ML19210A714
| ML19210A714 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/29/1976 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Arnold R METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7910310533 | |
| Download: ML19210A714 (5) | |
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[istribution NRC PDR Local PDR ORB 4 Rdg KRGoller Docket No. 50-239 TJCareer WR 2 O 1978 OELD OISE (3)
RWReid DBridges Metropolitan Edison Company RIngram A1TN:
Mr. R. C. Arnold DEisenhut Vice President - Generation TAbernathy P. O. Box 542 JBuchanan Reading, Pennsylvania 19603 ACRS (16)
VStello Gentlemen:
file We are currently reviewing your reload application of February 11, 1976 for the Three Mile Island Nuclear Station Unit 1 Cycle 2 core.
In order for us to complete our review it will be necessary for you to provide additional information in support of this application.
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Specific questions and areas needing further attention are itemized in the enclosure to this letter.
In order to keep the reload application review timely, you are requested to provide this information within 10 days of the receipt of this letter.
Your reply should include three (3) signed originals and 37 copies of the requested information.
Sincerely, ed WI e
Robert W. Reid, Chief Operating Reactors Branch No. 4 Division of Operating Reactors
Enclosure:
Request for Additional Information 1490 315 ec:
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March 29, 1976 o
Docket No. 50-289 Metropolitan Edison Com'pany ATTN:
Mr. R. C. Arnold Vice President - Generation P. O. Box 542 Reading, Pennsylvania 19603 Gentlemen:
We are currently reviewing your reload application of February 11,19',5 for the Three Mile Island Nuclear Station Unit 1 Cycle 2 core.
In order for t.s to complete our review it will be necessary for you to provide additional infomation in support of this application.
Specific questions and areas needing further attention are itemized in the enclosure to this letter.
In order to keep the reload application review timely, you are requested to provide this information within 10 days of the receipt of this letter.
Your reply should include three (3) signed originals and 37 copies of the requested.information.
Sineerely, l
,O
, j_, 4 4 M.
Robert W. Reid, Chief Operating Reactors Branch No. 1 Division of Operating Reactors
Enclosure:
Request for Additional Information cc:
See next poge 1490 316
Metropolitan Edist Company March 3, 1976 cc:
w/ enclosure G. F. Trowbridge, Esquire Shaw, Pittman, Potts, Trowbridge 5 Madden Barr Building 910 17th Street, N. W.
Washington, D. C.
20006 GPU Service Corporation Richard W. Heward, Project Manager Thomas M. Cric. mins, Jr., Safety
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and Licensing Manager 260 Cherry Hill Road Parsippany, New Jersey 07054 Pennsylvania Electric Company Mr. R. N. Conrad Vice President, Generation 1001 Bread Street Johnstown, Pennsylvania 15907 Mr. %cidca B. Archart, Chairnan Board of Supervisors of Londonberry Township 214S Foxiana P. cad Middletown, Pennsylvania 17057 Miss Mary V. Southard, Chairman Citizens for a Safe Environment P. O. Box 405 Harrisburg, Pennsylvania 17108 Government Publications Section State Library of Pennsylvania Box 1601 (Education Building)
Harrisburg, Pennsylvania 17126 1490 317 i
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REQUEST'FOR ADDITIONAL INFORMATION CYCLE 2 RELOAD THREE MILE ISLAND UNIT 1 1.
Three Mile Island, Unit 1, submittal of February 11, 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 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 measurements.
(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.
1490 318
2 2.
Rod bowing is not etasidered in the report. A discussion should be included on the effect of rod bowing and either justification given for not including the effects or revised technical specifications to account for rod bowing should be proposed.
3.
Provide justification for the moderator and doppler coefficients used in the accident and transient analysis (Table 7.1-1 of Reload Report) and explain how these values relate to those listed in Table 5.1-1.
4.
Indicate which of the values listed in Table 5.1-1 were observed in actual Cycle 1 operation and compare these observed values with calculations.
Parameters of specific interest include critical boron concentrations, control rod worths, and core temperature coefficients.
5.
It is our understanding that the check value proposed in your correspondence of April 19, 1975 to address the problem of long term cooling capability following a loss-of-coolant accident (LOCA) will not be availeble for installation prior to startup of Cycle 2.
If this is the case it will be necessary for you to provide specific information on how power would be restored to the necessary values following a failure of the 1C Engineered Safeguard Valve 480V control center prior to utiliti:ation of that aspect of the cooling system.
O O
1490 319