ML20037A593
| ML20037A593 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/24/1976 |
| From: | Check P Office of Nuclear Reactor Regulation |
| To: | Mcgough J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003160029 | |
| Download: ML20037A593 (2) | |
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MEMORANDUM FOR:
J. M. McGough, STS Group Leader, DOR
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P. S. Check, Chief. Core Perfor :mec Esanch, DSS
SUBJECT:
CRYSTAL RIVER - UNIT 3 TECHNICAL SPECIFICATIONS 3..
The Physics Section of'.the Core Performam e Branch has reviewed the.
Proof and-Review copy of the proposed Technical Specifications for Crystal River - Unit 3.-
The enclosed questions and cc:sents have been prepared.
Paul S. Check, Chief Core Perfor1.ance Branch Divinica of System; Safety w
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QUESTIONSANDCOMMENTSONTHETECHNICALSPECIFICATIONFORCRYSTALRIVER[ UNIT 3-232.1 Does this definition imply that separate quadrant (Definition 1.18) tilt values are measured for the top.and bottom halves of the core? Does the instrumentation permit this.
Technical Specificaiton 3/4.2.4 does not appear to be consistent with this definition.
232.2 (Page B2-1)
Was the W-3 correlation actually used for the DNB analysis rather than the BAW-2 correlation?
232.3 What is the basis for setting the Power-Flow Imbalance (Page B2-5) trip point to 104.5% FP (at 100% flow) rather than at 105.5% FP as in the Nuclear Overpower trip?
232.4 Should the statement from'the Bases 4.0.3 concerning (Spec. 4.0.3) the operation with equipment known to be inoperable in spite of having met the surveillance requirements be moved to the Technical Specification. The Bases section contains the disclaimer that they are not part of the Technical Specification.
232.5 The ordinate on this curve should be "% of A11ewable (Figure 3.1-4)
Power for Pu=p Combination."
232.6 Same cerment as in 232.5 above.
(Figure 3.1-5) 232.7 The action statements a and e seem to require different l
(Spec. 3.2.4) actions for the same condition.
In addition there appears to be na action to be taken if the quadrant i
I power tilt exceeds 9%.
232.8 There is no indication that fuel rod beving has been Bases 3/4.2 considered in establishing the Technical Specifications for Power Distribution Limits.
This effect should be considered. A statistical combination of the bowing penalty with the nuclear uncertainty factor will be considered by the staff if justification is provided.
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