ML19253C006
| ML19253C006 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/28/1972 |
| From: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | John Miller METROPOLITAN EDISON CO. |
| Shared Package | |
| ML19253C007 | List: |
| References | |
| NUDOCS 7911040014 | |
| Download: ML19253C006 (4) | |
Text
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UNITED STATES
- D ATOMIC ENERGY COMMISSION e$
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'*l WASHINGTON. D.C. 20545 i
f Docket No. 50-289 SEP 2 8 1972 Metropolitan Edison Company ATTN:
Mr. J. G. Miller Vice President.
P. O. Box 542 Reading, Pennsylvania 19603 Gentlemen:
In our continuing review of your application to operate the Three Mile Island Nuclear Station, Unit 1, we find that addi-tional information is needed to complete our evaluation. The information required is described in the enclosure.
We had requested and discussed this informstion verbally in meetings and via telephone with members of your staff during the past 2 months. Your immediate response to the requested additional information is required to maintain our present schedule for the November ACRS review of your application.
We have informed Mr. D. Reppert, General Public Utilities Company, of this letter and the required information.
Sincerely, R. C. DeYo., Assi tant Director for Pressurized Water Reactors Directorate of Licensing
Enclosure:
Request for Additional Information ec: w/ enclosure:
See page 2 f
1505 117 7911040 0/ 7
/9
i Metropolitan Edison Company cc: w/ enclosure General Public Utilities Service Corporation ATTN:
Mr. R. W. Heward Project Manager 260 Cherry Hill Road Parsippany, New Jersey 07054 General Public Utilities Service Corporation ATTN:
Mr. J. R. Thorpe Safety and Licensing Manager 260 Cherry Hill Road Parsippany, New Jersey 07054 Shaw, Pittman, Potts, Trowbridge & Madden ATIN:
Mr. Gerald Qiarnoff 910 17th Street, NW Washington, D. C.
20006 1505 118
REQUEST FOR ADDITIONAL INFORL\\ TION THREE MILE ISLAND NUCLEAR STATION, UNIT 1 DOCKET NO. 50-289 9.0 AUXILIARY Aa0 EMERGENCY SYSTEMS 9.4 In Section 9.7.1 of your FSAR it is stated that the fuel handling crane (110-ton capacity) is prevented by interlocks to pass over the spent fuel pool during " normal operations."
' Specify the meaning of " normal operations." Provide the design bases and a description of the cperations of this crane; in particular discuss and describe the provisions available to prevent heavy loads from passing over stored fuel when fuel handling is and is not (normal) in progress.
9.5 It appears from Figure 9-18 of your FSAR that the maximum drop height for a fuel cask is 43 ft et during transfer operations of a fuel cask onto a rail car. What methods are provided to prevent dropping the cask through this heigh t.
Provide the results of an analysis of this accident that includes the radiological consequences.
1505 119
13.0 INITIAL TESTS AND OPERATIONS 13.4 In our request for additional information dated August 8,1972, we listed seven specific tests that should be included in your proposed Power Ascension Tes tiIg Program, FSAR Table 13-2.
Four of these required tests were included in Amendment 28, dated August 31, 1972, the remaining three tests were declined in your letter dated August 22, 1972. We have reviewed your reasons for declining these tests and have concluded that they must be included in your Power Ascension Testing Program.
Provide a commitment and a test abstract of the following tests to be conducted during the Poser Ascension Testing Program:
Generator Trip Test Effluents and Effluents Monitoring System Test Shutdown from Outs'ide Control Room Test
- 13.."
We understand that your interpretation of the Loss of Offsite Power Test to be conducted during the Power Ascension Test Program does not include the loading of the diesel generators.
Provide an abstract of the Loss of Offsite Power Test that includes the loading of th.e diesel generators.
1505 120
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