ML18086B141
| ML18086B141 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/07/1981 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.E.1.1, TASK-2.F.1, TASK-2.F.2, TASK-TM NUDOCS 8112180433 | |
| Download: ML18086B141 (4) | |
Text
PS~G I Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201/430-7000 Mailing Address:
P. O. Box 570, Newark, N. J.
07101 December 7, 1981 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. 1 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 Several TMI related plant modifications are required to be implemented by January 1, 1982.
Since a unit outage is required to install the remaining modifications, PSE&G plans to complete their installation during the upcoming Salem Noa 1 refueling outage.
The refueling outage was originally scheduled for the fall of 1981, but has been rescheduled to commence on or about January 2, 1982 and have a duration of approximately ten weeks.
Every effort has been made to complete as much work as possible during unit operation, but most of the modifica-tions require a unit outage for implementation.
It is therefore requested that the required completion dates for the following TMI-related items be deferred until the end of the forthcoming refueling outage, approximately March 13, 1982.
- 1.
Wide Range Containment Pressure Indication (NUREG-0737,Section II.F.1).
In the interim, the four existing containment pressure transmitters have a range of -5 to
+55 psi, which extends well above the maximum calcu-lated pressure (45.2 psig) for a LOCA inside the con-tainment and the containment design pressure (47 psig).
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Dir. of Nucl. Reac. Reg. 12/7/81
- 2.
High Range Containment Radiation Monitors (NUREG-0737,Section II.F.1).
Interim containment radiation moni-toring is provided with the existing high range (107 R/hr) containment radiation monitor.
- 3.
Noble Gas Monitors and Iodine/Particulate Sampling (NUREG-0737,Section II.F.1).
A system for monitoring noble gas effluents in concentrations up to 100 uCi/cc is currently installed; as well as an interim system to continuously sample gaseous effluents.
The capability to analyze these samples for radioiodines and particu-lates also exists.
- 4.
Redundant Auxiliary Feedwater Storage Tank Level Indi-cation and Alarm (NUREG-0737,Section II.E.1.1).
The existing Auxiliary Feedwater Storage tank includes both a low and a low-low level alarm for control room annun-ciation and indication.
The low level alarm allows approximately 30 minutes for operator action and the low-low level alarm allows 10 minutes.
- 5.
Recorders for Containment Water Level Monitoring System (NUREG~0737,Section II.F.1).
The containment water level monitoring system is installed and operational, with the exception of the continuous recorder.
Level indication is available in the Control Room.
The TMI-related items described below require deferral of completion dates beyond the forthcoming refueling outage.
- 1.
Post-accident sampling (NUREG 0737,Section II.B.3)
The Sentry Post-Accident Sampling System was ordered in June 1980.
As the Engineering and Design of the system progressed, additional material requirements were identified, some of which were ordered in May 1981.
Delivery of this material is not expected to impact completion of this work.
Presently, 20% of the outside containment installation work and 5% of the inside con-tainment installation work is complete.
We expect to complete the inside containment work during the refuel-ing outage which will commence in January 1982.
Out-side of containment work is currently proceeding.
How-ever, because the Partitioning System to permit iso-topic analysis will not be delivered to April 1982, the
Dir. of Nucl. Reac. Reg. 12/7/81 entire sampling system cannot be made completely opera-tional.
The Partitioning System was part of the ori-ginal requirement and has been under development for some time by Sentry.
The equipment was just recently made available to us.
Once the entire system is in place, final testing and training of operating person-nel will be required.
Because of the above, we request that the required com-pletion date of Post Accident Sampling System be defer-red to July 1, 1982.
Interim procedures for post-accident sampling and analysis of reactor coolant and containment atmosphere are presently in use.
- 2.
Instrumentation for Inadequate Core Cooling (NUREG-0737,Section II.F.2).
The Reactor Vessel Level Instrumentation System was ordered from Westinghouse in August 1980.
Final design of the system is complete.
Material required for this system is available and all pre-outage work will be completed prior to the forthcoming refueling outage.
In order to complete this modification, the reactor vessel head must be removed and the primary loop drained to make the necessary connections.
Wherever possible, pre-fabrication of in-containment equipment is being done to expedite the installation.
Westing-house is providing scheduling assistance and super-vision of the installation, and will perform certain portions of the installation and testing, thereby taking maximum advantage of all available expertise.
Due to the complexity of this modification, however, it is estimated that even under optimum conditions, four to six weeks of work could remain at the completion of the refueling outage, currently scheduled for March 13, 1982.
We therefore request that the required completion date for the Reactor Vessel Level Instrumentation System be deferred until the completion of the fourth refueling outage, presently scheduled for the fall of 1982.
Should a forced outage of sufficient duration occur in the interim, every effort will be made to complete this work.
Existing instrumentation (subcooling meter) and procedures for detection of inadequate core cooling are operational for interim use.
Dir. of Nucl. Reac. Reg. 12/7/81 The measures identified to be used for interim operation until the above TMI-related modifications are completed have been previously approved by the NRC staff for Salem 2 in SER Supplement 5, Section 22.2 and 22.3.
These changes in completion dates, therefore, cause no undue risk to the health and safety of the public.
Should you have any questions in this regard, do not hesitate to contact us.
Very truly yours,
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'd E. A. Ll en FM:mw CC:
Mr. Leif Norrholm Senior Resident Inspector Mr. Gary C. Meyer Licensing Project Manager AQ18 1/4 Manager -
Nuclear Licensing