ML19319D479
| ML19319D479 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/23/1976 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003170605 | |
| Download: ML19319D479 (7) | |
Text
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NRCyR3195 u.s. NUCLE AR REGULATORY MMISSloN DOCKET NUMEE R w
t2 7 8 50-302
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NRC DISTRIBUTION coR PART 50 DOCKET MATERIAL TO:
FROM:
DATE OF DOCUMENT Florida Power Corp.
12/23/76 Mr. John Stolz S t. Petersburgh, Fla.
oats RECEivEo J. T. Rodcers 12/30/76 CLETTER NOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED E oRiciN AL p(UNCLAS$1FIE One itgned-Q.C.Q9.Y DESCR1PTloN ENCLOSURE
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Ltr. w/ attached....notorized 12/23/76....
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re 12/22/76 discussion between N. R. C. and
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of the Unit #3 Reactor Containtaent Building.
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(6-P) 1 PLANT NAME:
Crystal River Unit #3 SAFETY FOR ACTION /INFORMATION rNvTun 1/3/77 RJL ASSIGNED AD:
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- XBRANCH CHIEFe Stolz (f )
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--XPROJECT MAJACER; Engle/ 8 n.,e /c PROJECT MANAGER:
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Hylton LIC. ASST. :
INTERNAL DISTRIBUTION i
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SYSTEMS SAFETY PLANT SYSTEMS SITE SAFETY &
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SCHROEDER BENAROYA DENTON & MUTT.FR V OELD flTNAS k GOSSICK & STAFF ENGINEERING IPPOLITO ENVIRO TECH.
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MACARRY KTRKWOOD ERNST CASE
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Po. w..e._r 7y December 23, 1976 m.
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'Q. y Mr. John Stolz Branch Chief (D
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U.S. Nuclear' Regulatory Commission
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- i Operating License DPR-72
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Docket No. 50-302 b
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Dear Mr. Stolz:
gn W On December 22, 1976 a discussion took place between representatives of the Nuclear Regulatory Commission and Florida Power Corporation concerning the Structural Integrity Test of the Crystal River Unit #3 Reactor Containment Building. The discussion covered the following points:
1.
Two strain gauges (96 and 163) seemed to indicate undesirable behavior. These gauges were discussed in the final SIT Report and were reported as being bad gauges.
2.
Radial displacements of the containment cylinder walls, as reported in Section 11.0, Table 11.1, of the final SIT Report, were discussed.
FPC feels that the discussion in Section 11.0 adequately addresses ~
the comparison of predicted and measured radial displacements of the Reactor Containment Building.
3.
Containment wall meridional and hoop strains as reported in Tables 11.2, 11.3 and 11.4 of the final SIT Report were discussed.
FPC reviewad the evaluation of the strain data and submits the attached Tables 11.2, 11.3 and 11.4 as representing a correction in the reporting of this data.
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General Office 3201 Thirty fourtn street soutn. P.O Box 14042. st Petersburg. Flonda 33733 813-866-5151
Mr. John Stolz December-23, 1976
- It is our understanding that the discussion of the above items and the attached corrections to the SIT Report resolve the immediate outstanding issues with regard to the Crystal River Unit #3 Reactor Containment Building.
If we can provide additional information or comment, please contact us.
.Very truly yours, n0, _.
J.
. Rodgers Asst. Vice President JTR/mcm4/2 i
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IN WITNESS WHERE0F, the applicant has caused its name to be hereunto.
signed by J. T. Rodgers, Asst. Vice President, and its corporate seal to be hereunto affixed by J. H. Joyce, Asst. Secretary, thereunto duly authorized the 23rd day of December,1976.
FLORIDA POWER CORPORATION c
By J. T Rodgers V
Asst. Vice President ATTEST
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Es": #f44 (CORPORATESEAL)
Sworn to and subscribed before me this 23rd day of December,1976.
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Notary Public My Commission Expires:
Notary Public State of Florida at Large My Commission Expires July 9,1978
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TABLE 11.2 Containment Wall Hoop Strains (63.3 psig)
(A inches / inch)
Elevation Predicted Actual Difference (feet)
Value 90*
200*
333*
Average J
172 252 200 163 181
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204 258 220 249 235 244 106 146 153 123' 141 249 28 69 148 151 123 256
-62
-79
-31
-65 260
-79
-89
-89
-87
-88 266
-104
-323**
-58 125
-169 268
-94
-102
-112 102
-106
- Malfunctioning Gage.
- It is expected that this gage (61H*) was wired wrong causi~ng a sign reversal.
Therefore, the value is reported minus, cpposite that obtained from Table 9, page A19.
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TABLE 11.3 Containment Wall Meridional Strains (63.3 psig)
(* inches / inch)
Predicted Actual Difference Elevation Value 90' 200*
333' Average 172 167 143
'73 50 88 204 88
_,5 9 109 16~7 109 244 152 84 120 102 249 181 15 48 103 55 256 229 156 166 179 167 260 223 118 192 148 153 266 405 359 307 333 268 391 320 269 295
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- Malfunctioning Gage 4
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TABLE 11.4 Dome Strains (63.3 psig)
Guinches/ inch)
Predicted Actual Difference Location Value 75*
165*
255*
345*
Average 15' from apex 1 11 313 205 321 265 l
M 324 205 182 199 2H 317 237 194 215 M
324 236 294 265 3H 320 M
324 137 137-4 II 343 240 280 260 M
324 253 253 30' from apex 1H 354 351 420 386 M
492 533 617 575 2H 348 483 606 545 M
461 265 364 315 3H 343 M
431 4H 298 227 170 199 M
231 217 193 205 45' from apex 1H 220 108 346 242 104 200 M
497 200 144 255 414 253 2 11 199 185 297 215 453 287' M
465 78 136 236 158 152
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3H 178 103 83 93 M
433 4 II 48 163 280 230 243 229 M
241 37 167 40 167 103 i
- Malfunctioning Gage.
- Signs corrected for apparent wiring errors.
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