ML17207A450
| ML17207A450 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 09/13/1979 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910100005 | |
| Download: ML17207A450 (7) | |
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DIS TION Central fil C
PDR PSB Reading tPBIORANDUt1 FOR:
R. Reid, Chief, Operating Reactors Branch 84, DOR FROI'1:
SUBJECT:
G. Lainas, Chief, Plant Systems
- Branch, DOR.
ST.
LUCIE SITE VISIT - FIRE PROTECTION A site visit to the St. Lucie plant has been scheduled for the week of September 24, 1979 to obtain information for the resolution of open fire protection issues;-
The proposed agenda for the site visit is provided in the Enclosure.
Me request that the Enclosure be transmitted to the licensee for his i'nformation.'he licensee should be requested to make available the personnel and documents necessary to provide the desired information on the issues to be discussed.
l<e plan to be at the St. Lucie site on September 26 and 27, 1979.
Enclosure:
As stated G. Lainas, Chief Plant Systems Branch Division of Operating Reactors
Contact:
E. Sylvester X-27173 cc w/enclosure:
D. Eisenhut B. Grimes t<. Gammill G. Lainas R. Ferguson E. Sylvester
.T. llambach P. Erickson D. Notley I/ Asp N. Antonetti J. Toknley 0100
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SF.P 13 1919 MEMORANDUM FOR:
R. Reid, Chief, Operating Reactors Branch 84, DOR FROM:
SUBJECT:
G.'ainas, Chief, Plant Systems
- Branch, DOR ST.
LUCIE SITE VISIT - FIRE PROTECTION A site visit to the St. Lucie plant has been scheduled for the week of September 24, 1979 to obtain information for the resolution of open fire protection issues.
The proposed agenda for the site visit is provided in the Enclosure.
We request that the Enclosure be transmitted to the licensee for his information.
The licensee should be requested to make available the personnel and documents necessary to provide the desired information on the issues to be discussed.
We plan to be at the St. Lucie site on September 26 and 27, 1979.
Enclosure:
As stated G. Lainas, Chief Plant Systems Branch Division of Operating Reactors
Contact:
E. Sylvester X-27173 cc w/enclosure:
D. Eisenhut B. Grimes W. Gammill G. Lainas R. Ferguson E. Sylvester T.
Wambach P. Erickson D. Notley I. Asp M'. Antonetti J.
Townley
ENCLOSURE ST.
LUCIE SITE VISIT AGENDA The purpose of this visit is to obtain information to resolve the outstanding issues described below.
Information will be obtained by discussions with licensee personnel and tours of the plant areas of concern (exception:
there are no plans to enter the reactor containment building).
1.
Section 4.1 Safe Shutdown S stems Conclusions left open because of separation of certain redundant cables and barriers may be insufficient as identified elsewhere in the SER.
2.
S i
'l.3.1.1 ~S The adequacy of the measures used to ensure sufficient fire suppression water are still under review.
3.
Section 4.10 Se aration Criteria Conclusions left open because of adequacy of separation of certain redundant cables as discussed in SER.
4.
Section 4.11 Fire Barriers The proposed l-l/2 hour fire rated barrier between switchgear room and cable spreading room is still under review.
5.
Section 5.2 Cable S readin Room The adequacy of separation between cables and the adequacy of fire barriers in the cable spreading room are still under review.
6.
Sections 5.3 and 5.4 Switch ear Rooms The adequacy of cable separation in the switchgear room is still under review.
7.
Section 5.8
.Reactor Auxiliar Buildin - 19.50'levation The adequacy of cable separation in the reactor auxiliary building (19.5'levation) is still under review.
8.
Section 5.9 Reactor Auxiliar Buildin
- 0.50'levation The adequacy of cable separation in the reactor auxiliary building
(-0.5'levation) is still under review.
9.
Section 5.10 Containment Electrical Penetration Areas The non-rated door between containment electrical penetration areas is still under review.
10.
Section 5.11 Reactor Buildin The adequacy of'cable separation in the reactor containment building is still under review.
50- 55K ORBF4-223/79 w/inc.~
Milliam 0. Miller, Chief O t~
7r License Fee Management
- Branch, ADM Amended Form Date:
FACILITY ANENOIIENT CLASSIFICATION DOCKET NO(S). SO 3 ~ '5 Qg@4QQ F/bY/0/2 klo& B&d 2/ Air Ob g/f Plant Name and Vnit(s):
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License No{s):
~PE 67 Mail Control No: 7Kb 2S'bk52 g~ Request Dated:
5 Fee Remitted:
Yes No~
lAssigned TAC No:
'icensee's Fee Classification:
ClassI,II,III,IY,V, VI
~
~
None
~subject: 4 / a~a/ &J'dc7con wo/i~ Z s~bflcyo d7 i/YgnA/s i Amendment No.
Date of Issuance.
This request has been reviewed by DOR/DP14 in accordance with Section 170.22 of Part 170 and is properly categorized.
2.
This request is incorrectly classified and.should be properly categorizod as Class Justification for classification or reclassification:
3.
Additional 'information is required to properly categorize the request:
1 4.
This request is a Class 37K type of action and is exempt from fees because it:
{a) was filed by.a nonprofit educational institution, aECEiVEn a 0:ea
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was filed by a Government agency and is not for a power reactor,
)
is for a Class (can only be a I, II, or III) amendment which results from a written Commission request dated for the application and tne amendment is to simplify or clarify license or technical specificat.ions, has only minor safety significance, and is being issued for the convenience of the Commission, or Date,.
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'HE INITIAL FEE DETERIIINATION HAS BEEN REASSESSED AND IS HEREBY AFFIRMED The above request has been reviewed and is e empt from fees.
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lJilliam O.,Miller, Chief
~
Oath LFMB 6/78 License Fee Management Branch
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