ML20213E743
| ML20213E743 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/22/1984 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| Shared Package | |
| ML20213E339 | List: |
| References | |
| FOIA-87-152 NUDOCS 8402290065 | |
| Download: ML20213E743 (4) | |
Text
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s, O!STRIBUTION:
GRissuiz-im,4 0 Eisenhut ORB #1 Rdg.
Gray File D.b 2 2 1984 G. Lainas S Varga D Fischer MEMORANDUM FOR:
Thomas Rehm, Assistant for Operations, ED0 FROM:
Darrell G. Eisenhut, Director Division of Licensing, NRR
SUBJECT:
STATUS OF SALEM UNITS 1 and 2 Attached, per your request, is a summary of the status of Salem Units 1 and 2 over the past year.
Original signed by Darrell G. Eisenhut 03rrall G. Eisenhut, Directcr Division of Licensing, NRR
Attachment:
As stated above OR8 1
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a TWELVE MONTH STATUS REPORT SALEM UNITS 1 AND 2
o Licensee - PUBLIC SERVICE ELECTRIC AND GAS COMPANY 7
0 Description and Resolution of " Trip Breaker Events" at Salem Unit No. 1 On February 22 and 25,1983, the Salem Unit I reactor control rods failed to insert upon receipt of an automatic trip signal from the reactor protection system. Upon receipt of a manually initiated trip signal, however, the rods did insert and shut down the plant. These events were of major safety concern because the automatic reactor trip capability was not available; therefore, the plant safety was jeopardized when plant operating conditions required a fast shutdown to protect the integrity of the reactor core. Safe control of certain anticipated operating transients depends on the reliable and fast operation of a reactor trip, either automatically or manually.
Evaluation of these events and the circumstances which led up to them revealed a number of issues that required resolution by the licensee.
The'NRC safety evaluation report described the actions required by the 1
licensee to address and resolve equipment, operator procedures, training and response, and management issues identified in the NRC evaluation of the two events at Salem Unit 1.
Actions for Salem as identified in this report fall in two groups:
- 1) actions that were required to be satisfactorily resolved before plant startup; and 2) actions that could be completed after restart but which were required to complement the i
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pre-startup items. The actions required prior to the restart of Unit I were also implemented on Unit 2 prior to its restart.
The licensee proposed a corrective actions program describing 43 short term and 34 long term actions, and the implementation date for each long term item. To date all action items have been completed with the exception of 7 items. These 7 items involve the implementation of the recommendations for improvement of the licensee's management structure responsive to the evaluations of two consultant organizations, the implementation of training programs for supervisory, management, and non-station personnel, and the completion of the licensee's Managed Maintenance Program including an in-place Preventative Maintenance Program. The latter will result in a total overhaul of plant maintenance procedures for safety systems and components to aid in preventing a recurrence of events similar to the February 22 and 25,1983 events.
Progress on these items is being monitored by the NRC through bi-monthly meetings with the licensee and by special inspections.
Further, new procedures are now in place to make facility operations personnel totally aware of plant systems performance during and following plant transients.
i Salem Units 1 and 2 were permitted to re-start on May 6,1983. Following are the operating histories of both units from that date.
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Salem Unit 1 Unit No I was restarted on May 21, 1983 following the Reactor Trip Breaker Events. Since the restart the Unit has operated with a 92%
capacity factor. During this time period there were eight short-term shutdowns. Three of these outages were due to reactor trips occurring from unrelated steam generator level control failures. Two occurred due to minor leaks; one on a Reactor Control System valve and one on a steam generator handhole.
Two outages were due to spurious trips that occurred during surveillance testing on the solid state protection system. One outage resulted from lost circulating water due to grass plugging five of six circulating water screens. None occurred due to reactor trip breaker malfunctions.
O Salem Unit 2 Unit No. 2 was shutdown for refueling and reactor trip breaker concerns until July 3, 1983. During restart, leaks were identified on Reactor Coolant Pump No. 24; thus, the unit was shutdown to repair the seals.
Restart occurred July 23, 1983. On July 27, 1983 the reactor tripped due to a spurious signal while conducting nuclear instrument surveillance.
During restart several reactor trips occurred due to feedwater control problems. Power operations recommenced August 2,1983. August 11, 1983 another trip occurred due to the grass plugging of circulating water screens. On August 19, 1983 Unit 2 was again shut down to repair hydrogen leaks into the Generator Stator Cooling Water System. Unit 2 is still shut down to complete repairs and modifications to the Stator Cooling System.
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