ML19253B659
| ML19253B659 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/08/1976 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Goller K Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910160745 | |
| Download: ML19253B659 (2) | |
Text
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P00R ORENAl.
Karl R. Goller, A:sistant Diracht for 0;erating Reacters Division of Operatina Reactors TdREE MILE ISLKiD - t: LIT 1 Pl. LOAD (TAR-337")
PLXiT MAME: Thrae Mile Island, Unit 1 DOCXET.10.:
3'>-283 PROJECT 3RAtiQf A'lD PROJECT MNIAGER: ORS-4, D. 3ridaes REVIEW BRKiCH: Reactor Safety REVIE'4 STATUS: Awaiting Information The Raactor Safety Branch is reviewinn %tropolitan Edison's request for a technical specification change for the Three Mile Island, Unit i reload.
Attached is a list of additional infonr.ation we require to continue our review.
-: ~ir.; sie.ned by
.a umat Darrell G. Eisenhut, Assistant Director for Ocerational Technology Division of Operating Reactors Attac.hant:
As stated cc:
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50-289 THREE MILE ISLAND, UNIT 1 ADDITIONAL INFORMATION REQUEST 1.
The Three Mile Island, Unit 1, submittal of February 1,1976, is based on measured core flow rate (with 1.5% margin) rather than the design flow rate. The use of measured rather than design flow rate is acceptable to the staff provided:
(1) The flow measurement technique is acceptable.
(2) An error analysis is provided for the data measured.
(3) There is adequate conservatism between the flow rate actually measured and the flow which was used to develop plant technical specifications.
(4) There is periodic surveillance and/or additional testing to assure that the core flow rate does not decrease as a result of crud buildup, steam generator tube plugging, or other causes.
Based on these considerations, provide the following:
(1) A description of the flow measurement technique used along with the data measured and an error analysis for the meas urements.
(2) A discussion of the bases for the power to flow into reactor trip setting and the overpower trip setting (if it is based on measured flow).
(3) A proposed surveillance and/or test program to confirm that the value of the core flow rate has not decreased below the value used as the basis for reactor power / flow trip (and/or the overpower trip), including appropriate uncertainties.
2.
Rod bming is not considered in the report.
A discussion should be included on the effect of rod bming and either justification given for not including the effects or revised technical specifications to account for rod bowing should be proposed.
1445 226
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