ML20069L830
| ML20069L830 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/27/1983 |
| From: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20069L833 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-1.A.1.3, TASK-2.E.4.1, TASK-2.K.3.03, TASK-2.K.3.13, TASK-2.K.3.15, TASK-2.K.3.19, TASK-2.K.3.22, TASK-2.K.3.27, TASK-2.K.3.45, TASK-TM GL-83-02, GL-83-2, NUDOCS 8305020449 | |
| Download: ML20069L830 (3) | |
Text
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GENERAL OFFICE P.O. BOX 499 COLUMBUS. NEBRASKA 68601-0499 Nebraska Public Power D. tn. t is t
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April 27,1983 Office of Nuclear Reactor Regulation Operating Reactor Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Cemmission Washington, D.C. 20555 Attention:
Mr. D. B. Vassallo, Chief
Dear Mr. Vassallo:
Subject:
Proposed Change No.1 to Technical Specifications - NUREG-0737 Cooper Nuclear Station NRC Docket No. 50-298, DPR-46 In accordance with the applicable provisions specified in 10CFR50, Nebraska Public Power District requests that the Technical Specifications for Cooper Nuclear Station (CNS) be revised to incorporate the changes requested by Generic Letter 83-02 dated January 10, 1983, to all BWR Licensees.
The necessary discussion of each item is contained in the attachment, as are revised Technical Specification pages if applicable.
These changes have been reviewed by the necessary Safety Review Committees and payment for a Class II amendment in the amount of $1,200 is submitted.
The District has initiated a new system to track proposed Technical Specification changes submitted to the NRC and this change is designated Number 1.
Should you have any questions or require additional information, please contact me.
In addition to three signed originals, 37 copies are also j@
submitted for your use.
NNO.
Sincerely, no Y
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\\ 43 Attachments A
3 NUREG-0737 TECHNICAL SPECIFICATION CHANGES IN ACCORDANCE WITH GENERIC LETTER 83-02 1.
STA Training (I.A.1.1.3) -
STA training requirements are under consideration by the Commission and no Technical Specifications are submitted at this time.
2.
Limit Overtime (I.A.1.3) -
In discussions with the staff upon receipt of the June 15, 1982, Generic Letter (82-12) the District was directed to revise the Technical Specifications to state that working hours will be controlled in accordance with a CNS Station Operating Procedure.
This proposed change was submitted November 24, 1982, as Attachment 4.
3.
Dedicated Hydrogen Fenetrations (II.E.4.1) -
In a letter dated September 6, 1982, from J. M. Pilant to D. G. Eisenhut, the District informed the staff that no additional piping or valves are being installed at CNS at this time to meet this requirement; therefore, no Technical Specification changes are necessary.
4.
Containment Pressure Setpoint (II.E.4.2.5) -
The NRC approved the Districts' justification for not changing the setpoint by letter dated October 26, 1981; therefore, no Technien1 Specification changes are necessary.
5.
Containment Purge Valves (II.E.4.2.6) -
The NRC will send model Technical Specifications to the District at a later date.
6.
Radiation Signal on Purge Valves (II.E.4.2.7) -
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The NRC will establish Technical Specifications for this item af ter j
technical resolution of this issue with the BWR Owners' Group.
l 7.
Reporting SV and RV Failures and Challenges (II.K.3.3) -
Pages 231 and 234 of the Technical Specifications are revised to require prompt notification of valve failures and malfunctions and documentation l
of all challenges in the annual report.
8.
RCIC Restart and RCIC Function (II.K.3.13, II.K.3.22) -
The RCIC restart and automatic switchover from the condensate storage l
tank to the suppression pool were implemented utilizing existing level l
instrumentation for both reactor water level and condensate storage tank icvel. The calibration and functional test surveillance requirements for this instrumentation are already addressed by the CNS Technical Specifications.
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i In keeping with the manner in which an analgous functional test for the HPCI system automatic switchover from the condensate storage to the suppression pool is addressed, the District is of the opinion that the functional tests for the RCIC system restart and automatic switchover should be similarly addressed.
The HPCI functional test is addressed by a surveillance procedure without the specific test being covered by the Technical Specifications.
The District proposes that the RCIC tests be handled in the same manner (that is, without modifying the Technical Specifications).
A surveillance procedure revision has been generated to functionally test the RCIC automatic restart on a low water level signal subsequent to a high water level trip.
This procedure will be in ef fect by April 22, 1983.
A surveillance procedure for functionally testing the RCIC automatic switchover from the condensate storage tank to the suppression pool is already in existence.
The necessary Technical ' Specifications for this item were submitted August 26, 1981, and approved with Amendment 75 to the Facility Operating License.
10.
Interlock on Recirculation Pump Loops (II.K.3.19) -
This item is not applicable to CNS since it is a jet pump plant.
11.
Common Reference Level (II.K.3.27) -
A revised Technical Specifications figure defining reactor vessel water levels is attached.
This revised figure, to replace the existing figure in the Technical Specifications, reflects the commitments made to the NRC by the District in previous correspondence on this subject.
12.
Manual Depressurization (II.K.3.45) -
As the NRC stated in Generic Letter 83-02, no Technical Specification changes are required for this item.