ML20052D772
| ML20052D772 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/30/1982 |
| From: | William Jones OMAHA PUBLIC POWER DISTRICT |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-737, TASK-1.A.3.1, TASK-2.B.2, TASK-2.B.3, TASK-2.B.4, TASK-2.E.1.2, TASK-2.E.4.2, TASK-2.F.1, TASK-TM LIC-82-180, NUDOCS 8205070201 | |
| Download: ML20052D772 (5) | |
Text
Omaha Public Power District 1623 HARNEY OMAHA, NEBRASMA 68102 TELEPHONE S36-4000 AREA CODE 402 April 30, 1982 LIC-82-180 m
b REcy,VED Mr. Robert A. Clark, Chief
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/Sg, 'Tg U. S. Nuclear Regulatory Commission a
Office of Nuclear Reactor Regulation Division of Licensing 3
Operating Reactors Branch No. 3 D
Washington, D.C.
20555 N
Reference:
Docket No. 50-285
Dear Mr. Clark:
Subject:
Schedules for Completing NUREG-0737 Tasks The Commission's letter to the Omaha Public Power District, dated March 17, 1982, requested the District identify its schedule for im-plementing several tasks identified in NUREG-0737 which were scheduled to be implemented between July 1, 1981 and March 1, 1982.
The tasks of concern were detailed in Enclosure 1 of the March 17, 1982 letter. For those tasks listed on Enclosure 1 of the March 17, 1982 letter, con-firmation that the task is complete or a revised schedule with justi-fication for that revision is provided in Attachment 1 to this letter.
Attachments 2 and 3 detail compensatory measure-taken in the interim pending full implementation of the three tasks not completed on schedule.
Siqcerely, l \\,
W. C. Jones Divisi n Manager j
Produi: ion Operations Attachments cc:
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, D.C.
20036 i
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PDR ADOCK 05000205 P
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STATUS OF NUP.EG-0737 TASKS FOR THE FORT CALHOUN STATION Item Title Requirement Status I.A.3.1 Simelator Exams Include simulator exams in licensing exams, Completed October 1, 1981.
II.B.2 Plant Shielding Modify facility to provide access to vital Complete, with the exception areas under accident conditions.
of painting and cutting an access opening in the ceiling to allow access to the radwaste panel area. The permanent opening, the removable plug and painting are expected to I
be in place by May 30, 1982.
However,.from a functional standpoint, this modification is considered complete.
II.B.3 Post-Accident Sampling Install up' grade post-accident sampling Due date revised to June 30, 1982, capability.
as detailed in District's letter dated April 1,1982. See Attachment 2.
II.B.4 Training for Mitigating Complete training program.
Compl ete.
See District's letter Core Damage dated December 28, 1981.
l II.E.1.2 Auxiliary Feedwater
- Modify instrumentation to level.of safety Complete. See District's letter Initiation and Flow g rade, dated December 28, 1981.
Indicator II.E.4.2 Containment Isolation Part 5 - Lower containment pressure setpoint Complete. Part 5 closed out by Dependability to level compatible with normal operation.
Commission's letter to the District Part 7 - Isolate purge and vent valves on dated February 24, 1982.
For Part radiation signal.
7, see District's letter dated February 12, 1982.
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' Item Title Requirement Status II.F.1
. Accident Monitoring (1)
Install-noble gas effluent monitors.
(1) Revised due date to June 30, 1982. See District's letter-dated April 1, 1982 and Attach-ment 3.
(2) Provide capability for effluent monitoring (2) Revised due date to June 30, of iodine.
1982. See District's letter dated April 1,1982 and Attach-ment 3.
(3)
Install in-containment radiation-level (3) Complete. See District's moni tors.
letter dated December 28, 1981.
(4) Provide continuous indication of (4) Complete. See District's containment pressure.
letter dated December 28, 1981.
(5) Provide continuous indication of (5) Complete. See District's containment water level.
letter dated December 28, 1981.
(6) Provide continuous indication of (6)
Installation completed hydrogen concentration in containment.
December 31, 1981.
See District's December 28, 1981 i
and March' 10, 1982 letters.
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TASK II.B.3 POST-ACCIDENT SAMPLING INTERIM MEASURES In response to NUREG-0578, Task 2.1.8.a, the District implemented interim procedurts using existing equipment for obtaining and analyzing reactor coolant and containment atmosphere samples following an accident.
These interim procedures were reviewed and approved by ONRR during a plant visit on March 7,1980, as documented in the Commission's letter i
dated April 7, 1980.
During a subsequent inspection by IE (IE Report 81-12), a concern was identified regarding compliance with the personnel
. exposure limits using NUREG-0737 source terms.
The District has recently completed a reanalysis of the potential (worst case) personnel radiation exposure utilizing the existing interim sampling equipment and has determined that additional measures need to d
be taken to allow for interim post-accident sampling capability follow-ing most accident scenarios. The new permanent sampling system has been installed and is currently undergoing pre-operational testing, cali-bration, and personnel training.
It is presently expected that the permanent system will be operational by June 30, 1982.
In~the interim, improvements are being made to our existing capabilities to obtain reactor coolant system samples.
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TASKS II.F.1(1) AND II.F.1(2)
EFFLUENT fiOBLE GAS AND IODINE MONITORING INTERIM MEASURES In response to NUREG-0578, Task 2.1.8.b, the District developed interim procedures and/or installed temporary equipment for effluent monitoring of noble gas and radiciodine.
These interim measures were found accept-able by the Commission, as documented in the Commission's letter dated April 7, 1980.
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