ML19199A536
| ML19199A536 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/31/1977 |
| From: | Mcguzzen H NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Linenberger G, Luton E, Salo E Atomic Safety and Licensing Board Panel, WASHINGTON UNIV., ST. LOUIS, MO |
| References | |
| NUDOCS 7905030208 | |
| Download: ML19199A536 (3) | |
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y Edward I,uton, Ecq., Chairman Mr Gustave A. Linent>errer Atomic %fet) a nd 1.ic c a sin g Daard Atomic Safet y and Licenr.ing Daard U.S. Nucts ' ll e g ui..'. y Cxc.r.: a: ion U.S. Nuclen-Re,ulator) Co:nmic. ion Washington, D. C.
20555 Washington, D. C.
20555 Dr. Ernc.to O. Salo Prefce r.or, Fu,het :es Research Institute, MII-10 College of Fisheries Univusity of W..chington Seattle, Washington 9J!95 In the ! atter of Metropolitan' Edicon Company, et al.
(Three Mile Ish.nd Nuc! car Station, Unit 2)
Docket No. 5 0 - 3.^. 0 Genticmen:
At the January 28, 1977 pre-hearir.g conference in this proceeding, the Board requccted the identification of those mattern that vrould remain unresolved after issuance of Supplement No. I to the Safety Evaluation (SER). The Staff issued Supplement No. I during the wea?. of March 21, 1977 (copies are enclo. sed). Copies of Supplc: ent No. I have been for-warded to the parties in t,is proceeding by letter dated '.! arch 25, 1977.
Sup,Slement No.1 (Section 1.7) will show that the following matters have been resolved:
- Rc. design and/or reanalysis of the containment spray chemical additive syr. tem
- Seismic qualification of safety related display inctrumentation
- Schematics verifying design implementation
- Data on iodine removal capal;ilit y of two-inch charcoal hed deptlu
- Appendi:. I review he/
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- Pellet eladding mc chanical ir.teraction
- l' valuation of electrical penctration test report The staff c::pect: the following items to he resolved bf mid-April, l')77:
- Reactor cavity precsure response
- Rcactar building sump test
- Installation of flovi measure: rent des ices to assure adequate flow to lin.it borun concentration
- Test prograt:c for reactor protecticn s'/ stem and engineered safety feature actuation system respcase time testing
- Emergency core cooling analysis modifications Resolution of the remaining items which are licted below, is largely dependent en receipt cf ac'ditional ir. formation from the applicant.
- Completic.1 of revised steam line breah analysis
- Qualification as icolation devices of output relays in the safety features actuation system fest programs for control rod drop time testing to full insertion
- Evaluation of data on environmental qualification of balance-of plant Class IE electrical equipment
- Review of feed line break analysis
- Startup overprecsure protection With regard to the generic items listed below, as noted in the SER and Supplement No.1, the Staff believes that operation of thi:, facility will be acceptable untii the Staff completes its review of these matters. At that time the Staff will consider imposition of any genieric solution on 4
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Three Mile Ir.1:.nd, Unit 2 to add to the overall safety margin for the f a cilit y.
- Evaluation of reactor vessel supports
- Anticipatcd transients without scram Sincerely, J s,,c _, /*
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I _len8y J. McGurren l
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Counsel for h'RC Staff cc:
Mr Cfnuncey R.1;cpford Atomic Safety and Licensing Ms.1;arin t' Carter Board Panel George F Trowbridge, Esq.
Atomic Safety and Licensing Ms. Judith 11. Johnsrud Appeal Panel Docketing and Service Section i
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