ML18025A495
| ML18025A495 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/05/1975 |
| From: | Curtis N Pennsylvania Power & Light Co |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18025A495 (4) | |
Text
.NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL i
(TEMPORARYFORM)'MT r
FILE r
r FROM. Pennsylvania Per 5 Light Allentown, Eh N W Curtis TO:
Mr.
W A Butler DATE OF. DOC 6-5 ORIG 1 signed DATE. R EC'D 6=9-75 CC OTHER LTR XX TWX RPT SENT tRC PDR SENT LOCAL PDR OTHER CLASS UNC LASS KQGK PROP INFO INPUT NO CYS REC'D
. DOCKET NO:
50-'3 88 DESCRIPTION: Ltr with attachment re our letters of 4-17-75, end 4-2Q-75
~ provides add. info with regards to the LDCA related suppression pool hydrodynamic phenomena...
ENCLOSURES:
PLANT NAME:
Susquehana 1 5 2 FOR ACTION/INFORMATION
~ BUTLER (L)
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18101 June 5,
1975 Dr. h'alter R. Butler, Chief Light llater Reactors Branch 1-2 Division of Reactor Licensing U.S. Nuclear Regulatory Commission washington, D.C.
20555 SUSQUEHANNA SES ADDITIONAL INFORMATION-CONTAINKNT DESIGN ER 100450 FILES 840-2, 170 PLA-69
Dear Dr. Butler:
R'BPIlÃAflff)nl!IPft-I[a
- .".'-.'eLQtlgg "-.-
Jgy e) ci) I Docket Nos.
50-387 Ic) 50-388 ggUNIS litnil)Aj)C
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ig Your letter of April 17, 1975 indicated that the NRC requires additional information relative to the design of the containment for the Susquehanna Steam Electric Station, Units 1 and 2.
You requested that we submit to you within thirty days our program and schedule for prompt resolution of the potential problem's associated with the LOCA related suppression pool hydro-dynamic phenomena identified by General Electric during Mark III testing.
Your letter of April 23, 1975 requested additional information related to the effects of main steam relief valve operation.
You requested that we respond within 90 days or that we advise you within 15 days if >>e cannot meet this schedule.
Subsequently, we informed you that >>e would submit our proposed program and schedule for resolving these issues the week of June 2, 1975.
Since the investigations of the phenomena discussed in your letters are interr'elated, we have chosen to respond to both subjects together.
Prior to receipt of your letters,
>>e had begun a program to evaluate cer-tain suppression pool phenomena.
These phenomena, as identified in our April 4, 1975 letter to Mr. J.
P. O'Rei'lly, are:
1.
Suppression Pool Swell 2.
Containment Vent Pipe Horizontal Loads from Steam Condensation.
3.
Main Steam Safety/Relief Valve discharge pipe air clearing.
PENNSYLVANIA POWER IL L I GH T COMPANY
Page -2 The program to investigate these three phenomena, and the other phenomena mentioned in your letter, is described in the attachment and reflects our long-term approach to resolution of these problems.
The program and schedule were developed in conjunction with General Electric by the utilities owning plants with Mark II containments.
As part of our near term efforts to permit restart of containment construction, we have done a substantial amount of work in terms of defining bounding loads, based on information supplied by General Electric, and determining the capa-bility of the existing structures.
Based on this work, we have concluded that some of the "holds" placed on containment construction activities can be lifted.
Ne have scheduled a meeting for June 17 >>ith the NRC to discuss the bounding
- loads, methods of structural analysis used to determine structural capability, and our plans for the resumption of containment construction.
Very truly yours, N. N. Curtis Vice President-Engineering 5 Construction CTC:NB c-Messrs.
Mr. J.
P. O'Reilly -
US Nuc.
Reg.
Com.
Director-Region I U.S, Nuclear Regulatory Commission 951 Park Avenue King of Prussia, PA 19406
i~lARK ll CUBI'A1NHLNT PROGRAM Pg SCIIEDULE
~Pro ram Submit suppression pool and relief valve drawings reflecting current design.
Schedule
- July, 1975 LOCA guestions**
SRV uest ns**
5*
2.
3.
Submit a generic "Forcing Function Report" which will provide tho time history of pool dynamic forcing functions and the methods for relating these functions to the containment structures and components.
Submit a description of suppression pool temperature monitoring system.
(Temperature limits and transients will be described in the Final Safety Analysis Report.)
Sept.,
1975 Oct.,
1975 2, 7*
Not Appl.
1*
2 4*/
7, 8, 9,IO S.
Submit a preliminary assessment of containment structures and components based on the Forcing Function Report.
Nov.,
197S 3, 4, 5, 6, 7*, 8 3, 4*, 5 S.
Submit a schedule for the generic test program and mathematical models which justify the forcing functions used to assess containment structures and com-ponents.
Dec.,
1975 6.
Submit a schedule for the final assess-ment of containment structures and components.
First Quarter 1976
- Partial Answer Question Numbers correspond to the additional information requests contained in NRC letters dated April 17 and April 23, 197S.