ML20215N068
| ML20215N068 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/24/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NLR-N86151, NUDOCS 8611040236 | |
| Download: ML20215N068 (3) | |
Text
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Public Service Electric and Gas Company
' C;rbin A; McNeill, Jr.
Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge NJ 08038 609339-4800
%ce President-Nuclear October 24, 1986-NLR-N86151 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA Attention:
Mr. William F. Kane, Director Division of Reactor Projects Gentlemen:
NRC INSPECTION REPORT-311/86-26 SALEM GENERATING STATION UNIT NO. 2 DOCKET NO. 50-311 This letter forwards the Public Service. Electric and Gas Company
( PS E&G) res ponse to the above referenced inspection report.
A description of each open item and its appropriate response is provided in the accompanying Attachment.
Should you have any ~ questions regarding this i n fo rmat ion, please feel. free to contact us.
~
Sincerely, I
i l
l l
C Mr.
D.
C.
Fischer Licensing Project Manager i
Mr. T. J.
Kenny Senior Resident Inspector 8611040236 861024 PDR ADOCK 05000311 G
PDR I
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I.c o g
A s
ATTACHMENT 86-26-01:
Implementation of Task' Force-recommendations relating to maintenance and troubleshooting practices.
Response
During the post trip review process, the circumstances leading to the trip were reviewed by the appropriate maintenance department supervisors.
Representatives from the Nuclear Training Department.
. participated in this review in order to determine.
whether' improvements to the technician training
.It was concluded that for programs were required..the use of insulated test this particular event, probes and the use of the available terminal block for voltage measurement could possibly have prevented the reactor trip.
~
Insulated test probes are available at the Station.
~
However, the use of insulated probes is not possible in all situations nor is it practical'to attempt to identify all of the applications where their use would be preferred.
Similarly, terminal blocks are
-not installed in all applications.
Based on the above, the appropriate training programs will be re' vised prior to the next training cycle to stress the use of insulated test probes and terminal blocks for voltage measurement whenever possible.
86-26-02:
NRC review of the detailed analysis of the electrical transient.
Response
This is an NRC follow-up item:and as such no action is required by PSE&G.
As stated in the inspection report, a detailed review of the transient was performed by PSE&G and a formal. presentation made to the NRC on August 29, 1986.
86-26-03:
Replacemc.t'of dissimilar metal welded joints and the overall Service water System pipe replacement program.
Response
Prior to the restart of Unit 2, repairs to the No..:23 4
and 25 containment fan coil units were accomplished.
Other dissimilar metal welded joints'in the Unit 2 service water system (in containment) are being replaced by flanged connections with an intervening insulator.
This work is presently underway and is scheduled for completion during the Unit 2 refueling outage.
As part of a long term progtcm to improve service water system materials, PSE&G has instituted a piping replacement program utilizing 6% molybdenum high 1
alloy stainless steel, a highly corrosion resistant material.
An intensive testing program is being performed to confirm this materials' corrosion Dehavior in a brackish water environment.
j-c, io Piping spools of the new material and weld coupons' are being installed duringethe Unit 2; refueling outage.
More extensive piping replacement will begin
~
af ter sufficient test data becomes available.
Also included in the program is'the complete replacement' of existing strainers with an Aluminum Bronze alloy'
- material.
1 86-26-04:
NRC follow-up on the Operations' Department task force review of operator actions and procedural adequacy.
Res ponse:
This'is an inspector follow-upLitem and, therefore, no further action is required.
The task' force review
. has been completed and the results are available-for inspection.
86-26-05:
Correction or explanation of the. items listed in
~ Appendix C of the inspection report.
Res ponse:
The items listed'in Appendix C were.dispositioned prior to.the restart of Unit 2.
.These dispositions were made as'part of the post trip review process and are documented.in Administrative Directive-16,." Post
- Reactor Trip / Safety Injection Review Report," File No. 86-15.
A copy of this document was given to M r. 13. Pullani'during his follow-up visit of September. 4-5, 1986.
Although the. document given to Mr.-Pullani was-in draft form, the responses to the i
items requiring disposition prior-to restart were not altered.in-the final-version.
86-26-06:
Reanalysis of load additions, including transient
~
i response, and the adequacy of the 10 CFR 50.59 review process.
l-Response:. As indicated in.our September 30,~1986 letter, Power i
Technology, Inc.'is performing a detailed load L
analysis'for the Salem Station electrical' l
distribution system.
Their review will include an l
assessment of the present Station electrical j
distribution systems' transient response capability.
Public Service Electric and Gas Company is in the process of upgrading its 50.59 evaluation program.
This upgrading includes the' issuance of a Vice President Nuclear procedure (VPN-LEP-04).
The l
procedure will take into account available guidance on the sub ect and will require _ consideration of he j
effects of non-safety system changes on' safety related systems.
The intent of the procedure is to more closely control the review process by-requiring a documentedEanalysis with an appropriate level of management review.
A target date of October 30, 1986 l
- has been established for.the issuance of this procedure.
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