOF
'!It POWER 10 12 12 *I 10 12 ACTIVIT't CONTENT METHOD OF OTHe-A STATUS DISCOVERY DISCOVERY DESCRIPTION I~,___N_/_A ____ """""""'I
@J 13*
44 45*
46 I N/A 80 REL.EASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE
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. 7 8
. 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION I 0 I 0 10 I lZJ l~_*_---.N.._/=A...... ------------------*-..:J 7
9 11 12 13 i)
PERSONNEL INJURIES NUMBftR DESCRIPTION lillJIOIOIOI I N/A I
1 a 9 h
""12 _______ __,, __ __....__ _____________________
"""'eo OFFSITE CONSEQUENCES
~19.
N/A
- LOSS OR DAMAGE TO. FACILITY TVPI!
CUCAIPTION GJ!11z11 ~
'----------:;:N~/A~*-------------------------------------------cJ 7
8~ 10 Id PUBLICITY GEJ..,,_ __________________ _..,.+-"".__ ______ __... ______________________________ ~
7 89 80 ADDITIONAL FACTORS*
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1 a a ao
- NAME: __
T~**,_.,;L;;;,,,._-S_.p_e_,_n_c_e_r _________ _
PHONE: ( 609 ).365-7000 Ext.Salem-528 !
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