05000387/LER-1982-070, Forwards LER 82-070/03L-0

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Forwards LER 82-070/03L-0
ML20064H526
Person / Time
Site: Susquehanna Talen Energy icon.png
Issue date: 01/07/1983
From: Keiser H
PENNSYLVANIA POWER & LIGHT CO.
To: Haynes R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20064H534 List:
References
PLA-1475, NUDOCS 8301170332
Download: ML20064H526 (1)


LER-2082-070, Forwards LER 82-070/03L-0
Event date:
Report date:
3872082070R00 - NRC Website

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/ pg Northern States Power Company 414 Nicollet Mall Minneapoks. Minnesota 55401 Telephone (612) 330 5500 January 6, 1983 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 s

Implementation of Appendix I Technical Specifications on December 17, 1982 Amendment No. 15 to the Monticello Full Term Operating License was issued. This amendment authorized changes to the Technical Speci-fications to implement Appendix I of 10 CFR Part 50. These changes became effective on January 1, 1983. The purpose of this letter is to provide infor-mation related to three areas where work is still in progress to achieve full compliance with the new Technical Specifications.

Reactor Building Vent Isolation Section 4.8.B.1.B requires that noble gas effluent monitor gaseous release termination setpoints be determined in accordance with the ODCM. We intend to meet this require-ment for the reactor building vent by means of the wide range noble gas monitors installed in response to the TMI Action Plan. However, spurious alarms have been experienced from these complex new monitors; the frequency of the alarms is such that the reactor building ventilation would be isolated one or more times per day. These events are distracting to the operators and provide unnecessary challenges to safety systems such as the Standby Gas Treatment System. We are cooperating with the equipment supplier in resolving this problem in a timely manner but we feel that it would not be prudent at this time to implement the reactor building vent isolation using these monitors. Consequently, we will continue to initiate the isolation by means of the existing ventilation plenum monitors at the 6.3 mr/hr setpoint previously specified in Technical Specification 3.2.E.2.(a). Our review indicates that this setpoint is equivalent to the dose rate limits of Technical Specification 3.8.B.1.a.1. Upon correction of the spurious alarm problem, the isolation function will be pro-vided by the wide range noble gas monitors.

8301170322 830106 PDR ADOCK 05000263 P PDR

, NORTHERN CTATED POWER COMPANY o

Director of NRR January 6, 1983 Page 2 Discharge Canal Sample Monitor The New Technical Specifications require calibration for the discharge canal monitor once each operating cycle using a source traceable to National Bureau of Standards (NBS) standards.

This monitor must be in service at all times.

The existing monitors were never calibrated using a liquid source traceable to NBS standards. To permit this calibration to be done, the existing large carbon steel sample tank will be replaced with two smaller tanks. These tanks will be designed so they can be easily decontaminated. Each tank will have a detector. This will allow one detector to remain in operation while the other detector is being calibrated.

This modification will be completed in 1983 permitting the next calibration to be performed using a traceable source.

Turbine Building Roof Vents The new Technical Specifications contain no requirements for monitoring turbine building releases. Northern States Power Company committed to reroute all of the turbine building roof vents to the reactor building ventilation stacks which are continuously monitored. This modification was not completed during the last refueling outage, however. The modification is now scheduled for completion during the 1983 refueling outage.

Until this modification is completed, the turbine building roof vents will be tagged closed. No unmonitored release from the turbine building will be possible. The vents will be used only in the event of a fire emergency in the turbine building.

Delay in completion of this modification was due to engineering design changes required to meet our own specifications and those of our insurance company. A final approved design is now available. To satisfy ALARA requirements, however, the plant must be shut down while working on this modification.

The radiation levels on the turbine building roof are on the order of 30 to 50 mrem /hr during power operation.

Please contact us if you have any questions concerning these three modifications.

We believe the actions that are being taken until work is completed satisfy the intent of the new Technical Specification requirements and that full compliance with these new requirements will be achieved in a timely manner.

& k-w O David 'tuantf Manager - Nuclear Suppor Services DMM/hd cc: Regional Administrator-III, NRC NRR Project Manager, NRC NRC Resident Inspector G Charnoff