ML19210B389

Comparison of Structural Integrity Test W/Aec Reg Guide 1.18.

ML19210B389
Person / Time
Site:	Three Mile Island
Issue date:	02/01/1974
From:	METROPOLITAN EDISON CO.
To:
Shared Package
ML19210B388	List: ML19210B387 ML19210B389
References
RTR-REGGD-01.018, RTR-REGGD-1.018 NUDOCS 7911070712
Download: ML19210B389 (6)

Text

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COMPARISON OF STRUCTURAL INTEGRITY TEST WITH USEAC REGULATORY GUIDE 1.18 1584 337

%'911070 7, 3

THREE MILE ISLAND NUCLEAR STATION UNIT #1 Evaluation of the Structural Integrity Test as described in the Appendix SE of the FSAR with the USAEC Regulatory Guide 1.18, " Structural Acceptance Test for Concrete Primary Peactor Containments", revision 1 dated 12/28/72.

History The SIT program follows similar published testing programs that have been practiced for other nuclear facilities with similar containment structures.

The SIT pro; ram has been presented and discussed with the AEC on numerous occasions in the past. The differences and justification of the present SIT Program with the Regulatory Guide 1.18 will be described below.

Discussion At present the contract has been awarded to a contractor for the installation of instrumentation and acquistion of data for the SIT per the committments of the FSAR.

No new information will be required for compliance with R. G.1.18, but additional number of instruments already being used, is required. The additional equipment is as follows:

1. Level - 3' extra

2. Jig Transit - 1 extra

3. Invar tape - 3 extra

a. 325 feet of conduit protective cover of tapes

b. 29 brackets to support conduit

c. 3 scales to attached to invar tapee

4. Radial Displacement - Scales - 5 extra

a. 3 scale brackets for ring girder

b. 2 scale brackets for cylinder wall

5. Radial Displacements - LVDT - 4 extra

a. Cable - 1,500 feet required

b. 3 LVDT bracket supports for tendon gallery

c. 1 LVDT bracket support for wall-piece of angle It is possible to do the SIT without the extra levels and jig transit, but without these additional iustruments, extra time during the test is required to move the instrument from one position to another position. Moving the instruments can cause errors in the data since the instruments have to be leveled and checked for same position setting each time it is moved. Also, angpecident could occur in the moving of an instrument thus causing damage to instrument and thus introducing a chance for more errors and further loss of time.

1584 338

Brewer Engineering Laboratories, Inc. have contacted the vendors of the levels and jig transits and the vendors estimate that 8 weeks lead time to supply new instruments. There are no used jig transits available for sale or rental. The installation of the instrumentation at the additional three aximuths , which are dictated by the R.G.1.18, presents conflicts with existing permanent facilities. This problem includes installation of instrumentation supports, and installation and calibration of instruments.

Conclusion The Structural Integrity Test has been developed during the preliminary and final design stages of the job, to provide a test program which demonstrates that the structural response of the reactor building is within acceptable limits. Equipment and associated hardware, scaffolding and miscellaneous items have beea purchased in a timely manner. A late change to a different program, would at this time, cause a serious delay in the current final phase and start-up schedule. There is to our knowledge no engineering j'istification for changing to the Regulatory Guide test program.

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COMPARISON BETWEEN AEC REGULATORY CUIDE 1.18 AND TMI #1 FSAR STRUCTURAL INTEGRITY TEST TABLE #1 AEC R. G.l.18 TMI FSAR #1 NO. MEASUREMENT C0!DIENTS No. of No. Per No. of No. Per Azimuths Azimuth Azimuchs Azimuth

1. Radial 1 a. Cylinder displacements Displacements using the FSAR Program with nine points per azimuth will be supe-

a. Cylinder 6 3 3 9 rior in translating the data to Equipment shell stress in contact to the Access three points required by Reg.

Guide 1.18. A total of 27 points are measured in the FSAR Program as compared to 18 points required by Reg. Guide 1.18.

b. Tangentia] 1 12 1 14 1 b. Except for tangential dis-and Radia] points points placements, the intent of Reg.

Guide 1,18 has been met by the FSAR Program.

2. Vertical Dis- 2 a. Due to the extreme vertical placements shell stiffness, a total of 3 azimuths for vertical displace-

a. Cylinder 6 1 3 1 ments is quite acceptable. The difference in the vertical dis-placement is minute.

b. Dome Apex 1 1 1 1 2 b. Identical to Reg. Guide 1.18.

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TABLE #1 CONT'D AEC R. G. 1.18 IMI #1 FSAR NO, MEASURDIENT COMMENTS No. of No. Per No. of No. Per Azimuths Azimuth Azimuths Azimuth

3. Crack Pattero Areas

a. Equipment 1 Specifies 1 1 Quadrant The FSAR requirements are in Access only 40 1740 sq. excess of the Reg. Guide Re-sq. ft. ft. quirements,

b. Cylinder 1 40 sq. 1 36 sq.

Mid Height ft. ft.

c. Buttress 1 40 sq. 0 0

& Cylinder ft.

d. Base Mat 1 40 sq. 1 60 sq.

and Cylin- ft. ft.

der

e. Spring 1 40 sq. 1 Line ft.

f. Ring 1 40 sq. 1 Girder ft. Total of 240

g. Ring 1 40 sq. 1 sq. ft.

Girder ft.

h. Dome 0 0 1

4. Strain Gages

a. Cylinder 1 1 0 0 4 a. Displacement measurement at and Base this level can compensate for Mat Me- strain Gage readings, ridional and hoop

b. Equipment one on & 1 14 Hoop 'and 44 Me- 4 b. to 4 h. The FSAR Require-Access ST from ridional gages lo- ments are in excess of Reg.

Merid- edge of cated along Horiz. Guide 1.lE Requirements.

ional & opening & Vertical Center Hoop Axis,

c. Spring 1 1 3 2 Line Me-ridional

& Hoop 1584 341

TABLE #1 CONT'D AEC R. G. 1.18 TMI #1 FSAR NO. MEASURDENT C0FDE!ES No. of No. Per No. of No. Per Azimuths Azimuth Azimuths Azimuth

4. Cont ' d

d. Under Pre- 1 1 0 0 stressing Ancho r Shear

e. Ring 0 0 5 3 at 3 Girder 1 at 2

f. Dome 0 0 3 2

g. Cylinder 0 0 3 2 Liner (Rosse tte)

h. Liner at 0 0 3 14 Penetra-tion 1584 342