ML18086B139
| ML18086B139 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/30/1981 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM NUDOCS 8112180397 | |
| Download: ML18086B139 (3) | |
Text
PS~G Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201/430-7000 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20014 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing Gentlemen:
REVISED COMPLETION DATES TMI -
RELATED ITEMS NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 November 30, 1981 Facility Operating License DPR-75 identified certain TMI - related items which are required to be completed by January 1, 1982.
We have determined that certain of these items cannot be completed by that time and request deferral of the completion dates as described herein.
This letter updates and supersedes our letter of October 29, 1981 regarding NUREG-0737, items II.F.1.1 and II.F.1.2.
An order was placed in June 1980 for the Sentry post-accident sampling system.
Design changes and new material requirements wm;:ie identified as the engineering and design of the system progressed.
In May 1981, as the design progressed, six additional valves were identified as being required.
An order was placed immediately, but delivery cannot be made until June 1982.
Every effort has been made.to expedite these valves, however, the manufacturer cannot improve on the June date.
Additionally, the partitioning system has been under development for some time by Sentry and has just recently been made available to us, with delivery scheduled for April 1982.
Some progress in the installation was made during the periods when Salem 2 was not operating.
Presently, the inside containment work is approximately 75% complete and the outside containment work is approximately 20% complete.
Approximately four weeks outage time is
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I U.S. Nuclear Regulatory Commission 11/30/81 required to complete the installation.
However, there is no planned outage for Salem 2 until its first refueling, which is presently scheduled to commence in January 1983.
Because of the expected material delivery dates and the unit outage time required to complete the installation, we request the required completion date for the post-accident sampling system be deferred until the completion of the first refueling outage.
Should a forced outage of sufficient duration occur in the interim, every effort will be made to complete this work.
Interim procedures for post-accident sampling and analysis of reactor coolant and containment atmosphere are presently in use.
These proce-dures were approved by the NRC staff for interim use in SER Supplement 5, Section 22.2 (II.B.3).
Therefore, this change in completion date causes no undue risk to the health and safety of the public.
Engineering and design of the containment high range radiation monitor was completed in March 1981 and installation is approximately 95%
complete at the present time.
Installation of environmentally qualified connectors and final testing remains to be completed.
The environmentally qualified connectors are scheduled for delivery by December 1, 1981.
Approximately two weeks outage time is required to complete the installa-tion.
However, there is no planned outage for Salem 2 until its first refueling, which is presently scheduled to commence in January 1983.
Because of the expected material delivery dates and the unit outage time required to complete the installation, we request the required completion date for the containment high range radiation monitor be deferred until the completion of the first refueling outage.
Should a forced outage of sufficient duration occur in the interim, every effort will be made to complete this work.
At the time the noble gas monitor and iodine/particulate sampling and analysis capability were identified as requirements, an engineering investigation was initiated to determine the availability of qualified equipment.
PSE&G collaborated with other licensees and EPRI in this effort, but it was not until July 1981 that qualified equipment could be located and ordered.
This equipment is scheduled for delivery in late December 1981.
Approximately eight weeks outage time is required to complete the instal-lation of the noble gas monitor.
However, there.is no planned outage for Salem 2 until its first refueling, which is presently scheduled to commence in January 1983.
Because of the expected material delivery dates and the unit outage time required to complete the installation, we request the required completion date for the noble gas monitor be def erred until the completion of the first refueling outage.
Should a forced outage of sufficient duration occur in the interim, every effort will be made to complete this work.
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U.S. Nuclear Regulatory Commission 11/30/81 Approximately 10 weeks time is required for installation of the iodine/
particulate sampling equipment, although a unit outage is not required.
Because of the expected material delivery date and the time required to install this equipment, we request the required completion date for this item be deferred until June 1, 1982.
Interim containment radiation monitoring is provided with the existing high range (107 R/hr) containment radiation monitor.
A system for monitoring noble gas effluents in concentrations up to 100 uCi/c is currently installed, as well.as an interim system to continuously sample gaseous effluents.
The capability to analyze these samples for radioiodines and particulates also exists.
The measures identified above were approved by the NRC staff for interim use :in SER Supplement 5, Section 22.3 (II.F.l).
These changes in com-pletion dates, therefore, cause no undue risk to the health and safety of the public.
The reactor vessel level instrumentation system was ordered from Westinghouse in August 1980.
Final detail design of the system is essentially complete at this time, and the remaining material required for this system is scheduled to be delivered in Devember 1981.
In order to complete this modification, the reactor vessel head must be removed and the primary loop drained to make the necessary connections.
Since plant conditions of this nature occur normally during refueling outages~
we request that the required completion date for the reactor vessel level instrumentation system be def erred until completion of first refueling outage.
The existing instrumentation to detect*inadQquate core cooling (subcooling meter) and procedures were approved by the NRC staff for interim use in SER Supplement 5, Section 22.3 (II.F.2).
This change in completion date, therefore, causes no undue risk to the health arid safety of the public.
A formal request for amendment of Facility Operating License DPR-75 to reflect these revised completion dates will be forthcoming in the near future.
Your prompt and favorable consideration of this request will be appreciated.
EAL:sal CC Mr. Leif Norrholm Senior Resident Inspector Mr. Gary C. Meyer Licensing Project Manager Very J;;.l?uly
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E. A. Liden Manager - Nuclear Licensing