ML19253C000
| ML19253C000 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/25/1972 |
| From: | Schwencer A US ATOMIC ENERGY COMMISSION (AEC) |
| To: | John Miller METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7911040009 | |
| Download: ML19253C000 (3) | |
Text
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Docket No. 50-233 l
Metropolitan li.dison Company AITN :
Mr. Joita G. hiller Vice President P.O. Lox 542 Reading, Pennsylvania Cenclemen:
Wo find that we need additional information to couplete our review of your application for an operating license for the Three Mile Island duelear Station, Unit 1.
The specific infonnation required la described in the enclosure.
In order to maintain our licensing review schedule we will need a coupletely adequate response by November 20, 1972. Picase inform us within seven (7) days af ter receipt of this letter of your confirmation of the schedule or tne date you will be able to meu.
If you cannot unet our speciflod dat'e or if your reply is not fully responsive to our requests it is highly likely that the overall schedule for complet-ing the licensing review for this project will have to be ext. nded.
Since reassiganwnt of the staff's efforts will require completica of the new assignment. prior to returning to this project, the extent of l
oxtension will most likely be greater than the extent of delay in your response.
Please contact us if you have any questions regarding the enclosed requests.
Sincerely, l
Original S1gned by Albert Schwencer A. Schwencer, Chief
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Pressurized Water Reactors Branch 4
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Directorate of Licensing p
siclosure:
Request for Additional Information 1505 107 ec:
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Metropolitsa Edison Company OCT 2 51972 cc: General Public Ut111 ries Servica Corporation ATTN: Mr. R. W. Howard Project Manager Safety and Licensing 260 Cherry Hill Road Parsippany, New Jersey 07054 General Public Utilities Servica Corporatic,a ATIM Mr. John L. Thorpe Manager Safety and Licensing 260 Cherry Hill Road Parsippany, Eew Jersey 07054 Gerald Charnoff, Esquire Shaw, Pittman, Potts, Trowbridge and Maddan 910 17th Street, N.W.
Washington, D.C.
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Form AEC Jta iRev. 9-53) AECM 0240
4 REQUEST FOR ADDITIONAL INFORMATION METROPOLITAN EDISON COMPANY DOCKET No. 50-289 14.0 SAFETY ANALYSIS 14.9.1 Provide analyses of the containment pressure-time response for various (i.e., break sizes and break location) postulated design basis loss-of-coc19nt accidents.
Include analysis of a double-ended break at the largest reactor outlet pipe, the reactor coolant pump suction pipe and at the reactor coolant pump discharge pipe as well as a spectrum of smaller pipe breaks at the same locations.
The analyses should be extended, as a minimum, through the blowdown, reflood and post-reflood phases of the accidents (i. e., ab out an hour following the accident).
All assiaptions used in these analyses should be explained.
Assumptions should be selected on a conservative basis in the calculations of containment pressure response.
14.9.2 The reflood model that is used following blowdown should be described in detail.
The description should include the assumptions used to develop the model, e.g., hydraulic modeling of the primary coolant system, resistances of components (primary coolant pump, steam generator, piping and reactor core),
method to compute steam generation in core and energy sources (core stored energy, decay heat, thick and thin metal stored energy, and steam generator stored energy).
14.9.3 If the blowdown model, used for these analyses, dif fers f rom that described in the SAR for containment sizing, the difference should be discussed in datail.
14.9. 4 For the cold Icg break of the size and location resulting in the highest calculated containment pressure (analyzed in 14.9.1 above),
provide tables of mass release (pounds /sec) and the enthalpy of the mass (BTU / pound) released from the core, and the mass and enthalpy released to the containment throughout the blowdown and reflood phases of the accident.
Provide a graph showing core inlet velocity as a function of time for the reflood phase of the accident.
1505 109