ML19262A688
| ML19262A688 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/03/1979 |
| From: | Early P POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| IEB-79-14, NUDOCS 7912100316 | |
| Download: ML19262A688 (6) | |
Text
.
POWER AUTHORITY OF THE STATE OF NEW YORK to CoLUMeus CIRCLE NEW YORK. N. Y. too19 (212) 397 6200 TRUSTEES ogonogy,ggany
'"'s'R ATiNe Orr"lCs'R JOHN 5.DYSON OP JOHN W. BOSTON GEORGE L. INGALLS X
amaC Tiva vi p
VIC E CM AIR M AN OF POWER OPER ATIONS RICH AR D M. FLYNN
^
JOSEPH R. SCHMIEDER ROBERT 1. MILLON28 PersiCENT & CMiEP LEROY g." SINC, L
.,C.
T December 3, 1979 FREDERICK R. CLARK W
JPN-79-78 R, y OFFICER THOM AS R. FREY "2$" "E'E'N ai'"
Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. Thomas A.
Ippolito, Chief Operating Reactors Branch No. 3 Division of Operating Reactors
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 NRC I&E Bulletin 79-14
Dear Sir:
This letter provides a status of the Authority's program to address the requirements of the subject bulletin in accordance with our letter to the NRC Region I Director dated October 18, 1979.
I&E Bulletin 79-14 requires that all safety related pipe lines 2-1/2 inches and larger be field inspected to verify consistency between design and as built dimensions.
Enclosure (1) is a line list which identifies 194 pipe lines requiring inspection at the FitzPatrick Plant.
This list does not include the pipe lines which were analyzed by computer since these lines were previously veri-fied in response to the Show Cause Order of Marr:h 13, 1979.
A complete listing of the computer analyzed pipe lines was trans-mitted to you in our letter of June 8, 1979.
The field verification program was conducted in the same manner as reported to you in our letter of August 2, 1973.
Field inspection of all the 194 pipe lines requiring inspection is completed.
1522 iOB Aon s
79121003/6
/
U.
S. Nuclear Regulatory Commission.
Of the pipe lines inspected, 188 have been reevaluated with stresses on piping, penetrations and component nozzles determined to be within acceptable stressJinitations.
Approximately 1100 supports are associated with these reevaluated lines.
These sup-ports have also been determined to be within acceptable stress limitations, except for three supports which are operable but require minor modification.
The reevaluation also indicated the need to add two supports.
The three modified supports and two additional supports are described in detail in Enclosure (2).
Completion of the 79-14 Program is scheduled for December 15, 1979.
You will De notified regarding the results of the out-standing work upon completion.
Very truly yours, Paul J. Early Assistant Chief Engineer-Projects
- Atts, cc:
Boyce H. Grier, Director United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pa.
19406 0
1522 iG9
ENCLOSURE (1) 14 PROGRAM LINE LIST Line No.
MSK No.
Line No.
MSK No.
RESIDUAL HEAT REMOVAL CORE SPRAY SYSTEM SYSTEM 6"-W20-152-44A ll4S 4"-W20-152-40A ll4S 3"-W23-302-6A 117E 4"-W20-152-41A ll4S 3"-W23-302-6B ll7E 3"-W23-152-7A 6"-W20-152-44B 114S 3"-W23-152-7B 4 "-W 20- 15 2-4 0 B ll4S 4"-W20-302-19A ll4S REACTOR BUILDING COOLING 4"-W20-302-21 ll4S WATER SYSTEM 6"-W20-302-22 114S,1132, 1203 4"-W20-302-20 114S 4"-W25-152-16 114S 4"-WCL-151-39 1138,103C 4"-W20-152-41B 114S 4 " -WC L-151-4 3 103C 4"-WCP-302-123 1143 4"-WCL-151-47 103C 4"-W20-302-24A 114S 4"-WCL-151-60 103C 3"-W20-302-23A 114S 6"-WCL-151-61 103C 3"-W20-302-25A 114S 4"-WCL-151-70 1138 4"-W20-302-49A 114S 6"-WCL-151-72 103C s
4"-W20-302-48A ll4S 4"-WCL-151-74 103C 4"-W20-152-47A 114S 4"-WES-151-78 103C 4"-W20-302-49C 114S 6"-WES-151-103 103C 4"-W20-152-47C ll4S 6"-WES-151-104 103C 4"-W20-302-19B 114S 4"-WES-151-108 103C 4"-W20-302-24B ll4S 4"-WES-151-109 103C 3"-W20-302-23B 114S 4"-WES-151-lll 103C 3"-W20-302-25B 114S 6"-WES-151-115 103C 4"-W20-302-49B ll4S 3"-WES.-151-136 103C 4"-W20-302-469 ll4S 3 "-WES.- 15 L-13 7 103C 4"-W20-302-47D ll4S 4 "-WCL-151-13 8 310Al 4"-W20-152-47B 114S 6"-WCL-151-89 103C 4"-W20-302-49D 1.14S 6"-WCL-151-ll4 103C 4"-W20-302-81A 114S 4"-W20-302-818 114S HIGH PRESSURE COOLANT INJECTION SYSTEM REACTOR WATER CLEANUP SYSTEM 4"-W25-902-15 118E 4"-W25-152-16 ll8E 4"-WD-902A-14 101D 3"-G25-152-29 167E SERVICE WATER SYSTEM REACTOR CORE ISOLATION COOLING SYSTEM 4"-W22-902-4A 102B 6"-WES-151-40 332 A-1 2 1/2"-W220151-8B 1176 6"-WES-151-41 332 A-1 4"-W22-902-5 102B,1095 6"-WS-151-36 335 E-1 4"-W22-902A-4 102B,1095 6"-WS-151-37 335 E-1 1522 110
'**w*
w
. Line No.
MSK No.
Line No.
MSK No.
TURBINE BLDG. NORMAL VENTILATION (cont)
REACTOR BUILDING NORMAL VENTILATION 3"-WS-151-10 1311 4"-WS-151-6 1363 2 1/2"-W3-151-ll 1311 6"-WS-151-48 NA 2 1/2"-WS-151-12 1311 6"-WS-151-45 NA 3"-WS-151-13 1315 2 1/2"-WES-151-1 1294 2 1/2"-WS-151-14 1315 3"-WES-151-2 1355 2 1/2"-WS-151-15 1315 4"-WES-151-3 1355,1293 2 1/2"-WS-151-19 1264 4"-WES-151-4 1354,1355 3"-WS-151-20 1264 135J,1257 2 1/2"-WS-151-21 1264 3"-WES-151-5 1355 2 1/2"-WS-151-22 1265 2 1/2"-WES-151-7 1292 3"-WS-151-23 1264 2 1/2"-WES-151-8 1291 2 1/2"-WS-151-24 1265 2 1/2"-WES-151-9 1290 4"-WS-151-25 1264 2 1/2"-WES-151-10 1293 4"-WS-151-26 1262 2 1/2"-WES-151-ll 1295 4"-WS-151-27 FB-181C 2 1/2"-WES-151-12 1356 2 1/2"-WES-151-13 1257 CHILLED WATER ADMIN. BLDG.
2 1/2"-WES-151-14 1296 2 1/2"-WES-1:sl-54 2 1/2"-WES-151-55 1256 2 1/2"-WES-151-56 1253 6"-WS-151-1 335E,FF 21, 23 3"-WES-151-57 1360 s
2 1/2"-WES-151-58 FF-208 6"-WS-151-2 335E,FF-21, 18 4"-WES-151-59 1360,1359, 1255 4"-WS-151-3 1286 2 1/2"-WES-151-60 1251 2 1/2"-WS-151-4 1286 2 1/2"-WES-151-61 FF-214 4"-WS-151-5 1286 4"-WES-151-62 1357,1358, 2 1/2"-WS-151-6 NA 1297 2 1/2"-WS-151-7 1286 2 1/2"-WES-151-63 1295 4"-WS-151-10 1286 2 1/2"-WES-151-64 1254,1298 2"-WS-151-12 1286,FF-15 2 1/ 2"-WES-151-65 1257,1297 6"-WS-151-16 1258 3"-WES-151-66 1357 2 1/2"-WS-151-17 1258 2 1/2"-WES-151-67 1296 4"-WS-151-18 1258 4"-WS-151-19 1258 2 1/2"-WES-151-68 1306 6"-WES-151-69 1359 4"-WS-151-20 1258 2 1/2"WS-151-1 NA 2 1/2"-WS-151-21 1258 6"-WS-151-2 1363 4"-WS-151-22 1258 6"-WS-151-3 1354 4"-WS-151-29 NA 4"-WS-151-30 3353 TURBINE BLDG. NORMAL VENTILATION 4"-WES-151-1 335E,FF-29 4"-WES-151-2 335E,FF-13 4"-WES-151-3 FF-13 3"-WS-151-1 NA 4"-WES-151-4 1287 2 1/2"-WS-151-2 NA 4"-WAC-151-1 335E,FF-40 2 1/2"-WS-151-3 NA 4"-WAC-151-2 FF-44 3"'WS-151-4 1262 3"-WS-151-7 2 1/2"-WS-151-8 2 1/2"-WS-151-0 1522 111 Line No.
MSK No.
Line No.
MSK No.
CHILLED WATER ADMIN. BLDG.
STANDBY GAS TREATMENT (cont) 4"-G28-152A-55 and 56 FM-48A 2 1/2"-WAC-151-3 NA 6"-G28-152A-18 FM-18A 2 1/2"-WAC-151-6 FF-38 3"-WAC-151-14 FF-40,43 RECIRCULATION PIPING 3"-WAC-151-15 FF-41,40 3"-WAC-151-16 FF-45 Recirculation Loop A GE Dwg. 6.11 3"-WAC-151-17 FF-41 Recirculation Loop B GE Dwg. 6.11 3"-WAC-151-19 FF-45 2 1/2"-WAC-151-20 FF-41 2 1/2"-WAC-151-21 FF-45 2 1/2"-WAC-151-22 FF--45 2 1/2"-WAC-151-2 3 FF-41 3"-WAC-151-24 FF-44 3"-WAC-151-27 FF-43 2 1/2"-WAC-151-28 FF-43 3"-WA'-151-29 NA 2 1/'."-WAC-151-30 NA 2 3'2"-WAC 151-31 NA 2 1/2"-WAC-151-32 NA 4"-WAC-151-33 1287,FF-35 2 1/2"-WAC-151-34 1287,FF-35 2 1/2"-WAC-151-37 FF-36 4"-WAC-151-45 335E,FF-13 3"-WAC-151-46 FF-50 3"-WAC-151-18 1261 3"-WAC-151-50 FF-52 3"-WAC-151-51 FF-53 3"-WAC-151-52 FF-52 2 1/ 2"-WAC-151-53 1261 2 1/2"-WAC-151-54 FF-52 2 1/2"-WAC-151-55 1261 2 1/2"-WAC-151-56 FF-52 3"-WAC-151-57 1261 3"-WAC-151-60 FF-50 2 1/2"-WAC-151-61 FF-50 2 1/2"-WAC-151-62 FF-53 2 1/2"-WAC-151-63 FF-50 2 1/2"-WAC-151-64 FF-53 RESIDUAL HEAT REMOVAL 4
SLP-302-86A and 86B ll4S 4"-WCP-302-54A and B,C and D ll4S 6"-SLP-302-34A and 34B 167?
6"-W20-302-16B ll4S 1522 112
ENCLOSURE (2) - FIEID MODIFICATIONS SUPPORT NO,/LINE NO.
PROBLEM CORRECTIVE ACTION DATE COMPLETED 1.
H10-83
'the restraining Restore support to Repair in progress.
plate was not original design installed, condition.
Sub-sequently reanalyzed acceptable.
2.
2 "-WES-151-58 Reanalysis shows Install new support.
Repair in progress. :(
\\
overstress.
'3.
2\\"WES-151-60 Reanalysis shows Install new support.
Repair in progress.
overstress.
4.
Rod hanger RH#1 Reanalysis hows Remove Rod hanger Repair in progress.
on Line 6"-WES-that the Rod hanger RH#1.
151-40 would prevent up-Ifft of the pipe itne and cause undue stress.
5.
Rod hanger RH#1 Reanalysis show Remove Rod hanger Repair in progress.>
on Line 6"-WES-that the "'d hanger RH#1.
151-41 would prevet.-
p-lift of the p'se line and cause undue stress.
NUTES :
i 1
None of the above supports render any safety related systems inoperable.
s 2.
All modifications / repairs associated with the 79-14 Program will be scheduled for completion prior to a return to power following the 1980 scheduled re-fueling outage.
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