ML17212B450
| ML17212B450 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie |
| Issue date: | 03/16/1982 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0843, RTR-NUREG-843 L-82-96, NUDOCS 8203220255 | |
| Download: ML17212B450 (14) | |
Text
REGULATOR'i FORMATION DISTRIBUTION S EM (R IDS)
"'ACCESSION NBR: 8203220255 DOC, DATE: 82/03/16 NOTARIZED: -NO FACIL:50-389 St+ Lucie Plantq Uni<t 2q Florida Power,8 Light Cd ~
"AUTH~ NAME AUTHOR AFFILIATION UHRIG, R,E ~
Florida Power 8 Light Co, RECIP ~ NAME RECIPIENT AFFILIATION EISENHUTgDeG.
Division of Licensing
SUBJECT:
Forwards estimated completion dates for *all outstanding 8
confirmatory issues identified in Sections 1.7 8
1,8 of NUREG-0803<Suppl, DISTRIBUTION CODE:
B001S COPIES RECEIVED:LTR, ENCL SIZE ~,
TITLE: PSAR/FSAR AMDTS and Related Cor respondence NOTES:
DOCKET 05000389 RECIPIENT ID CODE/NAME A/D LICENSNG LIC BR P3 LA INTERNALS ELD IE/DEP/EPDB 35 MPA NRR/DE/EQB 13 NRR/DE/HGEB 30 NRR/DE/MTEB 17 NRR/DE/SAB 2Q NRR/DHFS/HFEBPO r4RR/DHFS/OLB 30 NRR/DSI/AEB 26 NRR/DSI/CPB 10 NRR/DSI/ETSB 12 NRR/DSI/PSB 19 NRR/
SB 23 E
F 00 EXTERNAL: ACRS 41 FEMA-REP DIV 39 NRC PDR 02 NTIS COPIES LTTR ENCL 1
0 1
0 1
0 1
1 1
0 3
3
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2 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
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'10 10 1
1 1
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1 RECIPIENT ID CODE/NAME LIC BR 03 BC NERSESiV ~
01 IE 06 IE/DEP/EPLB 36 NRR/DE/CEB 11 NRR/DE/GB 28 NRR/DE/MEB 18 NRR/DE/QAB
?1 NRR/DE/SEB 25 NRR/DHFS/LQB 32 NRR/DHFS/PTRB20 NRR/DSI/ASB 27 NRR/DS I/CSB 09 NRR/DS I/ICS8 16 NRR/DS I/RAB 22 NRR/DST/LGB 33 RGN2 BNL(AMDTS ONLY)
LPDR 03 NSIC 05 COPIES LTTR ENCL 1
0 1
1 1
1 3
3 1
1 2
2 1
1 1
1 1
1 1
1 1
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1 1
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1 1
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1 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 56 ENCL
'51
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1
P.O. BOX 529100 MIAMI,F L 33152 gQ hg FLORIDAPOWER 5 LIGHT COMPANY f1arch 16, 1982 L-82-96 Office of Nucl ear Reactor Regul ations Attention:
Nr. Darrell G. Eisenhut, Director Division of Licensing U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Hr. Eisenhut:
Re:
St. Lucie Unit g2 Docket No. 50-389 Saf'ety Evaluation Report Outstandi n and Confi rmator Com letion Dates b
8 y,@euy@
~~~8<m e'v Attached are Florida Power and Light Company estimated completion dates for all outstanding and confirmatory issues as identified in sections 1.7 and 1.8 of Nureg-0843, Supplement No.
1 dated
- December, 1981.
Some issues have been submitted for NRC review and will be acted upon receipt of comments.
If there are any comments or questions regarding this sub-
- mittall, please contact us at your convenience.
Very truly yours, Robert E. Uhrig Vice President Advanced Systems
& Technology REU:EWD:ga Attachment cc:
J.
P. O'Rei lly, Director, Region II (w/o attachments)
Harold F. Reis, Esquire (w/o attachments) pypI 8203220255 820316 PDR ADOCK 05000389
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ATTACHMENT ST. LUCIE UNIT I/2 SCHEDULE FOR 'COMPLETION OF OUTSTANDING AND CONFIRtATORY ISSUES NUREG 0843 (Supp.
1) b OUTSTANDING ISSUE DESCRIPTION COMPLETION DATE REMARKS (1)
Pump and Ualve Operability Assurance (3.9.3.2)
(2) Seismic Qualification (3.10)-
May, 1982 Site visits by the NRC are required to be conducted on both these items prior to completion (3) Environmental Qualification (3.11)
C,,
Program Submitted November 30, 1981 Site visit to occur in Hay, 1982.
NRC presently reviewing program (4) Seismic and LOCA Loads (4.2.3.3) b
- Hay, 1982 (5) Fuel Handling System Light Loads (9.1;4)
Hay, 1982 (6) Emergency Planning (13.3)
Complete Submitted 1/29/82 Revised staff augmentation times discussed in FPL letter L-82-77 of March 2, 1982 (7)
ATWS Procedures (15.10.6)
(8) THI Issues (Emergency Opeiating Procedures
~ I.C.l, I.C. 8)
May, 1982 Final emergency operating procedures will be submitted by Hay, 1982.
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ATTACK1ENT ST; LUCIE UNIT 82 SCHEDULE FOR COMPLETION OF OUTSTANDING AND CONFIRMATORY ISSUES NUREG 08343 (Suppl.
1)
CONFIKIATIORY ISSUE DESCRIPTION COMPLETION DATE REtiARKS (1) Surface faulting (marine seismic reflection survey 2.5.3)
- March, 1982 (2) Other Category I structures (Masonry Halls 3.8.4)
- June, 1982 (3) Dynamic analysis of reactor internals (3.9.2.2)
- March, 1982 (4) Preoperational flow-induced vibration testing of reactor internals (3.9.2.3)
- August, 1982 (5) Piping load combinations and stress limits (3.9.3.
Complete-(See Remarks)
NRC Action Item, based on Brookhaven National Labs independent analysis
Confirmatory Issue Description (Cont')
Completion Date Remarks (6) Inservice testing of pumps and valves (3.9.6)
(7) Intersystem LOCA (3.9.6)
Item (6) submitted 8/81 Item (7) procedures 9/82 Item (7)
~ Tech.
Spec.
input will be completed April, 1982 (8) Design stress and strain on fuel system (4.2.3.1)
(9)
CEA axial growth (4.2.3.1 (g)
- August, 1982 Quality assurance of Fuel Analysis will be completed by July, 1982 (10)
Rod pressure (4.2.3.1)
- Hay, 1982 (ll) Fuel rod mechanical fracturing (4.2.3. 2(g),
4.2.1.2(g))
Complete Under NRC review (12) Analog core protection calculator (4.4.5)
(14) Natural circulation cooldown tests,(5.4. 3)
- October, 1982 Completion of these issues is based on Songs startup test program, whose results will be available Sept.,
1982
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Confirmatory Issue Description (Cont'd)
Completion Date Remarks (15) Upper head voiding (5.4.3)
September, 1982 Cooldown procedures will be completed by September~
(16) Loose parts monitoring (4.4.4)
Later
~
Date will be furnished by April 1, 1982.
(17) Service history of HPSI pumps (6.3.2)
Completed Amendment 9
(FSAR)
(18)
Sump vortex test (6.3.3) 4 August 1, 1982 Test completion not expected until August 1, 1982 (19) Logic matrix and logic matrix power supplies
- August, 1982 (7.2.5)
This date reflects staff requirements (20) Shutdown Cooling System (7.4.4)
Complete NRC Action to confirm (21) Fire Protection (9.5.1)
Later Date will be furnished by May 1, 1982.
0 Pp
Confirmatory Issue Description (Cont'd)
Completion Date Remarks (22) Reactor Coolant Pump Shaft Complete Amendment 7 to FSAR 15.3.5 (23) Feedwater system pipe breaks (15.10-2)
April~ 1982 (24) Inadvertent boron dilution event (15.6.3)
- July, 1982 FPL to provide T.S. set points to complete issue (25) Inadvertent opening of PORV (15.10.5)
April, 1982 (26) Steam generator tube failure (with and without AC 15.10.4)
Complete Issue completed by response to NRC question 440.67 in FSAR amendment 7.
(27) Emergency Operating Procedures (I.C.7)
See remarks May, 1982 Final emergency operating procedures will be submitted by Hay, 1982 (28) Control Room -Design Review (I.D.1)
,r
- August, 1982 Expected last site visit on control room (29) Security Plan J
April, 1982
I