ML18079A997
| ML18079A997 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/24/1979 |
| From: | Schneider F Public Service Enterprise Group |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 7909290435 | |
| Download: ML18079A997 (3) | |
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 Conunission Office of Inspectia:n*-and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Grier:
NRC IE BULLETIN NO. 79-17 NO. 1 UNIT SALEM GENERATING STATION August 24, 1979 In response to your letter of July 26, 1979, transmitting NRC IE Bulle-t;:in No. 79-17 which was received on July 31, 1979, the following response is submitted for your review:
A review of safety-related stainless steel piping systems to identify systems and portions of systems which contain stagnant oxygenated borated water has been completed.
The results of
. this review are identical to a review conducted in 1977, based_
on the requirements of NRC IE Circular No. 76-06.
Also, in accordance with the.requirements defined in Circular No. 76-06, a program was established to define the surveillance to be conducted at Salem to assure the integrity of piping exposed to stagnant borated water.
A copy of this program and the first sixty-day report required by Circular No. 76-06 were submitted to the NRC by the General Manager - Electric Production letter of January 26, 1978.
In response to Paragraph 1 (a):
- 1) Hydrotesting - Hydrotesting is not scheduled to be conducted until the third Inservice Inspection period (1985-1987).
- 2) Service Pressure Visual Leak Examinations have been conducted as follows:
a) Safety Injection System (Nuclear Class _3), June, 197 8.
b) Charging and Volume Control, Part 1 (Nuclear Class 2),
January, 1979.
I Mr. Boyce 8/24/79
- 3)
- Service -Pressure Visual Leak Examinations scheduled are as follows:
a)
Residual Heat Removal (Nuclear Class 2), September, 1979.
b)
Chemical and Volume Control, Part 2 and 3, (Nuclear Class 2), November, 1979.
c)
Safety Injection (Nuclear Class 3}, June, 1980.
d)
Containment Spray (Nuclear Class 2 and 3}, June, 1980.
- 4)
Volumetric (UT} Examinations of welds have been conducted as follows:
Twenty-three Nuclear Class 2 welds were examined in the Residual Heat Removal and Safety Injection Systems during an outage in 1977.
Seven Nuclear Class 2 welds were ex-amined in the Residual Heat Removal, Safety Injection and Containment Spray.Systems during the 1979 Refueling Outage.
The Ultrasonic Examinations were conducted by Southwest
.Research Institute during both outages.
The procedures and qualifications were in compliance with the requirements of Section XI, ASME Code, 1974 Edition, Summer 1975 Addenda.
The procedures and qualifications are filed in the PSI and ISI. Plans.
The ISI Examination (sampling} Plan is in accord-ance with the same 1974 Code as is the acceptance criteria.
Data sheets of all thirty welds examined to date revealed no recordable or reportable indications, and none of the welds required corrective actions.
In response to Paragraph 1 (b):
Periodic samples are obtained on all systems and analyzed for pH, boron, and chloride levels.
Whenever the analysis indicates that the parameters do not meet the Westinghouse specifications as out-lined. in the "Chemistry Criteria and Specifications", corrective action is taken.
The corrective action consists of either addition of chemical to meet stated pH and boron levels or measures to reduce the boron or chloride levels.
The two means employed to reduce levels are, cleanup demineralizers or draining and flushing pro-cedures.
The frequency of sampling has been established to insure proper chemical control for the systems for both in service and out of service periods.
Sample schedules, chemistry specifications, and corrective *action to be taken have been included in the station administrative pr.ocedures.
""f' Mr. Boyce H. Grier*
8/24/79 In response to Paragraph 1 (c) :
Pre-Service Inspection (PSI) NDE for Salem Unit No. 1 was conducted between August, 1975 and August, 1976.
The examinations were con-ducted and results were accepted in accordance with the criteria established in Section XI, ASME Code, 1971 Edition, Winter 1972 Addenda.
Hydrotesting of systems and visual leak examinations were conducted in accordance with USAS B31.7 (Nuclear Power Piping).
Welds in the following safety-related systems that contain fluids of interest were included in the PSI Examinations when and to the extent they were required by the Code:
Residual Heat Removal Safety Injection Containment Spray Chemical and Volume Control Since ISI Examinations have been performed on stagnant portions of systems previously identified, Paragraph 2 of the Bulletin is not applicable.
If you require additional information, we will be pleased to discuss it with you.
cc: NRC Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D.C.
Mr. L.J. Norrholm NRC Hancocks Bridge, N.J.