ML19220B340
| ML19220B340 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/06/1975 |
| From: | Maccary R Office of Nuclear Reactor Regulation |
| To: | Moore V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904250650 | |
| Download: ML19220B340 (14) | |
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Docket No. 50 -320 g.'b
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MS No. 24-11 V. A. Moore, Assistant Director for Light Water Reactors, Group 2 Division of Reactor Licensing SAFETY E7ALUATION REPORT OF FSAR - THREE MILE ISLAND CIIT 2 Plant Name: Three Mile Island Nuclear Station Unit 2 Licensing Stage: OL Docket No. : 50-320 Responsible RL Branch & Project Manager: LUR 2-2, H. Silver Responding TR Branch & Technical Reviewer: MEB. R. J. Kiessel Requested Co=pletion Date: 10-10-75 Description of Response: Safety Evaluation Report P.eview S tatus :
Co= place, except as noted he Mechanical Engineering Branch has coupleted a review of sections 3.6, 3.9, 3.10, 4.2. 5.2, and 5.5 of the FSAR as amended throurh Ancadment 32.
The appropriate sections of the Safety Evaluation Report are enclosed and are identified by section nunbers and titles used by the applicant in the FSAR.
The sections of the SER provided are conthgent upon the satisfactory resol-ution of the deficiencies noted below. These sections should not be published in the version provided until such resolution has been attained.
Section Deficienev 3.6 The response to second round question 110.18 is not couplete in that part (a) of the question has not been responded to and the changes indicated in the respcuse have not been Ade in the taxt of the FSAR.
3.6 The respcuse to second round question 110.25 is not couplete in thet the stress analyses of the pipe lines has not been com-plated, there is no nention mde of the conponents identified in the response to first round question 11.5, and the changes indicated in the response have not been nade in the text of the FSAR.
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V. A. Moore Section Deficiencv_
- 3. 9. 2 The respcase to second round question 110.21 is not co=clete in that the response does not include sufficient detail to permit evaluation without the referenced document.
3.9.2 The response to second round question 110.2; is not co=plete in that the changes indicated in the response have not been made in the response to first round questien 11.10.
'.:n May 7,1975 the Nuclear Regulatory Commission staff was informed by the Virginia Electric and Power Company that one type of load that would occur in the unlikely event of a cold leg loss-of-coolant accident (LOCA) has been underesti=ated in the original design of the reactor vessel support systes for North Anns Units 1 & 2.
To determine if the same potential siro-blem exists in the case of Three Mile Isladd Unit 2 mid to assess its effects en the reactor vessel support system, a request for additional infer =ation is also forwarded. The applicant's response vill be evaluated and treated inna supplement to the SER.
R. R. Maccary, Assistant Director for Engineering Division of Technical Review cc w/ encl:
D. Eisenhut, MRR R, E. Heimman, TR ce v/o encl:
S. Varga, RL W. G. Mcdonald, MIPC M. Kehne=uyi, TR R. 3cyd, RL NRR: Docket No.
J. P. Knight, TR TR: Rdg. File R. J. 3 snak, n TR: ME2 Rdg. File H. Silver, RL R. J. Kiessel TR TR:ME3g TR:ME3rg/
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