ML20141J881

Forwards Proposed Amend to Permit Natural Circulation Test & Issues for Telcon Discussion

ML20141J881
Person / Time
Site:	Catawba
Issue date:	08/19/1997
From:	Tam P NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
TAC-M98728, NUDOCS 9708210382
Download: ML20141J881 (3)

Text

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 206tWM001 August 19. 1997 MEMORANDUM FOR: ' Docket" File; FROM: Peter S. Tam. Senior Project Manager Project Directorate 11-2 ( p Division of Reactor Projects - I/II ' ,

Office of Nuclear Reactor Regulation

SUBJECT:

CATAWBA UNIT 1 - PROPOSED AMENDMENT TO PERMIT A NATURAL CIRCULATION TEST (TAC M98728)

REFERENCE:

Memorandum. T. E. Murley to all NRR employees. June 20, 1988 (NRR Office Letter No.106. Revision No.1)

The attached message was faxed today to Robert Sharp and Mike Kitlan of Duke Power Company. The sole purpose of the message is to prepare Duke Power Company personnel for a conference call. While the staff may later formally communicate all or parts of the same mesnge, the message in its present form does not constitute a formal request for information or represent an NRC staff position.

Docket Numbers 502413 Distribution PUBLIC H. Berkow M..Shuaibi. 0-8 E23 3Fbl l

9708210382 970819 PDR ADOCK 05000413 P PDR

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i Catawba Nuclear Station, Unit 1 Proposed Amendment on Natural Circulation Issues for Telephone Discussion i

1. Test procedure and the t. jor recovery steps in the procedures that you stated would be used for recovery from the test.

2. The staff requests that should you experience problems which result in terminating the test, that you consult with us and get concurrence prior to any subsequent attempts.

3. An analysis or evaluation of the test you wish to perform. Include any evaluations that were performed during the steam generator replacement L effort to justify the replacement steam generator with respect to natural circulation and Branch Technical Position RSB 5-1.

4. During the initial test you experienced a-problem with the reactor coolant Jump that 'you described as follows: "

.. a reactor coolant pump could not 3e restarted for a period-of time at the completion of the test due to a high stand pipe level." Discuss how this problem will be prevented in this test. Discuss this not only'from the_ perspective of violating technical specifications out from the perspective of being able to start the pump.

5. The initial test was required to be performed at. core burnups which ensure that no significant core decay heat levels are present. In that case, a reactor trip would effectively terminate the event. In your pro)osed test you will use decay heat to conduct the. test and therefore, will lave significant decay heat. Justify conducting the test with the amount of decay heat that would be present and discuss any contingencies that you will have in place to cool the core in case of unexpected system behavior.

6. Discussion of how you will ensure that the RCS is in a loops-filled condition at the start of and throughout the test.

7. - Discuss any special training (class room, briefings, simulator, etc.) that the operators were/will be provided prior to conducting this test.

8. Discuss your reasoning for not conducting the entire natural circulation test including confirmation of boron mixing, auxiliary feedwater inventory, steam generator relief valve gas supply, etc..

9. In your submittal you provided a list of example test termination criteria.

Is there a complete list of the real test termination criteria and a list of expected values for the same parameters?

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10. In your submittal you state that the operators will1 verify natural circulation by observation of the wide range loop temperatures and core exit thermocouple. Explain how this verification is accom>l1shed and the

_ type of training-operators received in this regard (i .e. 10w will operators _know 1.f they have_ natural circulation).

11. Prerequisites for the test including those related to AFW system status. SG ,

relief valve' status, charging /high head safety injection system status, i etc. i l

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