ML19242A491

Discusses 790618 Getr Site Visit to Review Layouts of Completed & Proposed Mods for Facility Seismic Upgrade. Submits Resulting List of Questions Posed to GE

ML19242A491
Person / Time
Site:	Vallecitos File:GEH Hitachi icon.png
Issue date:	06/26/1979
From:	Herring K Office of Nuclear Reactor Regulation
To:	Noonan V Office of Nuclear Reactor Regulation
Shared Package
ML19242A490	List: ML19242A489 ML19242A491
References
NUDOCS 7908020328
Download: ML19242A491 (4)

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UNITED STATES 6

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NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555

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,g 2 6 EIS MEMORANDUM FOR:

V. S. Noonan, Chief Engineering Branch Division of Operating Reactors FROM:

K. So Herring Engineering Branch

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Division of Operating Reactors THRU:

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B. D. Liaw Section B Leader

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Engir.eering Branch P

Division of Operating Reactors

SUBJECT:

TRIP REPORT: GETR SITE VISIT On June 18, 1979, myself, J. Martore and H. Polk visited the site of the General Electric Test Reactor (GETR). The purpose of this visit was to familiarize J. Martore and H. Polk (who have recently been assigned to the task for the GETR review) with the site, and to review the layouts of the completed and the proposed modifications for the seismic upgrade of che facility.

The day was spent viewing in detail the modifications being made to the primary heat exchanger, the primary piping system, the reactor pool drain lines, the missile impact system for the protection of the reactor vessel and the fuel storage canal, the spent fuel storage tand, and the reactor vessel modifications. Additionally, the conceived laycut of the fuel flooding system was studied both inside and outside of the containment, in-ciuding actual hardware consisting of the flexible hese, the shield pipe and the valve cabinets. The tour was concucted by D. Hoggett of the General Electric Ccmpany, with some soecific details being provided by GE perscnnel responsible for the ecmoletion of various aspects of the modifications.

As a result of the site visit, the folicwing questicns were posed to GE:

(1) Provide the details of the evaluaticns of the effects of the impact of the stack, or any credible portien of the stack, and all of the cooling tower hardware on the fuel flooding system supply lines.

(E) Regarding the screw Jacks providing vertical support for the primary heat exchanger:

(a) Justify that it is not necessary to provide a lccking mecnanism (e.g. lock nuts).

(b) Discuss how impact loads were considered in Ine design of these succorts to resist earthquake loadings since taey are caoable 431 358 n o8020 Q_

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JUN 2 6 1971 V. S. Noonan of resisting only ccmpressive forces and verticle deflections due to upward loading may create gaps between the heat exchange and the jacks.

(c) Discuss in detail the installation procedures for these jacks, including the significance of any precempression and how the magnitude of this precompression was determined.

Indicate any systems inside the containment building which will have (3) to be moved to acconinodate the installation of the fuel ficoding system and describe in detail the nature of the required r,todifications.

Provide the deflection patterns and the deflections of the containment (4) building under the maximum seismic loadings, including the consideration of buckling.

(5) Demonstrate that all modes of containment building failure will not impact the fuel flooding system penetrations.

Discuss how base plate flexibility was considered in the design of (6) additional supports and in the evaluation of original supports for all safety related systems, equipment and components.

(7) Provide the factors of safety assumed for all new and original cancrete expansion anchor bolts used in the suppcrt systems for all safety related systems, equipment and ccmoonents. Justify the adequacy of the factor (s) of safety.

(3) Provide the height above finished grade of the tops of the walls surround-ing the water bladcers for the fuel ficcding system.

(9) Provide complete details of the autcmatic level sensing system for the fuel ficoding system.

Include a discussion of the confidence that can be placed on the functioning of this detection system and the basis for this confidence.

(10) Discuss the surveillance program whicn will be implemented on the ccm-ponents of the fuel ficoding system to assure that they will have the required strength to function subsequent to a seismic event.

Focus especially on deterioration of the fuel ficcding system hcses and bladders.

(11) Verify that short threaded bolts on the primary piping restraints will be replaced prier to any restart of GETR.

(12) Attachment 1 indicates that during the installation of thirteen (13) cut of fifty-six ancher bolts that rebar was encountered and drilled through. Additicnally, at some other places it was noted that when rebar was encountered in drilling,the supccrts were relocated and noles recrillec without the plugging of the initially dri tied holes.

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V. S. Noonan JUN 36 579 Indicate the locations where holes were left unplugged. Discuss the effects of tha drilling through of the rebar on the strength of the structure. Also, discuss the potential for and G.? consequences of moisture contacting the rebar (e.g., corrosion) in the hoies containing anchors and in the unplugged holes on the strength of the structure, the anchor bolts, and the overall support. Provide the bases for youc conclusions.

D. Haggett indicated that a formal response to these questions would be pro-vided within two wseks of the date of the NRC site visit.

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K. Herring N

Engineering Branch Division of Operating Reactors

Enclosure:

As stated cc:

0. G. Eisenhut B. K. Grimes W. Gamill J. P. Knight L. Shao C. Nelson V. Noonan B. D. Liaw J. Martore H. Polk s V acj(;

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