ML19329D693
| ML19329D693 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/26/1977 |
| From: | GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT |
| To: | |
| Shared Package | |
| ML19329D692 | List: |
| References | |
| PROC-770426, NUDOCS 8003160310 | |
| Download: ML19329D693 (8) | |
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FLORIDA POWER CORPORATION
-CRYSTAL RIVER UNIT 3 CONTAINMENT STRUCTURAL INTEGRITY i
DOME-SURVEILLANCE I
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. Prepared by: C11hert AssocIntes, Inc.
l'. O. Ilox 1498 Reading, Pa.~19603 J
I-Date: 4'-26-77 Rev. 1 80 03180.3)Q ;
TABLE OF CONTEUTS Section Page Table of Contents.
i 1.0 V SCOPE.
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2.0 DESCRIPTION
1 2.1 SURVEY OF DOME SURFACE ELEVATIONS.
1 2.1.1 Procedure.
1 2.1.2 Acceptance Criteria.
2 2.1.2.1 Normal Operation / Shutdown.
2 2.1.2.2 First Periodic Containment Integrated Leak Race Test (ILRT) 3 2.2 CRACK INSPECTION 3
3.0 SURVEILLANCE INTERVALS 3
4.0 REFERENCES
4 FIGURE 1 5
FIGURE 2 6
Date: 4-26-77 Rev.
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FLORIDA POWER CORPORATION CRYSTAL RI'!ER UNIT 3 CONTAINMENT STRUCTURAL INTEGRITY
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DOME SURVEILLANCE 1.0 SCOPE The Crystal River' Unit 3 operating license requires a surveillance program for the purpose of detecting future delamination of the Reactor Containment Building dome.
The dome is a combined prestressed and conventiorally reinforced concrete structure. The capability of the dome to withstand postulated loads is demonstrated by References 1 and 2.
This report describes an enhanced inservice surveillance program (in addition to tendon surveillance) which is responsive to the USNRC requirements.
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2.0 DESCRIPTION
The surveillance program described herein consists of periodic monitoring of relative vertical movements of the dome and in-s action of surface cracks.
2.1 SURVEY OF DOME SURFACE ELEVATIONS 2.1.1 Procedure Permanent benchmarks will be established at three (3) locations.
tm the ring girder to which survey mensiirements of the dome wi t L be referenced.
Seven (7) permanent survey points will be located Page 1 Date: 4-26-77 Rev.
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on the dome. A baseline survey will establish the clevation dif-ference between each of the seven. dome survey points and the three (3) benchmarks (see Figure 1).
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At the surveillance intervals specified in Section 3.0, the baseline survey procedure will be repeated. The elevation differences be-tween the survey points and the benchmarks will be computed and compared to baseline differences.
2.1.2 Acceptance criteria The measured changes in elevation differences will be compared to an acceptance criteria which is dependent upon the state of the structure at the time of the surveillonce. This state will be either normal operation / shutdown or pressurized for a contain-ment integrated leak rate test.
2.1.2.1 Normal Operation / Shutdown The vertical movement of the dome during normal operation / shutdown will be upward or downward from the baseline condition as a function of temperatures inside and outside the Reactor Contain-ment Building. The acceptance limit for this state of the strUc-ture is based on consideration of expected movement and survey accuracy coupled with an acceptable strain level for the radial reinforcement.
For example,,a change in elevation for the dome apex of 0.03 Ccet has been established as an acceptance limit.
Changes of a greater magnitude may be indicative of delamination and would necessitate evaluation and resolution.
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2.1.2.2 Firs't Periodic Containment Integrated Leak Rate Test (ILRT)
This inspection will verify that the structure continues to perform as predicte'd under an internal pressure load. Acceptance criteria will be sinilar to that foe the Structural Integrity Test (SIT, Reference 2) applied to the change in dome elevations during the ILRT.
2.2 CRACK INSPECTION Crack inspection will be made at the surveillance intervals specified in Section 3.0.
In a designated area of the dome, (see Figure 2) crack widths will be measured and crack patterns plotted. The designated.
area shown is the identical portion of the dome inspected during the SIT (Reference 2).
This area includes the circumferential joint between the new cap and the original structure.
Cracks wider than 0.010 inches will be measured and recorded.
Cracks greater enan 0.040 inches will require evaluation and resolution.
In addition, a general visual inspection of the entire dome surface area will be made.
3.0 SURVEILLMICE INTERVALS Dome surveillance subsequent to the SIT will be. performed at the following intervals:
(1) One (1) year after the SIT.
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6-(2) Eighteen (18) months after the SIT.
(3) Two (2) years after the SIT.
(4) Three (3) years after the SIT.
(5)
Forty (40) months I ten (10) months after the SIT coincident,
with the first periodic Integrated Containment Leak Rate Test.
(6)
Five (5) years af ter the SIT.
The need for continuing the enhanced surveillance program beyond the five (5) years will be evaluated af ter the five (5) year inspection.
4.0 REFERENCES
1.
" Reactor Building Dome Delamination", Crystal River Unit 3 Nuclear Generating Plant, Final Report, December 10, 1976, Florida Power Corporation.
2.
" Reactor Con;ainment Building Structural Integrity Test",
Crystal River Unit 3 Nuclear Generating Plant, Gilbert Associates, Inc.
Report No. 1930, December 7, 1976, Florida Power Corporation.
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SECTION A - A CR A CK PA TTERN-0 0ME STR E TCH O U T i
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FLORIDA Pot;ER CORPORATIO!!
CRYSTAL RtVER U?!LT 3 D0!!r. SURVEI'.I.Ai:CE FIGURE 2 DESIG?iATI:D ARP.A LOCAT[00 FOR CRACK I?lSPECTIO:: OF DottE 6
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