ML20039D604
| ML20039D604 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 12/28/1981 |
| From: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.C.1, TASK-2.B.3, TASK-2.F.1, TASK-2.K.3.22, TASK-2.K.3.28, TASK-2.K.3.30, TASK-2.K.3.31, TASK-TM LQA8100279, NUDOCS 8201050250 | |
| Download: ML20039D604 (3) | |
Text
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GENERAL OFFICE P. O. Box 499, COLUMRUS, NEHR ASKA 68601 Nebraska Publ. Power D. tr. t rEtEmo~E i.ome.sei ic is ic
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LQA8100279 O
December 28, 1981 q
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JAN5 1982> 78 aminarmerm Mr. Darrell G.
Eisenhut, Director
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g Division of Licensing Otfice of Nuclear Reactor Regulation t
U U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Post TMI-Requirements /NUREG 0737 Cooper Nuclear Station NRC Docket No. 50-298, CPR-46
Reference:
- 1) Letter from D. G. Eisenhut to All Licensees dated October 31, 1980
Dear Mr. Eisenhut:
Reference 1 required Nebraska Public Power District to complete or address certain TMI Action Plan Requirements by January 1, 1982.
Attached are discussions of the applicable items.
If additional clarif! cation on any item is necessary, please contact me.
Sincerely, M. Pilant Division Manager of Licensing and Quality Assurance JMP:JDW:cmk Attachment
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Page 1 of 2 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION NUREG 0737 IMPLEMENTATION EFFORTS REQUIRED AS OF JANUARY 1, 1982 I.C.1 - Short Term Accident & Procedures Review-Emergency Procedure Guidelines NUREG 0737 required that the EPG's be implemented by the first refueling outage in 1982.
Presently, it is the District's intent to refuel during May 1982. As the staff has been kept informed on the efforts of the BWR Owners Group to develop comprehensive EPG's, it is doubtful at this time whether the Owners Group efforts will be completed in time to allow the District to revise the CNS Emergency Procedures and adequately implement them by the required due date.
II.B.3 - Post Accident Sampling System This system has been installed and is operational.
II.F.1 - Accident Monitoring Instrumentation-Noble Gas and Iodine Particulate As acknowledged in the letter from T. A. Ippolito to J. M. Pilant dated Novcmber 18, 1981, the staff is aware of the delivery problems associated with the Victoreen instruments.
This modification involves tying together exhaust vents from the augmented radwaste and radwaste buildings into one common exhaust.
It is anticipated that this instal-lation will be completed prior to startup from the May 1982 refueling outage.
As regards technical deviations from the positions sta'ted in NUREG 0737, the District has been informed by our Architect-Engineer that the Victoreen system provides a continuous recording display in units of counts per minute (CPM).
NUREG 0737 states that the detector output be continuously recorded in units of Xe-133 (equivalent) concentrations or n'. Ci/cc of actual noble gases. The CNS system will require a simple manual conversion to obtain results in the NUREG 0737 specified units dependent upon the actual flow rates.
II.F.1 - Accident Monitoring Instrumentation-Containment Pressure, Level and Radiation The Containment Pressure and Level instrumentation has been installed and is operational.
The Containment Radiation instrumentation has been installed and is operational; however, the cable currently used to connect the sensor instrument package to the drywell penetration does not meet the required environmental qualifications. As soon as the vendoc is able to supply qualified connectors and cable, the existing cable will be replaced with qualified parts at the next plant outage of sufficient duration.
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Page 2 of 2 o
II.K.3.22 - Automatic Switchover of RCIC System Suction This modification has been completed.
II.K.3.28 - Oualification of ADS Accumulators The District was to verify that the accumulators for the ADS valves are provided with sufficient capacity to cycle the valves open five tiscs at design pressures, even considering normal leakage. Addi-tionally, air (or nitrogen) leakage through valves must be accounted for in order to assure that enough inventory of compressed air is available to cycle the ADS valves. As stated in our response to IE Bulletin 80-01 on January 16, 1980, the ADS accumulators were tested in November 1973 during the CNS preoperational testing. The tests were designed to verify that each accumulator could actuate the associated relief valve at least five times upon loss of air supply to the system. Testing of the ADS accumulator system to assure that j
the system performs as described in the FSAR, is performed once per cycle. The accumulator check valven at CNS have resilient seats.
The District was also to verify that the accumulators on the ADS valves are capable of performing their function for 100 days following an accident. The normal supply of gas to the SRV's is nitrogen from the containment inerting system.
Instrument air floats on the system and will provide a pneumatic supply if the nitrogen system f ails.
The plant air compressors are supplied with on-site (i.e. diesels or main generator) power.
Components are located to make the active portions of these systems accessible under post-LOCA conditions.
The accumulators, piping, and check valves associated with the ADS pneumatic supply are Seismic Class I.
The piping from the isolation valve outside containment to the ADS accumulator check valve is built to Seismic Class I criteria.
Postulated pipe breaks within the drywell were analyzed in the FSAR and loss of the normal ADS supply woulJ not result from a pipe break which requires ADS.
It can be concluded that the accumula-t' rs will be capable of performing their function over the 100 day o
period.
II.K.3.30 - Revised Small-Break LOCA Methods to Show Compliance with 10CFR50 Appendix K As a result of meetings with the NRC, GE submitted on June 26, 1981 the final program results which showed that the existing GE small break LOCA model already satisfies the concerns of NUREG 0626 and is in compliance with 10CFR50 Appendix K.
II.K.3.31 - Compliance with 10CFR50.46 As indicated in the response to II.K.3.30. this item is satisfied by the existing Plant Unique ECCS Analysis filed on the CNS docket.
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