ML20054L315

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Forwards Revised Schedules for Completing NUREG-0737,Items II.B.3, Reactor Coolant Post-Accident Sampling Sys, II.F.1.1, Main Steam Line Radiation Monitor, & II.F.1.2, Sampling Sys for Iodines & Particulates
ML20054L315
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 06/30/1982
From: William Jones
OMAHA PUBLIC POWER DISTRICT
To: Clark R
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-TM LIC-82-252, NUDOCS 8207070381
Download: ML20054L315 (5)


Text

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Omaha Public Power District 1623 HARNEY a OMAHA, NEBRASMA 68102 m TELEPHONE 536-4000 AREA CODE 402 June 30, 1982 9

LIC-82-252 Mr. Robert A. Clark, Chief U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch 'o. 3 Washington, D.C. 20555

Reference:

Docket No. 50-285

Dear Mr. Clark:

Schedules for Completing Selected NURFG-0737 Tasks Omaha Public Power District's letters to the Commission dated April 1 and April 30, 1982 identified the District's expected schedule for completing several NUREG-0737 modifications at thc irt Calhoun Station. Specifically, tasks II .B.3, II .F.1.1, n:e II.F.1.2 were delayed due to equipment delivery and construc' o. problems. Further equipment delivery and system testing problems have again delayed the completion of these modifications. The explanation for these delays and the revised schedules are attached.

Sincerely, y((f vm:p W. C. ' Jones Division Manager Produption Operations Attachment cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.

Washington, D.C. 20036 Oh 8207070381 820630 DR ADOCK 05000285 PDR

ATTACIIMENT 1 Task Action Plan Item II.B.3: Reactor Coolant Post Accident Sampling System NUREG-0737 Required Completion Date: January 1, 1982 Present Status and Reasons for Delay:

The installation and testing for this modification was expected to be complete June 30, 1982. During the testing phase, several unanticipated equipment and design problems were encountered, and these have delayed the completion of this system. The District would like to emphasize that the Post-Accident Sampling System for the Fort Calhoun Station is a unique system which will be used for sampling during both post-accident and normal conditions. This has required the purchase and installation of several state-of-the-art instruments and has re-quired a lengthy pre-operational testing procedure to simulate both normal and post-accident conditions. With the exception of the- following items detailed below and other minor hardware problems, the necessary actions have been com-pleted to correct the problems encountered during system testing.

1. During pre-operational testing, the Ion Chromatograph, which will be uti-lized to accurately detect Reactor Coolant boron and chloride levels, would not function as intended. The District is presently investigating the prob-lem but it is expected that several weeks will be required to correct the problem. In the interim, boron and chloride levels can be obtained using a diluted grab sample from the Post Accident Sampling System and these sam-ples can be evaluated utilizing equipment from the llot Lab. This interim sampling will be available commencing July 2, 1982.
2. During installation of the Canberra Intrinsic Gamma detectors and the associ-ated computer hardware, part of the equipment was accidentally dropped. The damaged equipment was returned to the vendor and repaired. This equipment is now installed and ready for calibration. However, to calibrate, a gas sample is needed from the National Bureau of Standards which is expected to be ship-ped to Fort Calhoun on July 19, 1982. Calibration is expected to be completed by August 10, 1982. As an interim measure, a sample, if necessary, can be collected and diluted using the Post Accident Sampling System and evaluated using the existing plant GeLi detector.
3. The District recently determined that the pli cell needs to be provided with overpressure protection or modified to withstand higher pressures. The District is presently evaluating which alternative is better from an opera-tional and safety standpoint.

In addition, for the system to be declared fully operational, the District must complete system training, and write several operational procedures which must be approved by the plant staff. Assuming that no further problems are encountered during the remaining system testing and that training commences the first week of July, 1982, the correction of the items identified above should be completed by the end of August, 1982. Allowing one month for contingencies, and plant acceptance of the system and operational procedures, the system should be fully operational by September 30, 1982.

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  • ATTACllMENT 1 (CON'T)

Expected Completion Date:

September 30, 1982 Interim Heasures:

In accordance with the requirements of NUREG-0578, Item 2.1.8.a, Interim Post Accident Sampling procedures were developed and have been accepted by the Com-mission as detailed in the Commission's letter to the District dated April 7, 1980. Also, as described above, in case of an emergency, the above detailed interim sampling measures can provide adequate Reactor Coolant sampling and analysis.

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ATTACllMENT 2 Task Action Plan Item II.F.1.1: Main Steam Line Radiation Monitor NUREG-0737 Required Completion Date: January 1, 1982 Present Status and Reasons for Delay:

The Main Steam Line Radiation Monitor was ordered from Victoreen, Inc. to be initially delivered by December 15, 1981. Victoreen then extended the delivery of the monitor to April 30, 1982. Accordingly, the District expected to complete the monitor installation and have it operational by June 30, 1982. However, the Main Steam Line Radiation Monitor was not received at the Fort Calhoun Station until June 10, 1982. Additionally, the detailed installation drawings were not received by the District until May 28, 1982. The late receipt of the installa-tion drawings resulted in a delay in issuing the Final Design Package for Plant Review Committee (PRC) approval. The PRC is presently expediting its review and approval of the design package. Assuming the monitor installation commences in mid-July,1982 and allowing six (6) weeks for installation, testing and calibra-tion, six (6) weeks for operator training, and two (2) weeks for contingencies, this monitor is expected to be operational by October 30, 1982.

Expected Completion Date:

October 30, 1982 Interim Measures:

In accordance with the requirements of NUREG-0578, Item 2.1.8.b.1, Interim Post Accident procedures were developed and have been accepted by the NRC, and can be ef fectively utilized, if necessary.

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ATTACHMENT 3 Task Action Plan Item II.F.1.2: Sampling System for Iodines and Particulates NUREG-0737 Required Completion Date: January 1, 1982 Present Status and Reasons for Delay:

The Wide Range Noble Gas Monitor and Sampling System for Particulates and Iodines were ordered from Victoreen, Inc., to be initially delivered by December 1, 1981.

Victoreen then extended the delivery of the system to May 8, 1982. Accordingly, the District's latest expected completion date for this task was July 30, 1982.

The May 8, 1982 delivery date was then revised to June 30, 1982, but the District has recently been informed that the June 30, 1982 date cannot be met and the ten-tative delivery date is now July 30, 1982. Additionally, Victoreen must provide the District with detailed installation dr wings which will permit the District to conduct the necessary pre-installation design work. Victoreen has stated these drawings will be provided in the near future. Provided the above schedules are met, and allowing eight (8) weeks for installation, testing and calibration, six (6) weeks for operator training, and two (2) weeks for contingencies, this samp-ling system is expected to be operational by November 30, 1982.

Expected Completion Date:

November 30, 1982 Interiru Measures:

In accordance with the requirements of NUREG-0578, Item 2.1.8.b.1, Interim Post-Accident procedures were developed and have been accepted by the NRC and the interim procedures can be effectively utilized, if necessary.

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