ML18079A839
| ML18079A839 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/12/1979 |
| From: | Schneider F Public Service Enterprise Group |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 7908220634 | |
| Download: ML18079A839 (4) | |
Text
Frederick W. Schneider Vice President Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/430-7373 Production 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 NO. 1 UNIT SALEM GENERATING STATION July 12, 1979 In response to your letter of June 25, 1979, transmitting NRC IE Bulletin No. 79-13 which was received on June 28, 1979, the follow-ing response pursuant to items 5.a, 5.b, and 5.c of the subject bulletin is submitted for your review:
ITEM SA -
Schedule for Inspections Scope of Work Part I Part II SG Inspection Points Inspection Points*
11 8
16 12 8
17 13 8
15 14 8
15 32 63
- Includes Auxiliary Feed Connections.
Schedule The sequence of inspe~tions will be: Part I (five are currently completed), Part II High Stress Points and then remaining Part II Welds.
In parallel, Southwest Research Institute (SWRI) will be conducting Part I-C inspections of feedwater system hangers and snubbers.
-e Mr. Boyce H.. Grier 7 /12/79 Two RT crews and one SWRI crew (with UT backup capabilities) will be working around the clock on twelve-hour shifts.
The work is expected to take seven days.
Part II-C inspections will also be included in the ISI Plan for the next refueling outage.
Item SB -
Adequacy of Emergency Instructions for Recognizing and Coping with a Feedwater Line Break A feedwater line break is addressed in three separate Emer~ency Instructions~
1..
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 injection, regardless bf 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 secDndary 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 isolation valves, which are outside the containment.
- 3.
EI I-4.12, "Loss of Feedwater".
This instruc:tion 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 a feedwater line break.
Item 5C -
Detection of Feedwater Leaks in Containment Feedwater leaks within the containment at greater than ambient conditions would be indicated by _the following:
- Mr. Boyce 7/12/79
- 1.
Increased containment temperature, pressure, humidity, dew point.
All of these ar~'accurately monitored and displayed in the Control Room using permanently installed instrumen-tation which is periodically calibrated in accordance with approved station surveillance procedures.
2w Increased frequency of containment sump pump operation.
3..
Increased drainage flow from the Containment Fan Coil Units.
The ~xact location of the source, i.e., which steam generator or whether it is steam or feedwater, is not determinable from
_the above indications..
That iden tifica ti on would have to be*
made utilizing instrumentation installed on each. st*eam gener-
- ator, includ~ng the following:
- 1.
Steam Flow
- 2.
Steam Genera tor Pres sure
- 3.
Feedwater Flow
- 4.
Feedwa ter Pres sure
- 5.
Steam Generator Level The leak rate can be determined very accurately by utilizing the existing Operating Instruction, OI II-1.3.5, "RC Leak Detection" which contains the appropriate calculation pro-cedures to determine the leak rate of fluid into the con-tainment, regardless of the origin.
(Reactor Coolant System, Main Steam, Feedwater, Service Water, Primary Water, or
- Component Cooling.)
--i
Mr. Boyce H. Grier
- _4_
7/12/79.
We anticipate that the balance of information requested (items 1 and 2) will be.submitted for your review by July 25, 1979.
Sincerely, Attach..
CC:
NRC Office of Inspe~tion and Enforcement Division of Reactor Operations Inspect~on Washington, D. C.
Mr. L. Norrholm NRC,. Hancocks Bridge, N.J.
.,