ML18081A379
| ML18081A379 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/18/1979 |
| From: | Martin T Public Service Enterprise Group |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 7910190165 | |
| Download: ML18081A379 (4) | |
Text
Thomas J. Martin
., Vice President Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201 /430-8316 Engineering and Construction September 18, 1979 Mr. Boyce H. Grier, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Grier:
NRC IE BULLETIN NO. 79-13, REVISION 1 NO. 2 UNIT SALEM GENERATING STATION In response to your letter of August 30, 1979, transmitting NRC IE Bulletin No. 79-13 (Revision 1), which was received on September 4, 1979, the attached report is offered pursuant to items 1-3 concerning "Actions to be Taken by Designated Applicants for Operating Licenses.
11 If you require additional information, we will be pleased to discuss it with you.
Sincerely, Attachment CC Off ice of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D.C.
Mr. L. J. Norrholm Hancocks Bridge, NJ Q
/6-S-' '.
J9101D 0..
\\
RESPONSE. NRC IE BULLETIN 79-13, All. l In accordance with the requirements of Bulletin 79-13, Revision 1, dated August 30, 1979, we submit the following response which pertains to the specified, "Actions to be Taken by Designated Applicants for Operating Licenses":
Item 1 -
Radiographic examination supplemented by ultra-sonic examination as necessary to evaluate indications will be performed on all feedwater nozzle-to-piping welds, adjacent pipe and nozzle areas a distance at least two wall thicknesses, prior to fuel loading.
In addition, a visual inspection of feed water piping system supports will be completed prior to fuel loading.
Item 2 -
During the first refueling outage, examinations as specified in Item 2 of the subject bulletin will be performed on the main steam generator feed piping within containment.
Item 3 -
A)
Our schedule for inspections referenced in Item 1 above, calls for all examinations to be completed by September 30, 1979.
Item 3 -
B)
Adequacy of Instructions For Recognizing And Coping With A Feedwater Break.
A feedwater line break is addressed in three separate emergency instructions as follows:
- l.
EI I-4.0, "Initiation of Safety Injection".
This instruction contains the immediate and supplementary actions required of the operator to respond to any safety injec-tion, regardless of the initiating event.
It also includes the steps required for the operator to distinguish between the initiating event and directs him to the appropriate instructions for a LOCA, loss of secondary coolant, SGTR or inadvertent actuation.
- 2.
EI I-4.6, "Loss of Secondary Coolant".
This instruction contains the actions required of the operator in the event of a loss of secondary coolant from either a main steam rupture or a feedwater rupture downstream of the feedwater header to isolation valves, which are outside the containment.
- 3.
EI I-4.12, "Loss of Feedwater".
This instruction deals with a general loss of f eedwater to the steam generators as a result of a line rupture, control valve failure or loss of pumps.
All of the above emergency instructions have recently been reviewed and revised as necessary in response to IE Bulletin No.79-06A, Revision 1.
The procedures, as written, are adequate for recognizing and responding to the feedwater line break.
Item 3 -
C)
Detection Of Feedwater Leaks in Containment Feedwater leaks within the containment at greater than ambient conditions would be indicated by the following:
- 1.
Increased containment temperature, pres-sure, humidity, and dew point.
All of these are accurately monitored and displayed in the control room using permanently installed instrumentation which is periodically calibrated in accordance with approved station surveillance procedures.
- 2.
Increased frequency of containment sump pump operation.
- 3.
Increase drainage flow from the Contain-ment Fan Coil Units.
The exact location of the source, i.e. which Stearn Generator or whether it is steam or feedwater, is not determinable from the above indications.
That identification would have to be made utilizing instrumentation installed on each Steam Generator, including the following:
- 1.
Steam Fl OW
- 2.
Steam Generator Pressure
- 3.
Feedwater Flow
- 4.
Feedwater Pressure
- 5.
Steam Generator Level The leak rate can be determined very accurately by util-izing the existing Operating Instruction, OI II-1.3.5, "RC Leak Detection" which contains the appropriate calculation procedures to determine the leak rate of fluid into the containment, regardless.of the origin.
(Reactor Coolant System, Main Steam, Feedwater, Service Water, Primary Water, or Component Cooling).
Item 3 -
D)
Written reports of the results of examin-ations specified by the subject bulletin~
will be submitted within 30 days of com-pletion of the examination.
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